NL-14-002, Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies
| ML14253A153 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/20/2012 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Division of License Renewal |
| References | |
| NL-14-002 | |
| Download: ML14253A153 (676) | |
Text
{{#Wiki_filter:ENTERGY Conceptual Design
~ ~~,:~~.~~~2:.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-009 Install a Reactor Cavity Flooding System Prepared?X ~v&~-R* Approved by:
-- i
//.
Date: q~ zo~2o12 Date: I -- '- -~-
**-' I Page 1 of7 IPEC00269597
ENTERGY Conceptual Design
~~~?,~~,~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST- Mechanical 8.0 PRELIMINARY MATERIAL LIST- Electrical/Instrumentation Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of7 IPEC00269598
ENTERGY Conceptual Design
~ ~~~~~~~2.::: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-009:
Install a Reactor Cavity Flooding System
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-009 in accordance with Entergy design engineering practices. For SAMA IP2-009, resolution is required to reduce potential containment damage as a result of concrete-core interaction from molten debris following core damage and vessel failure. This package will provide an installation using a standby pump and fire water to flood the reactor cavity in the event this emergent action is necessary. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. 3.0 EXISTING CONDITIONS IP2 does not contain a reactor cavity flooding system specifically designed to protect the containment structure from the impact of molten debris resulting from core damage and vessel failure. Page 3 of7 IPEC00269599
ENTERGY Conceptual Design
~ ~~;~~,~~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 4.0 DESIGN CONSIDERATIONS A permanently installed and readily available core cavity flooding mechanism would serve to limit damage to the containment's integrity. There is a fire water supply header routed underground in an area near the Fuel Storage Building that can be utilized for this purpose. In addition, the Hudson River is a source for a backup water supply that is also available. The proposed design will provide an alternative connection so that this option can be utilized if needed.
5.0 CONFIRMATION OF DESIGN The existing fire water supply header near the Fuel Storage Building area can be accessed and connected to a pump for flooding the containment. Calculations will be performed to verify the proposed 1OOOGPM pump flow rate is adequate The new pump will be permanently installed with a suction connection from the underground fire water supply piping. Also, an additional connection will be provided on the suction line to allow for an alternate water source such as the Hudson River. The pump will be diesel-driven to further ensure availability in the event of station blackout. The pump and a small diesel fuel oil day tank (with supply capacity to operate 72 hours) will be installed in a new outdoor weather proof enclosure in the immediate area of the Fuel Storage Building. The discharge of the pump will be connected to piping routed to Penetration #U-U in the containment structure, an elevation suitable for flooding the reactor cavity. A permanent Containment Isolation Valve (CIV) will be installed at this penetration. In support of this new configuration, the appropriate analysis and Technical Specification/FSAR changes to make this addition will be provided. Heat tracing, if required for any outdoor piping, will need to be provided. Page 4 of7 IPEC00269600
ENTERGY Conceptual Design
~ ~~~~'~£~:; Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0
- 6. RECOMMENDED SOLUTION
- 1. Diesel-Driven Pump Outdoors in the area of the Fuel Storage Building Area provide for the installation of the diesel-driven backup pump.
- At the southeast corner, install a concrete pad for mounting the pump and its weather proof enclosure.
- Mount and permanently install the pump.
- Install the weatherproof enclosure.
- Excavate and modify the fire water line with a tie-in of required valves and new pipe routed to the pump's suction connection.
- Construct an oil spill containment berm around the weatherproof enclosure.
- Route and install conduit and cable and terminate from distribution cabinet to enclosure to provide electrical power required for heating, ventilation, lighting and heat tracing.
- 2. Piping Connection to Containment From the pump's discharge connection, install required valves and new pipe routed to the containment piping penetration U-U at Elevation 56' -6" (Figures 1 and 1A).
- 3. Install required pipe supports
- 4. Provide heat tracing and insulation for any outdoor pump supply header piping.
- 5. Provide procedures and training to operate, test, and perform maintenance on the components of the newly installed system.
Page 5 of7 IPEC00269601
ENTERGY Conceptual Design
~~~~,~~te: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 7.0 PRELIMINARY MATERIAL LIST - Mechanical Item Description Quantity
- 1. 8" -150# Check Valve, Butt Weld, C.S., A216-WCB, 2 Mfr. VELAN or equal
- 2. 6"- 150# Check Valve, Butt Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 3. 8" -150# Gate Valve, Butt Weld, C.S., A216-WCB, 2 Mfr. VELAN or equal
- 4. 6"- 150# Gate Valve, Butt Weld, C.S., A216-WCB, 3 Mfr. VELAN or equal
- 5. 1"- 3000# Globe Valve, Socket Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 6. Pump, 1OOOGPM, Self-Contained Diesel-Driven Skid with Industrial 1 Weatherproof Enclosure (detailed specification to follow)
- 7. Day Tank, diesel fuel oil storage (72 Hour capacity) 1
- 8. 8" Schedule 40 Seamless pipe, Carbon Steel, A-106 Grade B 200 Feet
- 9. 6" Schedule 40 Seamless pipe, Carbon Steel, A-106 Grade B 30 Feet
- 10. 1" Schedule 40 Seamless pipe, Carbon Steel, A-106 Grade B 5 Feet
- 11. 3/4" Schedule 40 Seamless pipe, Carbon Steel, A-1 06 Grade B 10 Feet
- 12. 6" Schedule 40 B.W. Tee, A-106 Grade B 2
- 13. 6" 150# R.F. WN Flange, A-106 Grade B 3
- 14. 6" 150# R.F. Blind Flange, A-106 Grade B 2
- 15. 3/4"- 3000# Globe Valve, Socket Weld, C.S., A216-WCB, 4 Page 6 of7 IPEC00269602
ENTERGY Conceptual Design
~ ;;,~~~~~,~~,:;: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 8.0 PRELIMINARY MATERIAL LIST - Electrical/Instrumentation
- 1. 1"- Conduit and Supports 200 Feet
- 2. 120 VAC- 3/c Power Cable 200 Feet
- 3. 3/4" Stainless Steel tubing 40 Feet
- 4. Pressure Gauge 2
- 5. Differential Pressure Gauge 1 Page 7 of7 IPEC00269603
ENTERGY Conceptual Design
~~~~~~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269604
"=" Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 96 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. A~ A <lo...JC.E.P"f'UA\.. Engineering Change No.: Te 1.
- 00<1 Rev. No.: C~~u:* ..l 'fJ ~4.
Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallm~act Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering !BYES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering .YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modifv SSCs included in a Maintenance Rule function?
Nuclear Analysis DYES '[).(No
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES ~NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269605
~Entergy NUCLEAR MANAGEMENT MANUAL
~*
QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of 6 DESIGN ENGINEERING PROGRAMS PotentiallmRact ASME Section Ill Specifications II YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program DYES }g"NO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES ]g{'No
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program .YES DNO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor svstem procedures?
IPEC00269606
"=" Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 98 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET30F 6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmeact Computer Support and Software DYES ~NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES ){No
- Does the proposed activity impact or involve any changes to plant chemistry reQuirements, operations or procedures, or any chanQes to the environment?
Radiation Protection (RP) Program Impact DYES _)!No
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES DNO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallmeact ASME Containment In-service Inspection (IWE /IWL) Program .YES DNO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program BYES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269607
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmnact ASME In-service Inspection (lSI) Program .YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program .YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES )(_NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program .YES DNO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES Jil'No
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269608
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 100 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Flow Accelerated Corrosion (FAC) Program DYES )(No
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program .YES DNO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES l5(No
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES )a'No
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES ~NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s} maintains its qualification status?
PTCurves DYES Ji(No
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES }(No
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES pi(No
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269609
"==="' Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 101 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED) Potentiallmeact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES fl"No
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES ONO
- Does the proposed activity result in a change to the Fire Protection Program (includinQ 10CFR50 Appendix R) where the impact is more than neQiiQible?
Detailed Impact Screening (Attachment 9.4) Attached? I DYES ~NO IPEC0026961 0
ENTERGY Conceptual Design
~ ~~~~.?.~2!.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Reactor Cavity Flooding System - Flow Diagram
- 2. Figure 1A: Reactor Cavity Flooding System - Flow Diagram
- 3. Figure 2: Reactor Cavity Flooding System- Fire Water Tie-In
- 4. Figure 3: Reactor Cavity Flooding System -General Arrangement IPEC00269611
ENTERGY Conceptual Design
~~~~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-009 Rev. o INSIDE OUTSIDE MECH MECH PENET. PENET.
AREA AREA VENT
~~*~* ....
.-=-***
1, CONT. ON 1 * ... FIGURE 1A 6" EXISTING
........,.... , CONTAINMENT LEAK RATE TEST CONN.
PENET #U-U OPEN INSIDE OUTSIDE CONTAIN. CONTAIN. FIGURE 1 REACTOR CAVITY FLOODING SYSTEM FLOW DIAGRAM IPEC00269612
ENTERGY Conceptual Design
~~2!~~~ tndian Point Nuclear Station Unit 2 Package SAMA IP2-009 Rev. o CONT.
ON FIGURE 1. ENCLOSED SELF-CONTAINED PUMP SKID 8" 6" ALTERNATE
.------.1 WATER I SOURCE CONN.
8" 6" PUMP 1000 GPM
) 6"EXIST. F. P.
( ---------- FIGURE 1A REACTOR CAVITY FLOODING SYSTEM FLOW DIAGRAM IPEC00269613
ENTERGY Conceptual Design
~::~.~~~~~~ Indian Point Nuclear Station Unit 2 SAMA Package IP2-009 Rev. O 81
~l WI
~CONTAINMENT B~O~-
+
UNIT N0.2 ~l~IENANCE _ _ N6735~0'-~t-=,.,...,=--====if=H I ~ QUTAGE BLDG. I SEE DETAIL ~G~ FUEL DWG. A227551 STORAGE BLDG. PRIMARY ----!:!!!.! AUXILIARY BLDG. WASTE HOLD UP TANK PIT FIGURE 2 REACTOR CAVITY FLOODING SYSTEM FIRE WATER TIE-IN TITLE1 * ~
~v~A~Ro~F~IR~E~?RO~T~E~cr~ION~~P~rP"""r-NG....,.... -Jsrrtergy INDIAN POINT Ncd.earNu.~
IPEC00269614
ENTERGY Conceptual Design
~~;~~~~~~ tndian Point Nuclear Station Unit 2 Package SAMA IP2-009 Rev. 0 N
CONTAINMENT BLDG.
~II_ N0.2 + ____
MAINTENANCE AND OUTAGE BLDG. FUEL STORAGE BLDG. APPROX LOC. OF SELF CONTAINED
~t::: FAN ...._........ PUMP SKID
- JQ_
t-HOUSE
------~--~--~~~~~~~~--PROPOSED
_J Q::<:( w~ (/) <( PIPE ROUTEr-------. ZCl:: wo BORIC ACID OI TRANSFORMER YARD ZI- EVAP. BLDG. 03i: EL. 15'-0" 0 PRIMARY AUXILIARY BLDG. FIGURE 3 REACTOR CAVITY FLOODING SYSTEM GENERAL ARRANGEMENT l00\1Ii)lj: IPEC UNIT 1 ll 2
- APPROVALS -
=-MF IPEC00269615
ENTERGY Conceptual Design
~ ~~~,~~~~~~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. Typical Self Contained Diesel-Driven Pump (attached here)
IPEC00269616
rc
*" ~: "
*I mu
~
')
a* il ~, J
~ *~
;I
- _i i
c [Ft} ~ [ [1} Hole offers a variety of standard and custom self contained engine driven pumping modules with features designed to meet demanding applications. Our units can be mounted direct, bolted down, or set 1,1p as trailers for transportable firefighting protection at dock side. Varying in size and capability from small open chassis units to custom trailer pumping modules, they span a wide range of applications including marine firefighting pumps and industrial trailers. Hale builds water and foam pumping skids to meet the needs of government, forestry, and industrial customers. Units have been constructed for hurricane relief, fire protection at nuclear power sites, oil field fire fighting, hydrant systems, marine fire boats, dock protection, and more. These units are equipped with heavy dui 7 fan forced radiator cooling. I
~t\*l,
-'1-
~~
)
-.. .i
~" ~J
\
HALE Products Classf
* \ I ..
IPEC00269617
ENTERGY Conceptual Design
~ ~~~-~~,~~2~~"~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -009 Rev. 0 Attachment 4 Cost Estimate IPEC00269618
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-009 Conceptual PROJECT TITLE: Install a Reactor Cavity Flooding System []CAPITAL 0o&M ESTIMATOR: RCMT Preliminary JOB LOCATION: Containment Building, Yard near FSB PROJECT CODE: TBD Definitive 0 OUTAGE 0 NON*OUTAGE ORIGINATOR: ORIG. DATE: 07/12/2012 1----'---------1 ESTIMATE TOTAL $1,738,982 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-009 in accordance with Entergy design engineering practices. For SAMA IP2-009, resolution is required to reduce potential containment damage as a result of concrete-core interaction from molten debris following core damage and vessel failure conditions. This package will provide an installation using a standby pump and fire water to flood the reactor cavity in the event this emergency action is necessary. Prepared by: Date: IPEC00269619
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station lr**~**" EC #: SAlVIA IP2-009 Conceptual PROJECT TITLE: Install a Reactor Cavity Flooding System l.:'J CAPITAL OO&M ESTIMATOR: RCMT Preliminary JOB LOCATION: Containment Building, Yard near FSB PROJECT CODE: TBD Definitive 0 OUTAGE f.2l NON- OUTAGE ORIGINATOR: ORIG. DATE: 07112/2012 Item Description
- 1. This estimate assumes that this work will require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, Six days per week schedule.
- 3. This estimate assumes that a Prefabricated building will be purchased for erection on site by skilled local craft.
'5. Th;, ~Um*ffi *~om" This estimate provides for-~--tw c roo""ot
* . "'"'"""' "'"" of"'"'" m*iot.o.o~ po=oo*l
- 6. This estimate assumes trai nnel.
- 7. This estimate assumes that and valves will only require a C of C.
- 8. This estimate assumes that weld inspections ited to visual and LP testing.
- 9. The bulk of the work in this estimate is non outage and is assumed to occur in 2011 on a 4 day per week, 10 hour per day schedule.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 10. Estimate Classification System (see Attachment 3, Reference 2}. Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A Outside fence boundary- 20% B. Inside fence boundary - 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00269620
Page 1 of 4 10/3/2012 4:55PM IP2-009.xls INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2-009 PROJECT TITLE: Install a Reactor Cavity Flooding System [J CAPITAL U O&M TAKEOFF: JOB LOCATION: Containment Building, Yard near FSB EST. STATUS: 0 OUTAGE [J NON-OUTAGE I MANHOURS r PROJECT CODE TBD ORIGINATOR
'MATERIAL$ MATERIAL LABOR ESTIMATOR RCMT ORIG. DATE 07/12/2012 SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $1MH PER UNIT I-'D;:.'O:.OLi-iL'-';Ac;:R;-i;S=-t-;:D;;';OO;'L'TL7A;:;RS;;t;C"-O;;iN'i;;T;;;RA~C::;;Tt--T:o.O;;;:T;:-;A"L'$rl
*ESTIMATE LEVEL* ESTIMATE
SUMMARY
Conceptual MANHOURS DOLLARS Preliminary ENGINEERING Definitive 01 STUDY, DESIGN, & CLOSEOUT 160 $ 16,000 02 DESIGN ENGR CONST SUPPORT 40 $ 4,000 General Notes: 03 MODS ENGR SUPPORT $ 04 SYS ENGR/ S-U ENGR 100 $ 12,000 05 PROJECT MANAGEMENT 200 $ 24,000 06 TESTING (Calibration & Testing) 40 $ 4,000 07 TECH SPEC/FSAR, CALCS, ANALYSIS 675 $ 81,000 08 ENGR'G, DCP ACCEPTANCE REVIEW 40 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 1,200 $ 144,000 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 160 $ 16,000 11 OSG FIELD ENGRS I PLANNERS 140 $ 16,800 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 124,550 13 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 2,050 $ 278,526 15 LOST TIME 205 $ 27,853 16 SWEC DISTRIBS PLANT CRAFT LABOR 17 MECH MAl NT. $ 18 ELECT MAINT $ 19 I&C $ 20 CSG $ MISC SUPPORT 21 QUALITY CONTROL 180 $ 18,000 22 PLANNING & SCHEDULING 23 TRAINING 36 $ 4,320 24 CHEMISTRY $ 25 OPS 100 $ 12,000 26 HP/RP $ MISC CONTRACT SUPPORT 27 QUALITY CONTROL 130 $ 10,400 28 NDE 29 HP/RP 30 RADWASTE $ 31 NURSE $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL $ 36 VENDOR STOCKING $ 37 DECONTAMINATION CONTRACTOR $ 38 RBC'S $ 39 SECURITY $ 40 FIRE WATCH (Rover) $ 41 SAFETY 41 $ 2,788 CONTINGENCY 42 CONTINGENCY $ 318,495 ESTIMATE SUBTOTAL 5,497 $1,114,732 SITE ENCUMBRANCE PREMIUM (20%) $ 222,946 LOADERS (30%) $ 401,304 ESTIMATE TOTAL $1,738,982 IPEC00269621
Page 4 of 5 712512012 5:56 PM SAMA IP2-009_1nstaii_A_Reactor_Cavity_Fiooding_System- (6-01-11)
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP2-009 ADJECT TITLE: Install a Reactor Cavity Flooding System jltJ CAPITAL LJo&M TAKEOFF: JOB LOCATION: Con!ainmeni Building, Yard near FSB PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: QoUTAGE [ZJNON-0UTAGE ORIGINATOR* ORIG. DATE: 0711212012 MANHOURS 'MATERIAL $1 MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ Non-Outa eWork 1' Gather and stage tools and materials 1 LT LB 2 2.00 1.00 4 $ 78.15 $ $ 313 $ 313
- 2. Perform walkdown or work area. 1 LT LB 2 4.00 1.00 8 $ 78.15 $ - $ 625 $ 625
- 3. Perform walkdown of work area. 1 LT OP 1 4.00 1.00 4 $ 115.00 $ - $ 460 $ 460
- 4. Excavate to existing Fire Water line 1 LT OP 1 16.00 1.00 16 $ 115.00 $ - $ 1,640 $ 1,640
- 5. Excavate to existing Fire Water Line 1 LT LB 2 16.00 1.00 32 78.15 2,501 $ 2,501 I' 6.
7. PeJform tie in to existing fire line Backfill and compact excavation 1 1 LT LT PF OP 3 1 20.00 10.00 1.00 1.00 60 10 120.71 115.00 7,243 1,150 7,243 1,150
- 8. Bacl<fill and compact excavation 1 LT LB 2 10.00 1.00 20 $ 78.15 $ $ 1,563 $ 1,563
- 9. Excavate, fonm and pour slab with oil berm 1 LT OP 1 10.00 1.00 10 $ 115.00 $ - $ 1,150 $ 1,150
- 10. Excavate, form and pour slab with oil benm 1 LT LB 3 30.00 1.00 90 $ 76.15 $ 1,500 $ 7,034 $ 6,534
- 11. Excavate, form and pour slab with oil berm 1 LT CP 2 10.00 1.00 20 $ 96.00 $ - $ 1,920 $ 1,920
- 12. Obtain and erect insulated steel building. 1 LT MW 3 20.00 1.00 60 $ 134.00 $ 10,000.00 $ 10.000 $ 6,040 $ 18,040
- 13. Provide Light, Heat and Ventilation 1 LT EL 2 30.00 1.00 60 $ 123.32 $ 4,000.00 $ 4,000 $ 7,399 $ 11,399
- 14. Set Diesel Pump Skid 1 lT MW 2 20.00 1.00 40 $ 134.00 $ 50,000.00 $ 50,000 $ 5,360 $ 55,350 15, Ex,:avate and pour Pipe Support Piers 1 LT LB 2 40.00 1.00 80 $ 78.15 $ 4,000.00 $ 4,000 $ 6,252 $ 10.252
- 16. Excavate and pour Pipe Support Piers 1 LT CP 1 40.00 1.00 40 $ 96.00 $ - $ 3,840 $ 3,640
- 17. Excavate and pour Pipe Support Piers 1 LT OP 1 40.00 1.00 40 $ 115.00 $ $ 4,600 $ 4,600
- 18. Obtain Material and Erect Pipe Supports on Piers 1 LT PF 3 40.00 1.00 120 $ 120,71 $ 2,000.00 $ 2,000 $ 14,485 $ 16,485 19, Cut, Fit and Weld Piping from Diesel to Pene.U-U 1 LT PF 3 120.00 1.00 360 $ 120.71 $ - $ 43,456 $ 43,456
- 20. Tie in Piping at Pump and at Penet #U-U 1 LT PF 3 20.00 1.00 60 $ 120.71 $ - $ 7,243 $ 7,243
- 21. Mount and tie in diesel day tank 1 LT PF 3 10.00 1.00 30 $ 120,71 $ 1,000.00 $ 1,000 $ 3,621 $ 4,621
- 22. Prefabricate Containment spool piece for oufage. 1 LT PF 2 20.00 1.00 40 $ 120.71 $ $ 4,826 $ 4,828
- 23. Support testing as required 1 LT PF 2 20.00 1.00 40 $ 120.71 $ $ 4,828 $ 4,828
- 24. Clean-up area and restore 1 LT PF 2 10.00 1.00 20 $ 120.71 $ - $ 2,414 $ 2.414
- 25. Clean-up area and restore 1 LT LB 2 10.00 1.00 20 $ 78,15 $ - $ 1,563 $ 1,563 OUTAGE WORK
- 1. Obtain tools and material 1 LT PF 2 5.00 1.70 17 $ 120.71 $ $ 2,052 $ 2,052
- 2. Perform job brief and walk down are 1 LT PF 2 5.00 1.70 17 $ 120.71 $ - $ 2,052 $ 2,052
- 3. Install prefabricated spool in containment 1 LT PF 2 10.00 1.70 34 $ 120.71 $ $ 4,104 $ 4,104
- 4. Clean up and restore area 1 LT PF 2 5.00 1.70 17 $ 120.71 $ - $ 2,052 $ 2,052 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP* PRIME 1 LT PT 2 40.00 1.00 80 $ 95.16 $ 1,000 $ 7.613 $ 8,613
- 2. PAINTING & TOUCH-UP 1 LT PT 2 40.00 1.00 80 $ 95.16 $ 2,000 $ 7,613 $ 9,613 FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 120.00 1.70 204 $ 53.60 $ $ 10,934 $ 10,934
- 2. CRAFT SUPPORT FOR BOTTLE WATCH $ - $ - $ -
MISC SUB-CONTRACT 1' MISC SUB-CONTRACT 1 LT $ - $ - SUBTOTAL CRAFT & SUB-CONTRACTOR 1,733 $ 75,500 $180,148 $ - $ 255,648
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 139 $ 103.95 $ 14,449 $ 14,449 SUBTOTAL 1,872 $ 75.500 $184,597 $ $ 270,097
- RELATEO COSTS
- 1' WALKDOWN ALLOWANCE 1 LT PF 17.00 1.00 17 $ 120.71 $ 2,052 $ 2,052
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT PF 95.00 1.00 95 $ 120.71 $ 11,467 $ 11,467
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT El 66.00 1.00 86 $ 123.32 $ 8,139 $ 8,139
- 4. GENERAL CRAFT DISTRIBS. (10%) $ 19,460 $ 19,460
- 5. CRAFT IN PROCESSING (20%) $ 38,919 $ 38,919
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 3,892 $ 3,892
- 7. (112 day training, or- 2%)
SUBTOTAL 2,050 $ 75,500 $278,526 $ $ 354,026 PLANT SCOPE
- 1. MECH MAINTENANCE PL - $ $ - $
PL - $ $ $ - SUBTOTAL MECH MAINT. . $ $ - $ $ - 1' ELECT MAINTENANCE SUBTOTAL ELECT. MAINT. PL Pl
- 1. I&C (Oev. Instrument Calibration Proc&dures) 0 LT PL - - $ $ $
Pl - $ $ - $ SUBTOTALI&C MAINT. - $ $ - $ - $ - 1' CSG PL - $ - $ $ - PL - $ - $ - $ - SUBTOTAL CSG MAINT. - $ - $ $ $ IPEC00269622
Page 5 of 5 712512012 5:56 PM SAMA IP2-009_1nstaii_A_Reactor_Cavtty_Fiooding_System- (6-01-11)
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2-009
<OJECT TITLE: Install a Reactor Cavity Flooding System JOB LOCATION: Conwnmern Building. Yard near FSB
~~~CAPITAL UO&M ROJECT CODE: TBD TAKEOFF:
ESTIMATOR: RCMT EST. STATUS: OoUTAGE @NoN-oUTAGE RIGINATOR: ORIG.DATE: 07112/2012 MAN HOURS 'MATERIAL MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ SUBTOTAL PLANT $ $ - $ - $ - SUBTOTAL CRAFT/PLANT 2,050 $ 75,500 $278.526 $ - $ 354.026 IMPLEMENTATION SUPPORT 1. 2. MODS ENGINEERING DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 100.00 1 LT NM 1 40.00 1.00 40 $ $ 4,000 $ 4,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4.000
- 4. SYS ENGINEERING- ELECTRICAL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 5. SYS ENGINEERING - INSTR & CONTROL 1 LT NM $ $ -
- 6. SYS ENGINEERING CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 150.00 $ 6,000 $ 6,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 200.00 1.00 200 $ 120.00 $ 24,000 $ 24.000
- 8. TRAINING (OPS Staff) 1 LT NM 12 3.CO 1.00 36 $ 120.00 $ 4.320 $ 4,320
- 9. QA I QC VERIFICATION 1 LT NM 1 180.CO 1.00 180 $ 100.00 $ 18,000 $ 18,000
- 10. PLANNING & SCHEDULING 1 LT NM 1
- 11. HP I RPI ALARA 1 LT NM - $ - $ -
12. 13. CHEMISTRY OPS (DEVELOP/REVISE PROCEDURE(S)) 1 1 LT NM 100.00 1.00 100 120.00
$ 12.000 LT NM 1 $ $ 12.000
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per Diem) LT NM - $ - $
- 2. MODS PLANNING & SCH.- SWEC (Inc! Per Diem) 1 LT NM 1 160.00 1.00 160 $ 100.00 $ 16,000 $ 16,000
- 3. OSG FIELD ENGRSIPLAN- SWEC(Incl Per Diem) 1 LT NM 1 140.00 1.00 140 $ 120.00 $ 16,800 $ 16,800
- 4. QA I QC VERIFICATION 1 LT NM 1 130.00 1.00 130 $ 80,00 $ 10,400 $ 10,400
- 5. NDE 1 LT NM 1 - $
- 6. HP/RP 1 LT NM 1 - $
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM -
- 9. ELEVATOR CONTRACTOR 1 LT NM -
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIRE WATCH (Rover) 1 LT NM $ - $ -
- 18. SAFETY(2%) 1 LT NM 41 $ 68.00 $ 2,788 $ 2,788 19 LOST TIME (10%) 1 LT 205 $ 135.87 $ 27 853 $ 27,853 SUBTOTAL CRAFT/NON-MANUAL 3,382 $ $ - $ 502,187
- 1. 6" and 8" Sch 40 pipe Safely Class 1 LT MT $ 12,000 $ 12,000
- 2. 8", 6", 1" and 314" valves, 150# class, Safely Related 1 LT MT $ 30,000 $ 30.000 3, FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 7,050 $ 7,050 SUBTOTAL INSTALLATION COST 3,382 $ 124,550 $426,687 $ - $ 551,237
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 2. DESIGN ENGINEERING ELECTRICAL 1 LT NM 1 40.00 100 40 $ 100.00 $ 4,000 $ 4,000 3.
4. DESIGN ENGINEERING - INSTR. & CONTROL DESIGN ENGINEERING - CIVIUSTRUCTURAL 0 1 LT NM - 80.00 8,000 8,000 LT NM 1 1.00 80 $ 100.00 $ $
- 5. TESTING (Instrument Calibration and testing) 1 LT NM 2 20.00 1.00 40 $ 100.00 $ 4,000 $ - $ 4,000
- 6. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,200.00 1.00 1,200 $ 120.00 $144,000 $ $ 144.000 TECH SPEC I FSAR REVISIONS, CALCULATIONS, 7.
ANALYSIS 1 lT NM 1 675.00 1.00 675 $ 120.00 $ 81,000 $ 81,000
- 8. ENGRG DCP ACCEPTANCE REVIEW 1 LT I NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000 SUBTOTAL DESIGN COST 2,115 $245,000 $ $ 245,000 SUBTOTAL INSTALLATION & DESIGN COST $671,887 $ $ 796,237
- 1. CONTINGENCY ( 40%) $ 318,495 ESTIMATE SUBTOTAL 5,497 $ 1,114,732 IPEC00269623
ENTERGY Conceptual Design
~ ~~;~,~~~~'~!~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-021 Install Leak Monitoring Instrumentation for ISLOCA Pathway Isolation Valves Prepared by~ /i ~ j-~~. Approved by:
c;::~ ~ Date: q-- 2 o-zotz Date:
'~ --':' ~'I Page 1 of6 IPEC00269789
ENTERGY Conceptual Design
~ ~~~~~.~~~,~~.:~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00269790
ENTERGY Conceptual Design
~~~;.~~,~~ Indian Point Nuclear Station Unit2 Package SAMA IP2 -021 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-021:
Install Leak Monitoring Instrumentation for ISLOCA Pathway Isolation Valves
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-021 in accordance with Entergy design engineering practices. For SAMA IP2-021, resolution is required to provide remote monitoring of any fluid leakage past the isolation valves in ISLOCA pathways. This package will provide the piping connections and transmitters required to interface with the monitoring instrumentation located outside containment. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. Page 3 of6 IPEC00269791
ENTERGY Conceptual Design
~ ~~;~~~2,~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 3.0 EXISTING CONDITIONS In containment, the pathways of the Safety Injection (SI) System piping need to be monitored for potential leaks of liquid from the interfacing Reactor Cooling System (RCS) and Auxiliary Cooling System (ACS) piping. There are 22 check valves and 2 motor operated valves (MOV) installed in the Sl piping that interface with these systems to provide this isolation.
In each ISLOCA pathway there are redundant "blocking valves" that provide isolation from interfacing systems. The effectiveness of the valves' blocking function to provide an isolation boundary needs to be monitored. 4.0 DESIGN CONSIDERATIONS Check Valve Pathways Each of the "blocked" piping sections within an isolation boundary has an existing piping connection available to be adapted as a monitoring point. (Ref. Attachment 2 - Figure 2 - all sheets) MOV Pathway The "blocked" piping section within this isolation boundary will require modification of the piping to include a connection that can be adapted as a monitoring point. (Ref. Attachment 2 - Figure 2 - sheet 1) Monitoring for pressure change within each of the isolated boundaries will need to be transmitted to a remote location outside containment. 5.0 CONFIRMATION OF DESIGN There are nine (9) separate ISLOCA paths with blocked isolation boundaries that potentially can allow fluid to leak by. As stated above there are proposed connections located in each piping path for a sensing device to be applied to monitor them. Installation of a pressure transmitter at each of these piping connections will provide the means of measuring changes within an isolation boundary. In addition, the transmitter will enable this information to be electronically transmitted to a location outside containment for remote display and monitoring. Page 4 of6 IPEC00269792
ENTERGY Conceptual Design
~ ;~~.~.~~~2~;;, Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 6.0 RECOMMENDED SOLUTION
- 1. Check Valves A. For each isolation boundary listed in Attachment 2, Figure 3, perform the following:
- At the existing piping connection install small bore pipe, instrument root valves, instrument tubing, pressure transmitter and required supports.
- 2. MOVs
- For the isolation boundary listed in Attachment 2, Figure 4, perform the following:
- Within the "blocked" piping section that forms the isolation boundary, install a new connection to be adapted as a monitoring point.
- At the piping connection install small bore pipe, instrument root valves, instrument tubing, pressure transmitter and required supports.
- 3. Remote Leakage Monitoring Install new instrumentation outside containment, to display leakage data for each isolation boundary listed in Attachment 2, Table 1.
- 4. Conduit and Wiring A. Transmitters
- Route and support conduit from each transmitter to the two new junction boxes fitted with terminal blocks located in containment.
- Route and support a single conduit from each junction box, via containment penetration, to the new ISLOCA leak status monitoring panel outside containment.
- Install and connect wiring from the pressure transmitters to the new junction boxes.
- Install and connect wiring from the junction boxes to the new ISLOCA leak status monitoring panel.
B. Remote Leakage Monitor Panel
- Route and connect 120VAC power supply to the new monitor panel located in the Control Building at Elevation 33'- 0".
- 5. Provide procedures and training to operate, test, and perform maintenance on the components of the newly install system.
Page 5 of6 IPEC00269793
ENTERGY Conceptual Design
~ ~;~~~.~~~2~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Rosemount 1153 Series D Alphaline Nuclear 9 Pressure Transmitter
- 2. Valve - Valve Manifold 9
- 3. Yokogawa- DXAdvanced R4- DX1000 Recorder 1
- 4. Loop Power - Power Supply 1
- 5. Hoffman Junction Box with terminal blocks 2
- 6. Hoffman Wall Mounted Panel and enclosure, with 1 terminal blocks, 36" x 36" x 16"
- 7. Instrument Tubing- 0.375" x 0.065- 316 SS Tubing 950 Feet
- 8. 1"- Conduit 350 Feet
- 9. 2"- Conduit 350 Feet
- 10. Two Pair- Twisted Shielded Pair Cable 200 Feet
- 11. Six Pair- Twisted Shielded Pair Cable 1100 Feet
- 12. 2/c Cable 100 Feet
- 13. %" -1500# Socket Weld Globe Valve 28 CONVAL Model No. 12G3J-3163D or equal
- 14. %"Schedule 160 Seamless Pipe, A376 Type 316 40 Feet
- 15. %" -6000# Socket Weld Tee, A 182 F316 9
- 16. %"-6000# Screwed Cap, A182 F316 9
- 17. %"-6000# Sockolet, A182 F316 1 Page 6 of6 IPEC00269794
ENTERGY Conceptual Design
~ ~~~~~,~~~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269795
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. s Engineering Change No.: I=-P_2_~___ Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallm~act Civil/ Structural Design Engineering .YES ONO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any pipina enaineerinQ desian chanaes or activities?
Electrical Design Engineering .YES ONO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES ONO
- Does the proposed activity involve any I&C design or settinas chanQes or activities?
Mechanical Design Engineering .YES ONO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES ~NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269796
*-=- Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potential lmeact ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO Does the proposed activity involve control panel design including layout and labeling,
" visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) .YES DNO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
. Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program .YES DNO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00269797
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmgact Computer Support and Software DYES !Xi NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES fXrNo
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection {RP) Program Impact DYES D(i NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallmgact ASME Containment In-service Inspection (IWE /IWL) Program .YES DNO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program .YES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269798
."Pb NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmj;!act ASME In-service Inspection (lSI) Program .YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 {T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program .YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 {T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES Dlf NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES (XI NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES t&1 NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES IXJ NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES f8j NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269799
....-=-Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE ENwDC-115 I
PAGE 100 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potential lmf;!act Flow Accelerated Corrosion (FAC) Program .YES DNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES IX! NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES 1iJ NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES JXl NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES QCNO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES !g'j NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ} maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES rjNO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES lki'No
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES fKl NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269800
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 101 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET60F 6 PROGRAMS AND COMPONENTS {CONTINUED} PotentiallmJ;!act Welding Program .YES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES DNO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES Ill NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES Cfl NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R} where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES I)1S NO IPEC00269801
ENTERGY Conceptual Design
~ ~~~'~?~~::.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Existing Valve Tie-In Chart
- 2. Figure 2, Sheet 1 - A235296: Safety Injection System Flow Diagram (partial)
- 3. Figure 2, Sheet 2- A235296: Safety Injection System Flow Diagram (partial)
- 4. Figure 2, Sheet 3- A235296: Safety Injection System Flow Diagram (partial)
- 5. Figure 3 Typical Leak Detection Piping Connection at Check Valves
- 6. Figure 4: Leak Detection Piping Connection at MOVs IPEC00269802
ENTERGY Conceptual Design
~ ;;~~~?~~~~~: Indian Point Nuclear Station Unit2 Package SAMA IP2 -021 Rev. 0 Existing Boundary Location Valve No.
SX7 Test Connection between Valves 857B & 857F S-28 Test Connection between Valves 857A& 857M SXIO Test Connection between Valves 857D & 857H S-24 Test Connection between Valves 857C & 857G S-39 Test Connection between Valves 897 A & 895A/838A/857J S-42 Test Connection beh:veen Valves 897B & 895B/838B S-45 Test Connection between Valves 897C & 895C/838C/857K S-34 Test Connection between Valves 897D & 895D/838D NEW Test Connection between Valves M-730 & M-731 FIGURE 1 EXISTING VALVE TIE-IN CHART IPEC00269803
ENTERGY Conceptual Design Technologies Indian Point Nuclear Station Unit3 Package SAMA IP2-021 Rev. 0 TO LOOP 23 HOT LEG OF R.C.S. 2*-#56-2-SI-2501 R (9321-F-27.36) 1-z w
- 2 TO LOOP 21 z HQT LEG OF R.C.S.
2' -#16-2-SI-2501 R
<( (9.321-F -27.36) 1-z 0
U0 z w-oo _ _j TO LOOP 22 COLD LEG OF R.C.S. 2*-#15-2-SI-2501 R (f)- (9321-F-2736) z:J _m
~
TO LOOP 24 COLD LEG OF R.C.S. 2"-#15-2-S!-2501 R
*--! N
(.1) (9.321-F-27.38) NEW EXCEPT FOR 856() 2"-2501R 2"-2501R CONNECTION SEE DWG. A206121 (TYP (TYP) FIGURE 2 (SHEET 1) IPEC00269804
ENTERGY Conceptual Design Technologies Indian Point Nuclear Station Package Unit 2 SAMA IP2-021 Rev. 0 Power System Services
~
~I
~
Ol 0 z
~
LLI LLI
!I) zz 0 CONTINUED
(.) a:: ON e { FIGURE 2 SHEET 3
.l::l.Qill.
FOR TESTING OF S.I.S SYSTEM SEE FLOW DIAG. 8206115 6524 FIGURE 2 (SHEET 2) IPEC00269805
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 2 SAMA IP2-021 Rev. 0 ITEM: ACCUM.24 24AT 1o*-SI-2501R-f361/
- 1l N
I iii
- I CONTINUED}
0 ON FIGURE 2 SHEET 2 FIGURE 2 (SHEET 3) TITLE
- FLOW. DIAGRAM
** SAFETY IN-.IECTION SYSTEM INDIAN POINT MY IPEC00269806
ENTERGY Technologies Indian Point Nuclear Station Unit 2 SAMA IP2-021 Rev, 0 Power System Services 2--------9--()--2 EXISTING -............_ VALVE ~\7 1I ~~
~
x SEE FIG.#3 _w_,___ _ 3/4" NEW 3/4"
/VALVE NEW---...J NEW t:.J~ TEST PIPING 3/4" CONN SCH 160 HOFFMAN MISSLE CONTAINMENT NEW JUNCTION BARRIER PENETRATION 3/4" BOX VALVES LOCAL *
- TRANSMITIER *
- HOFFMAN WALL MOUNTED
*
- PANEL 3/S"SS TUBING ~RECORDER I
--------------' I
*
- I I SEE
- FIGURE 4 (2---J e
*
- y120 VAC
*
- CONTROL BUILDING
*
- EL. 33'-o" VALVE *
- MANIFOLD *
- FIGURE #3 TYPICAL LEAK DETECTION PIPING CONNECTION AT CHECK VALVES TITLE
- FLOW OIAC-RA~l STAHON -,
SAFETY INJECTION SYSTEM INDIAN POINTj IPEC00269807
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 2 SAMA IP2-021 Rev. 0
,......----NEW 3/4" -6000 # SOCKOLET (DRILL THRU 14" PIPE)
~EXISTING Jl(J-- -~(] ~ / MOV
/731 730 EXISTING NEW 314 ..
MOV VALVE NEW 3/4" VALVE 3/4" NEW PIPING - - . . II /NEW TEST CONN 3/4" SCH 160 u MISSLE CONTAINMENT BARRIER PENETRATION LOCAL *
- TRANSMITIER *
- I 3/B"ss--
TUBING I I
-----:-----:---2 SEE FIGURE 3 I I VALVE MANIFOLD FIGURE 4 LEAK DETECTION PIPING CONNECTION AT MOV'S TITlEt FLOW. DIAGRAM * . STATION .
SAFETY IN,JECTION SYSTEM
~~
-'Bn.tmgy. INDIAN *POINT A235296-'-
MY IPEC00269808
ENTERGY Conceptual Design
~ ~~~~,~~~~:,:,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. ENTERGY Specification 9321-01-248-18 Fabrication of Piping Systems-Indian Point Unit No. 2
- 4. Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitter (attached here)
- 5. Yokogawa- DXAdvanced R4- DX1000 Recorder (attached here)
IPEC00269809
Product Data Sheet 00813-0100-4388 Rev BA January 2008 Rosemount 1153 Series D Rosemount 1153 Series D Alphalin Nuclear Pressure Transmitter INDUSTRY LEADING PERFORMANCE
- Qualified per IEEE Std 323-1974 and IEEE Std 344-1975
- 5.0 x 10 7 rads TID gamma radiation
- 7 g ZPA seismic
- 420 op (215.6 °C) steam temperature
- 0.25% accuracy
( Contents Introduction . . . . . . . . .. ..................... page 2 Transmitter Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... page 2 Operation .......................................................... page 2 Dimensional Drawings. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... page 3 Nuclear Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... page 4 Performance Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............ page 5 Functional Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... page 6 Physical Specifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .............. page 8 Ordering Information ................................................ page 11
~
§ ROSEMOUNT" ~
Nuclear EMERSON~ www.rosemountnuclear.com Process Management IPEC00269810
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 Results Driven by Proven Measurement Introduction The Rosemount 1153 Series D Alphaline Nuclear FIGURE 1. The 3 -Cell. Pressure Transmitters are designed for precision Rosemount 1153DD, HD, GD pressure measurements in nuclear applications which Lead require reliable performance and safety over a Wires ~----::~~~ specified qualified life. These transmitters were qualified per IEEE Std 323-1974 and IEEE Std Capacitor 344-1975 to radiation levels of 50 megarads TID Plates gamma radiation, seismic levels of 7 g, and for steam pressure performance. Stringent quality control during Sensing
-Diaphragm the manufacturing process includes traceability of pressure-retaining parts, special nuclear cleaning, Rigid and hydrostatic testing. '*-11---lnsulatlon Transmitter Description Silicone Oil Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitters are uniquely built for Class 1E nuclear service while retaining the basic design of the Rosemount 1151 Series that has become a standard of reliable service. Units are available in absolute (A),
gage {G), differential {D), and high-line differential (H) configurations, with up to eight pressure range Rosemount 1153AD options. Direct electronic sensing with the completely sealed 8 -Cell' capacitance sensing element (see Figure 1) Capacitor Plates eliminates mechanical force transfer and problems associated with shock and vibration. Installation and Sensing commissioning are simplified by the compact design Diaphragm and 2-wire system compatibility. Wiring terminals and electronics are in separate compartments, so the electronics remain sealed during installation. Silicone Oil Operation The completely sealed 8 -Cell capacitance sensing element is the key to the unequalled performance and reliability of the Rosemount 1153 Series D Pressure Transmitter. Process pressure is transmitted through an isolating diaphragm and silicone oil fill fluid to a Reference sensing diaphragm in the center of the o -Cell (see Figure 1). A reference pressure is transmitted in the same manner to the other side of the sensing diaphragm. Displacement of the sensing diaphragm, a maximum motion of 0.004 inches (0.1 mm), is proportional to the pressure differential across it. The position of the sensing diaphragm is detected by capacitor plates on both sides of the sensing diaphragm. Differential capacitance between the sensing diaphragm and the capacitor plates is converted electronically to a 2-wire, 4-20 mA de signaL 2 IPEC00269811
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D DIMENSIONAL DRAWINGS ROSEMOUNT 1153DD AND 1153HD 0.75 (19) Clearance
--1 L for Cover Removal I _ (Typical)
Nameplate (Remove for Zero and Span Adjust)--;-.. Transmitter Circuitry (this Sid Welded DrainNent Valve j ~2) (Optional L'j t i 3.4 /4-18 NPT Available) (86.4) 0.8 (20) to End of Mating Tubing ompression Fittings (2) Swagelok for 3/a-in. Tubing (Optional 1/4-18 NPT Available)
/s-in.
Mating Tubing ROSEMOUNT 1153AD AND 1153GD DETAIL A 4.72 Max. 0.75 (19) Clearance 1 (119.9) / /2-14 J;IPT L__for Cover Removal
~<~----~~ Condwt [--(Typical)
Connection (1 place) Nameplate (Remove for (228.6) Zero and Span Adjust) 7
/16-20 UNF (Typical)
Terminal Connections 1.63 (this Side) (41.3)
- J Wefded DrainNent Valve (1)
Low Side Vent
'j [ ~/4-18 34 Optional (GD only)
I 7/16-14 UNC (8S.4)
- NPT Available) (4 Places) 0.8 (20) to End of Mating Tubing NOTE Compression Fittings (1)
All dimensions are nominal in inches (millimeters). Swagelok for 3/s-in. Tubing (Optional 1/4-18 NPT Available) 3 IPEC00269812
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 SPECIFICATIONS Steam Pressure/Temperature: Accuracy within +/-(4.5% upper range limit+ 3.5% Nuclear Specifications span) during and after exposure to steam at the following temperatures and pressures: Qualified per IEEE Std 323-1974 and IEEE Std 344-1975 as stated in Rosemount Report 08300040. 420 OF {215.6 oc), 95 psig for 3 minutes 350 oF (176.6 "C), 120 psig for 7 minutes Output Code P 320 "F (160 "C), 70 psig for 8 hours 265 oF (129.4 "C), 24 psig for 67 hours Radiation: Accuracy within +/-6% of upper range limit during Range Code 0: +/-(6. 7% of upper range limit + and after exposure to 5.19 x 107 rads, total 3.5% of span). integrated dosage. Additional Radiation: Range Code 0: +/-8.2% of upper range limit After completion of the above tests, the transmitters were exposed to an additional Seismic: 5.5 X 107 rads TID. Accuracy within +/-0.5% of upper range limit during and after a disturbance defined by a required Performance: +/-(1.5% of upper range limit+ 1.0% response spectrum with a ZPA of ?g. span). Range Code 0: +/-0.75% of upper range limit Range Code 0: +/-(2.3% of upper range limit + 1.0% of span). Steam Pressure/Transmitter: Accuracy within +/-{4.5% upper range limit +3.5% Post DBE Operation: span) during and after exposure to steam at the Accuracy at reference conditions shall be within following temperatures and pressures: +/-3% of upper range limit (4.5% for Range Code 0} for one year following DBE. 420 OF (215.6 °C), 95 psig for 3 minutes 350 OF {176.6 oc), 85 psig for 7 minutes Both Output Codes 320 OF (160 oc), 60 psig for 3 hours 240 OF (115.5 oc), 27 psig for 21 hours Chemical Spray: 176 OF (80 °C), 3 psig for 30 days simulating one Composition is 0.28 molar boric acid, 0.064 molar year post-DBE operation. sodium thiosulfate, and sodium hydroxide as required to make an initial pH of 11.0 and a Range Code 0: +/-(6.7% of upper range limit+ subsequent pH ranging from 8.5 to 11.0. 3.5% of span). Chemical spray is sprayed at a rate of 0.25 Post DBE Operation ga1/min/ft2 . Accuracy at reference conditions shall be within Quality Assurance Program:
+/-1.5% of upper range limit (2.25% for Range In accordance with NQA-1, 10CFR50 Appendix Code 0) for one year following DBE. B, and ISO 9001:2000 Output Code R Nuclear Cleaning:
Radiation: To 1 ppm maximum chloride content. Accuracy within +/-{1.5% of upper range limit+ Hydrostatic Testing: 1.0% span) during and after exposure to 5.5 x To 150% of maximum working pressure or 2,000 1o7 rads, total integrated dosage. psi, (13.8 MPa), whichever is greater. Range Code 0: +/-{2.3% of upper range limit+ Traceability: 1.0% of span). In accordance with NQA-1 and 10CFR50 Seismic: Appendix B; chemical and physical material Accuracy within +/-0.5% of upper range limit during certification of pressure-retaining parts. and after disturbance defined by a required response spectrum with a ZPA of ?g. Range Code 0: +/-0.75% of upper range limit. 4 IPEC00269813
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D Qualified Life: Overpressure Effect Dependent on continuous ambient temperature at the installation site (see Figure 2). Replacement Rosemount 1153DD: of the amplifier and calibration circuit boards at Maximum zero shift after 2,000 psi (13.8 MPa) the end of their qualified life permits extension of overpressure: the transmitter qualified life to the module Range Code Overpressure Effect qualified life. Details of the test are in the 3,4 +/-0.25% of upper range limit Rosemount Report D8300040. 5 :;!:1.0% of upper range l.imit 6,7 :;!:3.0% of upper range limit FIGURE 2. Qualified Life vs. Ambient Temperature. 8 '* :;t6.0% of upper range limit 3 o.o - 1 l' -J Mod~l~ - 2o.o
- i "\.. !"\...,.._ Qualified _ Rosemount 1153HD t:lectromcs!N* '\, Life. Maximum zero shift after 3,000 psi (20.68 MPa)
Qualifi~d * :"- : iii' 100 L1fe , *. ' . (----- overpressure:
- a f-----1
~6 Rosemount 1153GD and 1153AD 80 90 100 110 120 130 140 150 Maximum zero shift after 2,000 psi (13.8 MPa)
Temperature (°F) overpressure: PERFORMANCE SPECIFICATIONS Based on zero-based ranges under reference conditions. Maximum zero shift after 4,500 psi (31.0 MPa) overpressure: Accuracy
+/-0.25% of calibrated span; includes combined effects of linearity, hysteresis, and repeatability.
Maximum zero shift after 6,000 psi (41.34 MPa) Dead Band overpressure: None Drift
+/-0.2% of upper range limit for 30 months (+/-0.3% of Static Pressure Zero Effect upper range limit for Range Code 0).
Rosemount 1153DD: Temperature Effect Per 1,000 psi (6.89 MPa): Per 100 OF (55.6 oc) ambient temperature change. Range Code Temperature Effect 3 +/-(1.5% of upper range limit+ 1.0% span) 4-9 +/-(0.75% of upper range limit+ 0.5% span) 0 +/-(1.13% of upper range limit+ 0.5% span) Rosemount 1153HD: Per 1,000 psi (6.89 MPa): 5 IPEC00269814
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 Static Pressure Span Effect Power Supply The effect is systematic and can be calibrated out for Load limits are as shown in Figure 3 and Figure 4. a particular pressure before installation. Correction uncertainty equals +/-0.5% of input reading/1 ,000 psi FIGURE 3. Output Code P (6.89 MPa). - r_____4- __2_o_m_A__ D_c___________, 2000 Power Supply Effect 1650*-- -------------------------- 1500 Less than 0.005% of output span per volt 1325 ------ Load Effect g: 1000 No load effect other than the change in the voltage ..,c II> supply to the transmitter ...."' Ill 500
'iii II>
Mounting Position Effect r:r:
""C 0 No span effect; zero shift of up to 1.5 inH20 (372 "'
0
-l 4 Pa), which can be calibrated out 13.5 Power Supply (V DC)
Response Time FIGURE 4. Output Code R Fixed time constant (63%) at 100 oF (37.8 "C) as follows: 4-20mADC 1825-r------------------------~ Range Code Response Time 1575--1000 - 3 2 seconds or less 4 0.5 seconds or less g: 5-9,0 0.2 seconds or less Ill 100 0 c Design Adjustable damping is available through a special N ....Ill"' Region
'iii 50 Option. II>
r:r:
"C 0
FUNCTIONAL SPECIFICATIONS "' 0
-l 0
12 ~ 45 Service 13.5 Power Supply (V DC) Liquid, gas, or vapor Span and Zero Output Continually adjustable externally 4-20 mAde Zero Elevation and Suppression Maximum zero elevation: 600% of calibrated span (400% of calibrated span for Range Code 0) Maximum zero suppression: 500% of calibrated span (300% of calibrated span for Range Code 0) Zero elevation and suppression must be such that neither the calibrated span nor the upper or lower range value exceeds 100% of the upper range limit. Temperature Limits Normal Operating Limits: 40 to 200 oF (4.4 to 93.3 °C) Qualified storage limits: -40 to 120 oF (-40 to 48.9 °C) 6 IPEC00269815
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D Humidity Limits Rosemount 1153HD: 0.5 psia to 3,000 psig (3.4 kPa abs to 20.7 MPa) 0-100% relative humidity (NEMA4X) maximum rated static pressure for operation Volumetric Displacement within specifications; overpressure limit is 3,000 psig (20.7 MPa) on either side without damage to Less than 0.01 in 3 (0.16 cm3) the transmitter Turn-On Time Overpressure Limits 2 seconds maximum. No warm-up required. Rosemount 1153GD and Rosemount 1153AD: Pressure Ranges Operates within specifications from 0.5 psia Rosemount 115300 and 1153HD: (3.4 kPa abs) to upper range limit. Overpressure Range Code Pressure Ranges limits without damage to the transmitter are: Range Code Overpressure Limit 3 0-5 to 0-30 inH20 (D units only) (0-1.24 to 0-7.46 kPa) 3-8 2,000 psig (13.8 MPa) 4 0-25 to 0-.150 inH20 (0-,6.22.to 0-37.3 kPa) 9 4,500 psig (31.0 MPa) 5 0-125 to 0-750 inH20 0 6,000 psig (41.34 MPa) (0-31.08 to 0-186.4 kPa) 6 0-17 to 0..,100 psi (0.,.0.12to o..,.0.69MPa} 7 0-50 to 0-300 psi (0-0.34 to 0-2.07 MPa) 8 0-170 to 0-1,000.psi (D units only)
*. (0-1.1Tto 0-,6.89 MPa) ..
Rosemount 1153GD and 1153AD Range Code Pressure Ranges 3 0-5 to 0-30 in H20 (G units only) (0-1.24 to 0-7.46 kPa} 4 0-25 to 0-150 inH20 (G Units Only) (0-6.22 to 0-37;3 kPa) 5 0-125 to 0-750 inH20 (0-31.08 to 0-186.4 kPa) 6 0-17 to 0-100 psi {0.,.0.12 to 0.,.0.69 MPa) 7 0-50 to 0-300 psi (0-0.34 to 0-2.07 MPa) 8 0-170 to 0-t,OOO psi (0-1.17to 0-,6.89 MPa) 9 0-500 to 0-3,000 psi (G units only) (0-3.45 to 0-20.68 MPa) 0 '* 0-1 ,OOOto 0-4,000 psi (G units only}
.. (0-,6.89 to 0-27.56 MPa)
Maximum Working Pressure Rosemount 115300 and 1153HD: Static pressure limit Rosemount 1153GD and 1153AD: Upper range limit Static Pressure and Overpressure Limits Rosemount 115300: 0.5 psia to 2,000 psig (3.4 kPa abs to 13.8 MPa) maximum rated static pressure for operation within specifications; overpressure limit is 2,000 psig (13.8 MPa) on either side without damage to the transmitter 7 IPEC00269816
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 PHYSICAL SPECIFICATIONS Flange Bolts and Nuts: Plated alloy steel, per ASTM A-540 Materials of Construction Electronics Housing: Isolating Diaphragms: 316 SST 316L SST Mounting Bracket: DrainNent Valves: 316L SST 316 SST Mounting Bolts (Bracket to Transmitter}: Process Flanges: SAE J429 Carbon steel, Grade 2 or Grade 5 CF-8M (cast version of 316 SST) Process Connections Process 0-rings: 3/a-in. Swagelok compression fitting, 316L SST 316 SST (1/4-18 NPT optional) Electronics Housing 0-rings: Ethylene propylene Electrical Connections 1
/2-14 NPT conduit with screw terminals Fill Fluid:
Silicone oil Weight 24lb (10.9 kg) including mounting bracket. FIGURE 5. Rosemount 1153 Series D Pressure Transmitter. Exploded view. Circuit Boards Cover Process Flange (Optional) o-Cell Sensing Module Process Flange (optional) 8 IPEC00269817
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D FIGURE 6. Electric Block Diagram Sensor~ Demodulator Current Detector b>--0 I O*cl~- I Current Limiter A~
~
+
Test ~
~Pl Signal Control I Voltage Regulator Reverse 1-- Amp.
Polarity
... VI
- Current Control Protection I
FIGURE 7. Transmitter Wiring Diagram
-----+
Power Supply
+ ~
0 Terminal Side (Cover Removed) 9 IPEC00269818
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 FIGURE 8. Transmitter Mounting Configurations Center of Gravity (Bracket Included) Center of 1.8 (45,7) 2.81 (71.4) rr I liP~ I 3/a-in. 2.81~ Bolts (4) --1>1--"*75 (69.9) (71.4) (Customer 10 (254) Minimum Supplied) 5 Clearance (127) MOUNTING BRACKET FOR ACCEPTABLE ALTERNATE PANEL MOUNT SHOWN IN MOUNTING PANEL MOUNTING TYPICAL MOUNTING HOLE PATTERN CONFIGURATION (BACK SIDE) NOTES
- 1. Orientation with respect to gravity is not critical.
- 2. Units can alternately be mounted with process connection adjacent to bracket.
- 3. All dimensions are nominal in inches (millimeters).
Standard Accessories Documentation All models are shipped with a mounting bracket. One Certification is provided for each Rosemount 1153 instruction manual is included with each shipment. Series D Pressure Transmitter for accuracy, special cleaning, hydrostatic testing, and traceability. Calibration Chemical and physical reports and identification of pressure retaining parts are on file at Rosemount Transmitters are factory calibrated to the customer's Nuclear Instruments, Inc. specified range. If calibration is not specified, transmitters are calibrated at maximum range. Calibration is at reference conditions (ambient temperature and pressure). Options Consult the N-Options Product Data Sheet 00813-0100-2655 or call Rosemount Nuclear Instruments, Inc. for special transmitter needs. Tagging The transmitter will be tagged, at no charge, in accordance with customer requirements (96 characters maximum}. All tags are SST. The standard tag is permanently attached to the transmitter. Standard tag character height is 0.125 in. (3.18 mm). A wire-on tag is available on request. 10 IPEC00269819
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D ORDERING INFORMATION
- Model Code D
H A Product Description Pressure Measurement Differential Pressure; 2,000 psig (13.8 MPa) Static Pressure Rating Differential Pressure; 3,000 psig (20.68 MPa) Static Pressure Rating Absolute Pressure G Gage Pressure 4 0-25 to 0-150 inH 2 0 0-25 to 0-150 inH 2 0 N/A 0-25 to 0-150 inH 2 0 (0-6.22 to 0-37.3 kPa) (0-6.22 to 0-37.3 kPa) (0-6.22 to 0-37.3 kPa) 5 0-125 to 0-750 inH 2 0 0-125 to 0-750 inH2 0 0-125 to 0-750 inH 2 0 0-125 to 0-750 inH 2 0 (0-31.08 to 0-186.4 kPa) (0-31.08 to 0-186.4 kPa) (0-31.08 to 0-186.4 kPa) (0-31.08 to 0-186.4 kPa) 6 0-17 to 0-100 psi 0-17 to 0-100 psi 0-17 to 0-100 psia 0-17 to 0-100 psi (0-0.12 to 0-0.69 MPa) (0-0.12 to 0-0.69 MPa) (0-0.12 to 0-0.69 MPa) (0-0.12 to 0-0.69 MPa) 7 0-50to psi 0-50 to 0-300 psia 0-50 to 0-300 psi (0-0.34 to MPa) (0-0.34 to 0-2.07 MPa) (0-0.34 to 0-2.07 MPa) 8 0-170 to 0-1,000 psia 0-170 to 0-1,000 psi (0-1.17 to 0-6.89 MPa) (0-1.17 to 0-6.89 MPa) 9 N/A N/A N/A 0-500 to 0-3,000 psi (0-3.45 to 0-20.68 MPa) 0 N/A N/A N/A 0-1,000 to 0-4,000 psi (0-6.89 to 0-27.56 MPa) A Welded . Swagelok Compression Fitting Process Connection and Welded DrainNent Valve s<2l 1/4-18 NPT Process Connection and Welded DrainNent Valve c< 2l 1/4-18 NPT Process Connection and Drain Hole (DrainNent Valve Not Included) D One Flange Option Code A and one Remote Seal E<2 l One Flange Option Code B and one Remote Seal F(2 ) One Flange Option Code C and one Remote Seal G Two Remote Seals H Welded 3/a-in. Swagelok Compression Fitting on Process Connection and DrainNent Connection J(2) Welded 3/a-in. Swage/ok Compression Fitting Process Connection and 114-18 NPT Drain Hole L One Flange Option Code H and one Remote Seal M(2) One Flange Option Code J and one Remote Seal Typical Model Number:1153 0 0 4 R A (1) The Rosemount 1153 Series D with the Output CodeR Electronics is a/so available with adjustable damping. Specify this option by adding "N0037" to the end of the complete model number. For example: 1153DD4RAN0037. (2) Customer assumes responsibility for qualifying connection interfaces on this option. Contact Rosemount Nuclear Instruments, Inc. for details. 11 IPEC00269820
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 The Emerson fogo is a trade mark and service mark of Emerson Electric Co. Rosemount, the Rosemount logotype, and A/ph aline are registered trademarks of Rosemount, Inc. 3-Ce/1 is a trademark of Rosemount, Inc. Swagefok is a registered trademark of Swagelok Co. Emerson Process Management Rosemount Nuclear Instruments, Inc. t!: RosemounttoNuclear
~legislation lnstuments, Inc. satisfies all obligations coming from 8200 Market Boulevard Chanhassen, MN 55317
( harmonize product requirements in the European Union. Tel (952) 949-5210 Fax (952) 949-5201 Copyright 2008 Rosemount Nuclear Instruments, Inc. http://www.rosemountnuclear.com 11111111111111111111111111111111111111111111111 00813-0100-4388, Rev BA
~11111111111111111111111111 ~111111111~11111 EMERSON~
Process Management IPEC00269821
\
I, I,
; ' ! I Bulletin 04L41B01-01E IPEC00269822
"'U m () 0 0 I\.) (j) vagdant (.0 The dear path Ia operatianol excellence (X) I\.) (..) Euolueo features tor Yti:aiJJr The evolution of the global standard in paperless recorders has reached the next stage
-the DAQSTA nON DXAdvanced series R4 (release 4). Its basic functions have been further enhanced with an expanded security function option providing FDA 21 CFR Part 11 compliance, making it ideal for a broadening range of applications, such as in pharmaceutical manufacturing.
- Up to 48 channels of inpul
- User can start/stop recording by balch. and create data files!
- Expandable to up 10 348 channels wllh lhe MW100 automatic connection function
- Arrange lhe display your way with a custom function!
- Review historical data with date and lime calendar searCh functions
- Supports the PROFIBUS-DP and EtherNei/IP protocols!
- Expanded Web and networking functions!
- Dust- and splash-proof front panel {IP65, NEMA4 compliant)
*Highly reliable 1ntemal memory wilh error-correction function
- Front panel door locK and login function vanety of tasks includ1ng analysis.
setllngs, acquisition DAQSTANDARO: Supports settings and data file analysis DAQStudlo: Builder software for custom displays DAQWORX: Integrated Data Acquisition Software Su!le DAQManager: Data management Software
llfyrt Op Standard-equipped internal memory greatly A USB flash drive can be used to transfer data to increased (to 400MB). Even longer recording your PC. The optional front panel USB port also durations, and multichannel recording. allows an external PC keyboard to be used with the DXAdvanced to facilitate setting and text entry. II i All DXAdvanced models include a CompactFiash drive. This function provides control of the input value Rugged and readily available CompactFiash cards (CF correction schedule. Following a predetermined cards) serve as the removable media, and are available schedule, DXAdvanced displays a message as optional accessories. Up to 2 GB CF card supported. prompting the user to perform input value correction. This is convenient, for example, in Nadcap* related heat treatment applications.
*Nadcap: National Aerospace and Defense Contractors Accreditation Program
"~.' !
r.rteliia r Calibration schedule setling Message to prompt calibration This function ensures that the CF card always retains the latest data when files are saved to it automatically. -\t. i'cc.l.! ;< When the CF card is full, the oldest files are deleted Reports can be created automatically using a to make room for the newest files. The media FIFO spreadsheet template created in ExceL Reports are function allows you to use the DX continuously for long created in Excel format, greatly reducing time and periods of time without having to change the CF card. effort spent on making spreadsheets. Overview of the Media FIFO Function date (\, o.ted File 1 File 2 Saved I. -
- Medium Automatic creation Excel report IPEC00269824
STANDARD SPECIFICATIONS Capacity: 400MB Maximum number of files can be saved: General Specifications 400 files
- Construction (total number of display data file and event data file)
Mounting: Flush panel mounting (on a vertical plane)
*Alarm Function Mounting may be inclined downward up to 30 Number of alarm levels: Up to four levels for each channel degrees from a horizontal plane.
Alarm types: High and low limits, differential high and low limits, Allowable Panel Thickness: 2 to 26 mm high and low rate-of-change limits and delay high Front Panel: Water and dust-proof and low (based on IEC529-IP65 and NEMA No.250 TYPE4*)
- Alarm annunciator function:
- Input Alarm display based on alarm sequence, and relay output operation.
Number of Inputs: Supported alarm sequences: 3 (ISA-A-4, ISA-A, ISA-M) DX1000: 2, 4, 6, 12 channels
- Event action function DX2000: 4, 8, 10, 20, 30, 40, 48 channels General: Particular action can be executed by particular event.
Measurement Interval: Number of event action: 40 actions can be set DX1002, DX1004, DX2004, DX2008:
*Security functions
- 125 ms, 250 ms, 25 ms (fast sampling mode*)
General: Login function or key lock function can be set for DX1006, DX1012, DX2010, DX2020, DX2030, DX2040, DX2048: each key operation or communication operation. 1 s (Not available when ND integration time is set to Key lock function: On/off and password can be set for each operation 100 ms), 2 s, 5 s, 125 ms (fast sampling mode*) key and FUNC operation.
*AID integration time is fixed to 1 67 ms in case of fast sampling mode_ Login function: User name and password to login can be set.
"'Please refer the Advanced security function option (/AS1)
Inputs: DCV (20, 60, 200 mV, 2, 6, 20, 50 V, 1-5 V) for the models with the /AS1 option TC (R, S, B, K, E, J, T, N, W, L, U, WRe)
*Clock RTD (Pt1 00, JPt1 00)
Clock: With calendar function (year of grace) Dl (Contact input, TTL level) Clock accuracy: +/-10 ppm, excluding a delay (of 1 second, maximum) DCA (With external shunt resistor attached) caused each time the power is turned on. Measurement accuracy D1splay Input Range DST function (summer/wintertime): when the inteqration time is 16.7 ms or more resolution The time at which the daylight savings time DCV 1-5 v +/-(0.05% of rdg+3 digits) 1 mV adjustment is automatically calculated and Thermocouple* K +/-(0.15% of rdg+O.rC) 0.1'C configured. Resistance Pt100 +/-(0.15% of rdg+0.3~C) 0 1'C *Communication Functions thermometer detector Connection: Ethernet (10BASE-T)
*Does not 1nclude the accuracy of reference JUnctiOn compensation Protocols: TCP, UDP, IP, ICMP, ARP, DHCP, HTTP, FTP,
*Display SMTP, SNTP, Modbus, DX private Display unit: E-mail infornn function:
DX1000: 5.5-inch TFT color LCD (320 x 240 pixels) FTP client function: DX2000: 10.4-inch TFT color LCD (640 x 480 pixels) Transferred data file, FTP server function, Web server function, SNTP client Display group: function, SNTP server function, DHCP client function, Modbus client function, Number of display: DX1 000: 10 groups, DX2000: 36 groups Modbus server function Number of assignable channels for one group: EtherNet/IP server Connects to EtherNet/IP networks as an Adapter DX1 000: 6 channels, DX2000: 10 channels (Server). Display color:
- Batch function Trend/Bargraph: Selectable from 24 colors General: Data display and data management with batch
Background:
White or black selectable name, text field function and batch comment function Trend display: are available. Trend display type: Vertical, horizontal, landscape, horizontal split or
- Power Supply circular* selectable Rated power supply: 100 to 240 VAC (automatic switching)
.. Circular display is only for OX2000 Allowable power supply voltage range:
Bargraph display* 90 to 132 or 180 to 264 VAC Direction: Vertical or horizontal selectable Rated power supply frequency: Digital indication: 50/60 Hz (automatic switching) Display renewal rate: 1s Power consumption: Overview display: DX1000. 60 VA (max., for 240 VAG power supply) Number of indication channels: DX2000: 100 VA (max., for 240 VAC power supply) Measuring values and alarm status of all channels Information display: Alarm summary, message summary, memory Normal Operating Conditions information, report information, relay status, Mod bus status Power voltage: 90 to 132 or 180 to 250 VAC Tag display: Power supply frequency: 50 Hz +/-2%, 60 Hz +/-2% Tag number and comment display Ambient temperature: 0 to 50 'C No. of displayable characters Ambient humidity: 20% to 80% RH (at 5 to 40 'C) Tag no :16 max Tag comment :32max SPECIFICATIONS OF OPTIONAL FUNCTIONS Displayable characters: Tag no.: Alphanumerics Tag comments: Alphanumerics, Japanese, and *Alarm Output Relays (/A1, /A2, /A3, /A4', /A5") Chinese An alarm signal is output from the rear panel as a relay contact signal. Messages: Number or output: Select from 2, 4, 6, 12" and 24" points Number of characters: 32 characters maximum
- Only for DX2000.
Number of messaged: 100 messages (including 10 free messages) *Serial Communication Interface (/C2, /C3) Data referencing function: Display the retrieved data (display data or event Connection: EIA RS-232 (/C2) or RS-422N485 (/C3) data) from internal or external memory. Protocols: DX private protocol, Modbus(master/slave) protocol
- Custom display function: Setting/measurement server function:
User can change display object (trend, numeric, and bar graphs, etc.) sizes Operation, setting or output of measurement data and attributes, and add objects freely to create screens. are available by DX private protocol. No. of screens: 28 (3 from internal memory, 25 from external media (CF)) Modbus communication: Reading or writing of measurement data on other Max no. of placeable display objects: instruments are available by Modbus protocol*
~ /M1 option or /MC1 option is required to read data from 134 (normal: 80, scale: 4, trend: 4, list: 4, graphic: 40, other instrument bitmap: 2)
- VGA Video Output (/D5)
- Data Saving Function External storage medium: Resolution: 640 x 480 pixels 0/GA)
Medium: CompactFiash memory card (CF card)
- Fail/Status Output (/F1)
Internal memory: The relay contact output on the rear panel indicates the occurrence of CPU Flash memory failure or selected status. Medium: Itt IPEC00269825
- Fail & Alarm Output Relays 22 points (/F2, only for DX2000) PROFIBUS-DP master devices can access the following internal data.
Combination of "Fail/States output function" and "Alarm output relays 22 Load measurement char.nel data points". Load MATH channel data
- Clamped Input Terminal Write communication input channel data Clamped input type) is for :nput terminal. Node address setting range: 0 to 125
- Desk Top Type (IH5[ ], IH5') Interface: PROFIBUS-DP-VO Srave Provides carrying handle and power cord. Transmission medium: 2 dedicated cables
"'/H5 is only for 24 VOC/AC powBr s~..ppiy model (JP1), and does not include power coCe Transmission speed/distance: 9.6 m to 12 Mbps/1 00 m
*Mathematical Functions Termination resistance: external termination resistance)
Used calculating data, :rends and digital values, and recording
- Advanced security function calcu:ated data assigned to Security and electronic record/signature functions have been added that are Chancel assignable to calculated data: compliant with the USA's FDA title 21 CFR Part 11.
DX1002, DX1004: 12 channels, DX1006, DX1012: 24 channels Data anti*tamperfunction:Settings and measured data are saved as encrypted DX2004, DX2008: Up to 12 channels binary files. DX2010, DX2020, DX2030, DX2040, DX2048: 60 channels Login function: Using the login function (user name, user and Operation: you can enter security settings on the General arithmetic operations, Statistical operations, Special operations, Conditional operation User level and number of users: Constant: Up to 60 constants (K01 to K60) System administrator: 5 users (all can be operated) Report functions: General user: 90 users Report type* Hourly, daily, hocriy +daily, daily +weekly and daily Electronic signature function:
+monthly After that has finished being recorded, Operation: Max. 4 types selectable from average, maximum, you can add levels of electronic signature.
minimum, Instantaneous and summation select a pass/fail, and enter comments
- Cu10, Cu25 RTD Input /3 isolated RTD (IN1) Audit Trail Function* The settings change log and the operation 'og when This option allows Cu10 Cu25 inputs to added to the standard input change was made are saved.
types. Password management function:
- 3 legs Isolated RTD Input (IN2*) Logins are verified by a Kerberos authentication server A, B, b legs are of isolated input type.
- Only forOXc006. OX1012, OX2010. DX202C, OX2030, DX2040 and DX2C48.
- Extended Input Types (1~3)
This option allows extra inputs types as below to be added to the standard DX1000 f'qle! NRA l $p;l;;rq Unit rnm input types. TC; Kp vsAu7Fe, PLATINEL, PR40-20, NiNiMo, W/Wre26, TypeN (AWG14) RTD: Pt25, Pt50, Ni100 (SAMA), Ni100 (DIN), Ni120, J263*B. Cu53, Cu100.
~
........ (approx inch)
EB3*~ Pt46, Pt200
- 24 VDCIAC Power Supply (IP1)
Rated power supply: 24 VDC or 24 VAC (50/60Hz) Allowable power supply voltage 21.6 to VDCIAC Max. power consumption: DX1000. 28 VA (24 VDC), 45 VA VAC (50160 Hz)) DX2000: 45 VA (24 VDC), 70 VA VAC (50/60Hz))
- Remote Control (iR 1)
This option allows eight functions to be controlled remotely by a contact input.
- 24 VDC transmitter power supply (ITPS2*, ITPS4, ITPS8*)
Output voltage: 22.8 to 25.2 VDC (rated load current) Rated output current* 4 to 20 coADC
* 'TPS2 is only for DX1000, /TPS8 *s only for DX20CO
- Easy text entry (IKB 1, IKB2) DX2000 Remote control terminal is available to operate tt,e OX.
Number of units that can be controlled: Max. 32 units by ID setting
- L.;SB interface (IUSB1)
USB interface specification: Based on Revt. 1, host function 2 ports (Front and rear panel) Keyboard: 104189 keyboard (US) based on USB HID Class Ver.1.1 External medium: USB ~ash drive (Some of the USB flash drive may not be supported by DXAdvanced.)
- Pulse input (iPM 1)
Pulse input option includes mathematical functions option (IM 1) and remote control option (IR 1) Number of inputs: 3 points (8 points are available in case of using remote in puis) Input format Photocoupler isolation common) Isolated power supply input terminal (approx. 5 V)
*Calibration correction function (ICC1)
Corrects the measurement value of each channel using segment linearizer approximation. Number of segment points: 2 to 16 Two brackets are used in the DX1000 and DX2000. They
- External input function (/MC1, only for DX2000) may used either on the left right or top and bottom. See Yokogawa's Digital input channels via communication are extended to input data from General Specification (GS 04L41 801-01 E) for information on panel cutting other instruments. dimensions for DX1000 vertical or horizontal attact;menls. Unless otherwise Number of external input channels: indicated, tolerance is +/-3% (or +/-0.3 mm for dimensions under 10 mm).
Up to 240 channels (channel number: 201 to 440) Daqstation and DXAdvanc.ed are registered trademark ofYoKogawa Electric Corpora1ion.
- Only for DX2010, DX2C20, DX2030, CX2040 and OX2048 i\1icrcscft MS, and V\1ndows are registered trademarks or traderr.arks of M1crosc:'i "Fast sampling mode is no: available w'"'en eKtemallnp:.rt option is equipped" Corporation ln the United S!ates and ot'ler countlies
- Multi batch funct:on (IBT2) Pe'"'.t!um are registered trademarks of Intel Corporation User can start/stop recording independently by batch, and create data files. Ethernet is a -registered trademark of Xerox Ccrporation.
No. of multibatches: DX1000: 2 to 6 (DX1006,DX1012 only) Modbus is a registered trademark of AEG Schneider Au~orr.at10'1 Inc. DX2000: 2 to 12 Other company names a:1d product names appearing i"'. m:s document are registered (DX201 O,DX2020 ,Dx2030,DX2040,DX2048 only} trademarks or trademarks of their respective holders.
- PROFIBUS-DP communication interface function (ICP1) PROFIBUS-DP is a registered trademarks of PROF13US User Organization EtherNeUIP is a registered trademarks ofODVA{Open OeviceNe! Vendor Association) .,
IPEC00269826
DX2000 Model code Suffix Opt1onal Description code code DX2004 4ch 125ms\F ast sam lina mode* 25ms DX2008 8ch 125ms1Fast samolino mode: 25ms' OX2010 10ch. 1 sfFast samothn mode: 125ms DX2020 20ch. 's'Fast sarnolinc .11oda* 125ms DX2030 30ch. 1 siF ast samol;nq moea* 125ms\ DX2040 40Ch, 1 s'Fast samol:nq mode: 125rrs DX2048 48ch. 1 s(Fast samoFnq mode: 125msl Internal memorv 3 4COM8 E xteft'al med'a -4 CF card (with media Disolav lar.auaae -2 Eno:is~- deaF_ DSTtsummerlwinter time OptiOr'JS /A1 Alarm oLt::1ut 2 oclnts *1
/,A.2 Alarm output 4 ooints ~1
~cutout 6 points '1 outout 12 points *1 outout24 points '1 '2 2 mterface "3 IC3 RS-422-A/485 interface '3 105 VGA outout
/F1 FAIUStatus octput '2 '4 IF2 FAIL+ Alarm oct*ut 22 points '1 '4 IH2 Clamped input tem1inal (detachable 1~5 .Deskto 0 _t~P~. (for/Fe~~~~fl. without power code, screw tvoii power '5 IH5 Desktop type '6
/M1 Mat~~emat:cal functions
~
Cu10.Cu25 RTD inoutf3 leo isolated R 1D 3 lea iso:ated RTD '7 Extended iQpiJt tvoe fPR40*20, Pt50, etc 24 VDCIAC power suoolv IR1 Remote control ffPS4 24 VDC transmitter ocwer suool 141oopsl "8 ffPSB 24VDC transmitter oower suoolv 18 looos *g IKB1 Easv text entrv with irl:Jut terminai '10'11 JKB2 Easv text entrv (w:thout ir.out terrr:inal *1 0 IL:SB1 :JSB interface Puse_inp~t (i~~~~~;~o':.~~'!' oie 1 iPMc central and ICC1 Caiibrat;on correction fLnction lMC1 cxterngl inout functlon "13
/BT2 f\~ultr*batch functions ~14 iCP1 PRO~IBUS-DP functions "3 IAS1 Advanced securitv fur,ct;ons APPLICATION SOFTWARE Model code Description OS I DXA12C JA' lSTANDARc VVindows 2000/XPN!s:a I DXA170 1 [)AQSjudio 1 V\lindows :XPM>;ta J DXA25C Windows XPNista ACI..t:;::>vr :::i Product Model code (oart number) Soecificatio;-,
Shunt resister 4' 5920 250!1+/-0.1% (for screw input terminal) 415921 1000+0.1% 415922 100+/-0.1% Shunt resister 438920 2500+/-0.1% OXAdvanced Removable C'lassis Model f j J** i O i / (I j"\J (for damped input term ina~) 438921 1OOQ+/-0.1 °t~ Removable Chassis Model featuring ~""fJ* ,,.. 438922 100+/-0.1% easy maintenance. ,,~--,,-. *.~ f*:<,.~
- t CF card adaoter 772090 772093 512MB
*This mod.el enebles you to pull the inner chassis out fro<n II ,r'A .
CF card 772094 1GB the case without having to remove the pov.Ier supply, *4!111!!:t comrnun!cation, and input wiring on the rear panel Mount:og bracket 899008X Door lock i<ev B8706FX Remote control terminal 438227 For IKB1. IK82 ontion Validation documents 438230 For IAS1 QRtion VigilantPfant is. Yokogawo 1s. ou1omatlon concept for safe, reliable~ and profitable v1gdant plant operations, VigilantPJant aims to enoble on ongoing state of Operational Excellence where plant personnel ore waichfvl ond attentive, well-informed, The cle<lr path to operational excellence and ready to take actions thot optimize plant and business performance. YOKOGAWA ELECTRIC CORPORATION Network Solutions Business DivJPhone: (81 )-422-52-7179, Fax: (81 )-422-52-6619 ~ letSOI. Online Sign up for our free e-mail newsletl~r E-mail: ns@cs.jp.yokogawa.com YOKOGAWA CORPORATION OF AMERICA Phone: 800-258-2552, Fax: (1 )-770-254-0928 YOKOGAWA EUROPE B.V. Phone: {31)-88-4641000, Fax: (31)-88-4641111 Vig-RS-4E YOKOGAWA ENGINEERING ASIA PTE. LTD. Phone: (65)-62419933, Fax: (65)-62412606 For.ted 1n Japan, 001(KPJ [Ed ostbJ IPEC00269827
ENTERGY Conceptual Design
~ ~;~.~~~~~~;: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -021 Rev. 0 Attachment 4 Cost Estimate IPEC00269828
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station EC #: SAMA IP2-021 PROJECT TITLE: Install Leak Monitoring 0CAPrTAL Oo&M ESTIMATOR: RCMT Instrumentation for ISLOCA Pathway Isolation Valves PROJECT CODE: TBD
~;;._L-;......;...........;.._ _ _.,~JOB LOCATION: Containment & Control Bldgs. ORIG. DATE: 06/25/2012 0 OUTAGE 0 NON-OUTAGE ORIGINATOR:
ESTIMATE TOTAL $4,607,051 REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F .R. Part 51, Entergy perfomned SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package responds to the issue identified in the NRC's staff review of SAMA IP2-021 and provides the technical resolution and associated costs required for implementation. For SAMA IP2-021, resolution is required to provide remote monitoring of any fluid leakage past the isolation valves in ISLOCA pathways. Prepared by: Approved by: Date: Date: IPEC00269829
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
- ESTIMATE LEVEL* EC #: SAMA IP2..021
[ ] [ Conceptual PROJECT TITLE: Install Leak Monitoring Instrumentation for ISLOCA Pathway lsolati ESTIMATOR: RCMT q;;r Preliminary JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD 0 Definitive ORIGINATOR: ORIG. DATE: 06/25/2012 Item Descriotion
- 1. This estimate assumes tnat this work witl requ1re ooth non-outage and outage conditions to complete.
2
- This estimate assumes that the non-outage work work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that the outage work will be completed in 2014 working (2) 10 hour shifts 6 days per week.
- 4. This estimate assumes that~oductivity loss due to radiation or hazardous conditions ..
- 5. This estimate assumes that contract craftspersons in lieu of station maintenance personnel.
- 6. This estimate assumes that uting of wiring from the pressure transmitter junction boxes to the external panel location such that no new containment penetrations will be required.
- 7. This estimate assumes that the Outage worK wi111nvo1ve radiological conditions requiring additional briefing times, dressout times and reduced production due to dressout requirements.
- 8. This estimate assumes that a comercial dedication effort will be required to qualifY the Yokogawa Recorder for use in this application.
- 9. This estimate assumes that the piping/tubing components and instrumentation will be Safety Class 1 and the Electrical components will be Safety Class Electrical.
- 10. This estimate is based on the project's current level of scope definition and is classified Class 5 as defined per the AACE International Cost Estimate Classification System (see Attachment 3, Reference 2).
11' Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 12.
~es as follows:
boundary - 20% B. Inside fence boundary - 30%
~ty-40%
50% IPEC00269830
Page 1 of 3 7/5/2012 4:55PM SAMA IP2-0211NSTALL LEAl< MONITORING INSTRUMENTATION FOR ISLOCA PATHWAY ISOLATION VALVES 06-25-12.xls B ..0 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2..021 PROJECT TITLE: Install Leak Monitoring Instrumentation for ISLOCA Pathway Isolation Valves JOB LOCATION: Containment & Control Bldgs. .., 0CAPJ:TAL PROJECT CODE TBD OO&M TAKEOFF: ESTIMATOR RCMT EST. STATUS: 0 OUTAGE 0 NON-<JUTAGE ORIGINATOR ORIG. DATE: 06125/2012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/fi!H PER UNIT I DOLLARS DOLLARS CONTRACT TOTAL$
'ESTIMATE LEVEL' ESTIMATE
SUMMARY
t-w t-('] Conceptual MANHOURS DOllARS Preliminary EO/ ENGINEERING
!fr Definitive 01 STUDY, DESIGN, & CLOSEOUT 280 $ 28,000 8,000 02 DESIGN ENGR CONST SUPPORT 80 $
General Notes: 03 WELDING ENGR EOI SUPPORT eo $ 8,000 ()4 SYS ENGR/ S-U ENGR 180 $ 18,000 05 PROJECT MANAGEMENT 600 $ 72,000 08 WORK MANAGEMENT $ - 07 TRAVEL & LIVING EXPENSES $ 08 ENGINEERING DCP ACCEPTANCE REVIEW 80 $ 8,000 CONTRACTEN~NEBWNG 09 DESIGN ENGR CONTRACT SUPPORT 1,500 $ 180,000 10 SUPL CONTRACT MODS ENGR - $ - 11 MODS PLAN & SCHED -CONTRACT 160 $ 16.000 12 FIELD ENGRS I PLANNERS 300 $ 36,000 MATERIALS I M/SC CONTRACTS 13 MATERIALS $ 457,354 14 OTHER CONTRACTS $ 27,528 CONTRACT CRAFT LABOR 15 SWEC CRAFT LABORM'ALKDOWN 4,841 $ 703,273 16 LOST TIME 484 $ 86,054 17 SWEC DISTRIBS $ 197,098 PLANT CRAFT LABOR 18 MECHMAINT. - $ - 19 ELECTMAINT $ - 20 I&C 240 $ 24,000 21 CSG - $ - M/SC EO/ SUPPORT 22 QUALITY CONTROL 180 $ 18,000 23 TRAINING 48 $ 5,760 24 CHEMISTRY $ 14,400 25 OPS I OPS SUPPORT 120 $ 26 HP/RP 120 $ 12,000 MISC CONTRACT SUPPORT 27 QUALITY CONTROL 200 $ 15,000 28 NDE $ - 29 HPIRP $ - 30 RADWASTE $ 31 NURSE $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ - 34 HOUSEKEEPING $ - 35 COMMERCIA - $ - 36 CGD CONTRACT - $ 25,000 37 DECONTAMINATION CONTACTOR - $ - 38 RBC'S $ - 39 SECURITY - Wackenhut $ - 40 FIRE WATCH (Rover) - $ 7,358 41 SAFETY 102 $ CONTINGENCY 42 CONTINGENCY $ 984 413 ESTIMATE SUBTOTAL 9,595 $2,953,238 SITE ENCUMBRANCE PREMIUM (20%) $ 590,648 Loaders (30%) $1,063,186 ESTIMATE TOTAL $4,607,051 NON OUTAGE WORK
~r matenal and stage tools and materials
- r:T:l 2 10.00 1.00 20 $ 123.32 $ 2,466 $ 2,466 $ 4,932 with recorder and power supply 2 40.00 1.00 80 $12B2 $ 30,000 $ 9,866 $ 39,866
- 3. Run conduit and support as required to area of containment penetration.
Prefabricate new spoolivalvelcap assemblies (9 1 LT EL 2 40.00 1,00 80 $ 123.32 $ - $ 9,866 $ 9,866 4. sub assemblies). 9 LT PF 2 25.00 1,00 450 $ 120.71 $ 150,000 $ 54,320 $ 204,320
- 5. Pertorm v1sual and LP examtnetlon on sOCket welds on new spool/valve assemblies 9 LT NM 1 16.()J 100 144 $ 87.00 $ $ - $ 12,528 $ 12,528 U\ lAI>t: W JKI\
1 Gather and stage tools and materials, Perform 1 LT PF 2 10.000 1.70 34 $ 120.71 $ $ 6,977 $ 6,977 walkdown and briefing. 1 LT EL 2 10.000 1.70 34 $ 123.32 $ $ 7,128 $ 7,128 2 Stage, erect & modify scaffolding as required 1 LT CP 2 80.00 no 272 $ 96.00 $ - $ 44,390 $ 44,390 3 Stage, erect & modify scaffolding as required 1 LT LB 1 80.00 uo 136 $ 78.65 $ - $ 18,184 $ 18,184
- 4. Remove existing cap and install new 8 EA PF 2 10.000 1.70 272 $ 120,71 $ - $ 55,816 $ 55,816
- 5. Mount new transmiter, valve manffold and support 9 EA PF 2 mooo 1.70 308 $ 120.71 $ 225,000 $ 62,793 $ 287,793 6, and support new tubing balwaen valve 8 EA PF 2 15.000 1,70 408 $ 120.71 $ 10,000 $ 93,724 $ 93,724
- 7. ew sockolet to 14" existing pipe 1 EA PF 2 nooo 1.70 41 $ 120.71 $ - $ 8,413 $ 8,413
- 8. Prefabrlcated piping/valve sub assemblies 1 EA PF 2 10.000 1.70 34 $ 120.71 $ - $ 6,977 $ 6,977 to socklet. 1 EA PF 2 15.000 1.70 51 $ 120.71 $ - $ 10,466 $ 10,466
- 9. Route and support new tubing balwaen valve $ .
IPEC00269831
Page 2 of 3 71512012 4:55 PM SAMA IP2.021 INSTALL LEAK MONITORING INSTRUMENTATION FOR ISLOCA PATHWAY ISOLATION VALVES Q6.2S.12,xl$ El .0 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2~21 EST, STATUS' 12JoUTAGE I]JNON-oUTAGE I PROJECT TITLE: Install Leak Monrtoring Instrumentation for ISLOCA Pathway Isolation Valves JOB LOCATION: Containment & Control Bldgs, 12JCAP!TAL PROJECT CODE: TBD ORIGINATOR: OO&M TAKEOFF ESTIMATOR: RCMT ORIG. DATE: 06/2512012 MANHOURS MATERIAL$ MATERIAL LABOR SUB* ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ m NDE containment welds 36 EA NM 1 1.000 1.70 61 $ 87,00 $ $ 9,022 $ 9,022 11' Support testing as requested 1 LT PF 2 10.000 1.70 34 $ 120,71 $ - $ 6,977 $ 6,977 12, Mount Hoffman boxes in containment 2 EA EL 2 6.000 1.70 41 $ 123,32 $ . $ 8,595 $ 8,595 13, Route & Support Conduit from each Transmitter 1n containment to containment Hoffman Enclosure. 350 LF EL 2 0 2 214 123 $ 2.000 26390 $ 28,390 14 Pull eable from each transmitter to Hollman boxes 2 LT EL 2 40.00 1.70 272 $ 123.32 $ 3,000 $ 33,543 $ 36,543 Pull eable from 2 Containment boxes to external 15, 1 LT EL Hoffman Panel and enclosure and terminate 2 60.00 170 204 $ 123.32 $ 4,000 $ 25,157 $ 29,157 16, Provide testing as required 1 LT OP 2 80.00 1.70 272 $ 100.00 $ 5,000 $ 27,200 $ 32,200 17, Assist with testing as required 1 LT EL 2 60.00 20,00 170 204 $ 123.32 123.32
$ - $ 25,157 8,386 25.157 8,386 18 Dismantle scaffolding to storage 1 LT EL 2 1.70 68 $ $
- 19. Dismantle scaffolding to storage 1 LT CP 2 40.00 1.70 136 $ 96.00 $ . $ 22,195 $ 22,195
- 22. Cleanup and restore area 1 LT LB 1 40.00 1.70 68 $ 78,65 $ $ 9,092 $ 9,092 23 Cleanup and restore area 1 LT EL 4 10,00 1.70 68 $ 123.32 $ $ 8,386 $ 8,386 1 LT PF 4 10.00 1.70 68 $ 120.71 $ . $ 8,208 $ 8,208 PAINTING & TOUCH-UP REQUIREMENTS $
- 1. PAINTING & TOUCH-UP PT $ . $ $
- 2. PAINTING & TOUCH-UP PT $ $ . $
FIRE WATCH I BOTTLEWATCH REQUIREMENTS $ -
- 1. CRAFT SUPPORT FOR FIRE WATCH 2 LT FW 1 80.00 1.00 160 $ 53.60 $ - $ 8,576 $ 8,576
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW $
MISC SUB.CONTRACT $ 1' MISC SUB-CONTRACT Commercial Grade 1 LT NM $ - $ 25,000 $ 25,000 ISUtiiUIALCKAI"I & 4,L<SL M,t>LO li>1,UI ,Lt>'l
"' 4;;1,'1b0 "' t>U<>,;<
- 1. CONSTRUCTION SUPPORT (8% OF LABOR$) 1 LT 339 $ 143.73 $ - $ 48.724 $ 48,724 SUBTOTAL 4,571 $ 431,468 $ 656,994 $ 37,528 $1,125,988
- RELATED COSTS
- L WALKDOWN ALLOWANCE 1 LT EL 20 $ 123,32 $ - $ 2,468 $ 2,468
- 2. WALKDOWN ALLOWANCE 1 LT PF 30 $ 120.71 $ - $ 3,621 $ 3,621
- 3. WORK PACKAGE REVIEW 1 LT EL 30 $ 123.32 $ $ 3,700 $ 3,700 4 WORK PACKAGE REVIEW 1 LT PF 30 $ 120.71 $ . $ 3,621 $ 3,621
- 5. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 160 $ 123,32 $ - $ 19,731 $
19,731 65,699
- 6. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 65,699 7, CRAFT IN PROCESSING (20%) $ 131,399 $ 131,399
- e. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 13,140 $ 13,140 (112 day training, or- 2%)
SUBTOTAL 4,841 $ 431,468 $ 900,371 $ 37,526 $1,369,365 PLANT SCOPE 1, MECH MAINTENANCE PL - $ . $ . $ PL $ . $ $ SUBTOTAL MECH MAINT. $ - $ - $ $ . 1 ELECT MAINTENANCE EL $ $ . $ - Pl . $ . $ . $ . SUBTOTAL ELECT. MAINT. $ . $ . $ . $ - 1, t&t; (Uctv. <.;aiJQratlon ana Matntenanee Procedures 1 PL 2 120.00 1.00 240 $ 100.00 $ . $ 24,000 $ 24,000
- LT PL $ - $ $ .
SUBTOTAL I&C MAINT. 240 $ - $ 24,000 $ . $ 24,000 1' CSG 1 PL . $ $ $ PL - $ $ $ . SUBTOTAL CSG MAINT. - $ - $ $ - $ - SUBTOTAL PLANT 240 $ . $ 24,000 $ - $ 24,000 SUBTOTAL CRAFT/PLANT 5,081 $ 431,468 $ 924,371 $ 37,528 $1,393,365 IPEC00269832
Page 3 or3 71512012 4:55PM SAMA IP2*0211NSTALL LEAK MONITORING INSTRUMENTATION FOR ISLOCA PATHWAY iSOLATION VALVES 06-25-12.xla El -0 INDIAN POINT IMPLEMENT AT ION ESTIMATE WORK SHEET EC #: SAMA IP2-021 I PROJECT TITLE: Install Leak Monitonng Instrumentation for ISLOCA Pathway Isolation Valves JOB LOCATION: Containment & Control Bldgs. (2] CAPITAL PROJECT CODE: TBD OO&M TAKEOFF. ESTIMATOR: RCMT EST. STATUS (2] OUTAGE (2] NON.ouTAGE ORIGINATOR: ORIG. DATE: 0612512012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ IMPLEMENTAnON SUPPORT EO/
- 1. WELDING ENGINEERING 1 LT NM 1 60.00 1.00 eo $ 100.00 $ 6,000 $ 6,000
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 60.00 1.00 eo $ 100.00 $ 6.000 $ 8,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 4. SYSTEMS ENGINEERING - ELECTRICAL 1 LT NM 1 40.00 100 40 $ 100.00 $ 4,000 $ 4,000
- 5. SYSTEMS EINGINEERING - INSTR & CONTROL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6.000 $ 6,000
- 6. SYSTEMS ENGINEERING - CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 600.00 1.00 600 $ 120.00 $ 72,000 $ 72,000
- 6. TRAINING OPS STAFF 12 LT NM 1 4.00 1.00 48 $ 120.00 $ 5,760 $ 5,760
- 9. QA I QC VERIFICATION 1 LT NM 1 180.00 1.00 180 $ 100.00 $ 16,000 $ 18,000
- 10. CHEMISTRY 1 LT NM $ - $
$ 12,000
- 11. HP I RPI ALARA 1 LT NM 1 120.00 1.00 120 $ 100.00 $ 12,000
- 12. WORK MANAGEMENT $ - $
13 OPS I OPS PROCEDURE SUPPORT AND DEVELOPMENT 1 LT NM 1 120.00 1.00 120 $ 120.00 $ 14,400 $ 14,400
- 14. TRAVEL & LIVING EXPENSES 1 LT $ - $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING - SWEC (lncl Per Diem) 1 LT NM $ - $ -
2. MODS PLANNING & SCH.- SWEC (InC! Per Diem) 1 LT NM 1 160.00 1.00 160 $ 100.00 $ 16,000 $ 16,000
- 3. FIELD ENGRSIPLAN- SWEC(Inol Per Diem) 1 LT NM 1 300.00 1.00 300 $ 120.00 $ 36,000 $ 36.000
- 4. QA I QC VERIFICATION 1 LT NM 1 200.00 1.00 200 $ 75.00 $ 15,000 $ 15,000 $ 30,000
- 5. NDE 1 LT NM - $ - $
- 6. HPIRP 1 LT NM $ - $
- 7. RADWASTE 1 LT NM -
- 8. NURSE 1 LT NM -
- 9. ELEVATOR CONTRACTOR 1 LT NM -
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM -
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM -
- 13. VENDOR STOCKING 1 LT NM -
- 14. DECONTAMINATION CONTRACTOR 1 LT NM -
- 15. RBC's 1 LT NM -
- 16. SECURfTY 1 LT sec --
17. 18. FIREWATCH {Rover) SAFETY(2%) 1 1 LT LT NM NM 102 $ 72.14 7,358 7,358 19 LOST TIME (10%) 1 LT 484 $ 181.93 $ 88,054 $ 88,054 SUBTOTAL CRAFT/NON-MANUAL 7,735 $ 431,466 $ 1 242,943 $ 52,528 $1,726,937 FREIGHT SALES TAX & CONSUMABLE$ (6%)
~
- 1. $ 25,888 SUBTOTAL INSTALLAnON COST ,135 $1,242,943 $ 52,528 $1,752,825
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6,000 $ 6,000
- 2. DESIGN ENGINEERING -ELECTRICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 3. DESIGN ENGINEERING - INSTR. & CONTROL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ a,ooo $ 8,000
- 4. DESIGN ENGINEERING- CIVIL/STRUCTURAL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6,000 $ 6,000
- 5. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,500.00 1.00 1,500 $ 120.00 $ 180,000 $ 180,000
- 6. DESIGN ENG. DCP ACCEPTANCE REVIEW 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8000 $ 8000 SUBTOTAL DESIGN COST 1,860 $ 36,000 $ 180,000 $ 216,000 SUBTOTAL INSTALLAnON & DESIGN COST 9,595 $ 457,354 $ 1.278,943 $ 232,528 $1,968,825
- 1. CONTINGENCY ( 50%) $ 984,413 ESTIMATE SUBTOTAL 9,595 $2,953,238 IPEC00269833
ENTERGY Conceptual Design
~ ~:~"~'~~~~~';": Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-022 Add Redundant and Diverse Limit Switches to each Containment Isolation Valve Prepared ~p! f!.._ //1 Approved by:
//~ /!4~~. !
/
""**"'-~-----~--~
//
Date: q. ~ o- 2 e IZ Date: Page 1 of8 IPEC00269834
ENTERGY Conceptual Design
~ ~~~.~~,~~~2~,~.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST- Mechanical 8.0 PRELIMINARY MATERIAL LIST- Electrical Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of8 IPEC00269835
ENTERGY Conceptual Design
~ ~~~~~,~~~2!!,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-022:
Add Redundant and Diverse limit Switches to each Containment Isolation Valve
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-022 in accordance with Entergy design engineering practices. For SAMA IP2-022, resolution is required for remotely monitoring the open-close position of isolation valves in the ISLOCA pathways in containment. This package will install additional position switches on existing valves where possible or replace any existing valves that can't be modified with new ones that have position capability. This package will also provide for the valve's position to be monitored remotely outside of containment. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC} development and implementation at the Station. Page 3 of8 IPEC00269836
ENTERGY Conceptual Design
~ T.~~~'~'~E:,~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 3.0 EXISTING CONDITIONS In containment, the pathways of the Safety Injection (SI) System piping need protection against potential leaks of liquid from the interfacing Reactor Cooling System (RCS) and Auxiliary Cooling System (ACS) piping. There are 22 check valves and 2 motor operated valves (MOV) installed in the Sl piping that interface with these systems to provide this isolation.
The effectiveness of each check valve's normally closed blocking function and the MOV's operated closed position needs to be monitored to ensure isolation is maintained from these interfacing systems. A limit switch added to each valve for monitoring status will enable its position to be transmitted to a remote location outside containment. The switch to be added for the MOVs position indication would be redundant to existing switches already installed and used for the open and close operation of the valve. In the case of the check valves, further investigation has determined that these paths do not have existing limit switches on the check valves so the proposed change will be to upgrade the valves with position monitoring capability. 4.0 DESIGN CONSIDERATIONS Check Valves The modification being proposed can be implemented in a couple of ways; by modifying the existing valves in place or by removing the existing valves and installing new ones. Given the age of the currently installed valves, their modification could prove to be very difficult, if not unfeasible. Access to the installed valves for machining could be a problem. Performing any retrofit machining requirements by adding some type of positioning device would be difficult and time consuming. Testing in place versus shop bench testing would be a challenge. ALARA concerns and the need to ensure the functional operation of the valve pose further challenges. In view of these challenges, and also the availability of check valves with the position indication feature provided, there is no substantial advantage to retrofitting the existing valves. Accordingly, removing the existing valves and replacing them with new ones that transmit their position would be the most effective solution. Page 4 of8 IPEC00269837
ENTERGY Conceptual Design
~ ~~~~.~.~~~~,:: Indian Point Nuclear Station Unit 2 Package SAMA I P2 -022 Rev. 0 MOVs Traditionally, position/limit switches have been the most effective and efficient means to monitor the physical orientation of a mechanical hardware item. For years, Motor Operated Valves (MOVs) installed in nuclear power plants have been equipped with mechanically operated limit switches that are relied upon to transmit both intermediate and open-close positions. The operating requirement being addressed in this SAMA, for both types of valves, is no exception and is a candidate for this application.
As discussed above, using position indication switches with MOVs is a standard application used in the nuclear industry. This package will install the two existing MOVs with position switches that provide open-close monitoring. Remote Position Monitoring Wiring from position switches provided with the check valves and MOVs will need to be connected and routed to an "off-normal' indication display panel located in a user-friendly environment in an area outside containment 5.0 CONFIRMATION OF DESIGN Check Valves Based on the emphasis provided in the design considerations above, this package will remove the existing valves and provide and install new valves, each of which will have capability to transmit their open-close status for monitoring. MOVs Installation of a position indication switch on each of the existing MOVs will allow for remote monitoring of each valve's open-close status.
- 6. RECOMMENDED SOLUTION
- 1. Check Valves For each of the existing check valves listed in Attachment 2, Figure 1, perform the following mechanical operation:
- Cut the existing piping and remove the old valve
- Weld the new "open-close indication" check valves in place of the removed valves.
Page 5 of8 IPEC00269838
ENTERGY Conceptual Design
~ ~~:~~,~~!: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0
- 2. MOVs For each of the two existing MOVs listed in Attachment 2, Figure 1, perform the following:
- Install the "open-close status" position indication switch on the valve's actuator section.
- 3. Remote Position Monitoring Install a new panel outside containment, in the Control Building at Elevation 33'-
0", that will provide open-close indicating lamp status of each ISLOCA pathway valve listed in Attachment 2, Table 1.
- 4. Conduit and Wiring A Valves
- Route and support conduit from each valve to the two junction boxes fitted with terminal blocks located in containment.
- Route and support a single conduit from each junction box, via containment penetration, to the new ISLOCA status monitoring panel outside containment.
- Install and connect wiring from the valve switches to the new junction boxes.
- Install and connect wiring from the junction boxes to the new ISLOCA status monitoring panel.
B. Remote Position Monitor Panel
- Route and connect lamp power, from a source to be determined based on indicating lamp type, to the new monitor panel.
- 5. Inside containment, install supports for conduit and junction boxes as required.
- 6. Provide procedures and training to operate, test, and perform maintenance on the components of the newly installed system.
Page 6 of8 IPEC00269839
ENTERGY Conceptual Design
~ ::~~'~'~2:,:.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 7.0 PRELIMINARY MATERIAL LIST- Mechanical Item Description Quantity
- 1. 2 inch Check Valve (swing check or similar) 1500# pressure class, 10 ASME Section Ill scope of supply, (Spec, Code Year and Addenda TBD).
With integral (external) position indicator and remote monitoring capability (via use of IEEE qualified limit switches). Stainless steel materials and proprietary disc design with dual seating surfaces (Stellite or Norem and resilient seating material). Mfr: FLOWSERVE, or equal (estimated price $35,000 to $45,000 each)
- 2. 6 inch Swing Check Valve, 1500# pressure class, 4 ASME Section Ill scope of supply, (Spec, Code Year and Addenda TBD).
With integral (external) position indicator and remote monitoring capability (via use of IEEE qualified limit switches). Stainless steel materials and proprietary disc design with dual seating surfaces (Stellite or Norem and resilient seating material). Mfr: FLOWSERVE, or equal (estimated price $70,000 to $80,000 each)
- 3. 10 inch Swing Check Valve, 1500# pressure class, g*
ASME Section Ill scope of supply, (Spec, Code Year and Addenda TBD). With integral (external) position indicator and remote monitoring capability (via use of IEEE qualified limit switches). Stainless steel materials and proprietary disc design with dual seating surfaces (Stellite or Norem and resilient seating material). Mfr: FLOWSERVE, or equal (estimated price $90,000 to $100,000 each)
*Note: One valve required for qualification testing.
- 4. 2 inch S.S. Schedule 160 seamless pipe, A376 Grade, TP316 20 feet
- 5. 6 inch S.S. Schedule 160 seamless pipe, A376 Grade, TP316 20 feet
- 6. 10 inch S.S. Schedule 160 seamless pipe, A376 Grade, TP316 20 feet Page 7 of8 IPEC00269840
ENTERGY Conceptual Design
~ ~~~~,~~2,~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 8.0 PRELIMINARY MATERIAL LIST - Electrical 1 MOV Actuator Limit Switch Kits 2
- 2. Hoffman junction box with terminal blocks 2
- 3. Hoffman Wall mounted panel and enclosure, with terminal blocks and indicator lamps, 36" x 36" x 8" deep 1
- 4. 1" Conduit 800 feet
- 5. 2" Conduit 400 feet
- 6. 2c #14 cable 7000 feet Page 8 of8 IPEC00269841
ENTERGY Conceptual Design
~ ~~~~.~,~~!:,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269842
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process A TIACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. L Engineering Change No.: Rev. No.: .K"'
' Q ~
Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmQact Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settinqs chanqes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve anv I&C desiqn or settinqs chanqes or activities?
Mechanical Design Engineering .YES 0NO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications. Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES ~NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269843
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC~115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potentiallm(!act ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room. and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97/ PAM (Post Accident Monitoring) .YES DNO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES !krNo
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program .YES DNO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00269844
*-=-Entergy NUCLEAR MANAGEMENT MANUAl QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 3 OF6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmeact Computer Support and Software DYES r&rNo
. Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA}?
Chemistry and Environmental Impact DYES !XfNo
. Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES ~NO
. Does the proposed activity impact or involve any changes to the RP program?
. Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
. Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
. Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
. Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
. Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallmeact ASME Containment In-service Inspection (IWE /IWL) Program DYES f::i NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program .YES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269845
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 99 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F 6 PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmgact ASME In-service Inspection (lSI) Program .YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program .YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES fXI NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES ~NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES fXI NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functionaltesting of circuit breaker, relay or electrical equipment?
IPEC00269846
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallm~act Flow Accelerated Corrosion (FAC) Program DYES 18fNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES f8:1 NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES ~NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES IXfNO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification {EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES DII NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES TiJ NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES 1l! NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269847
~Entergy NUCLEAR MANAGEMENT QUALITY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Welding Program .YES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program DYES [&f NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES !i1 NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES ~NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES !JfNO IPEC00269848
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit2 SAMA IP2 -022 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Table 1: Affected Valves
- 2. Figure 1, Sheet 1 - A235296: Safety Injection System Flow Diagram (partial)
- 3. Figure 1, Sheet 2- A235296: Safety Injection System Flow Diagram (partial)
- 4. Figure 1, Sheet 3- A235296: Safety Injection System Flow Diagram (partial)
- 5. Figure 1, Sheet 4- A235296: Safety Injection System Flow Diagram (partial)
IPEC00269849
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 2 SAMA IP2 -22 Rev. 0 Size Tag No. Type Manufacturer Model# 2" 857A Clamp Seal Check CONVAL INC MDL-2C3-316 8578 857C 857D 857F 857G 857H 857J 857K 857M 6" 838A Swing Check VELANVALVE B14-3114B-13M 8388 CORP 838C 838D 10" 895A Swing Check ANCHOR DARLING S3502-SC 8958 VALVE 895C 895D 10" 897A Swing Check ANCHOR DARLING S350W-SC 8978 VALVE 897C 897D 14" 730 Gate-MOV COPES VULCAN UNK-VLV-2157-001 14" 731 Gate-MOV COPES VULCAN 1-133641 TABLE 1 AFFECTED VALVES IPEC00269850
1 Conceptual Design 1 *., SA::c~~~~02._2___,j_R_ev~O- ; LOQD 2! COLD LEG OF iO"-SI-250lR i 0 LOOP 22 COLO LEG o,c
- z: *~
LOOP 23 COLD LEG DF R.C.S.~
~
t-zQ f u cr e a t;;) (\J I u 0: t N
.I FIGURE 1 (SHEET 1)
I :,..'T' ,.. FLOv,.r DLA.GRAJ-1 I I;:,. Ll:::.. . . *.. *... *. . I
- S** ...*c-.r:.ry 'N'.l=.r
. .. 'l~ \...,.. . .. ; , "\,..,d.. .. J -...
_\_~*- ,ON. 1*. svc:.TEM
~ ....... } """" ~
l- UFSAR FIGURE NO. IPEC00269851
ENTERGY Conceptual Design
~ ~~,~~,~~'~'~\~},~,~ indian Point Nuclear Station Unit 2 Package SAMA IP2-022 l*-~----
tt I* TO LOOP 23 (932;-F-2738) t I 856F FIGURE 1 (SHEET 2) l! ~""T' .. ,... - I ,L Ll:..t . -*o'*'
.FL. Jl';
!"'j,I*A*si':'*I*H 1.-i ' l:'lt'\1';
f SAFETY .*.INJECTION SYSTEM IPEC00269852
; ENTERGY Conceptual Destgn R Technoloqi~'; Llnd1an Point Nuclear Stat1on Package 01 1 1
" '"" Untt 2 : SAMA IP2-022 Rev. 0 j l~--- ~ ~~-- -----~~j ______ ----'-- ~--------~
ITEM: ACCUM. 22 22AT FIGURE 1 (SHEET 3) 1 TITLE, FLOW DIAGRJ.\N IPEC00269853
Conceptual Design Package SAMA IP2-022 r ACCUMULATOR :3 i ---- TANK N0.23 ITEM:
.-,I *---*
ACCIJ1v1. 23 ITEM~ ACCUM. 24 I 23AT ~4AT _____-,-Jl V:\Entergy - l ~* r RCS i ____ SIS '":.
/
l " P.csim)
-~l FIGURE 1 (SHEET 4)
~ TITL;::*
- FLOW DLA.GRAM . .
I .*SAFETY INJECTION SYSTEM . UFSAR F!GURC N 0. IPEC00269854
ENTERGY Conceptual Design
~ ~~~~,~~~2:,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. Existing CONVAL ClampSeal Check Valve (attached here)
- 4. Existing VELAN Swing Check Valve (attached here)
- 5. Existing ANCHOR/DARLING Swing Check Valve (attached here)
- 6. Existing MOV Gate Valves 730 and 731 -Vendor Drawing 8259680 (attached here)
- 7. Typical Swing Check Style Valve Size 3 (attached here)
- 8. Typical Swing Check Style Valve Size 8 (attached here)
IPEC00269855
Conval Clampseal Check Valves are designed for demanding high-pressure applications where light weight and compact size are required. Al05,F22,F316, 316L Monelrt,~ 400, lconel'600, optional DESIGN FEATURES Clampseal Check Valves feature the exclusive The reliability of the Clampseal Check Valve is pressure seal bonnet which permits ready enhanced by use of the electron beam process access for maintenance, while ensuring a for welding the cast stellite seat into the body. positive pressure-actuated body to bonnet seal By using the inline maintenance tools under all operating conditions. available, long valve lite can be assured. The valve is comprised of five assemblies, with the piston and spring being the only moving parts. The piston utilizes two guide rings, and the spring is lnconel Xfor smooth operatiOn in any position at temperatures up to 1000*F. ISO 9001 certified since September 11, 1992 World Headquarters: 265 Field Road P.O. Box 1049, Somers, CT 06071-1049 USA Phone (860) 749-0761 Fax (860) 763-3557 e-mail: sales@Conval.com www.Conval.com Convai's policy is one of continuous development and improvement. Every effort is made to produce up-to-date literature but this catalog should not be regarded as an mfallible guide to current specrtrcations and does not form part ol any contract Con val reserves the right to make product improvements and changes wrthout prior notice IPEC00269856
BOLTED COVER Y£LAN SWING CHECKVALVES CARBON, ALLOY OR STAINLESS STEEL ASME CLASSES 150-900, 2'1* -24" (65-600 mm) ASME CLASS 1500, 2'/, -16" (65-400 mm) STANDARD MATERIALS {1) Other materials available. (2) Stellited. t:Allr(QNif[)f.i!tf!ett!Jsn*h~onta!Ji~*~~f!tiltions FLOW COEFFICIENTS Cv
- see pg.$., 50~51, t:ir cOfltactVelan Engineering; Flange dimensions are in accordance with ASME 816.5.
Flanges are welded on. DIMENSIONS - BUTT WELD END
- Stronger, leakproof bolted body bonnet joint. (See page 11.)
- No penetration of hinge pin to outside eliminates pin seal leak-age and provides in-line service.
- Compact cage unit.
All moving parts are attached to the carrier and can be removed easily for service.
- Forged seat/disc* is Stellited, ground and lapped to a mirror finish for maximum erosion resistance and long service life.
It is seal-welded to the body.
- Disc can partially rotate for tight shutoff. In the fully open position, it rests against a stop.
e Stellite bearings for hinge pin.
- Easy in-line service.
Seating faces can be re-lapped. tot Forged Bonnet (3) The following valves do not meet the ASME 816. 10 end to end dimensions.
- Cast option available 39 IPEC00269857
"'U m () 0 0 I'V --"""'\ (J) <D CX> CJl RETAINING BLOCK NUT IS SPOT WELDED JO RETAINING BLOCK CX> 11542-60-1 11542-4~ SECTION IAJA X -:piAMETER AND NUMBER OF UN-2A THREADS
.wll(
I. THE VALVE SHALL BE INSTALLED IN A HORIZONTAL PIPE WITH THE BONNET ABOVE THE CENTERLINE OF THE PIPE.
*NOTES CONTINUE ON SHEET 2.
>- e.G.
AB SCHEDULE 140 PIPE AS 10.656 '12.781 15.031 60 60 60 BONNET PART 11542-1 MAT'L. WAS A5TM A515 t;RADE 5.5
>tl)"..A!i"DIMEN.SION Ftl.EI. .*.*
SCHEDULE 160* PIPE. ---:--:= ADDED RECOMMENDED SPARE PARTS. ADDED VIEW A ADDED NOTE I WESTINGHOUSE ELECTRIC CORP. PART 1!542-1 MATERIAL _NUCLEAR ENER6Y SYSTEM WA'5 A201 GRADE A E GENERAl,... I. ADDED tz'VALVE DARLING VALVE&.MANUFACTURit-16, CO. WILLIAMSPORT~ PA. REV~5ED 'As' 01 MENS ION""'*
~ODED Ax'otMENSION ADDED TAG. NO. l..OCK WIR>E REVISIONS i'c II 542
"'U m ~- .. - - '- - - - - - - - - - ,, __s: ___ _ () - 0 ~ I II
~=<
0 I'V (J) <D CX> CJl <D U-Nil* i*nd) SPIN:U-I'io"¥l-~ SII..II.I~: .I.S ~UFACTLJk[O o.*.UIT IF!C.UlON LCTHR NO.: IPP-4<12/J
.WThORJH; o;Qil"'
I !ITt.LUTt *o. ~.o.I>Di'l>.(.l""- 0" ITt'"'- ... o*~-"' ~
~ .. ~l"tQ.O. ,.<ll(o.J;l :If A\'H~,t..IOI.-'1' * ~" Ulo~
~ L/0 LOlFI'""tt*t*n *ltl ~"-
~ l"i._ V,o.L'I'f. ~"ll.L~ Cl.l.o.<IUNT~O HQII<{QWl"-L.'( 1,_. T01\C PIPt Ll'<t TO lit fl(l-0 Wt:LDt'D),
,.,!!H-4 li-d_ ":>Tl'_ ... ~R.TICAL ll.,flOY[. TH( (LN.Tt.RLINL OF HIE. PIPE. C.Lf .... tV( NT O'i""tfA(I".o:.t..
!LIUITO~OUtt-lQI.I.U'IA.L~~TCRTOi.Qo.A:.*-'Ofl.U.:..,~TllCJK>>,,C. ll.ll.TE_-~"/1.\U.( ****VA.J..YE S00Tr.llH 1.4."!><:'"'-1.._01"'-El '"'hl:l Sl:.><&o Duh.[l,
- lP(IU,Tll.4(, 0ll"ft:R[.NT\,1o,L*(.DCP.~I., !.PHA.~l'_ '-OC.YCLl'_ \ ,4-0 lo'Ol-l"-(,f ., VAL'** E. t.OD-T YII!TH 14" SOI.IoLO I,_.Lf.T "-*.10 DulL( 1
- V.t.LVL 1..,::' l)\
l .C:,l M*A*l..O 011. A~Tio(*A.._*ll~ I !~. .:. ~~'-;
. ;,.. -V!:.L'~f._ ~1 l">O
~~~~~~~~:er:~~~~~~~cy~0~:~~Y~~~~~~~~5~~t*~~~.
[ ' '"-' *,.,- *-*
'I l FOR MDV lNFOFl-MAilON THIS ORAI.IlNG CREAlE:_O F <OM FOR VALVES 7304'731 SEE COPES -VULCAN. INC TN~S f PPMIS S1'STEM DI\TA 0\-/G. No. E- \-I 33<<20 HICROF1U1 No !973H"6"U
M C1) N UJ I C) s::::
*-~
ca I.. c il C1) ca IPEC00269860
co C1) N 111111111111111 (f) I C) c 111111111111111
~
ta c C1) ta IPEC00269861
ENTERGY Conceptual Design
~ ~~~~.~~~£~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -022 I Rev. 0 Attachment 4 Cost Estimate IPEC00269862
IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-022 0 Conceptual PROJECT TITLE: ISLOCA Pathway Isolation Valve Position Indication ESTIMATOR: RCMT u Preliminary JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD D Definitive 0outage 0 Non-Outage ORIGINATOR: 0CAPITAL 0o&M ORIG. DATE: 07/23/2012 ESTIMATE TOTAL $7,685,460 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package responds to the issue identified in the NRC's staff review of SAMA IP2-022 and provides the technical resolution and associated costs required for implementation. For SAMA IP2-022, resolution is required for remotely monitoring the open-close position of isolation valves in the ISLOCA pathways in containment. This package will install position switches on existing valves where possible or replace any existing valves that can't be modified with new ones that have position capability. This package will also provide for the valve position to be monitored remotely outside containment. Prepared by: Approved by:
,/1i; q_
t41~~ 4 ::~-~A-~~~<~~~ ~
~*
Date: " 2-D- 2. O('Z Date: y Z.J
- e. '/L/
IPEC00269863
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
...r-c EC #: SAMA IP2-022 ~T1MATE LEVEL*
Conceptual :.tli5i00il0Jli~e ISLOCA Pathway Isolation Valve Position Indication ESTIMATOR: RCMT Preliminary JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD 1-- Definitive ORIGINATOR: ORIG. DATE: 07/23/2012 Item Descriotion
- 1. This estimate ass s work will require both non-outage and outage conditions to complete.
2. This estimate assumes that the non-outage work work will complete during 2011 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that the outage work will be completed in 2014 working (2) 10 hour shifts 6 days per week.
- 4. This estimate assumes that the non-outage work will not suffer productivity loss due to radiation or hazardous conditions ..
- 5. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 6. equate penetrations exist tor routing of wiring from the position Indicating switches to the external panel location such that no new containment penetrations will be required.
- 7. This estimate assumes that safe ends will be welded to the valves in the shop and that blue checkes will be performed on valve seating surfaces prior to reassembly for installation. This work will be performed during non-outage conditions.
- 8. This estimate assumes that the results of the seat Blue check after welding will not require any machining of the valve seat.
- 9. This estimate assumes that (4) Fitter I Welders will be assigned for non-outage work and (2) of those will be assigned to 2nd shift for theOutage and (4) additional personnel will be assigned for the Outage, (2) for each shift.
- 10. This estimate assumes that the Outage work will involve radiological conditions requiring additional briefing times, dressout times and reduced production due to dressout requirements.
- 11. This estimate assumes NDE requirements include Visual, LP, UT and RT.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 12. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 13. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 14. and progresses as follows: A Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00269864
Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 11-0 EC #: SAMA IP2-022 fivay Isolation Valve Position Indication TAKEOFF: tainment & Control Bldgs. 0 CAPITAL Oo&M PROJECT CODE: TBD ESTIMATOR: RCMT STATUS: DouTAGE 0NON-OUTAG ORIGINATOR: ORIG. DATE: 0712312012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-TEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- ESTIMATE LEVEL * ~~ ""'" '~ ~u"""~"
tm" Conceptual MANHOURS DOLLARS "o Preliminary EO/ ENGINEERING Itt Definitive 01 STUDY, DESIGN, & CLOSEOUT 400 $ 40,000 02 DESIGN ENGR CONST SUPPORT 160 $ 16,000 General Notes: 03 MODS ENGINEERING EOI SUPPORT $ 04 SYS ENGR/ S-U ENGR 240 $ 24,000 05 PROJECT MANAGEMENT 600 $ 72,000 06 WORK MANAGEMENT $ 07 ENGINEERING DCP ACCEPTANCE REVIEW 100 $ 10,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 1,900 $ 228,000 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 280 $ 28,000 11 FIELD ENGRS I PLANNERS 240 $ 28,800 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 1,754,331 13 OTHER CONTRACTS $ 105,000 CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 5,417 $ 577,322 15 LOST TIME 542 $ 72,818 16 SWEC DISTRIBS $ 156,991 PLANT CRAFT LABOR 17 MECH MAl NT. $ 18 ELECT MAINT 54 $ 5,400 19 I&C 136 $ 13,600 20 CSG $ MISC EO/ SUPPORT 21 QUALITY CONTROL 240 $ 24,000 22 TRAINING 48 $ 5,760 23 CHEMISTRY $ 24 OPS I OPS SUPPORT 120 $ 14,400 25 HP/RP 120 $ 9,547 MISC CONTRACT SUPPORT 26 QUALITY CONTROL 260 $ 20,800 27 NDE $ 28 HP/RP $ 29 RADWASTE $ 50,000 30 NURSE $ 31 ELEVATOR CONTRACTOR $ 32 WASTE MANAGEMENT $ 33 HOUSEKEEPING $ 34 EQUIPMENT RENTAL CONTRACTOR $ 10,000 35 VENDOR STOCKING $ 36 DECONTAMINATION CONTACTOR $ 10,000 37 RBC'S $ 38 SECURITY- Wackenhut $ 39 FIRE WATCH (Rover) $ 40 SAFETY 112 $ 7,616 CONTINGENCY 41 CONTINGENCY $ 1 ,642,192 ESTIMATE SUBTOTAL 10,969 $ 4,926,577 SITE ENCUMBRANCE PREMIUM (20%) $ 985,315 LOADERS (30%) $ 1,773,568 ESTIMATE TOTAL $ 7,685,460 NON OUTAGE WORK
- 1. Gather and stage tools and materials 1 LT EL 4 10.00 1.00 40 $ 123.32 $ $ 4,933 $ 4,933
- 2. Gather and stage tools and materials 1 LT PF 4 10.00 1.00 40 $ 120.71 $ 4,828
- 3. Mount Hoffman wall mounted panel and enclosure and run conduit to selected external penetration. 1 EA EL 4 30.00 1.00 120 $ 123.32 $ $ 14,798 $ 14,798
- 4. Pull wire from containment external penetration box to new panel and terminate in new panel. 1 LT EL 4 24.00 1.00 96 $ 123.32 $ $ 11,839 $ 11,839
- 5. Cut and prep (20) 2" sch. 160 Pup pieces 1 LT PF 4 10.00 1.00 40 $ 120.71 $ $ 4,828 $ 4,828
- 6. Cut and prep (8) 6" sch.160 Pup pieces 1 LT PF 4 16.00 1.00 64 $ 120.71 $ $ 7,725 $ 7,725
- 7. Cut and prep (18) 10" sch.160 Pup pieces 1 LT PF 4 44.00 1.00 176 $ 120.71 $ $ 21,245 $ 21,245
- 8. Disassemble valve internals prior to welding pup 1 LT PF 4 5.00 1.00 20 $ $ 2,414 $ 2,414 pieces on (1 0) 2" valves. $ 120.71
- 9. Disassemble valve internals prior to welding pup 1 LT PF 4 7.00 1.00 28 $ $ 3,380 $ 3,380 pieces on (4) 6" valves. $ 120.71
- 10. Disassemble valve internals prior to welding pup 1 LT PF 4 10.00 1.00 40 $ $ 4,828 $ 4,828 pieces on (9) 10" valves. $ 120.71
- 11. Fit and weld (20) 2" Pup pieces to valves 1 LT PF 4 16.00 1.00 64 $ 120.71 $ $ 7,725 $ 7,725
- 12. Fit and weld (8) 6" Pup pieces to valves 1 LT PF 4 12.00 1.00 48 $ 120.71 $ $ 5,794 $ 5,794
- 13. Fit and weld (18) 10" Pup pieces to valves 1 LT PF 4 54.00 1.00 216 $ 120.71 $ $ 26,073 $ 26,073
- 14. Re-assemble valve internals and perform a seat 1 LT PF 4 5.00 1.00 20 $ $ 2,414 blue check on (10) 2" valves. $ 120.71 $ 2,414
- 15. Re-assemble valve internals and perform a seat 1 LT PF 4 3.00 1.00 12 $ $ 1,449 Blue check on (4) 6" valves. $ 120.71 $ 1,449
- 16. Re-assemble valve internals and perform a seat 1 LT PF 4 7.00 1.00 28 $ $ 3,380 Blue check on (9) 10" valves. $ 120.71 $ 3,380 IPEC00269865
~~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0CAP! !Jb&~ 11 EC #: SAMA IP2-022
~a~~.:ive"'Position Indication TAKEOFF tainment & Control Bldgs PROJECT CODE, TBD ESTIMATOR: RCMT STATUS ORIGINATOR_ ORIG_ DATE: 07/2312012 fY_ DESCRIPTION i CTY UOM CFT NO, UNIT MAN HOURS FCTR TOTAL $/MH MATERIAL$
PER UNIT MATERIAL DOLLARS LABOR DOLLARS SUB-CONTRACT TOTAL$ I 1- :ather and stage tools and materials, walk down
- 2. Gather and stage tools and matenals, walkdown 1
1 LT LT PF EL 8 8 10,00 10,00 OL TAGE WORK uo 170 136 $ 120,71 136 $ 123,32 s 16A17 16,772 s
$ 16,417 16,772
- 3. Remove existing valves and prep {(10.> 2" valves) 10 EA PF 1 3 00 1 70 51 $ 120,71 s 6,156 s 6,156 3 !Fit and weld (Hi) 2~ valves
- 4. 'Remove existing vafves and prep ((4) 6" valves) 5, Flt and weld (4} 6" valves 10 4
4 EA EA EA PF PF PF 1 1 1 7,00 18,00 15,00 uo 1 70 170 119 122 102
$ 120 71 s 120,71
$ 120,71 I' s s
14,364 14,727 12.312 s s 14,364 14,727 12,312 6, Remove existing valves and prep ((8} 10" valves} 8 EA PF 1 10,00 uo 136 s 120,71 $ 16.417 s 17 7, Fit and weld {8} 10" valves 8 1 20,00 170 272 $ 120.71 32,833 s 3;:~~: EA PF $ 8, NDE Profile {20) 2" welds 20 EA PF 1 200 170 68 s 120,71 $ 8,208 $ 9, NDE Profile (8) 6" welds 8 EA PF 1 400 uo 54 $ 120.71 s 6,518 $ 6,518 10, NDE Profile (16) 10" welds 16 EA PF 1 6.00 uo 163 $ 120,71 s 19,676 s 19,676 11, Route & Support. Conduit from each valve in containment 800 LF EL 1 0 16 170 245 $ 12332 $ s 30,213
$ 30,213 12, Mount Hoffman wall mounted panel and enclosure 2 LT EL 1 30.00 1.70 102 $ $ 12,579 $ 12,579 and run conduit to selected in containment $ 123,32 13 Route & Support Conduit from each junction box to 400 LT EL 1 0,20 1 70 136 $ $ 16,772 $ 16,772 containmen1 Penetration $ 123.32 14, COnnect power cable to containment penetrations 1 LT EL 4 60,00 1.70 408 $ $ 50,315 $ 50,315 on both sides of containment penetratton box.
123,32 15 16, Provide testing as reqt..nred Assist with testtng as required 1 1 LT LT PL EL 2 2 6000 30,00 1.70 1.70 204 102
$ 60.00 s 123,32 12,240 I 12,579 I s ~;:~;~
17, Dismantle scaffolding to siorage 1 2 24.00 82 96,00 s . 7,872 s
;:;~
LT CP 1.70 $ $ 18 Dismantle scaffolding to s:1orage 1 LT LB 1 24.00 1.70 41 Is 78,15 s . $ 3204 $ 19 10.00 1s 123,32 . 8,386
- ~:
Cleanup and restore area 1 LT EL 4 1.70 56 $ $ $ 20 Cleanup and restore area 1 LT. PF 4 10,00 1.70 68 s 120,71 $ $ 8.208 $ PAINTiNG & TOUCH-UP REQUIREMENTS $ 1, PAlNTlNG & TOUCH-UP PT $ . s s 2 PAINTING & TOUCH-UP PT s s $ FlRE WATCH I BOTTLEWATCH REQUIREMENTS s 1, CRAFT sUPPORT FOR FIRE WATCH 2 LT FW 1 300,00 uo 1,020 $ 53,60 $ . $ 54,672 $ $4,672
' CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW *I s - s $
MlSC SUB-CONTRACT I $ 1 MISC SUB-CONTRACT NDE Contractor 2, MISC SUB~CONTRACT MOV Contractor 1 1 LT LT NM NM I $ 70,000 35,000 s 70,000 35,000
~
4,687 $ $ 484,534 s 105,000 1 CONSTRUCT~ON SUPPORT (8% OF LABOR$) LT 375 s 103,38 $ 38,768 SUBTOTAL
. 5,0Q2 1Uo,UOO
'l
- RELATED COSTS
- 1 WALKDOWN ALLOWANCE 1 LT EL 42 s 123 32 l s 5,179 $ 179 2, WALKDOWN ALLOWANCE 1 LT PF s 120111 s
- ~
38 4,587 $ 3, WORK PACKAGE REViEW 1 LT I EL 50 $ 1a32 $ 6,166 $ 4, WORK PACKAGE REViEW 1 LT PF 48 $ 120 71 I $ 5,794 $ 5,794 5, II II TOOL ROOM ATTENDANTS 1 LT EL 177 $ 123.32 $ 21,628 $ 21,828 6, GENERAL CRAFT OUTAGE (10%) $ 52,330 $ 52,330 7, CRAFT IN PROCESSING {20%;)
'~6:~~~ I
$ $ 104,660 8, HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ $ 10,466 9, (1/2 day training, or- 2%)
SUBTOTAL 5.417 $ $ 734,313 $ 105,000 $ 639,313 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ $ $
PL s s $ SUBTOTAL MECH MAINT. $ s $ *Is 2
~
1, ELECT MAINTENANCE $ s 5,400 $ s $
$ 5,400 s
-~
L $ 1MOO SUBTOTAL I&C MAlNT. IS 1, CSG 1 I s $ $ SUBTOTAL CSG MAINT. $ $ $ s SUBTOTAL PLANT 190 s $ 19,000 $ $ 19,000 I i I I
~ $ s 753,313 $ 105,000 I
$ 858,313 IPEC00269866
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
@CAP! jJb&M EC #: SAMA IP2-022 TAKEOFF:
PROJECT CODE: TBD ESTIMATOR RCMT ORIGINATOR* ORIG. DATE: 0712312012 I MATERIAL$ MATERIAL LABOR SUB* DESCRIPTION QTY 1 UOM CFT NO. TOTAL $1MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ IMPLEMENTATION SUPPORT EOI
~~ I NM 1 WELDING ENGINEERING 1 NM >>j
- 2. DESIGN ENGINEERING SUPT DURING CONST 160 00 180 $ 100 18,000 i l $ 16,000 3.
4 SYSTEMS ENGINEERING- MECHANICAL SYSTEMS E"'GINEERI"'G- ELECTRICAL ' LT I NM LT t NM 80.00 80.00* 80 80 100 100 8,000 8,000 Is 6,000 8,000 5. 8. SYSTEMS EING!o.;EERING -INSTR & CONTROL SYSTEMS ENGINEERING- CIVIc STRUCTURAL 1 LT LT I NM NM 4000 4000 40 40 s 100 100 4,000 4,000 4,000 4,000 7, PROJECT MANAGEMENT 1 LT NM 600.00 600 $ 120 72,000 $ 72,000
- 8. TRAINING OPS STAFF 12 LT NM 400 48 $ 120 5,780 $ 5,760 9 QA I QC VERIFICATION 1 LT NM 240 00 240 s 100 24,000 $ 24.000 10 CHEMISTRY 1 LT NM I $
11. 12. HP I RPI ALARA WORK MANAGEMENT
,,'I LT LT NM NM 12000 1201 s 80 9,547 $
9,547
- 13. OPS I OPS PROCEDURE SUPPORT AND DEVE LT NM 12000 120 s 120 14,400' $ 14,400 11 14 1.
TRAVEL & LIVING EXPENSES CONTRACTOR SUPPORT FIS I MODS ENGINEERING- SWEC (Jncl Per Die 1, LT 1 I LT NM I 0 2~ MODS PLANNING & SCH.* SWEC (lncl Per Diem LT NM 280.001 260 100 28,000 $ 26,000 3 FIELD ENGRSIPLAN- SWEC LT NM 240.00 240 120 28,800 $ 28,800
- 4. QA I QC VERIFICATION LT NM 260 00 260 60 20,800 $ 20,800
- 5. NDE LT NM 0 $
- 6. HPI RP
~~I NM 0 7 RADWASTE NM 50,000 8 NURSE LT NM 0 9 ELEVATOR CONTRACTOR LT NM 0
- 10. WASTE MANAGEMENT LT NM 0
- 11. HOUSEKEEPING 1 LT NM 0 12 EQUIPMENT RENTAL CONTRACTOR LT NM 0 10,000 13 VENDOR STOCKING LT NM
- 14. DECONTAMINATION CONTRACTOR LT NM ~I 10,000 15 RBC's LT NM Oi 16 SECURITY LT SEC Ol
- 17. FIREWATCH (Rover) LT NM ol
- 18. SAFETY (2%) LT NM 112 s 68 00 7,616 l LOSTTlME 10% LT 542 $ 134.35 72,818 SUBTOTAL CAAFT/NON-MANUAL 8569 $ 1.077,054 175,000 1.252.054
- 1. FREIGHT, SALES TAX, & CONSUMABLE$ (8%) 17,508 17,508 2 Cable, Conduit, Switches, Boxes and Panel LT 30,000 30,000
- 3. 2", 8" & 10" A376, TP316, sch. 160 Pipe LT 38,800 36,800
- 4. 2" Check Valves, 1500 # Ciass, SR 10 EA 45,000 450,010
- 5. 6" Check Valves, 1500# Class, SR 4 9
EA EA ,80,000 320,004 LT NM i 80 1 LT NM 60 1 LT NM 80 1 LT 160 16,000 228,000 10000 50,000 228,000
$ 1,127,054 403,000 3,284,385 1,842,192 ESTIMATE SUBTOTAl. 10969 4,926,577 IPEC00269867
ENTERGY Conceptual Design
~ ~~~~~~~~;~:.~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-028 Install a Diesel-Driven Generator Set as Backup for Station Battery Charging Prepared byiJ Approved by:
;;t;:--tdf~.£.
1
~/~ /
Date: cr - 2 o - z. -o r'7- Date: ' ! < " .*,
~.
~~ / >~
Page 1 of6 IPEC00269868
ENTERGY Conceptual Design
~ ~,:.~.?},~~~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00269869
ENTERGY Conceptual Design
~ ~~~~,~~E~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-028:
Install a Diesel-Driven Generator Set as Backup for Station Battery Charging
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-028 in accordance with Entergy design engineering practices. For SAMA IP2-028, resolution is required to install and readily have available an alternate source for charging the Station's 125VDC battery system other than from the Station's 480VAC Switchgear Room. This package provides for a conceptual design to install a diesel-driven generator set to be available when required for charging the Stations 125VDC batteries in the event of Station Blackout. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. Page 3 of6 IPEC00269870
ENTERGY Conceptual Design
~ ~?~~~'~;,~,~~:~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 3.0 EXISTING CONDITIONS The IP2 130VDC Battery System consists of four battery banks ranging in capacity from 495 amp/hours to 1,800 amp/hours. They are located in separate and discrete Battery Cell Rooms and identified as #21, #22, #23, and #24. These rooms are in reasonably close proximity to each other. Their capacity is as follows:
Battery Bank #21 1,500 amp/hours Battery Bank #22 1,800 amp/hours Battery Bank #23 495 amp/hours Battery Bank #24 495 amp/hours Battery Cell Rooms #21, #22, and #24 are located in the Unit 2 Control Building at Elevation 33'-0". Battery Cell Room #23 is located in the retired Unit 1 Generator-Superheater Building also at Elevation 33'-0". Each Battery Cell room is separate from the other, totally enclosed, and accessible through an entry door. The battery banks are connected to their respective DC Power Panels located outside of the Battery Cell Rooms. Charging of the batteries is via wiring from the power panels connected to chargers fed from the Unit 2 480VAC electrical system. 4.0 DESIGN CONSIDERATIONS An alternative means for charging the Station's battery banks needs to be available in the event the Station's electrical supply as a charging source is unavailable. This alternative battery charger source, must be in place and readily available for use. The existing battery bank wiring connections need to remain in place undisturbed. New, permanent, and alternative connections to locations outside the Battery Cell Rooms need to be added to provide for battery bank charging. These new locations will be available for quickly providing connection to the alternate standby battery charging system. The charger will be permanently installed and available in the immediate area of the Battery Cell Rooms. 5.0 CONFIRMATION OF DESIGN Installation of a diesel driven generator at ground elevation outside the Control Building in the transformer yard will provide the AC required for input to the battery charger portion of the system. Page 4 of6 IPEC00269871
ENTERGY Conceptual Design
~ ~~~~?,~2!:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 There is room at Elevation 33'-0" in the vicinity of the Battery Cell Rooms for the permanent installation of the battery charger cabinet. The charger will be specified in accordance with the various size battery bank requirements and will provide the controls for regulating the charging of each battery bank as well as a power on-off disconnect switch.
There is area available on the exterior walls of the Battery Cell Rooms for individual Interlocked Receptacle enclosures to be provided for each battery bank. The enclosures include a disconnect switch and a plug-in twist-lock connector. The battery charger cabinet will be provided with a length of permanently connected cable fitted with a plug-in twist-lock connector for connection at each battery room's connection enclosure.
- 6. RECOMMENDED SOLUTION Diesel Driven Electric-Generator and Charger
- 1. Outdoors, in the transformer yard at Elevation 18'-0", provide for the installation of the diesel driven electric-generator.
- At the base of the north wall of the Control building, install a concrete pad for mounting the generator and enclosure.
- Mount and permanently install the generator and enclosure.
- Construct an oil spill containment berm around the weatherproof enclosure.
- Route and install conduit and cable and terminate from distribution cabinet to enclosure to provide electrical power required for heating, ventilation and lighting.
- 2. In the control Building at elevation 33'-0", provide for the installation of the battery charger cabinet.
- Across from Battery Cell Room #21 , install and permanently mount the battery charger cabinet and its associated length of "connection" cable with plug-in twist-lock connector
- Provide means for storing the length of plug-in jumper "connection" cable at this location.
- 3. Route and install conduit and cable and terminate as follows.
- From the outdoor mounted generator at Elevation 18'-0", penetrate the Control Building wall and connect to the battery charger cabinet mounted indoors at Elevation 33'-0".
Page 5 of6 IPEC00269872
ENTERGY Conceptual Design
~ ~~~~~,~~2!:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 Battery Cell Rooms
- 1. Install the individual battery room plug-in Interlocked Receptacle enclosures on the exterior walls of the Control Building Battery Cell Rooms.
- 2. Route and install conduit and cable and terminate as follows.
- Connect the existing DC power panel outside of each Battery Cell Room to its respective Interlocked Receptacle enclosure.
- 3. Provide procedures and training to operate, test, and perform maintenance on the components of the newly installed system.
7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Concrete pad 13' x 10' x 6" 1
- 2. Enclosure for diesel generator 13' x 10' x 10' 1
- 3. Cummins Diesel generator Series QSB5 with a prime rating of 69 kVA or Equivalent 1
- 4. Sub-base Fuel Tank 1
- 5. Solidstate Controls Battery charger 85-CC2500 or Equivalent 1
- 6. Russellstoll Maxguard Interconnection Systems Interlocked Receptacle w/Circuit Breaker or Equivalent 4
- 7. Russellstoll Maxguard Interconnection Systems Plug or Equivalent 1
- 8. 2"- Conduit and Supports 180 Feet
- 9. 1/0 Excelene Welding Cable or Equivalent 360 Feet
- 10. 480 VAG- 4/c Power Cable 120 Feet
- 11. 1" - Conduit and Supports 200 Feet
- 12. 120 VAG - 3/c Power Cable 200 Feet Page 6 of6 IPEC00269873
ENTERGY Conceptual Design
~ ~~~~~~~2:::,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269874
J!t NUClEAR QUALITY RELATED EN-DC-115 I REV.11
-=- Entergy MANAGEMENT MANUAl REFERENCE USE PAGE 96 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET1 OF6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. MA Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmQact Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings chanqes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES ~NO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES ilf NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269875
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS PotentiallmRact ASME Section Ill Specifications DYES txJ NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any chan!les to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES Ill' No
- Does the proposed activity involve any new or existin~ EQ components?
Hydrogen Control Program (1 0 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact eauipment or materials related to hydroaen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES IXJNo
- Does the proposed activity impact or involve any change to design, licensing or operations marains?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES IX! NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potential lmRact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected
.procedures, required actions and reQuired training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, reauired actions and reQuired trainin~?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES Qi1 NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES ~NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundarv or reactor svstem procedures?
IPEC00269876
*-=- Entergy NUCLEAR MANAGEMENT MANUAl QUALITY RELA TEO REFERENCE USE EN-DC-115 I
PAGE 98 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET3 OF 6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST PotentiallmQact Computer Support and Software DYES tifNo
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES l).d NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES !KTNo
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS* PotentiallmQact ASME Containment In-service Inspection (IWE /IWL) Program DYES !Jl'No
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES ~NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269877
dfl. NUCLEAR QUAUTY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} PotentiallmQact ASME In-service Inspection (lSI) Program DYES IXfNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES r&fNo
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES l)jNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES KINO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES tlf NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES IXJ NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269878
*-=-- Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potential lmQact Flow Accelerated Corrosion (FAC) Program DYES !XI NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES IX! NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program BYES DNO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES lXJNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES txt NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES I'm NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program BYES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component{s) maintains its qualification status?
PTCurves DYES (:ij NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES a.(! NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES IXJ NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269879
~Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE EN-DC-115 I REV.11 PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Welding Program .YES ONO Does the proposed activity impact or involve a special process, such as welding,
" brazing or soldering?
Safety Program .YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES ONO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES ONO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES Q!l NO IPEC00269880
ENTERGY Conceptual Design
~ ;:~~~~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Typical Schematic For New Diesel-Generator And New Alternate Battery Charger
- 2. Figure 2: Partial Site Plan Of Areas Affected
- 3. Figure 3: Transformer Yard Area Control Building-North Wall
- 4. Figure 4: Equipment Arrangement Control Building At El. 15'-0" Enclosure And Diesel-Driven Generator Location
- 5. Figure 5: Equipment Arrangement Control Building And Superheater Building At El.
33'-0" Battery Charger And Interlocked Receptacle Location IPEC00269881
0
~--NEW DIESEL-DRIVEN GENERATOR
~
~--NEW ALTERNATE BATTERY CHARGER
)
t------ APPROXIMATELY 60 FEET OF TWO 1/0 CABLES t----- STORAGE CABINET
~--NEW INTERLOCKED RECEPTACLE Wj CIRCUIT BREAKER TYPICAL FOR EACH
~--EXISTING 125VDC BATTERY PWR. PNL. CELL 1121, 1122, 1123, 1124 t----- EXISTING FUSE OR CKT. BKR FIGURE 1 TYPICAL SCHEMATIC FOR NEW DIESEL-GENERATOR AND NEW ALTERNATE BATTERY CHARGER IPEC00269882
"'U m 0 0 0 I\.) (J) <0 00 00 V) ENTERGY Conceptual Design
~ ;,~~'~c~~:,~P,,~,=~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-028 Rev, o CQI\jTAI'Hv1Ef'H B:_DC;,
t-:C Ul~iT r~O 2 zl-
~g§ a..z UNIT N0.2 TRANSFORMER PRI~;tARY A.UX!UARv BLDG.
YARD EL. 18'-0" NEW ALTERNATE DIESEL-DRIVEN ANd NEW ENCLOSUREGENERATOR BATTERY CHARGER I
**~**~"""-~""-,
CONTROL BLDG. EL. 33'-0" U\l'T NO, 1 SCR~ENWELL
,i UNI1 N0.1 I YOUSE i TURBIN[ I I i
- I_J\ ;--~ -~** _L J\ ~"-""~"*"-- ~~.J I
v, FIGURE 2
\
v I PARTIAL SITE PLAN OF AREAS AFFECTED (NOT TO SCALE)
ENTERGY Conceptual Design
~~ ~~"~'~'~:~2,:,:.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 INSTALL DIESEL-DRIVEN GENERATOR IN WEATHERPROOF ENCLOSURE FIGURE 3 TRANSFORMER YARD AREA CONTROL BUILDING-NORTH WALL IPEC00269884
0 NEW ENCLOSURE AND -~-.... DIESEL-DRIVEN GENERATOR tmiE.; ACTUAL LOCAnON TO BE ISOLATION TRANSFORMERS, DETERMINED AT FINAL FOR PRESSURIZER HEATER DESIGN. PANEL FEEDS. INST. AIR AFTERCOOLER (EL. 26'~ INST AIR COMPRESSOR COOUNG WTR. HEAT EXCHANGER TO NEW ALTERNATE BATTERY CHARGER FIGURE 5 FIGURE 4 EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 15' -0" ENCLOSURE AND DIESEL-DRIVEN GENERATOR LOCATION (REFERENCE DWG. 9321-F -3052) {NOT TO SCALE) IPEC00269885
-u m () 0 0 I'V Ci) <D CX> CX> Ci) ENTERGY Conceptual Design
*~ ;,;~~.~.~~2~,~": Indian Point Nuclear Station Unit 2 Package SAMA IP2-028 Rev. 0 I- ::X:
zt:;::
- 5o a..z STORAGE CABINET FOR CABLE CONTROL BUILDING 0 0 STAIR 110.4 NEW INTERLOCKED RECEPTACLE (OFFICIAL NUMBER 0 DETERMINED LATER) FOR EACH BATTERY CELL TO CONNECT TO NEW ALTERNATE BATTERY CHARGER.
NEW ALTERNATE BATTERY CHARGER FOR BATTERY CHARGING CAPABIUTY AND OFFICIAL NUMBER DETERMINED LATER. FIGURE 5 EQUIPMENT ARRANGEMENT CONTROL BUILDING AND SUPERHEATER BUILDING AT EL. 33' -0" SUPERHEATER BUILDING BATIERY CHARGER AND INTERLOCKED RECEPTACLE LOCATION (REFERENCE DWG. 138001) (NOT TO SCALE)
ENTERGY Conceptual Design
~ ~;,:,~~,~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. Cummins Diesel Generator set QSB5 Series Engine (attached here)
- 4. Solidstate Controls Battery Chargers for Nuclear Plants (attached here)
- 5. Russellstoll MaxGard Interconnection Systems (attached here)
IPEC00269887
Diesel generator set QSB5 series engine EPA emissions Cummins Power Generation commercial generator sets Cummins heavy-duty engine- Rugged 4-cycle, are fully integrated power generation systems providing industrial diesel delivers reliable power, low emissions optimum performance, reliability and versatility for and fast response to load changes. stationary and prime power applications. Alternator - Several alternator sizes offer selectable motor starting capability with low reactance 2/3 pitch This generator set is designed in facilities windings, low waveform distortion with non-linear loads certified to IS09001 and manufactured in and fault clearing short-circuit capability. facilities certified to IS09001 or IS09002. The Prototype Test Support (PTS) program Permanent magnet generator (PMG) - Offers verifies the performance integrity of the enhanced motor starting and fault clearing short-circuit generator set design. Cummins Power capability. Generation products bearing the PTS symbol Control system - The PowerCommand electronic meet the prototype test requirements of NFPA 11 0 for Level 1 systems. control is standard equipment and provides total genset system integration including automatic remote All low voltage models are GSA certified to starting/stopping, precise frequency and voltage product class 4215-01. regulation. Optional features include alarm and status message display, output metering, auto-shutdown at fault detection and NFPA 11 0 Level 1 compliance. The generator set is available Listed to UL2200, Stationary Engine Generator Cooling system -Standard integral set-mounted Assemblies. radiator system, designed and tested for rated ambient temperatures, simplifies facility design requirements for Engine certified to U.S. EPA Nonroad Source rejected heat. U.S. EPA Emissions Standards, 40 CFR 89, Tier 3. Fuel tanks - Dual wall sub-base fuel tanks are also offered. NFPA
- The genset accepts full rated load in a single step in accordance with NFPA 110 for Level 1 systems.
Warranty and service Backed by a comprehensive warranty and worldwide distributor network. Standby rating Prime rating Continuous rating Data sheets 60Hz 50 Hz 60Hz 50 Hz 60Hz 50 Hz Model kW lkV.lU kW lkVAl lkW lkVAl kW lkVAl kW lkVAl I kW lkVAl 60Hz 50 Hz DSFAA 35 (44) 32 (40) D-3366 DSFAB 40 (50) 35 (44) D-3367 DSFAC 50 (63) 45 (56) D-3368 DSFAD 60 (75) 55 (69) D-3369 DSFAE 80 (100) 72 (90) D-3370
©2008 I Cummins Power Generation Inc. I AB rights reserved I Specifications subject to change without notice I Cummins Power Generation and Cummins are registered trademarks of Cummins Inc. PowerCommand and "Our er1ergy working " are trademarks of Cummins Power Generation, Other company, product or service names may be trademarks or service marks of S-1559c (3/08)
IPEC00269888
Governor regulation class Voltage regulation, no load to full load +/- 1% Random voltage variation +/-0.5% Frequency regulation Isochronous Random frequency variation +/- 0.25% Radio frequency emissions compliance j ..-: \ j Design 4 cycle, turbocharged and charge air attercooled Bore 107 mm (4.21 in) Stroke 124.0 mm (4.88 in) Displacement 4.5 litres (272 in3 ) Cylinder block Cast iron, in-line, 4 cylinder 1000 amps minimum at ambient temperature of -18 'C to 0 'C Battery capacity (0 'F to 32 °F) Battery charging alternator 100 amps Starting voltage 12 volt, negative ground Fuel system Direct injection: number 2 diesel fuel Single element, 10 micron filtration, spin-on fuel filter with water Fuel filter separator Air cleaner type Dry replaceable element Lube oil filter type(s) One spin-on, full flow filter Standard cooling system High ambient radiator
- .i Design Brushless, 4 pole, revolving field Stator 2/3 pitch Rotor Single bearing, flexible disc Insulation system Class H Standard temperature rise 150 oc standby @ 40 oc ambient Exciter type Torque match (shunt) standard, PMG optional Phase rotation A (U), B (V), C f;.V)
Alternator cooling Direct drive centrifugal blower fan AC waveform total harmonic distortion < 5% no load to full linear load, < 3% for any single harmonic Telephone influence factor (TIF) <50 per NEMA MG1-22.43 Telephone harmonic factor (THF) <3 I 60 Hz Three phase line-neutral/line-line 60 Hz Single phase line-neutral/line-line
- 120/208
- 139/240
- 240/416
- 277/480 *120/240
- 120/240 Delta
- 220/380
- 255/440
- 347/600
- 127/220
- Note: Consult factory for other voltages.
Engine Alternator Generator set D PowerCommand Network D 120 V, 150 W lube oil heater D 105 oc rise alternator D AC entrance box Communications Module D 120/240 V, 1000 W coolant D 125 oc rise alternator D Battery (NCM) heater D 120 V, 100 W anti-condensation D Battery charger D Remote annunciator panel heater D
Enclosure:
aluminum, steel, D Spring isolators Fuel System D PMG excitation weather protective or sound D UL 2200 Listed D 24 hour dual wall sub-base D Single phase attenuated D 2 year prime power warranty tank D Export box packaging D 2 year standby power D 12 hour dual wall sub-base Exhaust system D Main line circuit breaker warranty tank D Genset-mounted muffler D 5 year basic power warranty D Heavy duty exhaust elbow D Slip on exhaust connection
*Note: Some options may not be available on all models- consult factory for availability.
Our energy working for you.' (02008 I Cummins Power Generation Inc. I All rights reserved I Specifications subjeci to crange without notice I Cummins Power Generation and Cummins are registered trademarks of Cummins Inc. PowerCommand and "Our energy working for you." are trademarks of Cummins Power Generation. Other company, product or service names may be trademarks or service marks of others. 8-1559c (3/08) c IPEC00269889
Analog AC metering panel - Provides color-coded
- Integrated Isochronous governing and fuel control display of generator set output voltage, current, system.
frequency, power factor, and kW. All phases of voltage
- Integrated 3-phase sensing voltage regulation system and current are simultaneously displayed. Easy to see with automatic single and three phase fault regulation.
output status from a distance.
- Integrated AC protective functions include over/under Graphical data display. Allows operator to view all voltage, short-circuit, overcurrent (warning and engine and alternator data; perform operator adjustments shutdown) and overload.
for speed, voltage and time delays; view fault history; and
- Integrated engine management system including set up and adjust the generator set (set up requires configurable cycle-cranking functions and configurable password access). A portion of the display is allocated start sequence.
to display system status, including alarm and shutdown
- Comprehensive warning and shutdown protection conditions. Display is controlled by sealed membrane including customer configurable warning and shutdown switches. Up to 9 lines of data can be displayed with conditions.
approximately 26 characters per line.
- Comprehensive data displays including 3-phase AC voltage, current, power factor, kW and kVA; engine oil LED status lamps The status lamps indicate remote pressure, coolant temperature, DC volts and other start command (green), not in auto (red-flashing), warning service functions; operating history (load and fault (amber) and shutdown (red). conditions) and system setup information.
Mode selector switch - Off/manual/auto and run/stop switches allow remote automatic starting or manual o 0 LonWorks or Modbus network interface. starting from the operator panel. Panel includes an LED D Control anti-condensation heater. lamp to indicate manual mode operation. o Key-type mode select switch. Exerciser switch - Automated exercise function in the D Relay outputs for genset running, common warning control allows an operator to initiate an exercise period and common shutdown. and have it automatically completed by the control. D Exhaust temperature alarm. o Alternator temperature alarm(s). Fault reset switch - Allows the operator to reset the control after a warning or shutdown condition. LED lamp with switch indicates that a fault is present on the system. Panel lamps and switch - Operator panel can be illuminated by a series of high-intensity LED lamps controlled by a membrane switch on the panel. Panel lamps include a time delay to automatically switch off after a preset time period. Emergency stop switch Provides positive and immediate shutdown of the generator set on operation. Construction - Operator panel is a sealed design with membrane switches for most functions. Mechanical switches are oil-tight design. Plug interfaces are provided to the generator set control system. Display panel labeling is configurable for language. NEMA3RIIP53. Our energy working for you. TM (.02008 I Cummins Power Generation Inc. I All r.ghts reserved I Specifications subject to change without notice I Cummins Power Generation and Cummins are registered trademarks of Cummins Inc. PowerCommand and Our energy working for you." are trademarks of Cummins Power Generation. Other company, product or service names may be trademarks or service rrarks of others, S-1559c (3/08) c IPEC00269890
Standby: Applicable for supplying emergency power for the duration of normal power interruption. No sustained overload capability is available for this rating (equivalent to fuel stop power in accordance with 1803046, A82789, DIN6271 and 885514). Nominally rated. Prime (unlimited running time): Applicable for supplying power in lieu of commercially purchased power. Prime power is the maximum power available at a variable load for an unlimited number of hours. A 10% overload capability is available for limited IT Dim"C" time (equivalent to prime power in accordance with 1808528 and overload power in accordance with 1803046, A82789, DIN6271 and 885514). This rating is
.LJ,.L,l,_~~~,_l not applicable to all generator set models.
f - - - - - - Dim ' A " - - - - - - - 1 Base load (continuous): Applicable for supplying power continuously to a constant load up to the full output rating for unlimited This outline drawing is for reference only. See respective model hours. No sustained overload capability is available for data sheet for specific model outline drawing number. this rating. Consult authorized distributor for rating (equivalent to continuous power in accordance with 1808528, 1803046, A82789, DIN6271 and 885514). This Do not use for installation design rating is not applicable to all generator set models. Dim"A" Dim"B" Dim"C" Set Weight* Set Weight* Model mm (in.) mm (in.) mm (in.) dry kg (lbs) wet kg (lbs) DSFAA 2104 (82.8) 1016 (40.0) 1255 (49.4) 1080 (2380) DSFAB 2104 (82.8) 1016 (40.0) 1255 (49.4) 1080 (2380) DSFAC 2104 (82.8) 1016 (40.0) 1255(49.4) 1120 (2470) DSFAD 2104 (82.8) 1016 (40.0) 1255 (49.4) 1140 (2520) DSFAE 2104 (82.8) 1016 (40.0) 1255 (49.4) 1220 (2690)
' Note: Weights represent a set with standard features. See outline drawings for weights of other configurations.
Cummins Power Generation 1400 73*d Avenue N.E. Minneapolis, MN 55432 USA Telephone: 763 574 5000 USA Toll-free: 877 769 7669 Fax: 763 574 5298 Warning: Back feed to a utility system can cause electrocution and/or property damage. Do not connect to any building's electrical system except through an approved device or after building main switch is open. Our energy working for you.' CQ2008 1 Cummins Power Generation lnc. I All rights reserved I Specifications subject to change without notice I Cummins Power Gelieration and Cummins are registered trademarks of Cummins lnc. PowerComrnand and "Our energy working for you." are trademarks of Cummlns Power Generation. Other company, product or service names may be trademarks or service marks of others. S-1559c (3/08) c "' IPEC00269891
BATTERY CHARGERS for NUCLEAR PLANTS
- DC Voltages-24, 48, 110, 130, 220, & 260 VDC
- Thyristor-Based Operation -Full-Wave Rectifier (6 Pulse)
- DC Output Isolated from AC Input
- Output Filter
- Battery Overcharge Protection
- Wide Range of Options
- Seismic and Environmental Qualifications to meet your lE Safety Related Applications
- Replacement in existing Charger footprints are accommodated Solidstate Controls, Inc. (SCI) has designed, manufactured and maintained hundreds of safety related, (I E) and non-safety, yet essential, Battery Chargers in Nuclear generating facilities around the globe. Each application requires a unique set of solutions in which SCI will help create the optimum Battery Charger System for your plant. SCI Battery Chargers are thyristor-based systems designed for high-efficiency conversion (>90%) of com-mercial AC power to DC power, for charging station type batteries. They are also compatible with our inverter systems to be used as an Uninterruptible Power System (UPS) as a float system, or as stand alone Charger for DC only applications. All models are equally compatible with all lead acid type batteries including, lead calcium &
antimony, nickel cadmium, or valve regulated for station DC systems. A dry type isolation transformer is used to isolate the DC output from the AC input and to provide the proper voltage for the rectification process. Standard output ripple filter, 2% with battery connected, is provided. Optional low ripple and battery eliminator low ripple options are available. The Charger can also be utilized, and packaged, with incorporation of a blocking diode, as a regulated rectifier package in SCI inverters. We are available to create solutions to solve your World Headquarters specific problems. (an ISO Certified Quality Management Systems Facility): 875
Dearborn Drive- Columbus,
OH 43085 Phone: 1-614-846-7500 Toll-Free 800-635-7300 (US & Canada) Fax: 1-614-885-3990 Phone: +1-614-846-7500 Fax:: +1-614-885-3990 or Please visit our website(s) for more information Asia Pacific Headquarters: and assistance from the Nuclear Engineering Golden Sun Ctr.-Flats F-G 12'h Fl- 59-67 Bonham Strand West Team. Sheung Wan Hong Kong-www.solidstatecontrolsinc.com Phone: +852-2526-1967 /1970 Fax: +852-2526-0225 www.nuclearUPS.com Latin American/South American Headquarters: Solidstate Controls, Inc. Argentina SRL Olive 1954--2000 Rosario Argentina Phone: +(54-34) 341-455-3332 Fax: +(54-34) 341-0142
~
CERTIFIED ISO SOD 1 If, SOLIDSTATE CONTROLS, INC . -m* ill~t A member of The Marmon Group of Companies IPEC00269892
General Specifications Cabinet Controls NEMA-1 (IP-20), Seismic Grade Float/Equalize Push buttons 0-100 Hr Equalize Timer, Cable Entry/Termination manual start, auto reset. Independent float and equalize Top (rear) Standard potentiometers on front panel Optional Bottom (front), side and custom entry/termination locations available ..... consult the Factory Standard Features Environmental Ambient Temp.: ooc to 40°C (50°C optional) Circuit Breakers Relative Humidity: 0-95% non-condensing AC Input: 3 pole molded case (Rated 14 KAIC) Operating Altitude: 0 to 2500 meters (0-8300 ft.) DC Output: 2 pole molded case (Rated 10 KAIC) Audible :\oise: <60 dB(A) at 1 meter (High KAIC ratings optional-*Consult the Factory) AC Input Meters (2% Panel type) Voltages: 208, 220, 380, 415, DC Output Voltmeter 480 & 600 VAC/3-phase, 3 wire DC Output Ammeter
*custom voltages available Custom meter locations and meter types available Range: +I 0, -I 0% for 1% output regulation including 1% switchboard and digital. *Consult the Factory Range: Optional + 10, -15% additional ranges Indicators and Alarms available Standard "LED" Indicators Frequency: 50 or 60 Hz +/-5% Isolated Form "C' Contacts DC Output Custom Capabilities Float Voltage: 135, 270 +/-5% adjustment Modular packaging for limited installation access Equalize Voltage: 140, 280 +/-5% adjustment Multiple alarm capabilities
*custom output voltages available Fail safe alarms Regulation (Float): +/-1.0% Custom metering Regulation (Equalize): 1.0% Transducers Ripple: <2% RMS with battery connected Mimic panels per NEMA PE-5 *optional & Louvered recessed breakers custom ripple filters available Annunicators Current Limit: Factory set at 125%, adjustable from 50-135%
Additional sizes up to 1200 AMPS available-Consult Factory we*gnt {est} Output ACIDC Cabinet Style Heat Loss (Watts) 130 VDC 260VDC Model Amps %.Eff 130VDC 260VDC 130VDC 260VDC Lbs. K2. Lbs. K2. i=~ 85-CC0500-XX 50 91 D 642 1200 61'1 278 740 336 85-CC0750-XX 75 91 D 964 1760 720 326 940 426 85-CCIOOO-XX 100 92 D D llOO 2100 765 347 975 442 85-CCISOO-XX 150 93 D D 1400 2750 940 426 1365 619 85-CC2000-XX 200 93 A G 1830 3650 1255 569 1955 887 85-CC3000-XX 300 94 A G 2350 4580 1535 696 2680 1216 85-CC4000-XX 400 94 G H 3100 6250 1720 780 2960 1343 85-CC5000-XX 500 94 H H 3900 7800 1950 3535 1603 888 85-CC6000-XX 600 94 H GH 4700 9300 2565 1163 4650 2109
..Weight of 60 Hz units, 50 Hz 7"/c more 24 & 48 VDC also avaiiable.Hconsult the factory- Larger sizes also available **Cabinet styles subject to change based on selection o~ filters and options
*Custom enclosures and dimensions are available to meet your specific needs. Please consult the Nuclear Engineering Team at Solidstate Controls. Inc, for assistance, Standard Cabinet Dimensions*
Cabinet St:yle H X Inches (mm) w X D c:::.:tl H X lnches(mm) w X D D (1448 57 X X 29 737 X X 28 711) G I (2159 85 X X 29 737 X X 36 914) A 78 X 29 X 36 H 85 X 56 X 36 (1981 X 737 X 914) (2159 X 1422 X 914) GH 85 X 85 X 36 Battery Charger Block Diagram (2159 X 2159 X 914) Specifications subject to change withoutnotice 1112001 IPEC00269893
Heavy lndustriaJ/Marine Russe/lsto/1 MaxGard Interconnection Systems 30-400/600 Load Maximum 600 VAC/250 VDC Receptacles, Inlets, Plugs, Connectors, Interlocked Receptacles, Explosion Proof Interlocked Receptacles Thick wall cast copper-free Standard conduit aluminum housing with openings through top or epoxy powder coat finish. side. (cutaway shown) (Optional sizes & locations) NEMA 4X interlocks available in 30-400 amp ranges through 4P5W, with 2 optional pilot/control contacts. Standard, high NC or NNbreaker switch. (cutaway shown) Options include:
- Shunt Trip Heavy on/off handle adds
- Auxiliary Switch mechanical to electrical
- Trip Ratings interlock function.
(External Lockout Option kit available) Gated, rotating dead-front - - - - + - - receptacle. Watertight = Screw cap cover Heavy duty sliding bar Splashproof Flap cover interlock mechanism. (Mates with plug padlock-out access hole) Protective screw cap (flap cap also available}.
/, /
© 2002Tnomas & Betts Corporation. Specifications are subject to change without notice. WWW.tnb.COm H11 IPEC00269894
Heavy Industrial/ Marine Russe/lsto/1 MaxGard Interconnection Systems 30-400/600 All available voltage polarizations on pg. H20. i5
~
Et Maximum 600 VAC 250 VDC, Load
=
hJj Breaking Male Plug'* Female Connector* Male Inlet'
~d~rd Ratings --- Sid. Sid.
s Bushing Bushing 1 W1res Voltage Cal. No. 1.0.** Cal. No. 1.0. ** Cal. No. 30 Amp /45* ~
'f' + 'f' -l<'f' 2P3W 125 OS31 07MPOOO Ys" OF31 07FPOOO Va" OS31 07MROOO OS3207MPOOO 7/,. Ys" 2P3W 250 ,g DF3207FPOOO OS3207Mi000 3P4W 125/250 OS3307MPOOO 1' OF3307FPOOO 1' DS3307MROOO 3P4W 30480 DS3404MPOOO 1' OF3404FPOOO 1' DS3404MROOO 4P5W 30Y 277/480 DS3504MPOOO His" DF3504FPOOO 1Yls" OS3504MROOO 60 Amp /90*
2P3W 250 OS6207MPOOO 1¥Je" OF6207FPOOO 1¥1e" DS5207MROOO 3P4W 125/250 DS6307MPOOO 1o/ie" DF6307FPOOO 1o/is" DS6307MROOO 3P4W 30 480 DS6404MPOOO 1o/is" DF6404FPOOO 1o/is" DS6404MROOO 4P5W 30Y 277!480 OS6504MPOOO 1W' Of6504FPOOO iYz' OS6504MROOO 100 Amp /150* 2P3W 250 DS1207MPOOO 11!-\s" OF1207FPOOO 11J!is" OS1207MROOO 3P4W 125/250 OS1307,'v1POOO 1'3!Je" OF 1307FPOOO 113!Je" OS1307MROOO 1 3P4W 30480 DS1404MPOOO 11o/1s" DF1404FPOOO 113!Js" DS1404MROOO 4P5W 30Y 277/480 DS1504MPOOO 2" DF1504FPOOO 2" DS1504MROOO 200 Amp I 300* 3P4W 277/480 DS2304MPOOO 2Y:i" DF2304FPOOO 2W DS2304MR000 3~J4iN 30 480 DS2404MPODO 2W DF2404FPOOO 2'14" DS2404MROOO 4P5W 30Y 277!480 DS2504MPOOO 2Y2" OF2504FPOOO 2W OS2504MROOO I 400 Amp I 600* 3P4W 277/480 DS4304MPOOO 3" DF4304FPOOO 3" DS4304MROOO 3P4W 30480 DS4404,'v1POOO 3' DF4404FPOOO 3' DS4404MROOO 4P5W 30Y 277/480 DS4504MPOOO 3W DF4504FPOOO 3%" DS4504MROOO
- Special Disconnect Service Ratings Available (Consult Factory) 150% non-UL ratings (consult technical services) with separate disconnect service.
'* Standard cable bushings shown. Additional sizes available, see page H26. Rating Max.Conductor Size AWG Entrance Dia.
t Always fLrnished w'th screw collar. We recommend cup cap with male inlet and male plug; 30 #8AWG 7 Strand or Flexible Condu;t .187" order catalog number DS(X)CC. (X) is t'le amperage 3~0, 6=50, 1~~00, 2=200 &4=400 #4AWG 7 Strand or Flexible Conduit .302" 60 Boldface figures are for voltage assignment; for different ratings see following pages. 100 #OAWG 19 Strand or Flexible .386"
'f' Control contacts for plugs/receptacles: Use "K" where noted. 200 #4/0 AWG -19 Strand or Flexible .625' Ex: DS3104MROOK 400 SOOMCM-37 Strand or Flexible .937' + "F" Flap Cap style Cover option also available.
ex: "OF ____" vs. l{l Male Inlets: Mounted same as receptacle, all options
- 400 AMP olugs and connectors are suppliec' with cast alur.::num handles. :. available. See pg. H29.
H16 © 2002 Thomas & Be:ts Corporation. SpBcificatioos are subject to change wi\hout notic. WWW.tnb.cOm IPEC00269895
ENTERGY Conceptual Design
~ ~~~.~~~~~.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -028 Rev. 0 Attachment 4 Cost Estimate IPEC00269896
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-028 ~
0 Conceptual PROJECT TITLE:Dies-Driv Gen Backup Sta Batt Charg ESTIMATOR: RCMT
~
0 Preliminary JOB LOCATION: Transformer Yard & Control Bldgs. PROJECT CODE: TBD rcr Definitive Ool!TAGE 0 NON-OLITAGE ORIGINATOR: ORIG. DATE: 06/22/2012 ESTIMATE TOTAL $ 2,137,804 0 CAPITAL Oo&M REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C. F. R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-028 in accordance with Entergy design engineering practices. For SAMA IP2-028, resolution is required to install and readily have available an alternate source for charging the Station's 125VDC battery system othe than from the Station's 480VAC Switchgear Room. This package provides for a conceptual design to install a diesel-driven generator set to be available when required for charging the Stations 125VDC batteries in the event of Station Blackout. Prep*reO byjJ _L ~.:1- ,_.{' Approved by:
""'.,..~~,
q ... ':::!-e... or~
*r_::;;c Zo
/
Date: ?. Date: 7 L IL IPEC00269897
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
~liMA It: Lt:Vt:L EC #: SAMA IP2-028 1-- Conceptual PROJECT TITLE:Dies-Driv Gen Backup Sta Batt Charg ESTIMATOR: RCMT 1-- Preliminary JOB LOCATION: Transformer Yard & Control Bldgs. PROJECT CODE: TBD 1-- Definitive ORIGINATOR: ORIG. DATE: 06/22/2012 Item on
- 1. 1his estimate assumes that this work will not requ1re outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate assumes that core boring is required between Transformer Yard and 33'- 0" cable spreading area (Control Building).
- 6. This estimate assumes that a new diesel generator will be installed in Unit 2 Transformer Yard.
- 7. This estimate assumes that a new battery charger will be installed at Elevation 33'- 0" cable spreading area (Control Building).
- 8. This estimate assumes that new diesel generator and battery charger will be connected and powered by Station Maintenance personnel.
- 9. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 1D. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00269898
Pege 1 of3 7/51201:2 4:53PM SAMA IP:2-tl:28 ESTIMATE DIES-DRIV GEN (6-22*12).xlsx
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
.0 EC #: SAMA IP2.028 PROJECT TITLE:Dies-Driv Gen Backup Sta Batt Charg TAKEOFF:
JOB LOCATION: Transformer Yard & Control Bldgs. PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: ORIGINATOR: ORIG. DATE: 06122/2012 MAN HOURS 'MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QlY UOM CFT NO UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
-
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
- Conceptual MANHOURS DOLLARS - Preliminary Definitive EO/ ENGINEERING 01 STUDY, DESIGN, & CLOSEOUT 480 $ 48,000 02 DESIGN ENGR CONST SUPPORT 160 $ 1B,OOO General Notes: 03 MODS ENGR EOI SUPPORT $
04 SYS ENGRI 5-U ENGR 140 $ 14,000 05 PROJECT MANAGEMENT 500 $ 60,000 06 WORK MANAGEMENT 160 $ 1B,OOO 07 TRAVEL & LIVING EXPENSES $ 08 ENGINEERING DCP ACCEPTANCE REVIEW 120 $ 12,000 CONTRACT ENGINEERING 09 DESIGN ENGR CONTRACT SUPPORT 2,700 $ 324,000 10 SUPL CONTRACT MODS ENGR s 11 MODS PLAN & SCHED -CONTRACT 60 $ B,OOO 12 FIELD ENGRS I PLANNERS 30 $ 3,600 MATERIALS I MISC CONTRACTS 13 MATERIALS $ 2B0,9B2 14 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 15 SWEC CRAFT LABOR/WALKDOWN 1,041 $ 11B,733 1B LOST TIME 104 $ 14,74B 17 SWEC DISTRIBS $ 32,23B PLANT CRAFT LABOR 1B MECH MAINT. $ 19 ELECT MAINT 60 $ B,OOO 20 I&C $ 21 CSG $ MISC EOI SUPPORT 22 QUALilY CONTROL $ 23 TRAINING 48 $ 5,760 24 CHEMISTRY $ 25 OPS I OPS SUPPORT 120 $ 14,400 26 HPIRP $ MISC CONTRACT SUPPORT 27 QUALilY CONTROL 60 $ 4,BOO 28 NDE $ 29 HPIRP $ 30 RADWASTE $ 31 NURSE $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL CONTRACTOR $ 36 VENDOR STOCKING $ 37 DECONTAMINATION CONTACTOR $ 36 RBC'S s 39 SECURilY- Wackenhut $ 40 FIRE WATCH (Rover) s 41 SAFElY 22 s 1,567 CONTINGENCY 42 CONTINGENCY $ 391539 ESTIMATE SUBTOTAL 5,805 $ 1,370,387 SITE ENCUMRANCE PREMIUM (20%) $ Z74,077 Loaders (30%) $ 483,338 ESTIMATE TOTAL $ 2,137,804
- 1. Gather and stage tools and materials 1 LT EL 4 10.00 1.00 40 $ 123.32 s $ 4,933 s 4,933
- 2. Install concrete pad for diesel generator 1 EA IW 2 20.00 1.00 40 $ 137.33 s s 5,493 s 5,493
- 3. Install concrete pad for diesel generator 1 EA CP 2 20.00 1.00 40 $ 96.00 $ s 3,840 $ 3,840
- 4. Install concrete pad for diesel generator 1 EA LB 1 20.00 1.00 20 s 7B.50 s $ 1,570 $ 1,570
- 5. Procure and set new diesel generator 1 EA EL 4 20.00 1.00 eo $ 123.32 $ 38,000.00 $ 36,000 $ 9,886 $ 47,886 B. Procure and set endosure for new diesel 1 EA CP 2 20.00 1.00 40 $ 96.00 $ 14,000.00 $ 14,000 $ 3,840 $ 17,840
- 7. Stage, erect & modify scaffolding as required 1 LT CP 2 12.00 1.00 24 $ 96.00 $ $ 2,304 $ 2,304 B. Stage, erect & modify scaffolding as required 1 LT LB 1 12.00 1.00 12 $ 78.65 $ $ 944 $ 944
- 9. Core drill as required to route new conduit 1 LT EL 2 10.00 1.00 20 s 123.32 $ $ 2,466 $ 2,466
- 10. Procure & install new battery charger in Control 1 EA EL 2 20.00 1.00 40 $ 123.32 s 170,000.00 $ 170,000 $ 4,933 $ 174,933
- 11. Procure & install storage cabinet and inter1ocked 1 EA EL 2 20.00 1.00 40 $ 123.32 $ 42,000.00 s 42,000 $ 4,933 $ 48,933
- 12. Procure and field ered. conduit supports 22 EA EL 5 1.00 1.00 110 $ 123.32 $ B.OO $ 132 $ 13,565 $ 13,B97
- 13. Procure and erect 2" conduit as required 160 LF EL 2 0.20 1.00 72 $ 123.32 $ 1.75 $ 315 $ B,B79 $ 9,194
- 14. Procure, pull & route 480VAC 4/c power cable as 120 LF EL 2 0.03 1.00 7 $ 123.32 $ 1.50 $ 1BO $ 863 $ 1,043
- 15. Procure, pull & route 1/0 power cable as required 360 LF EL 2 0.030 1.00 22 $ 123.32 $ 1.25 $ 450 $ 2,713 $ 3,1B3 1B. Connect 480VAC 4/c power cable to new diesel 1 LT EL 2 20.00 1.00 40 $ 123.32 s $ 4,933 $ 4,933
- 17. Connect 1/0 power cables to inter1ock.ed 1 LT EL 2 60.00 1.00 120 $ 123.32 $ $ 14,798 $ 14,798
- 18. Connect 110 power cable (plug-in jumper) to 1 LT EL 2 20.00 1.00 40 $ 123.32 $ $ 4,933 $ 4,933
- 19. Provide testing as required 1 LT OP 2 10.00 1.00 20 $ 100.00 $ $ 2,000 $ 2,000
- 20. Assist with testing as required 1 LT EL 2 20.00 1.00 40 $ 123.32 $ $ 4,933 $ 4,933
- 21. Dismantle scaffolding to storage 1 LT CP 2 12.00 1.00 24 $ 96.00 $ $ 2,304 $ 2,304
- 22. Dismantle scaffolding to storage 1 LT LB 1 12.00 1.00 12 $ 78.65 $ $ 944 $ 944
- 23. Cleanup and restore area 1 LT EL 4 8.00 1.00 32 $ 123.32 $ $ 3,948 $ 3,946 IPEC00269899
PBQe2of3 7/512012 4:53PM SAMA IP2-028 ESTIMATE DIES-ORIV GEN (&-22-12}.x1sx
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
.() EC #: SAMA IP2-028 PROJECT TITLE:Dies-Driv Gen Backup Sta Batt Charg TAKEOFF:
JOB LOCATION: Transfonner Yard & Control Bldgs. PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: ORIGINATOR: ORIG. DATE: 06122/2012 MANHOURS 'MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT $ $ $
- 2. PAINTING & TOUCH-UP PT $ $ $
FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 2 LT FW 1 50.00 1.00 100 $ 53.60 $ $ 5,360 $ 5,360
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW $ $ $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ $
SUBTOTAL CRAFT & SUB-CONTRACTOR 895 $ 285,077 $ 99,457 $ $ 364,534
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 72 $ 111.13 $ $ 8,001 $ 8,001 SUBTOTAL 967 $ 285,077 $107,458 $ $ 372,535
- RELATED COSTS *
- 1. WALKOOWN ALLOWANCE 1 LT EL 10 $ 123.32 $ 1,233 $ 1,233
- 2. WORK PACKAGE REVIEW 1 LT EL 30 $ 123.32 $ 3,700 $ 3,700
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 34 $ 123.32 $ 4,193 $ 4,193 4 GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 10,746 $ 10,746
- 5. CRAFT IN PROCESSING (20%) $ 21,492 $ 21,492
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 2,149 $ 2,149
- 7. (112 day training, or- 2%)
SUBTOTAL 1,041 $ 285,077 $150,971 $ $ 416,048 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ $ $
PL $ $ $ SUBTOTAL MECH MAINT. $ $ $ $
- 1. ELECT (DEV. MAINTENANCE PROCEDURES) 1 LT EL 1 80.00 1.00 80 $ 100.00 $ $ 8,000 $ 8,000 PL $ $ $
SUBTOTAL ELECT. MAINT. 60 $ $ 8,000 $ $ 8,000
- 1. I&C PL $ $ $
PL $ $ $ SUBTOTAL I&C MAINT. $ $ $ $
- 1. CSG PL $ $ $
PL $ $ $ SUBTOTAL CSG MAINT. $ $ $ $ SUBTOTAL PLANT 60 $ $ 8,000 $ $ 8,000 SUBTOTAL CRAFT/PLANT 1,121 $ 285,077 $158,971 $ $ 424,046 IMPLEMENTATION SUPPORT EO/
- 1. WELDING ENGINEERING 1 LT NM $ $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 160.00 1.00 160 $ 100.00 $ 16,000 $ 16,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM $ $
- 4. SYSTEMS ENGINEERING- ELECTRICAL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 8,000 $ 6,000
- 5. SYSTEMS EINGINEERING- INSTR & CONTROL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 6. SYSTEMS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 500.00 1.00 500 $ 120.00 $ 60,000 $ 60,000 B. TRAINING OPS STAFF 12 LT NM 1 4.00 1.00 48 $ 120.00 $ 5,760 $ 5,760
- 9. QA I QC VERIFICATION 1 LT NM $ $
- 10. CHEMISTRY 1 LT NM $ $
- 11. HP I RP/ ALARA 1 LT NM 1 $ $
- 12. WORK MANAGEMENT 1 LT NM 1 160.00 1.00 160 $ 100.00 $ 16,000 $ 16,000
- 13. OPS I OPS PROCEDURE SUPPORT AND 1 LT NM 1 120.00 1.00 120 $ 120.00 $ 14,400 $ 14,400
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per 1 LT NM $ $
- 2. MODS PLANNING & SCH.- SWEC (Inc! Per Diem) 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6,000 $ 6,000
- 3. FIELD ENGRS/PLAN- SWEC(Incl Per Diem) 1 LT NM 1 30.00 1.00 30 $ 120.00 $ 3,600 $ 3,600
- 4. QA I QC VERIFICATION 1 LT NM 1 60.00 1.00 60 $ 60.00 $ 4,BOO $ 4,BOO
- 5. NDE 1 LT NM $ $
- 6. HP/RP 1 LT NM $ $
- 7. RADWASTE 1 LT NM B. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIREWATCH (Rover) 1 LT NM $
- 16. SAFETY (2%) LT NM I~
1 22 $ 72.14 $ 1,587 1,567
- 19. LOST TIME (10%) 1 LT 104 $ 141.81 $ 14 748 14,748 IPEC00269900
Page 3 of3 7151"2012 4:53PM SAMA IP2-02B ESTIMATE DIES-ORIV GEN (6-22-12).xlsx
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-0 EC #: SAMA IP2-028 PROJECT TITLE:Dies-Driv Gen Backup Sta Batt Charg TAKEOFF:
JOB LOCATION: Transformer Yard & Control Bldgs PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS* ORIGINATOR: ORIG. DATE: 06/22/2012 MAN HOURS 'MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 1. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 15.905 $ 15,905 2,525 *s 280,982 $315,866 $ - .$ 596,848
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 2. DESIGN ENGINEERING
- ELECTRICAL 1 LT NM 1 340.00 1.00 340 $ 100.00 $ 34,000 $ 34,000
- 3. DESIGN ENGINEERING- INSTR. & CONTROL 1 LT NM $ $
- 4. DESIGN ENGINEERING- CIVIUSTRUCTURAL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6,000 $ 6,000
- 5. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 2,700.00 1.00 2,700 $ 120.00 $ 324,000 $ 324,000 6 DESIGN ENG. DCP ACCEPTANCE REVIEW 1 LT NM 1 120.00 1.00 120 $ 100.00 $ 12000 $ 12 000 SUBTOTAL DESIGN COST 3,280 $ 58,000 $ 324,000 $ 382,000
- 1. CONTINGENCY ( 40%) $ 391,539 ESTIMATE SUBTOTAL 5,805 $ 1,370,387 IPEC00269901
ENTERGY Conceptual Design
~ ~~~"~~,~2~,:; Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-044 Provide an Alternate Water Source as Backup for Steam Generator Inventory Prepared by: Approved by:
,&tif~~* .,
/,7
- Date: q ~ 2 o -z o tz Date: ('*
Page I of6 IPEC00269902
ENTERGY Conceptual Design
~ ~~,~~'~,~~,~.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00269903
ENTERGY Conceptual Design
~ ~~~.~~,~2~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-044:
Provide an Alternate Water Source as Backup for Steam Generator Inventory
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-044 in accordance with Entergy design engineering practices. For SAMA IP2-044, resolution is required for the steam generators to be enabled with an alternate means for getting backup inventory water. This package will provide a backup Aux Feedwater Pump and city water as an additional provision for ensuring steam generator water inventory is maintained. The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. 3.0 EXISTING CONDITIONS Steam generator water level is provided for and supplied by the Auxiliary Feed Water (AFW) system. The system's pumps are supplied by connections to supply headers from the Station's Condensate Storage Tank and as an alternate the Station's city water line. The existing pump portion consists of two electrically operated feedwater pumps and a backup turbine-driven pump. Page 3 of6 IPEC00269904
ENTERGY Conceptual Design
~ ~~.~~.~~~:: Indian Point Nuclear Station Unit 2 Package SAMA I P2 -044 Rev. 0 If operation of the electric pumps is unavailable and the turbine-driven pump is also unavailable, supplying the steam generators with water will not be possible.
Provision for an alternate means of supplying and pumping water to the steam generators is required. 4.0 DESIGN CONSIDERATIONS A backup, alternate feedwater installation independent of the Station's existing normal AFW system is required. There is city water piping inside the Auxiliary Feed Pump Building that can be modified with a connection to a new backup pump that will provide another means of supplying water to the steam generators. The pump will be diesel-driven to further ensure availability in the event of station blackout. The pump will be installed in a new outdoor weather proof enclosure along with a small diesel fuel oil day tank with supply capacity to operate 24 hours .. Heat tracing for any outdoor piping will need to be provided. 5.0 CONFIRMATION OF DESIGN The city water piping header enters the Aux Feed Pump Building and connects to the three feedwater pumps. New piping connected to this supply header will provide backup water to the new pump. The new pump and its piping will parallel the existing three pump installation with the new pump's discharge subsequently re-connecting downstream of the existing three pumps. There is room along the west wall (in the northwest corner) of the Aux Feed Pump Building for the installation of an outdoor weather enclosed diesel-driven pump. Exposed outdoor piping will be provided with heat tracing as required. Page 4 of6 IPEC00269905
ENTERGY Conceptual Design
~ ~:'~"~~,~~~2~:,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0
- 6. RECOMMENDED SOLUTION
- 1. Diesel-Driven Pump A. Outdoors along the west wall (in the northwest corner) of the Aux Feed Pump Building provide for the installation of the diesel-driven backup pump.
- At the base of the west wall of the Aux Feed Pump Building, install a concrete pad for mounting the pump and its enclosure.
- Mount and permanently install the pump and enclosure.
- Construct an oil spill containment berm around the weatherproof enclosure.
- Route and install conduit and cable and terminate from distribution cabinet to enclosure to provide electrical power required for heating, ventilation, lighting and heat tracing.
- 2. Aux Feed Pump Room A. At the city water piping entering the room, install piping that penetrates the west wall and connects to the inlet of the new diesel-driven backup pump.
B. At the discharge piping of existing Steam-Driven Pump 22, install piping that penetrates the west wall and connects to the outlet of the new diesel-driven backup pump.
- 3. Install required pipe supports 4 Provide the associated valving required for the installation.
- 5. Provide heat tracing and insulation for any outdoor piping along with a heat source for the enclosure building.
- 6. Provide procedures and training for this new requirement Page 5 of6 IPEC00269906
ENTERGY Conceptual Design
~ ~:,:~'~'~2~::,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. 6"- 150# Gate Valve, Flanged, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 2. 6"- 900# Gate Valve, Butt Weld, C.S., A216-WCB, 2 Mfr. VELAN or equal
- 3. 6"- 900# Swing-Check Valve, Butt Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 4. 3"- 900# Gate Valve, Butt Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 5. 1"- 3000# Gate Valve, Socket Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 6. .6"- Schedule 40 Seamless Pipe, C.S., A 106- Grade B 75 Feet
- 7. 6"- Schedule 80 Seamless Pipe, C.S., A106- Grade B 75 Feet
- 8. 10 Feet x 15 Feet Weather-Proof Enclosure with HVAC and Lighting 1 Mfr. Butler Building PANL-LINE or equal
- 9. Pump, Diesel-Driven, 800 GPM, (detailed specification to follow) 1 WORTHINGTON or equal
- 10. Day Tank, diesel fuel oil storage 1
- 11. 1" - Conduit and Supports 200 Feet
- 12. 120 VAC- 3/c Power Cable 200 Feet Page 6 of6 IPEC00269907
ENTERGY Conceptual Design
~ ~~~.~~~~2~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269908
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 96 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. SA A Engineering Change No.: I P O~Lf Rev. No.: L Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallml!act Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering DYES rKJ NO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C desi!ln or settings chans:~es or activities?
Mechanical Design Engineering .YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES mlNo
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269909
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS Potentiallmeact ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a desiQn specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any chanaes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES IJ.1NO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact equipment or materials related to hvdroQen control?
Human Factors Program DYES CifNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES [)(No
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance DYES 1ll NO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required trainina?
I&C Maintenance DYES [J!NO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and reauired trainina?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES l)tNo
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES ~NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00269910
*~Entergy NUCLEAR MANAGEMENT MANUAl QUALITY RELATED REFERENCE Use Engineering Change Process EN-OC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmj;!act Computer Support and Software DYES (XI' NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES ~NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES tx!No
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite} into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallmgact ASME Containment In-service Inspection (IWE /IWL) Program DYES IX! NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES ~NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269911
~Entergy NUCLEAR MANAGEMENT QUALITY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallm(;!act ASME In-service Inspection (lSI) Program DYES !XfNo
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES ~NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES I:I5JNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES IXf NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES rxJ NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES i&fNO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES LlJ NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES lKJNo
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269912
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 5 OF 6 PROGRAMS AND COMPONENTS {CONTINUED} PotentiallmQact Flow Accelerated Corrosion (FAC) Program DYES jgi'NO
. Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES (&1 NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanQer proQram?
Predictive Maintenance Program .YES DNO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact .YES DNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES !ENO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES DifNo
.. Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
.. Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES IX1 NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES IXf NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269913
.....Entergy
"='
NUCLEAR MANAGEMENT QUALITY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} PotentiallmQact Welding Program .YES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program DYES !XfNO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES IXJ NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES DNO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES {JJ NO IPEC00269914
ENTERGY Conceptual Design
~ ~~:~~,~~2!;,~ Indian Point Nuclear Station Unit 2 Package SAMA I P2 -044 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Location Plan- New Backup Auxiliary Feedwater Pump
- 2. Figure 2: New Backup Aux Feedwater Addition
- 3. Figure 3: Aux Feed Pump Building -West Wall Area
- 4. Figure 4: City Water Supply Header
- 5. Figure 5: Aux Feedwater Pump #22 IPEC00269915
ENTERGY i Conceptual Design
~~!~~~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-044 Rev. 0 N
AUX. FEED PUMP BLDG ELEV. 18'-6" EXISTING AUXILIARY FEED PUMPS NEW BACKUP AUX. FEEDWATER PUMP CONTAINMENT BLDG. UNIT N0.2 YARD FIGURE 1 LOCATION PLAN* NEW BACKUP AUXILIARY FEEDWATER PUMP IPEC00269916
ENTERGY Conceptual Design Technologies Indian Point Nuclear Station Package t------; II>< S<><.rt:r of Scwl So10Jtio11> Unit 2 SAMAIP2 044 Rev. 0 PMP NEW B/'<,CKUP AUX. FEEDWATER PUMP AUXILIARY BACKUP AUX. FEED PUMPS D PUMP ENCLOSUR PMP
#21 6"
PMP
#22 NN.
BFD-31 INSU AND HEAT TRACED (TYP.) (J) CITY WATER ---' (Jl EXI 8"-1 AUX. D PUMP BLD'G. FIGURE 2 NEW BACKUP AUX. IPEC00269917
ENTERGY Conceptual Design
~ ;:~~'~,?.~~~.~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 *v i
- .1' . 1 (
I ; : l .
.l I
! 1 r :
,__ __.........,.l
' t
'~ -, .
. . !f:
PROPOSED LOCATION FOR NE~~
- BACKUP AUX FEEDWATER PUMP FIGURE 3 AUX FEED PUMP BUILDING WEST WALL AREA IPEC00269918
ENTERGY Conceptual Design
~~~~~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 It ID f?
0: w tit 3::
>- i t:
u L*- FIGURE 4 CITY WATER SUPPLY HEADER IPEC00269919
ENTERGY Conceptual Design
~ ~~~~?~~~.~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 I ~*
i FIGURE 5 AUX FEEDWATER PUMP #22 IPEC00269920
ENTERGY Conceptual Design
~ ~~~~~.~2:.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. BUTLER Metal Building Systems,- Typical Weatherproof Enclosure (attached here)
IPEC00269921
Steel building systems, metal building systems and metal roof systems from Butler Manuf... Page 1 of 1
> > Panl-line"" Building System Pani-LineTM building systems offer a size and type for every small-building need.
Two distinctive appearances are available with the single-slope roof design of Pani-Line"' I buildings and the gable roof design of Pani-Line'M II buildings. Both offer maximum usable and volume in a small building, a high degree of functional flexibility. Relocatable end walls make expansion simple. Pani-Line'"' buildings can be used for a multitude of purposes-from simple storage space to complex computerized control stations.
;.i i'l; Jlr ;:,. *'
http://v.vvw.butlermfg.com/building_systems/panl_line.asp 3/9/2011 IPEC00269922
ENTERGY Conceptual Design
~ :::~"~~,~~~2~::: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -044 Rev. 0 Attachment 4 Cost Estimate IPEC00269923
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-044 PROJECT TITLE: Install an Alternate Water Source as Back Up for Steam Generator ESTIMATOR: RCMT Inventory.
JOB LOCATION: Yard near Existing Aux Feed Pumps PROJECT CODE: TBD 0 OUTAGE 0 NON*OUTAGE ORIGINATOR: 0CAPITAL Oo&M ORIG. DATE: 7/11/2012 1---L------.......1 ESTIMATE TOTAL $3,046,418 REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-044 in accordance with Entergy design engineering practices. For SAMA IP2-044, resolution is required for Steam Generators to be enabled with an alternate means for getting backup inventory water. This package will provide an installation using a standby pump and city water as an additional provision for ensuring steam generator water inventory is maintained. Prepared by: Approved by: Date: lf-'Z.D-ZOIZ IPEC00269924
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station 1::::> I IlVlA II:: LI::VI::L t:G ~: ::lAMA lf'Z-044 ~CAPITAL LJO&M PROJECT TITLE: Install an Alternate Water Source as Back Up for Steam Generator 0 Conceptual ESTIMATOR: RCMT Inventory. lJ Preliminary JOB LOCATION: Yard near Existing Aux Feed Pumps PROJECT CODE: TBD D IJIJTAGE (2] NON-OUTAGE
~
Definitive ORIGINATOR: ORIG. DATE: 7/11/2012
~
- 1. This estimate assumes tha
- 2. This estimate assumes tha on site by skilled local craft
- 3. This estimate assumes tha ons in lieu of station maintenance personnel.
- 4. This estimate provides for
- 5. This estimate assumes tra
- 6. This estimate assumes tha This estimate assumes that weld inspections will be limited to visual and LP testing on suction side piping and visual, LP and RT on discharge 7.
piping.
- 8. The bulk of the work in this estimate is non outage and is assumed to occur in 2014 on a 4 day per week, 10 hour per day schedule.
- 9. This estimate assumes the pump discharge piping is 6" diameter schedule 80 and will run approximately 75' outside the building.
- 10. This estimate assumes the recirc. Piping downstream of the isolation valve will not be Safety Class 1.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 11. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point The projected costs provide for 12 anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 13. and progresses as follows: A Outside fence boundary- 20% B. Inside fence boundary - 30% C. Implementation complexity- 40% D. Inside Containment- 50% I IPEC00269925
Page 1 of3 10/312012 4:56 PM IP2-044.xls PROJECT TITLE: Install an Alternate Water Source as Back Up for Steam Generator Inventory. 0cAPITAL Do&M TAKEOFF: JOB LOCATION: Yard near Existing Aux Feed Pumps EST. STATUS: DouTAGE []NoN-OUTAGE I PROJECT CODE* TBD ORIGINATOR: . I ESTIMATOR: RCMT ORIG. DATE: 7/11/2012 MAN HOURS 'MATERIAL$ MATERIA LABOR SUB-ITEM DESCRIPTION IN~O-. .--'"'U'"'N""ITo""T'-"F"'c"=T"=Rc=T"'O"'T=-A'"'L-,----=$""iM""H.,---ll PER UN IT QTY UO M 11-c=FT=--r.-o DOLLARS DOLLARS CONTRACT TOTAL$
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
Conceptual MAN HOURS DOLLARS Preliminary ENGINEERING Definitive 01 STUDY, DESIGN, & CLOSEOUT 180 $ 18,000 02 DESIGN ENGR CONST SUPPORT 40 4,000 General Notes: 03 MODS ENGR SUPPORT 04 SYS ENGR/ S-U ENGR 140 14,000 05 PROJECT MANAGEMENT 200 24,000 06 TESTING (Calibration & Testing) 80 8,000 07 CONTRACT DESIGN EVALUATION SUPPORT 08 ENGINEERING DCP ACCEPTANCE REVIEW 50 5,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 2,150 258,000 09 SUPL CONTRACT MODS ENGR 10 MODS PLAN & SCHED -CONTRACT 280 22,400 11 OSG FIELD ENGRS I PLANNERS 240 28,800 MATERIALS I MISC CONTRACTS 12 MATERIALS 458,450 13 OTHER CONTRACTS CONTRACT CRAFr LABOR 14 SWEC CRAFT LABOR/WALKDOWN 3,090 340,933 15 LOST TIME 309 38,786 16 SWEC DISTRIBS 92,067 PLANT CRAFT LABOR 17 MECH MAl NT. 18 ELECT MAINT 40 4,000 19 I&C 20 2,000 20 CSG MISC SUPPORT 21 QUALITY CONTROL 240 24,000 22 PLANNING & SCHEDULING 23 TRAINING 48 5,760 24 CHEMISTRY 25 OPS 180 21,600 26 HP/RP MISC CONTRACT SUPPORT 27 QUALITY CONTROL 260 20,800 28 NDE 29 HP/RP 30 RADWASTE 31 NURSE 32 ELEVATOR CONTRACTOR 33 WASTE MANAGEMENT 34 HOUSEKEEP! NG 35 EQUIPMENT RENTAL 36 VENDOR STOCKING 37 DECONTAMINATION CONTRACTOR 38 RBC'S 39 SECURITY 40 FIRE WATCH (Rover) 41 SAFETY 63 4,284 CONTINGENCY 42 CONTINGENCY $ 557,952 ESTIMATE SUBTOTAL 7,610 $ 1,952,832 SITE ENCUMBRANCE PREMIUM (20%) $ 390,566 LOADERS (30%) $ 703,020 ESTIMATE TOTAL $ 3,046,418 Non-Outage Work Pour Slab for Pump Enclosure with Berm
- 1. Perform walkdown of work area. 1 LT LB 2 8.00 1.00 16 $ 78.15 $ 1,250 1,250
- 2. Gather and stage tools and materials 1 LT LB 2 4.00 1.00 8 $ 78.15 $ 625 625
- 3. Excavate, form and pour slab with oil berm 1 LT LB 2 40.00 1.00 80 $ 78.15 $ 6,000.00 $ 6,000 $ 6,252 12,252
- 4. Excavate, form and pour slab with oil berm 1 LT OP 1 20.00 1.00 20 $ 115.00 $ $ 2,300 2,300
- 5. Excavate, form and pour slab with oil berm 1 LT CP 2 20.00 1.00 40 $ 96.00 $ 3,840 3,840
- 6. Backfill and compact excavation 1 LT OP 1 20.00 1.00 20 $ 115.00 $ 2,300 2,300
- 7. Backfill and compact excavation 1 LT LB 2 20.00 1.00 40 $ 78.15 $ 3,126 3,126 Set Pump Assembley and Install Building
- 1. Perform walkdown of work area. LT MW 10.00 1.00 20 $ 134.00 $ $ 2,680 2,680
- 2. Perform walkdown of work area. LT IW 10.00 1.00 30 $ 137.33 $ 1,500.00 $ 1,500 $ 4,120 5,620
- 3. Perform walkdown of work area. LT OP 10.00 1.00 10 $ 115.00 $ 1,150 1,150
- 4. Obtain Diesel Pump Skid and required tools. LT MW 10.00 1.00 20 $ 134.00 $ 125,000.00 $125,000 $ 2,680 127,680
- 5. Set Diesel Pump Skid LT MW 20.00 1.00 40 $ 134.00 $ 1,500 $ 5,360 6,860
- 6. Set Diesel Pump Skid LT OP 10.00 1.00 10 $ 115.00 $ 1,500 $ 1,150 2,650
- 7. Set Diesel Oil Day tank LT MW 10.00 1.00 20 $ 134.00 $ 1,000.00 $ 2,680 2,680 Set Diesel Oil Day tank LT OP 5.00 1.00 5 $ 115.00 $ 575 575
- 7. Obtain and erect insulated steel building. LT IW 40.00 1.00 120 $ 137.33 $ 15,000.00 $ 15,000 $ 16,480 31,480
- 8. Obtain and erect insulated steel building. LT OP 40.00 1.00 40 $ 115.00 $ 4,600 4,600
- 9. Provide Light, Heat and Ventilation LT EL 40.00 1.00 80 $ 123.32 $ 10,000.00 $ 10,000 $ 9,866 19,866
- 10. De mob and Clean Up Area LT EL 10.00 1.00 20 $ 123.32 $ $ 2,466 2,466 IPEC00269926
Page 2 of3 10/312012 4:56 PM IP2-044.xls PROJECT TITLE: Install an Alternate Water Source as Back Up for Steam Generator Inventory. 0cAPITAL Do&M TAKEOFF: JOB LOCATION: Yard near Existing Aux Feed Pumps EST. STATUS: DouTAGE []NoN-OUTAGE I PROJECT CODE* TBD ORIGINATOR: . I ESTIMATOR: RCMT ORIG. DATE: 7/11/2012 MAN HOURS 'MATERIAL$ MATERIA LABOR SUB-ITEM DESCRIPTION QTY UO M 11-c=FT=-"'""' IN"'O- . .--""'U""'N""ITo""T'-"F"'c"=T"=Rc=T"'O"'T=-A'"'L-,----=$""iM""H.,---ll PER UN IT DOLLARS DOLLARS CONTRACT TOTAL$ Run and Tie-In Piping from Diesel to Supply and Chem-Ciean Lines
- 1. Obtain Material and Erect Pipe Supports on Building. 1 LT PF 40.00 1.00 120 $ 120.71 $ 4,000.00 $ 4,000 $ 14,485 18,485 Perform walkdown and Co-ordinate Core Bore Into 2
- Aux. Feed Pump Building 1 LT PF 10.00 1.00 30 $ 120.71 $ 3,621 3,621
_ Perform walkdown and Co-ordinate Core Bore Into 3 Aux. Feed Pump Building 1 LT LB 20.00 1.00 40 $ 78.15 $ 3,126 3,126
- 4. Perform Core Bores (2) Into Aux Feed Pump Room 1 LT LB 20.00 1.00 40 $ 78.15 $ 3,126 3,126 Cut, Fit and Weld 6" diameter Sch. 80 Piping from
- 5. Diesel discharge to Pene. In Aux. Feed pump room, then to 6" Chem. Clean nozzle. (90ft.) (12 welds) 1 LT PF 200.00 1.00 600 $ 120.71 $ 190,000.00 $190,000 $ 72,426 $ 262,426
- 7. Tie in Piping at Pump and Chem. Clean connection. 1 LT PF 40.00 1.00 120 $ 120.71 $ $ 14,485 $ 14,485 Cut, Fit and Weld 6" diameter Schedule 40 Piping from 8.
Diesel suction to Pene. In Aux. Feed pump room, then 1 LT PF 100.00 1.00 300 $ 120.71 $ 70,000.00 $ 70,000 $ 36,213 $ 106,213
- 9. Mount and tie in diesel day tank 1 LT PF 20.00 1.00 60 $ 120.71 $ 1,000.00 $ 1,000 $ 7,243 $ 8,243
- 10. Support testing as required 1 LT PF 40.00 1.00 80 $ 120.71 $ $ 9,657 $ 9,657
- 11. Clean-up area and restore 1 LT PF 10.00 1.00 20 $ 120.71 $ $ 2,414 $ 2,414
- 12. Clean-up area and restore 1 LT LB 10.00 1.00 20 $ 78.15 $ $ 1,563 $ 1,563 Perform Electrical and I&C installations
- 1. Provide Heat Tracing as Required 1 LT EL 20.00 1.00 40 $ 123.32 $ 3,000.00 $ 3,000 $ 4,933 7,933
- 2. Provide Piping Insulation as Required 1 LT AW 20.00 1.00 40 $ 97.70 $ 3,000.00 $ 3,000 $ 3,908 6,908 PAINTING & TOUCH-UP REQUIREMENTS $
- 1. PAINTING & TOUCH-UP 1 LT PT 80.00 1.00 160 $ 95.16 $ 1,000.00 $ 1,000 $ 15,226 16,226 FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 200.00 1.70 340 $ 53.60 $ 18,224 18,224
- 2. CRAFT SUPPORT FOR BOTTLE WATCH $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT SUBTOTAL CRAFT & SUB-CONTRACTOR 2,649 $ 430,500.00 $432,500 $284,150 $ $ 716,650
- 1. CONSTRUCTION SUPPORT (8% OF LABOR$) 1 LT 212 $ 107.27 $ 22,741 22,741 SUBTOTAL 2,861 $432,500 $ 306,891 $ $ 739,391
- RELATED COSTS *
- 1. WALKDOWN ALLOWANCE LT PF 25 $ 120.71 $ 3,018 $ 3,018
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING LT PF 104 $ 120.71 $ 12,554 $ 12,554
- 3. TOOL ROOM ATTENDANTS (-3.5%) LT EL 100 $ 123.32 $ 12,332 $ 12,332
- 4. GENERAL CRAFT DISTRIBS. (10%) $ 30,689 $ 30,689
- 5. CRAFT IN PROCESSING (20%) $ 61,378 $ 61,378
- 6. HUMAN PERFORMANCE & ALARA TRAINING LT $ 6,138 $ 6,138
- 7. (1/2 day training, or- 2%)
SUBTOTAL 3,090 $ 432,500 $ 433,000 $ $ 865,500 PLANT SCOPE
- 1. MECH MAINTENANCE PL PL SUBTOTAL MECH MAl NT. $ $
- 1. ELECT MAINTENANCE 1 LT PL 20.00 1.00 40 $ 100.00 $ 4,000 4,000 SUBTOTAL ELECT. MAINT. 40 $ $ 4,000 $ $ 4,000
- 1. I&C (Dev. Instrument Calibration Procedures) 1 LT PL 20.00 1.00 20 $ 100.00 $ 2,000 2,000 PL $
SUBTOTAL I&C MAINT. 20 $ $ 2,000 $ $ 2,000
- 1. CSG PL PL SUBTOTALCSG MAINT. $ $
SUBTOTAL PLANT 60 $ $ SUBTOTAL CRAFT/PLANT 3,150 $432,500 $ 439,000 $ $ 871,500 IPEC00269927
Page 3 of3 10/312012 4:56 PM IP2-044.xls Rev. I INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 11-0 EC #: SAMA IP2-044 PROJECT TITLE: Install an Alternate Water Source as Back Up for Steam Generator Inventory. 0cAPITAL Do&M TAKEOFF: JOB LOCATION: Yard near Existing Aux Feed Pumps PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: DouTAGE 0NON-OLJTAGE I MAN HOURS ORIGINATOR:
'MATERIAL$ MATERIA ORIG. DATE: 7/11/2012 LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM $ $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 4. SYS ENGINEERING- ELECTRICAL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 5. SYS ENGINEERING- INSTR & CONTROL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 6. SYS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 200.00 1.00 200 $ 120.00 $ 24,000 $ 24,000
- 8. TRAINING (OPS Staff) 1 LT NM 12 4.00 1.00 48 $ 120.00 $ 5,760 $ 5,760
- 9. QA I QC VERIFICATION 1 LT NM 1 240.00 1.00 240 $ 100.00 $ 24,000 $ 24,000
- 10. PLANNING & SCHEDULING 1 LT NM 1
- 11. HP I RP/ ALARA 1 LT NM $ $
- 12. CHEMISTRY 1 LT NM $ $
- 13. OPS (DEVELOP/REVISE PROCEDURE(S)) 1 LT NM 1 180.00 1.00 180 $ 120.00 $ 21,600 $ 21,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per Diem) LT NM $
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 280.00 1.00 280 $ 80.00 $ 22,400 $ 22,400
- 3. OSG FIELD ENGRS/PLAN- SWEC(Incl Per Diem) 1 LT NM 1 240.00 1.00 240 $ 120.00 $ 28,800 $ 28,800
- 4. QA I QC VERIFICATION 1 LT NM 1 260.00 1.00 260 $ 80.00 $ 20,800 $ 20,800
- 5. NDE 1 LT NM $ $
- 6. HP/RP 1 LT NM $ $
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEP! NG 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIRE WATCH (Rover) 1 LT NM $ $
- 18. SAFETY(2%) 1 LT NM 63 $ 68.00 $ 4,284 $ 4,284
- 19. LOST TIME (10%) 1 LT 309 $ 125.52 $ 38,786 $ 38,786 SUBTOTAL CRAFT/NON-MANUAL 5,150 $432,500 $ 647,430 $ $ 1,079,930
- 3. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 25,950 $ 25,950 SUBTOTAL INSTALLATION COST 5,150 $458,450 $ 647,430 $ $ 1,105,880
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. DESIGN ENGINEERING- INSTR: & CONTROL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 4. DESIGN ENGINEERING- CIVIL/STRUCTURAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 5. TESTING (Instrument Calibration and testing) 1 LT NM 2 40.00 1.00 80 $ 100.00 $ 8,000 $ $ 8,000
- 6. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 2,150.00 1.00 2,150 $ 120.00 $ 258,000 $ 258,000
- 7. ENGINEERING DCP ACCEPTANCE REVIEW 1 LT NM 1 50.00 1.00 50 $ 100.00 $ 5,000 $ 5,000 SUBTOTAL DESIGN COST 2,460 $ 26,000 $ 258,000 $ 289,000 SUBTOTAL INSTALLATION & DESIGN COST 7,610 $ 673,430 $ 258,000 $ 1,394,880
- 1. CONTINGENCY ( 40%) $ 557,952 ESTIMATE SUBTOTAL $ 1,952,832 IPEC00269928
ENTERGY Conceptual Design
~ ;,~;,~,~~E:,~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-053 Keep Pressurizer PORV Block Valves Open Preparep~- f?.Ja4{~ Approv~
c;::; ~
/
Date: c?f -2D-2C>I7. Date: ~r . ' "\ '-' ; Page 1 of5 IPEC00269929
ENTERGY Conceptual Design
~ ~;~,~~,~~~~'~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of5 IPEC00269930
ENTERGY Conceptual Design
~ ;~~~~.~!~,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-053:
Keep Both Pressurizer PORV Block Valves Open
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-053 in accordance with Entergy design engineering practices. For SAMA IP2-053, resolution is required for Pressurizer Power Operated Relief Valve (PORV) Block Valves MOV535 and MOV536 to be open when the plant is operating under normal conditions. This package un-installs the modification that currently keeps the block valves closed during normal operating conditions. The package will restore the original design requiring the valves to be open during normal operating conditions. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. 3.0 EXISTING CONDITIONS Originally, the PORV Block Valves at IP2 were intended to be open during normal plant conditions and automatically close in order to isolate a PORV should it leak or Page 3 of5 IPEC00269931
ENTERGY Conceptual Design
~ ~~~.~~~~2~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 fail open. However, a modification has been made to each block valve control circuit that maintains the block valve closed during normal plant conditions.
Specifically, Modification FEX-96-12241-E installed an interlock in each block valve's control circuit. The interlock was added to the opening circuit of each block valve to keep it closed during normal plant conditions and automatically open the closed block valve when approaching the PORV's actuation setpoint. 4.0 DESIGN CONSIDERATIONS The control circuit of each PORV Block Valve would be modified to function as originally designed. The presently installed Modification FEX-96-12241-E will be removed and the operation of the block valves' original design restored. 5.0 CONFIRMATION OF DESIGN This package will provide the required evaluation, analysis, calculations, and design basis documentation required for the modification. This package will also provide the documentation and work steps to physically remove the modification made to the PORV Block Valves. It will also include the provisions for re-installing the wiring that will restore each valve's original isolation function.
- 6. RECOMMENDED SOLUTION
- 1. Perform an evaluation of the Fire Protection System and its cable separation requirements. Provide the basis to confirm that the change being made will preserve the integrity of the block valve's power wiring and its ability to function as required
- 2. Prepare a new Design Package to make the required modifications. The package will, at a minimum, include documentation equivalent to that originally provided in Modification FEX-96-12241-E.
- 3. Physically remove the existing modification installed by FEX-96-12241-E.
NOTE: This effort will be the greater extent of the field work required.
- 4. Install the wiring associated with the PORV Block Valve control circuits and necessary to restore each valve's original isolation function Page 4 of5 IPEC00269932
ENTERGY Conceptual Design
~ ~:~,~,~~2~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0
- 5. Perform a circuit continuity and functional testing of PORV Block Valve circuits and function.
- 6. Provide procedures and training for the PORV Block Valves.
7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Miscellaneous cable and wire Minimal Page 5 ofS IPEC00269933
ENTERGY Conceptual Design
~ ~~~.~~,~~2~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269934
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 1 OF6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. Rev. No.: A Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmQact Civil/ Structural Design Engineering DYES txJNo
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES (')a NO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES Q§1 NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00269935
***Entergy
-===-
NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I PAGE 97 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of 6 DESIGN ENGINEERING PROGRAMS PotentiallmQact ASME Section Ill Specifications DYES ~NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (1 0 CFR 50.44) (if applicable) DYES 00NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program 1111 YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES ~NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected '
procedures, required actions and required training? Mechanical Maintenance DYES ~NO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES OU'No
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES ~NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00269936
A NUCLEAR QUALITY RELATEO EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 98 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET3 OF6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallm~act Computer Support and Software DYES tK] NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental impact DYES IXJ NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES ~NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite} into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) DYES D!j'NO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering DYES Q!!No
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallm!;!act 1 ASME Containment In-service Inspection (IWE /IWL) Program DYES I! No
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES [8jNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testin~:J?
IPEC00269937
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmaact ASME In-service Inspection (lSI) Program DYES 00NO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES 00NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES ~NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES ~NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Pipina & Components?
Boric Acid Corrosion (BAC) Program DYES DJ!No
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269938
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET50F6 PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Flow Accelerated Corrosion (FAC) Program DYES lXI NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES IXfNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES ilJ NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES f8l NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program .YES ONO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES iXJ NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES ONO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES ~NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves {fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES tRfNO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES fXl NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269939
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY REI.ATEO REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 101 OF 150 REV.11 ATIACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmeact Welding Program DYES 1)!1 NO
- Does the proposed activity impact or involve a special process, such as welding, brazing or solderinQ?
Safety Program DYES ~NO
- Does the proposed impact or activity involve personnel or industrial safetv?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES DNO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES DNO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R} where the impact is more than negligible?
IDetailed Impact Screening (Attachment 9.4) Attached? DYES ~NO IPEC00269940
ENTERGY Conceptual Design
~ ~~~~~,~~~2:,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 Attachment 2 Conceptual Design Sketches N/A IPEC00269941
ENTERGY Conceptual Design
~ ~:~"~'~,~~~2~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. Indian Point Design Engineering Modification No. FEX-96-12241-E, Auto Open of PORV Block Valves (attached here)
IPEC00269942
*Doc. ID.
FEX- Lt ~ 122 Lf 1-£
.. J *
**Rev. No. I Seq. No.-* . . '
IPEC00269943
IliQ~ POINT STATION
~ . DESiGN ENGINEERING ATTACHMENT 7.2 Page i of3 Closeout Tracking Form- Post Return To Service Checklist (P-RTS)
TASK RESPONSIBLE N/A COMPLETED OPEN REFERENCE DEPARTMENT ITEM I OPEN
/ ITEM#
- 1. Appropriate Drawings Transferred DE
.2. Department Procedures, including SE D D Graphs, Logs, COLs, Preventative Maintenance, etc I&C *-: .* D / ET OPS u
/
MAINT u u CHEM D
- D RadPro D D operations & I&C
- rq; Jfi*. : '
- 4. Work Packae:es PS&O I t7.~
* *5. UFSAR Licensing ...
- 6.
- Tech SJ)eCS Licensing '\'....
*1:: LicenSing Commitment Database Licensing
- 8. Design Basis Documents ES N/A
' 9. Major Component Database ES
- 10. Component Function Database ES
- 11. PlaDt Equipment Database (Maximo PEDB)
ES
- {p }. 10
- 12. SPIN DE IS"
- 13. Calculations DE J
- 14. Coudition Reports Various
- N/A
- 15. ALARA RadPro
- 16. EQProgram DE jO
- 17. Aluminum in Containment DE 1'2*-
- 18. NRC89-10MOVs P&CE '/
- 19. AOV' P&CE /
- 20. CheckValve P&CE I "'1..--"
- 21. EPIX Program P&CE
- 22. Maintenance Rule Program Changes SE /
- 23. lSI ASME section XI P&CE
-- -] I,I'U v
- 24. 1ST P&CE
- 25. SQUG (Seismic) DE J IPEC00269944
JJO* 14..0-':1
- IND~POINTSTATION REV.4 DESIGN ENGINEERING ATTACHMENT 7.2 Page2of3 Closeout TraekiDJ! Form - Post Return To Serviee Checklist lP-RTS TASK RESPONSffiLB N/A COMPLETED OPEN REFERENCE DEPARTMENT ITEM I OPEN ITEM#
- 26. Operator Training OPSTRAIN J
- 27. Simulator Training Guides, Lesson Plans, NUCTRAIN 0 0
*
- Student Handouts, and Training Sehedules updates identified and planned. /
- 28. Technical Training NUCTRAIN
- 29. Simulator Simulator Trainin2 / '2.. '?>0
- 30. Plant Process Computer includin2 PICS Comouter APS ~ /
- 31. Software Quality Assurance . CoiiiDuter APS r=li[.- I '1,...-
- 32. CMs Maintenance ]'/
Parts Procurement lk:
- 34. Fire Protection P&CE It-3S. FloW Accelerated Corrosion (FAC) P&CB ll!" . \1-oo"
- 36. Vendor ManUals SE ~
- 37. S~D~tiou Trainin2 J lw 38.
39. Plan Plan
- 40. Procn:rement Requisitions, Purchase Security IEP Procurement Hu;: ., I
\\
Orders, Warehouse Records and Procurement Specificatiou updates- ' . identified. ' /
- 41. Plant Chemistry SE, Chemistry l 42.
43. 45. 46. 47. 48 .
.49.
References:
s> ~~ ?~~ D~-k~
- 9) 1~'-'S d~P~
- 10) __:_M..::....o~=---=-"P.:....~==u..A..e..__;;::::;..._....:.F'_e__:_"{_-_q..:......:::.b_-_f_:.")...._L-__:..4....:..1_E:"'.:::-__;_~
__ * ....:...t_ __ IPEC00269945
LJE- 12.629
* *~POINTSTATION REV.4 DESIGN ENGINEERING
- 18) ----~~~~~~~~~~~~~~~~--~~~~-----------
1~ --~dL~~~~--~~~~~~~~~~EC~~~~~~==**~~~~------ 20} O.., \;,_,CL. <i~~r~\....
- 21) ~\;'-lit Se .... rc..\- .,.p. iL Co_....:-t.X"IRa<.b~.;kb'-".C I
- 22) (o..,.).;'ti:.:..J ~.. ...,""' C e.-"1.92 .-2od\.f-Ofl~'C...
- 23) CAJ~v\~ ~~Y~ ~.~ __GP";,-2-pcf-~
n , * - " r \ -.:rtt..-JJ:;eJo ~"fi
- 24) C ¥-> IJ.S Yl... 'l,...l.k \ ~c \ua ' C(?.. S -X\'> ;t -I "f'n,- 0'25o'+-~..U:.?'l:-lf!f8.;../ooYi
- 25) .:C,..,c 'uhJ. ,.k- JA,a-J r-~ -' +.;~ ~ pt;. *~fl. c.,.,_.. . * *.
- 26) :S:t.l ~QU<;, cLJ*~~J 'ot..\~o ~J4.ol':d.D<ls~r~sg~6 I
- 27) 1\..u,\uiW_;_ ~(¥=*;4 '- ~ e.o\'N..,_">];~D~
- 28) f'- IJ. J s.a-:t- ~ s t.U'._\k...L.. J-e~ u.er!:~ *a..... F P. r Jl...v ~
- 29) NoOo-<V~m~..e-~ ~'M"J\-,>fi~D q<!?s oc~ .........~ Hob.
- 30) b~~ ?-~ C ~ ~ ,,\;o\4--T~ Mo-4'~
- 31) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
3~ ---------------------------------------------------------
- 33) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
3~ ---------------------------------------------------------
- 35) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Post Modification Testing CPMD - Does the modification involve Reactor Protection System, Engineering Safeguard System, or SSCs that can affect the reliability or power generation of Indian Point 2 {refer to~ject Guidance document for further details)? Yes 0 No 12{ If yes, was a PMT initiated and performed as required? - - - - - - - - - - - - - - - - - - - IPEC00269946
-*, FORM Wli>(J0/961 CONSOLIDATED EDISON CO.-INDIAl~ POINT STATION MODIFICATION PROCEDURE COVER SHEET
***' Sheet I of 3
*
- MJWu: £J Minor £J Set Point Only Q Generic Major £J Generic Minor £J Environmental Mod No. FEX-96=12241- E Preparer ~
Title/Subject Auto Open of PORV Block Valves Project No. 12241-26 ESRIFER No. - - - - - - - - - - - Class: * * .A £J FP 0. MET £J Non-class Penetrates Existing Fire Barriers * ~ £J No Mandate: £J Yes Wl::f.2 Mandate Source - - - - - - - - - - - - - - - - - - Withdrawal Date: ~D,.,ec..._2..:8...,. ..,1.c_99 4 7,___ _ __
Purpose:
This modification adds an interlock to the control circuits ofMOV-535 and MOV-536 to open these PORV block valves when the RCS pressure increases near the actuation setpoint of the PORV's Construction Documents: Attached Drawings Reference Documents: EI-6009, REV lO. Safety Evaluation: 97-008-MD N" .2. Classification: Cf 1 - 008 C.. L Specifications: _..._N:u./.QA~------- DBDs: RCS I Steam Generators I. Drawings: See attached list Other: Cleaning: ------=.a..----------------- Special Test Equipment: _ _ _,_,.~.;!LO.---------------- Special Precautions and/or Limitations: -~.0..-------------- Scope of Work: See Sheet 2 and Sheet 3 Procedural Requirements: SAS Change? Q Yes J!L.N2 Simulator Change? * .:US a No CCR Human Engrg? - B Y§ £J No System Oeser Change?
- Ya £J No Se~int ChglAd~? a YM a No EQ Equipt!Requirements? £J Yes *l:l.2 Loop Sketch* Change? II Y£s a No -
Contains an Essential Corrective Action? a Yes
- N.Q TNMS Change? C:: 9 'tes * ~
<@ARChang!? * :W a ~"iCht:.S Prerequisite & Corequisite Mods and Projects at Other Stations: _,.~N.:!!/..:!A.____ _ _ _ _ . ------
Test Requirements and Acceptance Criteria: functional tests li~ted on sheet 2 and other tests as deemed appropriate ASME XI Quality Group: a A OB ac
- Exempt/Qutsjd,e Boundaries Weld Requirements: _........_!L.<:!~-----------------------
11 anager, Sy Engineering and nalysis _.~~~~ fv)441ht..~ y/zy~ Manager, Q 1ty Assurance
----~N~A _______________
':i Manager, Nuclear Safety and l;!_c.e":~ng*
trze.ll. '-ltwltJ
.f:t';;JCK£i=1 * ~m\
SNSC Meeting No:(s Required)r
*Required for Minor and Set Point Only Modifications Rtw 0 is fer Pre Olltage Werlt ertl)*. This Pre etdage work is described on Sheet 3 of3
)RI IPEC00269947
Mod. Proc. EEX-96-12241-E Eage 2 of3 Scope of Work
- A) Addition ofan Interlock This work involves adding an interlock to the opening circuit of the PORV block valves (MOV -535 and MOV-536) to automatically signal the PORV block valves to open prior to reaching the PORV actuation setpoint. The interlock will use spare contacts of relays which are actuated by pressure controilers (PC-474B and PC-457F). These controllers will energize auxiliary relays when the pressurizer pressure reaches 2300 psig. PC>474B will provide a signal to open block valve MOV-535. PC-457F will provide a signal to open block valve MOV-536. These pressure controllers presently provide a signal to act as a permissive to open the PORV associated with the particular block valve.
The circuit change for MOV-535 will involve installing a cable (1-7/C-12 A WO) in existing raceway between panel FBF and panel SB2. Two spare conductors of existing cable JC3-JJ4/1 will be used to connect from panel SB2 to panel G3. The use of the existing spare conductors is necessary to aid in construction. This wiring will be used to connect in parallel an existing nonnally open contact of relay PC-474B/X with the other signals which energize the open contactor of the motor starter. The circuit change for MOV-536 will involve installing a cable (1-7/C-12 A WO) in existing raceway between panel El and panel H4. Two spare conductors of existing cable JH5-JJ4 will be used to connect from panel El to panel 03. The use of the existing spare conductors is necessary to aid in construction. This wiring will be used to connect in parallel an existing normally open contact of relay PC-457F/X with the other signals which energize the open contactor of the motor starter. B) Change ofHigb RCS pressure alarm setpoint The high RCS pressure alarm setpoint of PC-4551 will be changed from 2310 PSIG to 2300 PSIG. This will be the same setpoint as PC-474B and PC-457F mentioned above. In addition, spare contacts of both relays, i.e. PC-474B/X and PC-457F/X, will be wired in parallel with the existing contacts of relays PC-4551/X and PC-4560/X to annunciate on panel SAF, window 1-2, when the RCS pressure reaches the setpoint or the PORV block valves receive an auto-open signaL The engraving on the lens of window 1-2 will be change to" Pressurizer High Press 2300 PSIO." Test and Acceptance Requirements
- Verify the usability of existing cables by continuity testing .
- Verify the operation ofPC-4551 at the new setpoint of2300 PSIG by a calibration check
- Simulate the operation of relays PC-457F imd PC-474B, confinn the opening ofMOV-535 and MOV-536 respectively by control room valve position indicating lights. Verify the actuation of annunciator window SAF, window 1-2 when either PC-457F or PC-474B is actuated.
- Simulate a process signal of2300 PSIO to PC-4551 and verify the actuation of annunciator SAF, window 1-2.
- *With the block valve in the open position, operate the control switch to the "close" position and the "pull to lock" position". Confirm closure of the associated block valve.
IPEC00269948
Mod. Proc. FEX-96-12241-E Page 3 of3
- Drawing Ljst DMD 206782 - AC DMD 208823- AE DMD 225255- AA DMD 225305- AB DMD 225412- AK DMD 241169- AX DMD 241169- AY DMD 244415- AG DMD 244416- AK DMD 9321-3268- AG DMD 9321-3281- AN DMD IP2--S-000209- AF DMD IP2--S"000210- AF DMD 1971M2304 - AF IP2F- 000001* BH IP2F- 000002- BG IP2F- 000003- AG IP2F- 000004- CP EM 309071 -00
)
Rl IPEC00269949
Changes to the FSAR due to Mod Procedure FEX-96-12241-E
- 1) Add the following description to the FSAR:
Permissive open interlocks for each power operated relief valve (PORV), PCV-455C and PCV-456, are generated when the reactor coolant pressure is 2300 psig or higher. At thi*s point, the motor operated block valves associated with a PORV will also open and an control room annunciation will be generated. The actuation signals for th~ PORV.s are generated by separate instrument channels.
- 2) Change Figure 7.2-21 as marked on attached copy .
IPEC00269950
"'U m () 0 0 1\.) (J') (.0 (.0 r~ C1l ") --ll. 0 i1 o-
;2 c:v {
..,I)
. ~
13 t' 0"" I o-Vi N rJ
~ ~
..c.
' I rt, I
., ISU I I
, o. 7..1*111 ' '
AVAil.ABLE f'Oft CONTitDL FIIIICTIOH SWITtiUNe AVAILI\BLE FOft CONTROL ruKctiOH SlfiTtlllltlt WRIHO lliRIHG TESTS TEllS
'"'0
"'1 I'D ttl. f"JI.T. 111. r.11.r. ttl. f"JI.J
- VI 0 r:::
.... z0 i0en
"'1
'"'ON
~
""'~ro
~-s I'D-o Ul-*
j; z r-0 Lo. r.n.r. Let, f'.R,T. LO, ,..R.T. Lo. r.n.r. n-s rt(l) c
"'1 , ~
. . . .y VN..V£1 o.,
- ,c (I)
"'-I Q nl0 I z
tn""'~
'<I'D
.,n "N
I N
-t m c 0c;; TO CIU(SEE FIG. 7.Z- 34) TO Ctt.U(SEE FIG l2-34) ,TO Cit. W(SEE FlO. T.Z-34) TO Clt.lll(SEE FlO. lZ-34)
ClT ClT AT
~-c.
r+o I'D:;, z ClT S.P. S. P. S. P. S. P. AIHABlt: 3c-r
"'1
=t 0z liE ATlAS 0 N
_. n p
- J 0..
0
- J IJl
~-------~~-------
NOT EaR FABRICATION INSTRUMENT LOOP SKETCH OR INSTALLATION
...:! OF .._
FOR REFERENCE ONLY ILOOP 3 .9S 1
#_....:::....;:::......;;::...__ _ ~
REVIS ION 0 DA':::'E -t - t ?' * :t a REFERENCES P- ,;_ ';' ..? :3 * ..;: :J ,f:., ~ ~--!--.
) * ?"' ;..:.; :.4 ~
I:. !. R
!.l'. *: InS':. =~rrn.:! !Rl!V. :1 IPEC00269952
"1J m () 0 0 1\.) z
.I
~ ~
(j) t"' 0 00 (!) >r:J <: 0 i'IJ ::U8 (!) lrJ H 'tl 1--i rn*n Fflof1 FtroM
- n ti~
0'1
~
FRot1 V> f'J*I**U:fA Prt*iS'A f>l1*fS1A Pt1* 4 74-11 !.'0 ! i'\; !1:
~~u
!2: (J),
n z 111 1--i
~~
~~~
t"'
- 1-1 n 0
~
*~ ~
>r:J i!;
I~~* (\'.. tJ
'I) !I" H
0 ~Q
\ ~] z !2:8
'l
~
tol
-'\)
C"l H 0
!2:
r....
"' """..,. u:.0 "fl,. "
H z
""'t Cu tl (j\ s:::' ,
>r:J UJ 0 ti
!d
~
~{\
-li.
....... ~re
>r:JZ 1:'11-i
'0
~ f
*u ~n t"'
0 0
})\ 1:'1 'tl
.....* \}\ 0 (J)
~ti li\ "'
c'-- 1-<:ti n
"a '
\: ::ll Q) 0 h,
~ t"'
(,..
- 0 0
0 ~ 'tl
~
~ ,,
\ ....
~ .__._
~
I t.. I I I" I I l2:1lf1-~ I~.!.f:l
~
~ LOC:ATI!.D IN <!. t! * 'R. 0 @ t t:
X
~
\'.
I 1\,. Orl Ft.><13o 11(0 v Rl'\ Cii JJ-6 " TO Pt! V-"'N.SF"* TlfiP Pol'\V'; TO Pff(,(./CJII11( It VII lilA IJU
~
~
..P~:!>-*"-N~ UTt:. t.'.u.Jt::t..
()
FORM Nl32 1/95
- Modification No. EEX-96-12241-E System Reactor Coolant System Function: Alarm/Control SET POINT DEVICE DATA FORMS Rev__
Tag(s) ~------ Date Feb 6. 1997 ALARM Action: Incr., Decr,JSet, Reset Iocr. Process Range: (Units.: PSIG, F, GPM, Other) 1700-2500 PSIG Signal Range: (Units: Volts, Millivolts, Amps, Milliamps, PSlG, Other) .J0-50mA Dead Band Range (Units: PSlG, F, GPM,% Scale, Other) 0.3-06 rnA below set point Set Point (Process Units) - (Summer/Winter HV AC Only) 2300 PSIG Set Point (Signal Units)- (Summer/Winter HV AC Only) ..40.0mA Set Point Tolerance (Process Units) ..+1* 0.4 rnA Set Point Source{s) Linear jnter:polatjon of prevjous sewoint of 23 I 0 .t!SIG at 4Q.5 rnA Process Critical Value (Signal Units) NIA Source of Critical Value
) (Tech Spec, MFR. etc) N/A Function js Alarm only. no actuation js based onJP.js alarm First Consequence of Exceeding Critical Value (eg, Tank Rupture, Tech Spec Violation) _ _.JtN,../....,A,_ _ _ _ _ _ _ _ _ _ _ _ _ __
Overall Channel Accuracy(%) N/A Remarks Process ran~e js 1700 - 25()() I!SfG,...Jbe ran:e at the transmitter is 1720
- 2520 I!SIG.
This modification chan~es th<: se!point of this instrument to match the setpojnt of the conttollers used to generate the PORY block valves auto-open interlock signal ( pc.457F and PC-474B).
':i>,*~~
Preparedby: _,._~~t~er~K~el~lv~-~-~~~~~~~r-----------~F~e~b~6,_lw9~21
. Print/Sign \ Date Mgr. System Engineering and Analysis - - - - - - - - - - - - - - - - - - - - - - - - -
(Implemented) Print/Sign NOTES: I. The set points listed are initial settings for the devices issued with this modification procedure. Any subsequent set point changes shall be handled as a separate plant modification.
- 2. State set point and/or calibration range for each device in the loop(s) from sensor(s) to bistable(s).
- 3. For protective relays, fill out attachment fonn "Protective Equipment Data and Test Record."
- 4. For instruments, Mechanical Engineering Specification MP90*112, "Guidelines for Preparation of Instrument Loop Accuracy and Setpoint Detennination Calculations" shall be complied with.
IPEC00269954
safety valves. -The ?ower Operacec ~elief Valves are provided to limit the operacion of che spr~~~ 1 oade~ ~-=s~~-;~Q- sa~Q~v valves.
,---- The ?ORV' s w:.11 also open at a programmed pressure secpoint: (as a par: cf the O?Sl wha~ che ~eact:o; Cocl~~~
c~~erature is becween 0°: ~~d 295°:. This provides protect:ion for the Reaccor Vessel against: brittle-fracture due to ccld ove=;>ressurization by preva~~ing the RCS pressure from ~~ceeding the Appendix "G" cu~~es. (See Section 3.l.!l. I 4* MOV-535 ~*d MOV 536 (see :i;ure )?-1 are installed ups:ream cf PCV-453C and PCV-436, respectively, ~n order to isolate a ?ORV should.i: leak or fail open. This is allowable since the code sa!ety valves are sized to prot:ect the ~c-s !rem ove=;>ressure wi:hout the aic c! either ?ORV. The motor operatec block *..-a~ves operate on 480V .'b..C
)r "",__.
power; MOV-536 is supplied :rem MCC-25A, MOV-535 from MCC-253: Soth valves fail *as is* on loss cf electrical ~ower. ~ach block valve has its own 4 position switch on panel ?C? in the control room.
' I I c. t.,*, The switch ~csitions are TF.I? Pu~LOt~. CLOSZ, l..v~ !-......:.. '-'='-.~~ )wt..,....J,O,
}..UTQ, and OPEN.
t>J Prvfo '~ v.:.\v~ ...ttl I ope tJ ..._,'~,......., ~ K.c..s. pru.&........,!/.Q_ A nitrocr~r. acc*~lato; =v~tom SU?plies actua~~ng e..,_'-"-e.ls 2Joo f'S'j. ~ ..\.,<A f~uid for open~ng the ?ORVs. This arrang~~ent
~ ......\\.., cl~ ""~
~ \' rw:~ <r d.z.c.r""""'eA k \.....,
prevents a common air supply fail~== from causing c:.. ":!. & 0 rs*s . inoperability of both PORVs. (}. detailed description of the OPS Nitrogen Accumulatory syst~~ is provided in section 3.1.!.1). s ';~k-... 1>-CA.*f ~ sf I Kcs
~to.-..,.+/- .\.o 1'-\oJ 7r.;:,uzJ.c........L F fi:Y - c:, b- 1 tl.. '-11-e *** IPEC00269955
There are twe c~ncrol chains and the *:cxboro* switch is sat up s~ch that independent ccn:rcl signals are always usee for :he :.we cha~~s. Cha~~els II! and :V are also used
~o generate interlock si~als for power operated relief valves ?CV-456 and ?CV-455C respec=ively at pressure abo~e 2185 psi, and i~~tiate a l~w press~== alarm when the pressure fa:!.ls bel.ow 2185 psi .
... 6 The first c~n::rol chain/is usee. ::o initiate a fixed low pressure ala:=m ( ?C-~5~ at ~ psig and open power F' operated relief valve ?CV-456 at 2335 psig (?C-45~;-
providec the interlock fr~m cha~,el !!I is satisfied (refer
- o ?i~~== 15). This in=erlock will be satisfied if cha~,el
--- * ~nc~ca~~ng
~~~ ~s * * *
- a pressure a~ove * ~-oo
'~
- ps~g. The ac::ua*ticn of a ?ower Opera~ed aelief Valve. The switching circuit~y is in:erlock. !n aCdi~ion, ?:-45&G ac~ivates a fixeC high pressure alarm a~
2335 ;:si;&
!n order to prevent Departure from Nucleate 3ciling (D~3) in the aeact~= Coolant, ::he ?ressuri~e= pressure is maintained above tha~ c~rrespcncing ::~ the saturation press~re for the full l~ad c~elant ho:: leg temperature. ?~,
additional mar;in of safety is also included to allow fer higher t9rn9eratures d~ring load and ove~ower transient condi:.ions. On this basis, the pressure control point was selected at :he value 2235 psig (?Refl, which =~~ins
- R. c.~ ~+~ ~e \. ~ -h Mc.J ?f"bet.J.
r~ IPEC00269956
Now consider the events associated with a pressure drift above the setpoint. The modulating heaters will decrease in the outp~t and be full off at 2250 psig. Spray flow will be initiated at 2260 psig, via valve PCV-455A (controlled by PC-455G on the Flight Panel), and will increase proportionally until it is full on at 2310 psig,
.....*** * - .."-- '-~ with both PVC-455A. and PCV-455B (controlled by PC-4SSH one:*\
~ the Flight panel) wide open passing 650 gpm of spray. A *QL i>ns.s.....,c. ~~ *2)o~ plrj the same press'l:l:re {2319! a high pressure alarm will be
- J
*---~cti~e_~ by t~e deviation signa~--~-~-~oug:: PC-455I_:., If the
(--- l pressure continues to rise, Power Operated Relief Valve i1..t f0LJ('t Dpll.\.c..t-.1 \ PCV-455C (controlled by PC-455F) will open at 2335 psig. 1..:\,.J v~\.'4. .b/oc.lc.. ~~ Note that another high pressure alarm (from the fixed 6*
;*.._\.~es flr;Jv* !:>-?.!' ~ } control chain and PC-45~ is also ~vated at 2335 psig.
tA:>v-5~{, uull oft:;tJ ( This alarm is annunciated by the sbne a'Q,._ight on the SA I
- uel' b Pc*"11'ff> ' panel ; therefore, it will not :{e seen as a n~larm
.c-.-tv"o
* \ p ua_ *'t
- . i' unless PC-455I failed to ala nr( at 231 At n62 psig
., 5 1 r , .,
!)..N6
~!;:~TI.~e ~ a.
1 I) +- \the Reactor will be tripped on "High ressurizer P!\su:re*.
\ .
~ ~~nally, at 2485 psig the Precs . . urize Valves ,ill
.4 {>fH~...._ JC" 2.3ol f{~i- . 1 1\L l~ft. (
*~*s"oll.-o op~ .... 11.1~ *1 1 f) z 3 oo )
~"~ vt..\..Jt.. w.U C.O.~! \ ,
-' ~ , t. ,Note that some of the actuation ~sures described_.....**"ln this
# .:.o--..o ~ 0 .. f'.,_"', ' \ . r-
' A "1"1' 1. \
- a. CV.......vl *
*discussion are theoretical. That is ,'-J:..b.e .....functi.o"n
~ /controlled by the main pressure controller {PC-455Kl deviation signal will actuate at the given pressures only when the normal output is 30 rna for P=2235 psig. These conditions can be changed in two ways.
First, the whole range can be displaced by changing the setpoint dial on the main controller. For example, the first spray valve is set to open at 25 psi above the setpoint which will correspond to 2260 psig only when the setpoint is 2235 psig. S '1.S ~ ~:2.5 C/ll r hoN ...
/4-~c kMa-::{- ~ M ~J t?r~c..-aJc..v..t Fe)< -1b- 122VJ-c.-
- 7Q..s.R_*
3 o~ C"' IPEC00269957
/'": . **--- .... --~--------------~
2310 psig - Sl"lravs Wide Open{ aAd. Ceviaeien II.:..~h F-e.!!:!!ure ,
~---------.) \
~
Al;'a;n\ 2300 psig _( Power Operated Relief Valve InterlockJ &I~L~ ~~lv l -----..___...____..___ Ofli'IV fl-"'~ *:t.lQ.A. . . . ~JJ~ 1 ll.cvto~~.ht~"' 1+-~~ Pru.Jr...N- Alc.A...,, 2260 psig - Spray Initiated .._,_____ - * * / 2250 psiq - Modulating Heaters off -;-----*-~ 2235 psig - fi0pna1 P,..essure FtJfG.76
-IZZ.'fl-f:::.-
2220 psig - Modulating Heaters Full On 2210 psig - Backup Heaters Off (when already on from 2185 setpoint)
- 2185 psig - Low Pressure Alar.m Backup Heaters On (will stay on until pressure reaches 2210) 1940 psig - Low Pressurizer Pressure Permissive (SI unblockl 1930 psig - Low Pressure Reactor Trip 1840 psig - Low Pressure Safety Injection Actuation it:
Sy Sr~ ]aS CiLr(rht.,, I A-+-+4c ~ """'~....J Jo P11)cl fro c..2 J~ F1- . 1b -: IZ:'L 'f I -G: ..
'Pc.y! 4 uF _s-
- IPEC00269958
"U m () 0 0 I'V 0> CD CD 0'1 Fl(1l/ff£ NO. l'f :PRESSURIZER PRESSURE INSTRUMENTATION CD
~ 1s. .\e:.w-. ) IUlC 1\ p h1M .t:1 I I
'g..C5
,.t+Ac.-H*n16)0T ~ ..-~~J Pro<:.P.dUAL FeX 1zz 'fl -£
~~~T~~\.ES lttJS l.oO: ,... ~..r
'!:.lo.fli1(
INlEC. "'lo"'
.,.'R,I' I S'fO ~sIP..
t "T'(I"IU*l.)
1.1.3.1.2 Process Measuring Loop Instrumentation All local or CCR mounted instrumentation identified in Table 2.4-1 are ~o~i thin the boundaries of the RCS instrumentation and. controls. 1.1.3.1.3 Supervisory Annunciator Points The folloving are the RCS interfaces vith the plan~ Supervisory Annunciator System: CCR PANEL ANNUNCIATOR POINT LOCATION DR.AioTING "Reactor Coolant Pump CCR Panel SA 7.1.5.1 Standpipe High Level 1 Ft" "Pressurizer High CCR Panel SA 7.1.5.1 Pressure~ PSIG" "Pressurizer High CCR F'anel SA 7.1.'5.1 Level 70! Sr."
"Pressurizer Relief CCR Panel SA 7.1.5.1 Line High Temp 240°F"
- i. "Pressurizer Relief Tank CCR Panel SA 7.1.5.1 Liquid High Temp 130°F" "Reactor Coolant Pump CCR Panel SA 7.1.5.1 Stand Pipe Lo Level 4 Ft" "Pressurizer High Temp 665°F" CCR Panel' SA 7.1.5.1 "Pressurizer Safety Valve CCR Panel SA 7.1.5.1 Outlet High Temp 240°F" "High-T-AVG 555°F" CCR Panel SA 7.1.5.1 "Reactor Coolant Pump CCR Panel *SA 7.1.5.1 Motor Oil High Level 1 In."
*b~D c.\...~~
ft.TIA-c.. \-\ M E,")Jl 10 _ ~ D cl "ro CR.J 1.cA.t. F6"i - 1 b - I "2. 2 '-1 t -t::.
***--. ?j.. of I L> 1-16 RCS/SG DBD, Rev. 0 November 25, 1991
- IPEC00269960
*I~'\
' 1..1) ~
( ~~ ~ Motor operated valves (HOVs) 535 and 536 are located upstream of
*~-; i ~ ~1* \
\
PORVs PCV-455C and PCV-456 respectively. The MOVs are utilized
- i. ~ ~ <:::~.. 1 to remove PORVs from service should they leak to an unacceptable
' ~ v-- ~ I . t.l~e.d
( 1.... 1 .- degree. The HOVs 535 and 536 are~ during normal plant Or- >' ~ d 1.!1 ~ \ operation. Each valve is provided wit~ a CLOSE/PULL/TO/LOCK/
-+ L1. ~ ~
~ CLOSE-AUTO-OPEN control svi tch vi th red and green position indi-I
~ ~1
... ~. -c:....
\!l eating lights mounted above it. The valve will open automati-I * ~ 8 g cally in response to the OPS signal. The OPS vas installed by
{
~e ., Hodification Procedure ESG-77-2-008 (Reference 7.5.3.4). Under I ! ~ ~:1 j the OPS, the HOVs will open automatically, when the reactor cool-II S~-9-t( ~ ant temperature is betveen 0°F and 290°F, to relieve the RCS from
""';: \
i l .>) j Q.. \
' 5~ exceeding the pressure limits given in 10CFR50 Appendix 'G'
~ ' ; \(References 7.5.6.26, 7.5.1.1).
~ ~ ~-!; \..-
f;~ t *JAs
\\
i part of OPS, three vhi te supervisory lights are provided above
\
~ ~ ~ \the control s~itcnes for HOVs 535 and 536, on CCR Panel FB. The
'-- 0 *
~ g]."" ilights are labeled as:
*II M '% -t: ~
~~ - j !
~- ~ . . . . .~. :~1. ~.IN A RCS Ov~RPRESSURIZATION NOT AVAIU..BLE o oq;;_: ~
"-- ~{ 1~ 2. TRAIN B RCS OVERPRESSURIZATION NOT AVAILABLE
\ ==!"a~ j3. ANY RCS OVERPRESSURIZATION TRAIN ARMED
\ ~ : *~1
~ ~~ ~
Lights in item 1 and 2 above are illuminated vhen the control l
\ ~
~ ;11o~
w vr d svitches, for HOVs 535 and 536 respectively, are turned to CLOSE/PULL/TO/LOCK position. Light in item 3 is illuminated when at least one of the tvo trains is armed.
;. ~ .....
.-..:;, ~
t i o ! Pressurizer Heaters
'"'-, ;i (References 7.5.1.1, 7.1.4.6, 7.1.4.7 and 7.1.4.8)
*,._J
*PLI-RCS-014 Df1"b cJ" 't. " 5e..J A+-+t>rc'-' n\e..d fr, f't'\, cl
* **~
F E,'-1( - 9 b- I 2.2. '1 I- ~
?o.~ ~of I o 2-59 RCS/SG DBD, Rev. 0 November 25, 1991 IPEC00269961
** The second selector switch, P/455A, located in Foxboro Rack B-6, is used to select which channels are to be used for control and will so indicate by illuminating the pressure indica-tors of the selected channels. This switch is labeled "Defeat 2,3", "Defeat 3,4" and "Pefeat 1,4" which refers to the two chan-nels which are "defeated" or ignored for control functions.
There are two control chains and the switch is set up such that independent control signals are always used for the two ~hains. Channels III and IV are also used to generate interlock signals for Power Ooerated Relief Valves PCV-456 and PCV-455C ~** r. L \
* .........!. ., ope-. i'oltJ bloc.~o~D...lll&o tlq:oV-SJb-..!. Mo,.-..c...., ""p.o...vlllll!- jJ respectively,~t pressures above~PSIG, and initiate a low pressure alarm on the CCR Panel SA when the pressure falls below 2185 PSIG.
q . The first cont~l chain is u~to initiate a fixed low pressure alarm (PC-45~ at 2185 PSIG~and open Powe: Operated Relief Valve PCV-456 at 2335 PSIG (PC-45~ provided the interlock from .chan-nel III. is satisfied. This--interlock vill be satisfied if chan-nel III is indicating a pressure above 2300 PSIG. The interlock is provided to protect against false actuation of the Power Operated Relief Valve. The svitching circuitry is set up so that the signal to open the valve vill never come from the channel ~ used to derive the interlock. In addition, PC-45~ctfVat;; a fixed high pressure alarm at 2335 PSIG. This is a redundant alarm since the control chain annunciates the same alarm light at
~PSIG, therefore, it vill not be seen unless there vas a failure of the alarm in the control circuit. The annunciator vindovs are labeled as follovs:
z~oo (- PREssURIZER HIGH PRESS. ~SIG ~~ (Initiating Devices: PC-455I1 ~C-45~~?c.- Y"l'i B~J.. ~c..-YS7 F" PRESSURIZER LOV PRESS. 2185 PSIG Initiating Devices: PC-455J & PC-45~ (r
- b (1 0 C...~et....~~. ji .s. J 1:},.,-lk ltlole'JVT Tn -
-Mo! Proc:.:.~uAA. t=e:~-1b- tz:z.**fl-t
?a..'t'- 7 c>f I0 2-66 RCS/SG DBD, Rev. 0 November 25, 1991 IPEC00269962
ENTERGY Conceptual Design
~ ~~~?,~2~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -053 Rev. 0 Attachment 4 Cost Estimate IPEC00269963
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station EC #: SAMA IP2-053 PROJECT TITLE: Keep Pressurizer PORV Block Valves Open ESTIMATOR: RCMT JOB LOCATION: Panels FBF, SB2, G3, E1, H4 PROJECT CODE: TBD 1--.......Definitive _ _ _ _ ___. EJ OUTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 06/22/2012 ESTIMATE TOTAL $1,467,848 0CAPITAL E!o&M REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-053 in accordance with Entergy design engineering practices. For SAMA IP2-053, resolution is required for Pressurizer Power Operated Relief Valve (PORV) Block Valves MOV535 and MOV536 to be open when the plant is operating under normal conditions. This package un-installs the modification that currently keeps the block valves closed during normal operating conditions. The package will restore original design requiring the valves to be open during normal plant operating conditions. Prepared by: Approved by: Date: IPEC00269964
ENTERGY NUCLEAR NORTHEAST
. r::<> IIIYIF\ I r:: Ll::VI:.L !--- Conceptual !--- Preliminary F IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station EC ., SAMA IP2-053 E: Keep Pressurizer PORV Block Valves Open N: Panels FBF, SB2, G3, E1, H4 PROJECT CODE: TBD ESTIMATOR: RCMT !--- Definitive ORIGINATOR: ORIG. DATE: 06/22/2012 Item Descriotion
- 1. This estimate assumes that this work will require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 1o hours per shift. Six days per week schedule.
- 3. This estimate assumes that a three buck scaffold will be reouired for conduit installation and wire oullino in the Switchgear Room.
- 4. This estimate assumes that all work will be performed bv trained contract craftsoersons in lieu of station maintenance personnel.
- 5. This estimate provides for continuous fire watch durino cable trav breechino.
- 6. This estimate assumes trainino for 24 Plant Qps.Personnel.
- 7. This estimate assumes that theAppendix R Evaluation will be performed by a Contract person for a cos! of $250000.
8. This estimate is based on the project's current level of scope definition and is classified Class 5 as defined per the AACE International Cost Estimate Classification System (see Attachment 3, Reference 2).
- 9. Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide for anticipated billing rate increases of 3% per year.
- 10. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is A. Outside fence boundary- 20%
B. Inside fence boundary- 30% C. Implementation comolexitv- 40% D. Inside Containment- 50% IPEC00269965
Page 1 of3 71512012 3:38PM SAMA IP2-053 ESTIMATE KEEP PRESSURIZER PORV BLOCK VALVES OPEN (4-2~11).xls s -0 PROJECT TITLE: Keep Pressurizer PORV Block Valves Open JOB LOCATION: Panels FBF, SB2d3, E1, H4 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2-053 PROJECT CODE: TBD TAKEOFF: ESTIMATOR: RCMT EST. STATUS: 0 OOTAGE NOtHlUTAGE 0CAPITAL 00&M ORIGINATOR: ORIG. DATE: 06/2212012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QlY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
' ESllMATE LEVEL ' ESTIMATE
SUMMARY
1-- Conceptual MANHOURS DOLLARS 1-- Preliminary ENGINEERING 1-- Definitive 01 SllJDY, DESIGN, & CLOSEOUT 140 $ 14,000 02 DESIGN ENGR CONST SUPPORT 80 $ 8,000 General Notes: 03 MODSENGR SUPPORT $ 04 SYS ENGRJ S-U ENGR 80 $ 8,000 05 PROJECT MANAGEMENT 200 $ 24,000 06 TESTING (Calibration & Testing) 40 $ 4,000 07 CONTRACT DESIGN EVALUATION SUPPORT $ 250,000 08 ENGINEERING DCP ACCEPTANCE REVIEW 45 $ 4,500 CONTRACT ENGINEERING 09 DESIGN ENGR CONTRACT SUPPORT 1,700 $ 204,000 10 SUPL CONTRACT MODS ENGR $ - 11 MODS PLAN & SCHED -CONTRACT 40 $ 3,200 12 FIELD ENGRS I PLANNERS 80 $ 9,600 MATERIALS I MISC CONTRACTS 13 MATERIALS $ - 14 OTHER CONTRACTS $ - CONTRACT CRAFT LABOR 15 SWEC CRAFT LABORIWALKDOWN 970 $ 110,916 16 LOST TIME 97 $ 13,438 17 SWEC DISTRIBS $ 28,088 PLANT CRAFT LABOR 18 MECH MAINT. - $ - 19 ELECTMAINT - $ 20 I&C 120 $ 12,000 21 CSG $ MISC SUPPORT 22 QUALITY CONTROL 40 $ 4,000 23 PLANNING & SCHEDULING $ - 24 TRAINING 24 $ 2,880 25 CHEMISTRY $ - 26 OPS 80 $ 9,600 27 HP/RP 40 $ 4,000 MISC CONTRACT SUPPORT 28 QUALilY CONTROL 60 $ 4,800 29 NDE - $ - 30 HP/RP 40 $ 3,182 31 RADWASTE - $ - 32 33 NURSE ELEVATOR CONTRACTOR 34 WASTE MANAGEMENT $ 35 HOUSEKEEPING $ - 36 EQUIPMENT RENTAL - $ 37 VENDOR STOCKING - $ 38 DECONTAMINATION CONTRACTOR $ - 39 RBC'S $ - 40 SECURilY $ 41 42 FIRE WATCH (Rover) SAFElY 22 1,587 CONTINGENCY 43 CONTINGENCY $ 217137 ESTIMATE SUBTOTAL 3,898 $ 940,928 Site Encumbrance Premium (20%) $ 188,186 Loaders (30%) $ 338,734 ESTIMATE TOTAL $ 1,467,848
- 1. Gather and stage tools and materials 1 LT EL 2 2.00 1.70 7 $ 123.32 $ - $ 863 $ 863
- 2. Perfonm walkdown of work area. 1 LT EL 2 4.00 1.70 14 $ 123.32 $ - $ 1,726 $ 1,726
- 3. Gather and transport materials to work area. 1 LT EL 2 6.00 1.70 20 $ 123.32 $ 2,486 $ 2,486
- 4. Stage, erect and modify scaffolding 1 LT CP 2 8.00 1.70 27 $ 96.00 $ - $ 2,592 $ 2,592
- 5. Stage, erect and modify scaffolding 1 LT LB 1 8.00 1.70 14 $ 78.65 $ - $ 1,101 $ 1,101
- 6. Remove Insulation as required 1 LT AW 2 10.00 1.70 34 $ 97.70 $ $ 3,322 $ 3,322
- 7. Remove existing modificaUon 1 LT EL 2 60.00 1.70 204 $ 123.32 $ - $ 25,157 $ 25,157
- 8. Perfonm wiring modifiCations. 1 LT EL 2 40.00 1.70 136 $ 123.32 $ $ 16,772 $ 16,772
- 9. Perfonm Testing as Required 1 LT OPS 2 20.00 1.70 68 $ 123.32 $ $ 8,386 $ 8,386
- 9. Support Testing as Required 1 LT EL 2 20.00 1.70 68 $ 123.32 $ $ 8,386 $ 8,386
- 10. Replace Insulation as required 1 LT AW 2 10.00 1.70 34 $ 97.70 $ 3,322 $ 3,322
- 11. Dismantle scaffold, return to storage and cleanup 1 LT CP 2 8.00 1.70 27 $ 96.00 $ $ 2,592 $ 2,592
- 12. Dismantle scaffold, relum to storage and cleanup 1 LT LB 2 8.00 1.70 27 $ 78.65 $ - $ 2,124 $ 2,124
- 13. Cleanup and restore work areas 1 LT EL 2 10.00 1.70 34 $ 123.32 $ $ 4,193 $ 4,193 IPEC00269966
Page 2 of 3 7/5/2012 3:38PM SAMA IP2.Q53 ESTIMATE KEEP PRESSURIZER PORV BLOCK VALVES OPEN (4-28-11).xls
~ .()
PROJECT TITLE: Keep Pressurizer PORV Block Valves Open INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2-053 TAKEOFF: JOB LOCATION: Panels FBF, SB2r:j3, E1, H4 PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: 0 OUTAGE NON-oUTAGE 0CAPITAL 00&M ORIGINATOR: ORIG. DATE: 06/22/2012 MANHOURS MATERIAL$ MATERIAL LABOR SUB* ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT - $ $ $ -
- 2. PAINTING & TOUCH-UP PT $ $ $ -
ARE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 40.00 1.70 68 $ 53.60 $ $ 3,645 $ 3,645
- 2. CRAFT SUPPORT FOR BOTTLE WATCH - $ $ - $ -
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ $
SUBTOTAL CRAFT & SUB-CONTRACTOR 782 $ . $ 86,647 $ . $ 86,647
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 63 $ 110.80 $ 6,980 $ 6,980 SUBTOTAL 645 $ . $ 93627 $ . $ 93,627
' RELATED COSTS '
- 1. WALKDOWN ALLOWANCE 1 LT EL 9 $ 123.32 $ 1,110 $ 1,110
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT EL 86 $ 123.32 $ 10,606 $ 10,606
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 30 $ 123.32 $ 3,700 $ 3,700
- 4. GENERAL CRAFT DISTRIBS. (10%) $ 9,363 $ 9,363
- 5. CRAFT IN PROCESSING (20%) $ 18,725 $ 18,725
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 1,873 $ 1,873
- 7. 1112 dav trainina or- 2%1 SUBTOTAL 970 $ . $ 139004 $ . $ 139,004 PLANT SCOPE
- 1. MECH MAINTENANCE PL . $ $ $ .
PL - $ $ $ SUBTOTAL MECH MAINT. . $ $ $ . $ .
- 1. ELECT MAINTENANCE PL . $ $ . $
PL $ $ . $ SUBTOTAIL ELECT. MAINT. . $ . $ . $ . $ .
- 1. I&C (Dev. Instrument Calibration Procedures) 1 LT PL 1 120.00 1.00 120 $ 100.00 $ . $ 12,000 $ 12,000 PL $ $ . $ .
SUBTOTAIL I&C MAINT. 120 $ . $ 1z,OOO $ . $ 12000
- 1. CSG PL $ $ $ .
PL $ . $ $ . SUBTOTAIL CSG MAINT. . $ . $ . $ . $ . SUBTOTAL PLANT 120 $ $ 12,000 $ . $ 12000 SUBTOTAIL CRAFT/PLANT 1090 $ . $ 151004 $ . $ 151,004 IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM . $ . $ .
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 3. SYSTEMS ENGINEERING* MECHANICAL 1 LT NM $ . $ .
- 4. SYS ENGINEERING* ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 5. SYS ENGINEERING -INSTR & CONTROL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 6. SYS ENGINEERING -CIVIL STRUCTURAL LT NM $ . $ .
- 7. PROJECT MANAGEMENT 1 LT NM 1 200.00 1.00 200 $ 120.00 $ 24,000 $ 24,000
- 8. TRAINING (OPS Slaff) 1 LT NM 24 1.00 1.00 24 $ 120.00 $ 2,880 $ 2,880
- 9. QA I QC VERIFICATION 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 10. PLANNING & SCHEDULING 1 LT NM 1 1.00 . $ $ .
- 11. HP I RPI ALARA 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 12. CHEMISTRY 1 LT NM $ $ .
- 13. OPS (DEVELOP/REVISE PROCEDURE($)) 1 LT NM 1 80.00 1.00 80 $ 120.00 $ 9,600 $ 9,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ . $ .
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING - SWEC (Inc! Per Diem) LT NM . $ $ .
- 2. MODS PLANNING & SCH.* SWEC (lncl Per Diem) 1 LT NM 1 40.00 1.00 40 $ 80.00 $ 3,200 $ 3,200
- 3. FIELD ENGRSIPLAN- SWEC(Incl Per Diem) 1 LT NM 1 80.00 1.00 80 $ 120.00 $ 9,600 $ 9,600
- 4. QA I QC VERIFICATION 1 LT NM 1 60.00 1.00 60 $ 80.00 $ 4,800 $ 4,800
- 5. NDE 1 LT NM . $ $ .
- 6. HPIRP 1 LT NM 1 40.00 1.00 40 $ 79.56 $ 3,182 $ 3,182
- 7. RADWASTE 1 LT NM .
- 8. NURSE 1 LT NM .
- 9. ELEVATOR CONTRACTOR 1 LT NM .
- 10. WASTE MANAGEMENT 1 LT NM .
- 11. HOUSEKEEPING 1 LT NM .
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM .
- 13. VENDOR STOCKING 1 LT NM .
- 14. DECONTAMINATION CONTRACTOR 1 LT NM .
- 15. RBC's 1 LT NM .
- 16. SECURITY 1 LT SEC .
- 17. FIRE WATCH (Rover) 1 LT NM $ $
- 18. SAFETY(2%) 1 LT NM 22 $ 72.14 $ 1,587 $ 1,587
- 19. LOST TIME (10%) 1 LT 97 $ 138.54 $ 13,438 $ 13,438 IPEC00269967
Page 3 of 3 71512012 3:36PM SAMA IP2..053 ESTIMATE KEEP PRESSURIZER PORV BLOCK VALVES OPEN (4*211-11}.xls
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
.4) EC #: SAMA IP2-053 Open TAKEOFF TION: Pa~:BF, SB2113, E1, H4 PROJECT CODE: TBD ESTIMATOR: RCMT TUS: I OUTAGE 0011M
~.
NOtHl!JTAGE 0CAPITAl ORIGINATOR: MANHOURS MATERIAl.$ MATERIAL ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAl. $/MH PER UNIT DOLLARS TOTAL$ SUBTOTAl. CRAFT/NON-MANUAL 1,973 $ * $ 247,291
- 1. FREIGHT, SALES TAX, & CONSUMABLE$ (6%) $ . $
SUBTOTAL INSTA!.LATION COST 1,973 $ $ 247,291 $ . $ 247,291
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM $ $
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 3. DESIGN ENGINEERING- INSTR. & CONTROL 1 LT NM 1 60.00 1.00 80 $ 100.00 $ 6,000 $ 6,000
- 4. DESIGN ENGINEERING* CMUSTRUCTURAL 1 LT NM $ $
- 5. TESTING {Instrument Calibration and lesting) 1 LT NM 2 20.00 1.00 40 $ 100.00 $ 4,000 $ . $ 4,000
- 6. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,700.00 1.00 1,700 $ 120.00 $ 204,000 $ . $ 204,000
- 7. Appendix R Evaluation 1 $ 250,000 $ 250,000
- 8. DESIGN ENG. DCP ACCEPTANCE REVIEW 1 1.00 45 $ 100.00 $ 4500 $ - $ 4500 SUBTOTAl. DESIGN COST 1925 $ 226,500 $ - $ 476,500 SUBTOTAl. INSTALLATION & DESIGN COST $ 473,791 $ - $ 723 791
- 1. CONT1NGENCY ( 30%) $ 217,137 ESTIMATE SUBTOTAL 3,898 $ 940,928 IPEC00269968
ENTERGY Conceptual Design
~ ~~:~~~~~~~'~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-054 Install 480 VAC Switchgear Room flooding detection to provide an alarm at the Control Room Prepare~~ I.J/~.K Approved by:
c;;:~~~ Date: Cf-20-ZOfZ Date: ',! [ _:.._ '.j ! Page 1 of6 IPEC00269969
ENTERGY Conceptual Design
~ ~~~~~,~~~2~~ Indian Point Nuclear Station Unit 2 Package SAMA I P2 -054 Rev. 0 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 ISSUE 3
2.0 BACKGROUND
3 3.0 EXISTING CONDITIONS 4 4.0 DESIGN CONSIDERATIONS 4 5.0 CONFIRMATION OF DESIGN 5 6.0 RECOMMENDED SOLUTION 5 7.0 PRELIMINARY MATERIAL LIST 6 Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00269970
ENTERGY Conceptual Design
~ T:2:.?,~~2~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-054:
Install 480 VAC Switchgear Room flooding detection to provide an alarm at the Control Room
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-054 in accordance with Entergy design engineering practices. For SAMA IP2-054, resolution is required to detect flooding potential in the 480 VAC Switchgear Room (Switchgear Room) and provide an alarm at the Control Room. This package provides for a conceptual design to install water intrusion detection in the Unit 2's Control Buildings 480 VAC Switchgear Room at Elevation 15'- 0". This device, detecting water at a pre-determined set-point level in the Switchgear Room, will provide an alarm signal connected to the annunciator in the Control Building's Unit 2 Control Room at Elevation 53'- 0". The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. Page 3 of6 IPEC00269971
ENTERGY Conceptual Design
~ ~~2.~~,~~2:,:; Indian Point Nuclear Station Unit2 Package SAMA IP2 -054 Rev. 0 3.0 EXISTING CONDITIONS Cooling water piping is routed to mechanical equipment located within the Switchgear Room. Also within the boundary of the Switchgear Room is a "deluge closet area" with large diameter piping providing water for the fire protection system. The Switchgear Room can potentially become flooded in the event of any breakage/leakage of these piping systems and critica1480 VAC will be unavailable. Early notification of this potential flooding condition is necessary for timely response and the actions to mitigate the situation.
4.0 DESIGN CONSIDERATIONS All the switchgear is set upon the same level grade. Existing drains provided are for minimum discharge of water being used for floor and equipment cleaning purposes. These drains cannot be considered for mitigation of any substantial discharge of water. Piping that can potentially discharge water in the event of a break or leak is routed throughout the entire Switchgear Room. As a result, based upon the locations of the electrical equipment in the Switchgear Room, more than one detection device will be utilized. Spurious alarms need to be avoided, but at the same time since water intrusion will have occurred before alarming, providing the earliest detection is necessary. Based upon the above considerations water intrusion will be detected at one-half (1/2) inch above the floor grade. To alleviate further concerns with spurious alarms, the device selected will provide adjustment for sensitivity Power requirements for the detector unit will need to be provided from a source that is not affected by the Switchgear Room water intrusion. New wiring is required to be installed for power to the new units. Wiring is also required for the alarm signal to be routed to the Control Room's annunciator above at Elevation 53'-0". A window in the Control Room annunciator for this alarm is also required. Page 4 of6 IPEC00269972
ENTERGY Conceptual Design
~ ~~~?,~~2~,:;: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 5.0 CONFIRMATION OF DESIGN The situation here is typical for any condition that needs monitoring. In conditions where detection and alarming is required, it is provided in the most significant manner relating to the condition. In some cases the alarm is an early warning indicating a potential problem and in other cases it signifies a failure has occurred.
In this scenario the alarm condition is of a failure having already occurred. Therefore, mitigation will be the only alternative available for alleviating the condition. The design concept being recommended will provide Operations the earliest warning obtainable. 6.0 RECOMMENDED SOLUTION
- 1. Install new redundant, nuclear qualified, FCI Model FLT93S FlexSwitch water level detection devices in the Switchgear Room at Elevation 15'-0"; based upon the locations of the electrical equipment.
- 2. Protective measures to be considered for protection of water level detection devices based upon installed location.
- 3. Provide power to the detection devices from a source that is not affected by the switchgear room water intrusion
- Install power wiring in conduit raceway from Control Room at Elevation 53'-0" to the devices in the Switchgear Room at Elevation 15'-0".
- 4. Provide alarm connection from the level detection devices to the annunciator
- Install 125VDC wiring in conduit raceway from the devices in the Switchgear Room at Elevation 15'-0" up to the cable spreading area at Elevation 33'-0"
- Continue routing wiring in cable trays at Elevation 33'-0" up to the annunciator in the Control Room at Elevation 53'-0"
- 5. Connect wiring to new "480 VAC SWITCHGEAR ROOM-WATER INTRUSION" alarm window in the Control Room's Supervisory Panel Electrical Section annunciator
- 6. Provide procedure for flood switch calibration and setpoint.
- 7. Provide procedures and training for mitigation relating to this condition Page 5 of6 IPEC00269973
ENTERGY Conceptual Design
~~~~~~2~,~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. FCI Model FLT93S FlexSwitch 2
- 2. 1"- Conduit 200 Feet
- 3. Cable 400 Feet A. 2 - 125 VDC Cables B. 2- 120 VAC Cables
- 4. Support for water level switch 2
- 5. Junction Box with terminal blocks 1 Page 6 of6 IPEC00269974
ENTERGY Conceptual Design
~ ~~~'~'~E~,:; Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00269975
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATEO REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. Sf\MA Engineering Change No.: TPZ-0 4 Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmQact Civil/ Structural Design Engineering .YES DNO
. Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settinQs chanQes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNo
- Does the proposed activity involve any I&C desi{:!n or settinQs chanQes or activities?
Mechanical Design Engineering DYES CsfNo
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES !XfNo
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENNIENS-PL-158, ENS-DC-199, etc.)
IPEC00269976
J*
- NUCLEAR QUALITY RELATED EN-DC-115 REV.11
~Entergy MANAGEMENT 1 REFERENCE USE PAGE 97 OF 150 MANUAL Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potentiallmgact ASME Section Ill Specifications DYES IXJ NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES iJNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES liJ NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES lXI NO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES !X1 NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring) indications?
MAINTENANCE Potentiallmgact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance DYES ~NO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential Impact Nuclear Fuel Design DYES !XfNO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES fXfNo
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor svstem procedures?
IPEC00269977
*"=" Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT9.3 IMPACT SCREENING
SUMMARY
SHEET 3 OF 6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST PotentiallmQact Computer Support and Software DYES jgJ NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES ~NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES ~NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS PotentiallmQact ASME Containment In-service Inspection (IWE /IWL) Program DYES 1&1 NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES fXl NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00269978
A NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
-=- Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmgact ASME In-service Inspection (lSI) Program DYES (KI'No
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES [XfNo
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES ~NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST pro~:~ram documents?
Air Operated Valve (AOV) Program DYES !Xi NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES ~NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried PipinQ & Components?
Boric Acid Corrosion (BAC) Program DYES t:KJ NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES 00 NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES QtfNO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00269979
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potential lmQact Flow Accelerated Corrosion (FAC) Program DYES lg] NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES !XfNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES Jgf NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
. Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES IX] NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES li'f NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES ~NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
. Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PTCurves DYES IX} NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES iXf NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00269980
- P!L NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT REFERENCE USE PAGE 101 OF 150 MANUAL Engineering Change Process ATTACHMENT9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potential lm eact Welding Program .YES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program DYES DO NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES DNO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES fBI' No
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES blfNo IPEC00269981
ENTERGY Conceptual Design
~ ~~~~?~~~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 15'- 0"- FLOOD SWITCH LOCATION PLAN VIEW
- 2. Figure 2: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 15'- 0"- FLOOD SWITCH LOCATION
- 3. Figure 3: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 33' - 0"- CONDUITS DUMPING INTO CABLE TRAYS
- 4. Figure 4: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 53'- 0"- ANNUNCIATOR WINDOW LOCATION AND POWER FOR FLOOD SWITCH
- 5. Figure 5: DETAIL FOR FLOOD SWITCH AND SUPPORT IPEC00269982
ENTERGY Conceptual Design
~~;!~~~:.: indian Point Nuclear Station Unit 2 Package SAMA IP2- 054 Rev. 0 ...,.....**a--........:P:....:LA:...;;N:..::..:T_-<( ISOLATION TRANSFORt.4ERS.
NORTH FOR PRESSURIZER HEATER PANEL FEEDS. INST. AIR AFTERCOOLER (EL 26'4") INST AIR COt.4PRESSOR COOLING WTR. HEAT EXCHANGER t::..i::ll"t--,COOUNG WATER PUidPS &: t.IOTORS FLOOD SWITCH ti.Q.UJ ACTUAL LOCATIONS TO BE DETERidiNED AT FINAL DESIGN. ALSO THE OPTION OF ADDING A THIRD DETECTOR FOR ADDITIONAL COVERAGE WILL BE CONSIDERED.
- CONTROL PANEL (5} SERVICE WATER PUidPS (5) CONT. RECIRCULATING FANS Figure 1 EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL 15' -0" -FLOOD SWITCH LOCATION (REFERENCE DWG. 9321-F-3052)
{NOT TO SCALE) IPEC00269983
- PLANT NORTH < -@
(FLOOD
~
SWITCH
~ INSTRUMENT PBU3 AIR TRANS F. COMPRESSOR PBU2 TRANS F.
PBU1 TRANS F. INSTRUMENT AIR COMPRESSOR 21 CONDUIT TO JUNCTION BOX AT CEILING LOCATED NEAR PENETRATION TO ELEVATION 33' -0" FLOOD SWITCH STATION STATION SERVICE SERVICE TRANS. TRANS. NO. 6 NO. 5 A A
-v Figure 2 '::QUIPMENT ARRANGEMENT CONTROL BUILDING AT 15' -0"-FLOOD SWITCH LOCATION (REFERENCE DWG. 9321 -F -3052)
(NOT TO SCALE) IPEC00269984
_,..**11111---~-~-~-~----<< CAB TRAYS (ROUTE CABLES THROUGH TRAYS TO THE MAIN CONTROL ROOM) CONDUITS ROD CONTROL CABINET FROM PENETRATION FIGURE 2 i
~:::::..----""
Figure 3 UIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 33' 0" CONDU DUMPING INTO CABLE TRAYS (R E DWG. 9321 3052) (NOT TO SCALE) IPEC00269985
ENTERGY Conceptual Design Technologies Nuclear Station Package r------.-.J Unit 2
....,..**11--_PLA.;,.__NT_ _
NORTH
~, _ _;\r A
___l
~-~-'- I 118VAC
~INSTR. BUS 21(PE8)
LJ (POWER FOR I TURB. FLOOD SWITCH)
.RCD'R.
SDF r~~'VSUPERVISORY PANEL I ELEC. I (LOCATION FOR FLOOD i SHF i ALARM ANNUNCIATOR
- '-***-' WINDOW AND 125VDC POWER SOURCE)
L~J Figure 4 EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 53' -0" ANNUNCIATOR WINDOW LOCATION AND POWER FOR FLOOD SWITCH (REFERENCE DWG. 1999MC3415) (NOT TO SCALE) IPEC00269986
ENTERGY Conceptual Design
~ ~~s:~c~?~~2!,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-054 Rev. 0 CONDUIT\
ANCHOR BOLT FLOOD SWITCH FLOOR FLOOD SWITCH AND SUPPORT Figure 5 DETAIL FOR FLOOD SWITCH AND SUPPORT (NOT TO SCALE) IPEC00269987
ENTERGY Conceptual Design
~ ~:~"~'~,~~2:,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. FCI Model FLT93S FlexSwitch (included here)
IPEC00269988
FCI FLUID COMPONENTS INTERNATIONAL LLC
,,~ * ' ' j FLT93S FlexSwitch Level Switch Products Level Switches
- FLT93 Series has FLT93B
- .*.s*.*****.*l
. ~. :. ' ~ ...* ,._, ...2**
_.-li* *,. .' FLT93S '"--~
* :Co~iance Raing
-~~. *' ¥ .,,,"'f FLT93F FLT93C Download literature for this product Level Switch Summary L 100 The FLT93S insertion type FlexSwitch for level and temperature monitoring represents the first true technological breakthrough in thermal technology in over 8-668 a decade. This product was designed for heavy industrial environments including high temperature and high pressure. FCI is the only thermal manufacturer providing temperature compensation to ensure set point accuracy for process temperatures that vary up to +/- 100° F. The FLT93S is easily field-configured or factory preset, providing unparalleled flexibility, accuracy and stability for all multiple process sensing and switching requirements.
For an operational demonstration of FCI's FLT93 FlexSwitch Series, please follow this link. Applications Interface/level detection in settling Interface and sump level detection IJ vessels Interface/sump level detection in a separation vessels Foam or sediment level control [J Agitation detection Liquid/resin interface detection Specifications For level/Interface Service: Accuracy: +/- 0.25 inch [+/- 6.4 mm] Repeatability: +/- 0.125 inch [ +/- 3.2 mm] Page 1 of3 IPEC00269989
For Temperature Service: Accuracy: +/- 2° F [ +/- 1 o C] Repeatability: +/- 1 o F 0.6° C] Response Time: As low as 3 seconds
Enclosure:
Powder coated aluminum enclosure is rated for hazardous location use Groups B, C, D, F and G, CENELEC EEx d IIC and resists the of weather and corrosion per NEMA/CSA Type 4X (equivalent to IP66). Stai steel is available as an option. Agency Approvals: FM, CSA, CENELEC, ATEX, CE Mark, T4 Rated (System Approval) and CRN. Flow Element Materials of Construction: All-welded 316L stainless steel for all wetted surfaces. Hastelioy Monel 400 and Titanium are available as an option. Process Connection: mStandard: 0. 75 inch male NPT. c Optional: 1 inch male NPT, flanges or retractable sensing element. Inse**tion Length: c 1.2 inch [30 mm] c 2 inches [51 mm] c 4 inches [102 mm] ll 6 inches [152 mm] c 9 inches [229 mm] 13 12 inches [305 mm] c 18 inches [457 mm] Customer specified lengths are available as an option. Operating Temperature: c Standard: -4° to +350° F [-20° to +177° C] c Optionai: -100° to +500° F [-73° to +260° C] or 100° to +850° F [-73° to
+454° C]
Ope1*ating Pressure: To 3500 psig [240 bar(g)] Control Circuit Operating Temperature: -40° to +140° F [ -40° to +60° C] Input Power: Field selectable 115 +/- 15 Vac or 230 +/- 30 Vac, 50/60 Hz; 21 to 28 Vdc or 18 to 26 Vac; 7 watts maximum. Relay Contacts: Field configurable dual SPDT or single DPDT rated 6 amps at 115 Vac, 240 Vac or 24 Vdc. Hermetically sealed relays are available as an option. Output Signal: Analog DC vol related to flow or level/interface signal and proportional to temperature. Electrical Connection: 1 inch female NPT Remote Configuration: Available as an option with customer specified interconnecting cable length. Optional N.I.S.T. Flow Calibration Services Factory N.I.S.T. calibration in air or water is available as an option for customer specified setpoint(s) or a flow curve based on the media ranges specified above. Page 2 of3 IPEC00269990
lome I About FCI I Products I Applications I Sales I News/Events I Support I Contact FCI I Search I Site Map 2011 Fluid Components International LLC. All Rights Reserved Contact Us at 800-854-1993 or 760-744-6950 Legal & Privacy Statements Page 3 of3 IPEC00269991
ENTERGY Conceptual Design
~ ~:;.~,~,~~~2:.:,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -054 Rev. 0 Attachment 4 Cost Estimate IPEC00269992
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-054 PROJECT TITLE: Flood Detection System 0CAPITAl 0o&M ESTIMATOR: RCMT JOB LOCATION: 480 Volt Switchgear Room PROJECT CODE: TBD OoUTAGE 0NON-OUTAGE ORIGINATOR: ORIG. DATE: 06/14/2012 ESTIMATE TOTAL $456,985 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-054 in accordance with Entergy design engineering practices. For SAMA IP2-054, resolution is required to detect flooding potential in the 480 VAG Switchgear Room (Switchgear Room) and provide an alarm at the Control Room. This package provides for a conceptual design to install water intrusion detection in the Unit 2's Control Buildings 480 VAG Switchgear Room at Elevation 15'- 0". This device, detecting water at a pre-determined set-point level in the Switchgear Room, will provide an alarm signal connected to the annunciator in the Control Building's Unit 2 Control Room at Elevation 53'- 0" Prepared by: Approved by: Date: q- 2 0 -2 0/2 IPEC00269993
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-054
~ Conceptual PROJECT TITLE: Flood Detection System ESTIMATOR: RCMT Preliminary JOB LOCATION: 480 Volt Switchgear Room PROJECT CODE: TBD r-- Definitive ORIGINATOR: ORIG. DATE: 06/14/2012 Item Descriotion
- 1. This estimate assumes that this work will not require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate assumes that a three buck scaffold will be required for conduit installation and wire pulling in the Switchgear Room.
- 6. This estimate assumes that the detection device mountinrJ brackets will be fabricated in the shop for installation in the Switch[lear Room.
- 7. This estimate provides for continuous fire watch during cable tray breeching
- 8. This estimate assumes that a blank annunciator panel is available for use in the existing Unit 2 Control Room.
- 9. This estimate assumes training for 12 Plant Ops.Personnel.
- 10. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 11. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide fo 12. anticipated billinq rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 13. and progresses as follows: A. Outside fence boundary- 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00269994
Paget of3 7/512012 3:54PM IP2-054 450V SWGR Flood Detection Estimate (Rev_6-14-12).>ds
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-0 EC #: SAMA IP2-054
~~sr PROJECT TfTLE: Flood Detection System TAKEOFF:
JOB LOCATION: 480 Volt SwitChgear Room D ESTIMATOR: RCMT EST. STATUS Ornma 0NON-ouri'GE R ORIG DATE: 06/1412012 MAN MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM F PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
' ESTIMATE LEVEL ' ESTIMATE
SUMMARY
]C Conceptual MANHOURS DOLLARS
- a= Preliminary Definitive 01 02 ENGINEERING STUDY, DESIGN, & CLOSEOUT DESIGN ENGR CONST SUPPORT 80 40 8,000 4,000 General Notes: 03 MODSENGR SUPPORT s -
04 SYS ENGR/ S-U ENGR eo $ 8,000 05 PROJECT MANAGEMENT 240 s 28,800 06 TESTING (Calibration & Testing) 20 $ 2,000 07 TRAVEL & LIVING EXPENSES s 08 ENGINEERING OCP ACCEPTANCE REVIEW 25 $ 2,500 COHTRACTENGWEERING 09 DESIGN ENGR CONTRACT SUPPORT 480 s 57,600 10 SUPL CONTRACT MODS ENGR . $ 11 MODS PLAN & SCHED -CONTRACT 20 $ 2,000 12 OSG FIELD ENGRS I PLANNERS 80 s 9,600 MATERIALS I MISC CONTRACTS 13 MATERIALS $ 14 OTHER CONTRACTS s - CONTRACT CRAFT LABOR 15 SWEC CRAFT LABORIWALKOOWN 504 $ 54,410 16 LOSTTIME 50 $ 5,322 17 SWEC DISTRIBS $ . PLANT CRAFT LABOR 18 MECH MAINT. . s 19 20 ELECTMAlNT I&C 120
$ 12,000 21 CSG - s -
/lfiSC SUPPORT 22 QUALITY CONTROL 40 $ 4,000 23 24 PLANNING & SCHEDULING TRAINING 12
$ 1,440 25 SIMULATOR CHANGES 120 s 12,000 26 OPS 80 $ 9,800 27 HPIRP llfiSC CONTRACT SUPPORT 28 QUALITY CONTROL 40 $ 3,200 29 NDE $ -
30 31 HP/RP RADWASTE 32 NURSE s - 33 ELEVATOR CONTRACTOR -- $ - 34 WASTE MANAGEMENT $ - 35 HOUSEKEEPING s - 38 37 EQUIPMENT RENTAL VENDOR STOCKING - s 38 DECONTAMINATION CONTRACTOR - s - 39 RBC'S - $ 40 SECURITY - s - 41 42 FIRE WATCH (Rover) SAFETY 12 s 668 43 CONTINGENCY ! 67,801 ESTIMATE SUBTOTAL 2,043 $ .292,939 SITE ENCUMBRANCE PREMIUM (20%) $ 58,61!8 LOADERS (30%) $ 105,468
*ESTIMATE TOTAL $ 468,985
- 1. Gather and stage tools and materials for brackets 1 LT EL 2 2.00 1.00 4 s 123.32 $ 40.00 $ 40 s 493 $ 533
- 2. Fabricate supports for detectors 1 LT EL 2 4.00 1.00 8 $ 123.32 $ s 987 $ 987
- 3. Gather and transport detectors, wire and conduit 1 LT EL 2 6.00 1.00 12 $ 123.32 $ $ 1,480 $ 1,480
- 4. Locate and install water level detector brackets 1 LT EL 2 10,00 1,00 20 $ 123.32 s $ 2,488 $ 2,468
- 5. Stage, erect and modify scaffolding 1 LT CP 2 8.00 1.00 16 s 96.00 s $ 1,538 $ 1,538
- 6. Stage, erect and modify scaffolding 1 LT LB 1 8.00 1.00 8 $ 78.65 $ $ 629 $ 829
- 7. Fabricate and install conduits for new detectors 240 LF EL 2 0.0525 1.00 25 $ 123.32 $ 1.50 $ 380 s 3,083 s 3,443
- 8. Procure and install conduit supports 10 EA EL 2 2.00 1.00 40 $ 123.32 $ 10.00 s 100 s 4,933 $ 5,033
- 9. Procure and install Junction Boxes 2 EA EL 2 2.00 1.00 8 $ 123.32 $ 10.00 $ 20 $ 987 $ 1,007
- 10. Cora Bore between EL 15 and EL 33 1 LF EL 2 10.00 1.00 20 $ 123.32 s $ 2,488 $ 2,468
- 11. Procure and Install FCI Model FLT 93 FlexSWITCH 2 EA EL 2 2.00 1.00 8 $ 123.32 $ 1,100.00 $ 2,200 $ 987 $ 3,187
- 12. Remove Control Room fire seal and route new wiring 1 LT EL 2 10.00 1.00 20 s 123.32 $ s 2,488 $ 2,466
- 13. Procure, pull and terminate 125 VOC detector wiring 240 LF EL 2 0.030 1.00 14 $ 123.32 $ 1.25 $ 300 $ 1,728 $ 2,026 14, Procure, pull and terminate 120 VAC detector wiring 240 LF EL 2 0.030 1.00 14 s 123.32 s 1.25 s 300 $ 1,728 $ 2,028
- 15. Replace and test Control Room fire seal as required 1 LT EL 2 6.00 1.00 12 s 123.32 s $ 1,480 $ 1,480
- 16. Procure and install annunciator in Control Room 1 EA EL 2 12.00 1.00 24 $ 123.32 $ 150.00 $ 150 $ 2,960 $ 3,110
- 17. Termlnate and test annunciator In Control Room 1 EA EL 2 4.00 1.00 a $ 123.32 $ 150.00 $ 150 $ 987 $ 1,137
- 18. Dismantle scaffold, return 1o storage and cleanup 1 LT CP 2 8.00 1.00 18 $ 96.00 $ - $ 1,536 $ 1,538
- 19. Oismanue scaffold, return to storage and cleanup 1 LT LB 1 8.00 1.00 8 $ 78.65 $ $ 629 $ 629
- 20. Cleanup and restore work areas 1 LT EL 2 4.00 1.00 8 $ 123.32 s - $ 987 s 987 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT $ -
- 2. PAINTING & TOUCH-UP PT $ -
IPEC00269995
Page 2 of 3 71512012 3:54 PM IP2-054 480V SWGR Flood Detection Estimate (Rev_6-14-12).xls
~
INDIAN POINT IMPLEMENTA110N ES11MATE WORK SHEET
-0 EC #: SAMA IP2..054
~ ~~
PROJECT TITLE: Flood Detection System TAKEOFF: JOB LOCATION: 480 Von SwitChgear Room TCODE TBD ESTIMATOR: RCMT EST. STATUS: 00UTAGI: @NON.ouTAGI: TOR ORIG. DATE: 0611412012 MATERIAL$ MATERIAL LABOR SUB- ! ITEM DESCRIPTION QTY UOM CFT NO. $1MH PER UNIT DOLLARS DOLLARS CONTRACT I TOTAL$ I I FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 1.00 80 $ 5360 $ $ 4,286 $ 4,288
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW 8000 $ $ $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ - $ -
SUBTOTAL CRAFT & SUB-CONTRACTOR 373 2,376 1,464 $ 3,620 $ 38,532 $ - $ 43,916
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 30 $ 104.11 $ 3,123 $ 3,123 SUBTOTAL 403 $ 2480 1,464 $ 3,620 $ 41,955 $ -$ 47,039
' RELATED COSTS *
- 1. WALKDOWN ALLOWANCE 1 LT EL 5 $ 123.32 s 617 $ 617
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT EL 62 s 123.32 $ 10,112 $ 10,112
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 14 $ 123.32 $ 1,726 $ 1,725
- 4. GENERAL CRAFT DISTRIBS. (10%) $
5 CRAFT IN PROCESSING (20%) $ - 6. 7. HUMAN PERFORMANCE & ALARA TRAINING (112 dav trainina. or- 2%) 1 LT $ - SUBTOTAL $ 3,620 $ 54,410 $ $ 511,030 PLANT SCOPE
- 1. MECH MAINTENANCE PL - $ - $ - $
PL - $ $ - $ SUBTOTAL MECH MAINT. - $ - $ - $ - $
- 1. ELECT MAINTENANCE PL - $ - s - $ -
PL - $ - $ - $ SUBTOTAL ELECT. MAINT. - $ - $ - $ - s
- 1. I&C (Dev. Instrument Calibration Procedures) 1 LT PL 1 120.00 1.00 120 $ 100.00 s - s 12,000 $ 12,000 PL - $ - $ $
SUBTOTAL I&C MAINT. 120 $ - $ 12000 $ - $ 12.000
- 1. CSG PL - I~
PL - - $ $ SUBTOTAL CSG MAINT. I$ - $ $ - $ - SUBTOTAL PLANT 120 $ -$ 12,000 $ - $ 12,000 SUBTOTAL CRAFT/PLANT 624 $ 3,620 $ 66,410 $ $ 70,030 IMPLEMENTATION SUPPORT 1. 2 MODS ENGINEERING DESIGN ENGINEERING SUPT DURING CONST 1 1 LT LT NM NM 1 40.00 1.00 40 $ 100.00
$ 4,000
$ 4,000
- 3. SYSTEMS ENGINEERING -MECHANICAL 1 LT NM - $ . $ -
- 4. SYSTEMS ENGINEERING- ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 5. SYSTEMS EINGINEERING *INSTR & CONTROL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 6. SYSTEMS ENGINEERING -CIVIL STRUCTURAL 1 LT NM - $ $
- 7. PROJECT MANAGEMENT 1 LT NM 1 240.00 1.00 240 $ 120.00 $ 28,600 $ 28,800
- 8. TRAINING (OPS Sial!) 1 LT NM 12 12.00 1.00 12 $ 120.00 $ 1,440 $ 1,440
- 9. QA I QC VERIFICATION 1 LT NM 1 40.00 1.00 40 s 100.00 $ 4,000 $ 4,000 10.
11. PLANNING & SCHEDULING HP I RPI ALARA 1 1 LT LT NM NM
- 12. SIMULATOR CHANGES 1 LT NM 1 120.00 1.00 120 $ 100.00 $ 12,000 $ 12,000
- 13. OPS (DEVELOP/REVISE PROCEDURE($)) 1 LT NM 1 60.00 1.00 eo $ 120.00 $ 9,600 $ 9,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $ -
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING
- SWEC (InC! Per Diem) lT NM - $ $
- 2. MODS PLANNING & SCH.- SWEC (InC! Per Diem) 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 3. OSG FIELD ENGRSIPLAN- SWEC (lncl Per Diem) 1 LT NM 1 60.00 1.00 80 $ 120.00 $ 9,600 $ 9,600
- 4. QA I QC VERIFICATION 1 LT NM 1 40.00 1.00 40 $ 80.00 $ 3,200 $ 3,200
- 5. NDE 1 LT NM $ $
6. 7, RP STE 1 1 LT LT NM NM B. 1 LT NM 9, ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIREWATCH (Rover) LT NM $ $
- 18. SAFETY(2%) 1 LT NM 12 s 72.14 $ 866 $ 866 19 LOST TIME 110%\ 1 LT 50 $ 106.43 $ 5322 $ 5322 SUBTOTAL CRAFT/NON-MANUAL 1,438 $ 3,620 $ 155,238 $ - $ 1511,8511 IPEC00269996
Page 3 of3 715120!2 3:54PM IP2-<l54 4BOV SWGR Flood Detection Esfirnote (Rev_6-14-12).xls
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-0 EC #; SAMA IP2-054 PROJECT TITLE: Flood Detection System JOB LOCATION: 480 Volt Swit~ear Room
~~CAPITAL ROJECT CODE: TBD
~o&M TAKEOFF:
ESTIMATOR: RCMT EST. STATUS: 000TAGE 0NON<XJTAGE RIGINATOR: ORIG. DATE: 06/1412012 MAN HOURS MATERIAU MATERIAL LABOR sua. ITEM DESCRJPnoN QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 1. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 217 $ 217 SUBTOTAL INSTA 1.436 $ 3,637 $ 155,236 $ . $ 159,075
- 1. DESIGN ENGINEERING *MECHANICAL 1 LT NM . $ . $
- 2. DESIGN ENGINEERING* ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. DESIGN ENGINEERING* INSTR. & CONTROL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 4. DESIGN ENGINEERING- CIVILJSTRUCTURAL 1 LT NM - $ - $ .
5 6. TESTING (Instrument Calibration and testing) CONTRACT ENGR DESIGN SUPPORT 1 1 LT LT NM NM 2 1 10.00 460.00 1.00 1.00 20 $ 100.00 460 $ 120.00 2,000 $ 57,600 2,000 57,600
- 7. DESIGN ENG. ACCEPTANCE REVIEW 1 LT NM 1 25.00 1.00 25 $ 100.00 $ 2500 $ 2 SUBTOTAL DESIGN COST 605 $ 70,100 $ . $ 70 SUBTOTAL INSTALLAnoN & DESIGN COST 2,043 $ 225.336 $ . $ 225,336
- 1. CONTINGENCY ( 30%) $ 67.601 ESTIMATE SUBTOTAL 2,043 $ 292,939 IPEC00269997
ENTERGY Conceptual Design
~ ~~"~'?'~~~£,:.: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-056 Keep RHR Heat Exchanger Discharge Motor-Operated Valves (MOVs) Open Prepared blJ ,.r / Approved by:
IX P.lf ~ aP( ~,;:> Date: C(- 20--ZC:J(Z Date: ' / :' Page 1 of 10 IPEC00269998
ENTERGY Conceptual Design
~ ~~~~~~~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of 10 IPEC00269999
ENTERGY Conceptual Design
~ ~~~~,~~~2,:,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-056:
Keep RHR Heat Exchanger Discharge Motor-Operated Valves (MOVs) Open
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-056 in accordance with Entergy design engineering practices. For SAMA IP2-056, resolution is needed to determine the changes and requirements necessary for the Station to be operating with the Residual Heat Removal (RHR) Heat Exchanger Discharge MOVs maintained open. The RHR system was originally designed to operate with the MOVs normally closed. The change proposed herein is for the MOVs to be maintained open when the Station is operating, eliminating the potential risk of the MOV not opening when required. This package will assess revising the applicable Station Operating Procedures as the solution for accommodating the proposed change. In addition, this package will also provide a physical modification to the Station that is required in conjunction with the procedural change recommended. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also supportive sketches as required. These descriptive details and sketches provide the basis for initiating the all inclusive conceptual cost estimate for Engineering Change (EC) development and implementation at the Station. Page 3 of 10 IPEC00270000
ENTERGY Conceptual Design
~ ~;.~,~,?.~~~'~": Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 3.0 EXISTING CONDITIONS RHR MOV-747 and RHR MOV-746 are currently installed in the outlet paths of Residual Heat Exchangers No. 21 and No. 22 respectively. At presentthe RHR MOVs remain closed during normal operations of the Station, isolating the RHR system from the Sl system, and only open when required. When the MOVs are opened, the flow from these two HX outlets inter-connect with the Safety Injection (SI) system. An operating preference would be for them to remain open when the Station is operating in order to eliminate the risk of the valves not opening when required.
Although changing the operating state of the MOVs has its benefits, there is a potential issue that the outlet flow from the RHR system could interfere with the Sl system's functionality. Further analysis will be required to evaluate this issue. 4.0 DESIGN CONSIDERATIONS This conceptual package will define the requirements necessary in order to make the operability change for the MOVs. It will also include the details for installation of a physical modification required in conjunction with the procedural changes being made. Pre-requisites In order to change the operating mode of the Heat Exchanger Discharge MOVs to normally open, an approved procedure is necessary. As a pre-requisite to issuing the procedure, analytical confirmation of the proposed change is also required. With the revised operating state of the MOVs, a review of the Hx outlet flow's resulting influence on the RHR/SI systems is needed. The results of this evaluation will be the basis for the physical modifications proposed in addition to the procedure change. Modifications The intended option being proposed here will be to provide IP2 with the same configuration presently installed on IP3 (IP3 currently operates with the equivalent MOVs normally open). This package will provide a design similar to IP3's solution for protecting the Sl system's availability. This package will provide for the installation of pressure relief valves and additional piping required for the diverted flow. Page 4 of 10 IPEC00270001
ENTERGY Conceptual Design
~ ~;;.~,~,~~,~~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 5.0 CONFIRMATION OF DESIGN The proposed package will provide the rationale, analysis, and calculations in order to justify making changes to the operating mode of MOV 746 and MOV 747. The package will provide the changes required to existing operating procedures and also identify if there is the need for creating additional procedures.
The package will also provide the design details necessary to modify the Station's physical condition with a modification required in conjunction with the proposed operating change. The modification proposed will install safety related pressure-relief valves in the inlet piping of each of the MOVs (Figure 1). Each pressure-relief valve's discharge will be connected to new piping. The new piping installed will be used for routing the relief-valve's discharge flow to its final destination at Pressurizer Relief Tank (PRT) No. 21. Note: Final design considerations will determine how the "PRT connections" will be accomplished. The intention is to modify existing PRT inflow piping to accept the new connections rather than modifying the actual vessel. 6.0 RECOMMENDED SOLUTION Pre-requisites
- 1. Perform the necessary calculations required. Provide an evaluation and analysis of the systems involved to confirm the proposed operating change is acceptable.
Verify that the integrity of the systems involved and their ability to function as required is not diminished.
- 2. Revise procedures to enable operating the Station with the MOVs kept open.
- 3. Provide the required training necessary to implement the new procedure(s).
Modifications
- 1. Provide a design package for modifications in the Containment Building that will:
- At Elevation 68'-0", locate and install a safety related relief valve in the inlet piping of each MOV.
- At Elevation 46'-0", provide the modifications to inflow PRT piping necessary for connecting the new piping routed from the safety valves.
- At Elevation 68'-0", install safety related 1" piping routed from the new relief valves to the new "PRT connections" at Elevation 46'-0".
- Install the supports required for installation of the new 1" piping.
Page 5 of 10 IPEC00270002
ENTERGY Conceptual Design
~ ~;;,~,?,?~2~,~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Relief valve, S.S., %" x 1"- 2500# rating, CROSBY (or equal) 2
- 2. 3/4 inch Sockolet, Schedule 160, A182 Grade, F316 2
- 3. 1 inch Sockolet, Schedule 160, A182 Grade, F316 2
- 4. 3/4 inch Schedule 160 seamless pipe, A376 Grade, TP 316 6 Feet
- 5. 1 inch Schedule 160 seamless pipe, A376 Grade, TP 316 600 Feet
- 6. 1 inch elbow, 6000# rating, A182 Grade, TP F316 12 Page 6 of 10 IPEC00270003
ENTERGY Conceptual Design
~ ~~,~~.~!2:.~: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 Attachment 1 Entergy Impact Screening Summary Page 7 of 10 IPEC00270004
*~Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE Engineering Change Process EN*DC-115 I
PAGE 96 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET1 OF 6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. 0 ~ u 1.. Rev. No.: ~l G. P c. Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmRact Civil/ Structural Design Engineering II YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any pioina enaineerina desian chanaes or activities?
Electrical Design Engineering DYES l&fNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering I!IYES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering II YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering II YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis II YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES ti1NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.}
IPEC00270005
*~Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE Engineering Change Process
(:N-OC-115 I PAGE 97 OF 150 REV.11 AnAcHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of 6 DESIGN ENGINEERING PROGRAMS Potentlallmeact ASME Section Ill Specifications II YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program DYES ~NO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) II YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) II YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES ~NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program 1111 YES DNO
- Does the proposed activity involve control panel design induding layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management II YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES ~NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance DYES fi'l NO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance II YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance II YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES 181 NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program QYES 181 NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270006
eEniefiD' NUCLEAR MANAGEMENT QUAUTY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 98 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET30F6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST PotentiallmQ!ct Computer Support and Software DYES iJ NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES 181 NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES 181 NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations !BYES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) BYES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) IIIII YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering I liVES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS PQ~!ntiallmQ!ct ASME Containment In-service Inspection (IWE /IWL) Program DYES UZI NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment leak Rate Testing) Program DYES ~NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testinQ?
IPEC00270007
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS (CONTINUED} Potentlallmgact ASME In-service Inspection (lSI) Program II YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program II YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program II YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES 181 NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES l&J NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES EJNO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES I8J NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES I(JNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical eQuipment?
IPEC00270008
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET50F6 PRQQRAMS AND CQMPONENTS (CONTINUED} PotenUallmeact Flow Accelerated Corrosion (FAC) Program I) YES DNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program !BYES DNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES J&'l NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proPOsed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES jgl NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES jgl NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PTCurves DYES t8) NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature reactor materials)?
Relief Valve Program Ill YES DNO
- Does the proposed activity impact or involve the design, operation and testing of relief valves safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270009
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 101 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET60F6 PROGRAMS AND COMPONENTS (CONTINUED} PotentlallmJ:!act Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program II YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering RYES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program Ill YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact I!IYES ONO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES f8l NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than neQiiaible?
Detailed Impact Screening (Attachment 9.4) Attached? D YES I .,...1211'110 IPEC00270010
ENTERGY Conceptual Design
~ ~~,:.~~,~~~2,:,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Addition of Pressure Relief Valves at MOV 746 and MOV 747 Page 8 of 10 IPEC00270011
ENTERGY Conceptual Design
~ ;:~~~,~~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 ADD ADD Rl
!IB+DI I
I I I
,... \.,
r** .... -** I TllE SIDE I r--~,
#21 , #22 ,
I I
, ,,I
,,I RESIDUAL ,I I
I HEAT~ I I I
. __-~--
I l __ . ... a£J..L SIDE M
. -~-_j
__ l __ . I
' j Figure 1 Addition of Pressure Relief Valves at MOV-748 and MOV-747 Ref. Dwg. A235298 FLOW DIAGRAM SAFETY INJECTION SYSTEM IPEC00270012
ENTERGY Conceptual Design
~ ~~~~.~.~~'~": Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process ....... Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. FLOW DIAGRAM 9321-F-2720 ............................... 1P2 Auxiliary Coolant System
- 4. FLOW DIAGRAM 235296 ......................................... IP2 Safety Injection System
- 5. DWG 9321-F-2502 ...... 1P2 Containment Arrangement Plan, Above Elevation 68'-0"
- 6. DWG 9321-F-2503 ...... 1P2 Containment Arrangement Plan, Above Elevation 46'-0"
- 7. FLOW DIAGRAM 9321-F-27353 ................................ IP3 Safety Injection System
- 8. FLOW DIAGRAM 9321-F 27473 ................................ IP3 Reactor Coolant System Page 9 of 10 IPEC00270013
ENTERGY Conceptual Design
~ ~~,~~~£:,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2-056 Rev 0 Attachment 4 Cost Estimate Page 10 of 10 IPEC00270014
IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
- ESTIMATE LEVEL* EC #: SAMA IP2-056 Conceptual PROJECT TITLE: KEEP RHR Hx DISCH MOV's OPEN ESTIMATOR: RCMT JOB LOCATION: Containment Building. PROJECT CODE: TBD
~:;_.~,;D;;.e;;.f;.;.in;.;.i;.;.ti;.;V..;;e_ _ __. 0 OUTAGE 0 NON-OUTAGE ORIGINATOR: 0 CAPITAL 0 O&M ORIG. DATE:02/16/2012 EST!MATETOTAL $1,705,367 REVISION 10-4 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy pertormed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SA MAs is related to aging management under 10 C. F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package responds to the issue identified in the NRC's staff review of SAMA IP2-056 and provides the technical resolution and associated costs required for implementation. For SAMA IP2-056, resolution is required for operating with the RHR HX Discharge MOV's open. This package will revise procedures to change the normal mode of MOV 7 46 and 747. The package will also provide a design change adding pressure relief valves and associated piping for each MOV. Prepared by: Approved by: Date: IPEC00270015
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station EC #: SAMA IP2-056
*ESTIMATE LEVEL*
t]'[ Conceptual PROJECT TITLE: KEEP RHR Hx DISCH MOV's OPEN ESTIMATOR: RCMT
~ Preliminary JOB LOCATION: Containment Building. PROJECT CODE: TBD Definitive 0 OUTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE:OZ/1612012
~
Item 1' This estimate assumes that this work will require both non s to complete.
- 2. This estimate assumes that the non-outage work work will complete during 2012.
- 3. This estimate assumes that the outage work will be completed in 2012 working (2 ) 10 hour shifts 6 days per week.
- 4. This estimate assumes that the non-outage work will not suffer productivity loss due to radiation or hazardous conditions ..
- 5. This estimate assumes that all work will be performed by trained contract crafispersons in lieu of station maintenance personnel.
- 6. This estimate assumes that the new relief valves will be purchased with all required qualifications and certifications and will be tested just prior to installation.
- 7. This estimate assumes that (4) Fitter I Welders will be assigned for non-outage work and (2) of those will be assigned to 2nd shift for theOutage and (4) additional personnel will be assigned for the Outage, (2) for each shift.
- 8. This estimate assumes that the Outage work will involve radiological conditions requiring additional briefing times, dressout times and reduced I production due to dressout requirements.
- 9. This estimate assumes NDE requirements include Visual, LP, UT and RT.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 10. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 12. and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary - 30% C. Implementation complexity 40% D. Inside Containment - 50% IPEC00270016
Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 10-4 EC #: SAMA IP2-056 PROJECT TITLE: KEEP RHR Hx DISCH MOV's OPEN []CAPITAL UO&M TAKEOFF: JOB LOCATION: Containment Building. EST. STATUS: [J OUTAGE I [J NON-OUTAGE I I MANHOURS PROJECT CODE: TBD ORIGINATOR: MATERIAL MATERIAL ESTIMATOR: RCMT ORIG. DATE:12/16/2012 LABOR SUB-ITEM DESCRIPTION QTYI UOMI CFT I NO.I UNIT I FCTR TOTAL! $/MH I PER UNIT IF.ID:";0:7L-:=L';;A;::R:;=St-:-:=:7-::::::-+-=-::,.;:;::'=-::-::=-+-=T::O=TA"'"'L:-:::-$--I DOLLARS I CONTRACT ESTIMATE
SUMMARY
MANHOURS DOLLARS
- ESTIMATE LEVEL
- EO/ ENGINEERING Conceptual 01 STUDY, DESIGN, & CLOSEOUT 140 $ 14,000 Preliminary 02 DESIGN ENGR CONST SUPPORT 80 $ 8,000 Definitive 03 WELDING ENGINEER 80 $ 8,000 04 SYS ENGR/ S-U ENGR 80 $ 8,000 General Notes: 05 PROJECT MANAGEMENT 160 $ 19,200 06 ENGINEERING DCP ACCEPTANCE REVIEW 40 $ 4,000 07 WESTINGHOUSE ANALYSIS AND CALCS $ 200,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 900 $ 108,000 09 SUPL CONTRACT MODS ENGR $
10 MODS PLAN & SCHED -CONTRACT 80 $ 8,000 11 FIELD ENGRS I PLANNERS 60 $ 7,200 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 111,108 13 OTHER CONTRACTS CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 1,611 $ 200,759 15 LOST TIME 161 $ 20,948 16 SWEC DISTRIBS $ 43,853 PLANT CRAFT LABOR 17 MECH MAl NT. 18 CSG MISC EO/ SUPPORT 19 QUALITY CONTROL 70 $ 7,000 20 TRAINING 96 $ 11,520 21 CHEMISTRY $ 22 OPS I OPS SUPPORT 200 $ 22,400 23 HP/RP 120 $ 9,547 MISC CONTRACT SUPPORT 24 QUALITY CONTROL 90 7,200 25 NDE 26 HP/RP 27 RADWASTE 28 NURSE 29 ELEVATOR CONTRACTOR 30 WASTE MANAGEMENT 31 HOUSEKEEPING 32 EQUIPMENT RENTAL CONTRACTOR 10,000 33 VENDOR STOCKING 34 DECONTAMINATION CONTACTOR 10,000 35 RCB'S 36 SECURITY- Wackenhut 37 FIRE WATCH (Rover) 38 SAFETY 32 2,176 CONTINGENCY 39 CONTINGENCY $ 252,273 ESTIMATE SUBTOTAL 4,000 $ 1,093,184 SITE ENCUMBRANCE PREMIUM (20%) $ 218,637 LOADERS (30%) $ 393,546 ESTIMATE TOTAL $ 1,705,367 IPEC00270017
Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 10-4 EC #; SAMA IP2..056 PROJECT TITLE: KEEP RHR Hx DISCH MOV's OPEN l.:d CAPITAL Oo&M TAKEOFF JOB LOCATION Contamment Building PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS 0DUTAGE 0NDN-QUTAGE ORIGINATOR ORIG. DATE: 2/1612012 MAN HOURS !MATERIAL MATERIA LABOR SUB-ITEM DESCRIPTION Qrvl UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT I DOLLARS DOLLARS I CONTRACT I TOTAL$ NON OUTAGE WORK
- 1. Gather and stage tools and materials 1 LT PF 4 10.00 1.00 40 $ 120.71 $ 4,626 $ 4,828
- 2. Cut and prep 3/4" sch. 160 pipe 1 LT PF 2 10.00 1.00 20 $ 120 71 $ $ 2414 $ 2,414 3 Cut and prep 1" sch. 160 pipe 1 LT PF 4 16.00 LOO 64 $ 120.71 $ $ 7.725 $ 7,725 4* Pop test 1" relief valves prior to installation. (QA 2 LT PF 2 7.000 1.00 28 $ $ 3,380 verify) $ 120.71 $ 3,380 OUTAGE WORK 4,104 4,104
~~ ~
1 Gather and stage tools and materials, walkdown 1 LT 10.00 1.70 34 $ 120.71 $ $ 2 Prep relief valves ( 1" valves) 2 EA 3.00 1.70 20 $ 120.71 $ 2,414 $ 2,414 3 Install scaffolding 1 LT 24.00 1.70 82 $ 9600 $ 7,872 $ 7,872 4 Install scaffolding 1 LT 24.00 1.70 82 $ 78.15 $ 6,408 $ 6,408 5 Fit and weld 3/4" and fittings 2 EA PF 2 7.00 1.70 48 $ 120.71 $ 5,794 $ 5,794
- 6. Install new 2 EA PF 2 5.00 1.70 34 $ 120.71 $ 4,104 $ 4,104
- 7. Fit and weld 1" piping, and install supports 4 EA PF 2 15.00 170 204 $ 120.71 $ 24,625 $ 24,625
- 8. Provide testing as test) 1 LT PF 2 60.00 170 204 $ 120.71 $ $ 24,625 $ 24,625
- 9. Dismantle scaffolding to storage 1 LT CP 2 24.00 1.70 82 $ 96.00 $ $ 7,872 $ 7,672
- 10. Dismantle scaffolding to storage 1 LT LB 2 24.00 1.70 82 $ 78.15 $ $ 6,408 $ 6,408
- 11. Cleanup and restore area 1 LT PF 4 10.00 1.70 68 $ 120.71 $ $ 8,208 $ 8,208 PAINTING & TOUCH*UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT
- 2. PAINTING & TOUCH-UP PT FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 2 LT FW 1 80.00 1.70 272 $ 5360 $ - $ 14.579 $ 14,579
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT NDE Contractor 1 lT NM $ 35.000 $ 35,000 SUBTOTAL 1,364 $ $ 135,360 $ 35,000 $ 170,360
- 1. CONSTRUCTION SUPPORT (8% OF LABOR$) 1 lT 109 $ 99.24 $ $ 10,817 $ 10,817 SUBTOT dUR 1,4 3 - 146, $
- RELATED COSTS *
- 1. WALKDOWN ALLOWANCE 1 LT PF 38 $ 120.71 $ 4,587 $ 4,587
- 2. WORK PACKAGE REVIEW 1 LT PF 48 $ 120.71 $ 5,794 $ 5.794
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT PF 52 $ 120.71 $ 6.277 $ 6,277
- 4. GENERAL CRAFT OUTAGE DISTRIBS (10%) $ 14,618 $ 14.618
- 5. CRAFT IN PROCESSING (20%) $ 29,235 $ 29,235
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 lT $ 2,924 $ 2,924
- 7. 1112 dav trainina. or - 2% l SUBTOTAL 1,611 $ . $ 209 612 $ 35,000 $ 244,612 PLANT SCOPE
- 1. MECH MAINTENANCE 1 LT PF PL
- 1. CSG 1 LT PL PL SUBTOTAL PLANT $ $ $ * $ -
SUBTOTAL CRAFT/PLANT 1,611 $ $ 209,612 $ IPEC00270018
Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 10..4 EC #: SAMA IP2..056 PROJECT TITLE* KEEP RHR Hx DISCH MOVs OPEN TAKEOFF JOB LOCATION* Conta1nment Build1ng. ESTIMATOR RCMT EST. STATUS: (!]OUTAGE ORIG. DATE: 211612012 ATERIAL MATERIA LABOR SUB-ITEM DESCRIPTION Q UOM CFT NO. $1MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ IMPLEMENTATION SUPPORT EOI
- 1. WELDING ENGINEERING 1 LT NM 80.00 1.00 80 $ 100.00 $ 8,000 $ 8.000
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 80.00 100 80 $ 100.00 $ 8,000 $ 8000
- 3. SYSTEMS ENGINEERING -MECHANICAL 1 LT NM 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 4. SYSTEMS ENGINEERING- CNIL STRUCTURAL 1 LT NM 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 5. PROJECT MANAGEMENT 1 LT NM 16000 1.00 160 $ 120.00 $ 19.200 $ 19.200 6 TRAINING OPS STAFF 12 LT NM 8.00 1.00 96 $ 120.00 $ 11.520 $ 11,520
- 7. OA I QC VERIFICATION 1 LT NM 70.00 1.00 70 $ 100.00 $ 7,000 $ 7.000
- 8. CHEMISTRY 1 LT NM
- 9. SIMULATOR SUPPORT 1 lT NM 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 10. HP I RPI ALARA 1 LT NM 120.00 1.00 120 $ 79.56 $ 9,547 $ 9,547
- 11. WORK MANAGEMENT 1 LT NM $
- 12. OPS I OPS PROCEDURE SUPPORT AND DEVEL 1 LT NM 120.00 1.00 120 120.00 14,400 $ 14,400
- 13. TRAVEL & LIVING EXPENSES LT CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (Inc! Per Die LT NM
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) LT NM 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 3. FIELD ENGRSIPLAN- SWEC(Incl Per D1em) LT NM 60.00 1.00 60 $ 120.00 $ 7.200 $ 7,200
- 4. QA I QC VERIFICATION LT NM 9000 1.00 90 $ 8000 $ 7,200 $ 7,200
- 5. NDE LT NM 6 HP/RP LT NM 7 RADWASTE LT NM 8 NURSE LT NM
- 9. ELEVATOR CONTRACTOR LT NM
- 10. WASTE MANAGEMENT LT NM
- 11. HOUSEKEEPING LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR LT NM $ 10,000 $ 10,000
- 13. VENDOR STOCKING LT NM
- 14. DECONTAMINATION CONTRACTOR LT NM 10,000 $ 10,000
- 15. RBC's LT NM
- 16. SECURITY LT SEC
- 17. FIREWATCH (Rover) LT NM $
- 18. SAFETY(2%) LT NM $ 68.00 $ 2,176 $ 2,176 10°/o LT $ 130.11 $ 20,948 $ 20,948
- 1. $ 4,3.08
- 2. $ 3.6,800
- 3. $ 70,000 2,920 $ 348,803 $ 55,000 $ 514,911
- 1. 40.00 40 $ $ 4,000
- 2. 100.00 100 $ $ 10,000 900.00 900 $ $ 108,000 ESTIMATE SUBTOTAL $1,093,184 IPEC00270019
ENTERGY Conceptual Design
~Technologies Indian Point Nuclear Station Package The Sm:rcr of S.TD:t 5CJ'u(icns Unit 2 SAMA IP2 -060 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-060 Prevent Water Intrusion of the 480VAC Switchgear Room from Adjacent Stairwell 4 Prepared ; ; .
/ .l
!]. .
/ *.//
Approved by: AJ vAl~~ c::;;~~---- ~* Date: 1 . . zD"'z or2 Date: '; ~* ~ ( <~ Page 1 of6 IPEC00270020
ENTERGY Conceptual Design
~ ;:,~.~~~2!~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00270021
ENTERGY Conceptual Design
~ ~~:~,~?~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-060:
Prevent water Intrusion of the 480VAC Switchgear Room as a result of flooding in the adjacent Stairwell 4
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-060 in accordance with Entergy design engineering practices. For SAMA IP2-060, resolution is required to prevent flooding at Elevation 15'-0" in Stairwell4 from entering the adjacent 480VAC Switchgear Room (switchgear room). The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. 3.0 EXISTING CONDITIONS There is fire protection system piping in Stairwell 4 immediately adjacent to the switchgear room which can potentially rupture. The piping varies in size up to four-inches in diameter. Page 3 of6 IPEC00270022
ENTERGY Conceptual Design
~ ~~;"~'~'~2~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 There are two doors in Unit 2's Stairwell4 at Elevation 15'. The stairwell entry from Unit 1's retired Superheater Building Raw Water Treatment Room is a solid one-piece steel door hinged to open inward into the stairwell. In the event of a pipe break in the stairwell, it is assumed that sufficient water cannot escape through that passageway to prevent damage to the 480V Switchgear.
The other door inside Stairwell 4 is the switchgear room entry door, a solid one-piece security door hinged to open inward to the switchgear room. This door, although being solid, may not prevent water resulting from of a pipe rupture from eventually entering the switchgear room. A solution is needed to eliminate the potential for water entering the switchgear room and also to remove the water accumulated in Stairwell4 as quickly as possible. 4.0 DESIGN CONSIDERATIONS The existing switchgear room entry door is a security door. To increase the opening's structural integrity, the existing door will be removed and replaced with a door hinged that opens inward into the stairwell. This re-orientation of the door jamb will ensure the door remains closed tightly when water pressure is present due to flooding. In addition, ensuring that the door remains closed and seated firmly against the jamb reduces the potential for flooding of the switchgear room. The accumulated water in Stairwell 4 will need an escape path to discharge to a suitable area outside the stairwell. Because the existing solid entry door from Unit 1's retired Superheater Building Raw Water Treatment Room to Stairwell 4 is not part of a fire zone boundary, the door can be modified by installing a hinged mechanical "flapper" in it to allow water from the stairwell to escape. In the event of a pipe rupture, the water will exit through the door's flapper into Unit 1's retired Superheater Building Raw Water Treatment Room. The Raw Water Treatment Room is equipped with a sub-floor drainage trench system which will accommodate most of the initial flood waters. In the event the ruptured piping flow is not terminated quickly and the trenches overflow, the Raw Water Treatment Room's grated floor opening and stairs will provide a path for the flood waters into the Unit 1 cellar. If the cellar fills up (an unlikely event if rapid response is taken), the water will then spill up over the south stair way and flow into the 15' yard. This flooding poses no threat to the Unit 2 safe shut down but would require a substantial effort to clean up and return the non-essential equipment to service. Page 4 of6 IPEC00270023
ENTERGY Conceptual Design
~ ~~;.~.~.~E~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 In addition, since flooding may not be directly observed by personnel, an alarm is required to provide early detection of this condition. Based upon the above considerations, water intrusion will be detected at one (1) inch above the floor grade at Elevation 15'-0". To avoid spurious alarms, the detection setting of the device selected may be appropriately adjusted New wiring is required for power to the new detector unit and will need to be provided from a source that is not affected by the Switchgear Room water intrusion.
Wiring is also required for the alarm signal to be routed to an assigned window of the Control Room's annunciation system at Elevation 53'-0". 5.0 CONFIRMATION OF DESIGN In this scenario, mitigation is used to alleviate the condition. The design concept being recommended will provide Operations with the earliest warning of the condition. Removing the water from Stairwell 4 in the event of a pipe rupture is the first course of action. This is accomplished with the installation of the mechanical flapper in the door leading to Unit 1's retired Superheater Building Raw Water Treatment Room. In addition, this potential condition requires an alarm which is typical for any situation that needs monitoring. Since detection of the rupture and subsequent flooding may not be immediate, providing the earliest notification to Operations is the optimum solution.
- 6. RECOMMENDED SOLUTION
- 1. Install a new switchgear room entry door to open into Stairwell 4.
- 2. Modify the existing solid entry door from Unit 1's retired Superheater Building Raw Water Treatment Room to Stairwell 4. Install a mechanical hinged flapper to swing open into the Raw Water Treatment Room.
- 3. Install a FCI Model FLT93S FlexSwitch water level detection device in the Stairwell at El. 15'-0" in an area that will not inhibit passage.
- 4. Provide Instrument Bus AC power at Elevation 53'-0" to the detection device
- Install AC power wiring in conduit raceway from Control Room at Elevation 53'-0" to the device in Stairwell4 at Elevation 15'-0".
Page 5 of6 IPEC00270024
ENTERGY Conceptual Design
~ ~~,:~,~.?.~~E,~,:~ Indian Point Nuclear Station Unit 2 Package SAMA I P2 -060 Rev. 0
- 5. Provide alarm connection from the level detection device to the annunciator
- Install 125VDC wiring in conduit raceway from the device in Stairwell4 at Elevation 15'-0" up to the cable spreading area at Elevation 33'-0"
- Continue routing wiring in cable trays at Elevation 33'-0" up to the annunciator in the Control Room at Elevation 53'-0"
- Connect wiring to new "EL. 15 FT- STAIRWELL 4 FLOOD" alarm window and 125VDC power source
- 6. Provide procedure for flood switch calibration and setpoint.
- 7. Provide procedures and training for mitigation relating to this condition.
7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Solid metal switchgear room entry door and frame 1
- 2. Metal Spring-Loaded Hinged Mechanical Flapper 1
- 3. FCI Model FLT93S FlexSwitch 1
- 4. 1"- Conduit and Supports 200 Feet
- 5. Cable 200 Feet A. 1 - 125 VDC Cable B. 1 - 120 VAC Cable
- 6. Support for water level switch 1
- 7. Junction Box with terminal blocks 1 Page 6 of6 IPEC00270025
ENTERGY Conceptual Design
~ ~:~.~~,~~2~~.: Indian Point Nuclear Station Unit2 Package SAMA IP2 -060 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270026
.Tb NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 96 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. SAMA L Rev. No.: K Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmRact Civil I Structural Design Engineering .YES ONO
- Does the proposed activity involve any civil/ structural {including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any pipinQ enQineerinQ desiQn changes or activities?
Electrical Design Engineering .YES ONO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES ONO
- Does the proposed activity involve any I&C design or settings chanQes or activities?
Mechanical Design Engineering .YES ONO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical desiQn changes or activities?
PSA Engineering .YES 0NO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES Q!!r NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270027
Jfb NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
-===-- Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 97 OF 150 Engineering Change Process ATIACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS PotentiallmQact ASME Section Ill Specifications DYES D!fNo
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES [RI'NO
- Does the proposed activity involve any new or existing EO components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES Od'No
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES IX] NO
- Does the proposed activity impact or involve any change to design, licensing or operations maroins?
Reg. Guide 1.97/ PAM (Post Accident Monitoring) DYES 00 NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE PotentiallmQact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
l&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES C$.1 NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES ~NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270028
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmgact Computer Support and Software DYES IXf NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES !x1 NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection {RP) Program Impact DYES (!1 NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite} into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage {PS&O) DYES iXrNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallmgact ASME Containment In-service Inspection (IWE /IWL) Program DYES l}t] NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J {Primary Containment Leak Rate Testing} Program DYES iXf NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270029
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmgact ASME In-service Inspection (lSI) Program DYES ~Ia'No
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES IX1 NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES ~NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES !if NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES IKI NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES liT NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES 18] NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES lXf NO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical eQuipment?
IPEC00270030
-=-Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN~DC-115 I REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallm(!act Flow Accelerated Corrosion (FAC) Program DYES 00 NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES IXJNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES 1Xf NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
. Does the proposed activity involve thermography?
. Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES I8J NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES (gfNo
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES f&TNO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES IX! NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES [Kl NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES fxl NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270031
d** NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new traininQ?
Simulator Impact .YES ONO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES ONO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES ~NO IPEC00270032
ENTERGY Conceptual Design
~ ~~~~.~,?.~~2~:~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Stairwell Flood Switch Location
- 2. Figure 2: Flood Switch Installation IPEC00270033
Indian Point Nuclear Station Unit 2 FLOOD SWITCH--""'""' ACTUAL LOCATION TO BE DETERMINED AT FINAL DESIGN UNIT 2 480VAC SWITCHGEAR CJ\LST ROOM REPLACE DOOR STAIRWELL 4 EVAPORATCR INSTALL I\JPU1 PULPS FLAPPER
#11 m#12 IN DOOR w-,
fAONOBED
#11 Figure 1 FLOOD SWITCH LOCATION AT ELEV 15' 0" Owg Ref: A 138000 UNIT 1 GENERATOR SUPERHEATER BLOCS IPEC00270034
18f1 CONDUITS\ WALL MTD JUNCTION BOX ANCHOR.., BOLT FLOOD SWITCH AND SUPPORT Figure 2 FLOOD SWITCH INSTALLATION (NOT SCALE) ~"~"---*------------------------------......---1 IPEC00270035
ENTERGY Conceptual Design
~ ~~~~~~~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 10
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3 Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. FCI Model FLT93S FlexSwitch (included here)
IPEC00270036
FCI FLUID COMPONENTS INTERNATIONAL LLC
... Jl .
FLT93S FlexSwitch Level Switch Products I Level Switches FI.T93B FtT93S r-LT93F FLT93C *Download literature for this product Level Switch Summary L HJO The FLT93S insertion type FlexSwitch for level and temperature monitoring represents the first true technological breakthrough in thermal technology in over a decade. This product was designed for heavy industrial environments including high temperature and high pressure. FCI is the only thermal manufacturer providing temperature compensation to ensure set point accuracy for process temperatures that vary up to+/- 100° F. The FLT93S is easily field-configured or factory preset, providing unparalleled flexibility, accuracy and stability for all multiple process sensing and switching requirements. For an operational demonstration of FCI's FLT93 FlexSwitch Series, please follow this link. Applications Interface/level detection in settling IJ Interface and sump level detection [] vessels Interface/sump level detection in IJ [J Foam or sediment level control separation vessels [J Agitation detection IJ Liquid/resin interface detection Specifications For Level/Interface Service: Accuracy: +/- 0.25 inch [+/- 6.4 mm] Repeatability: +/- 0.125 inch [+/- 3.2 mm] Page 1 of3 IPEC00270037
For Temperature Service: Accuracy: +/- 2° F [+/- 1 o C) Repeatability: +/- 1 o F [+/- 0.6° C) Response Time: As low as 3 seconds
Enclosure:
Powder coated aluminum enclosure is rated for hazardous location use Groups B, C, D, E, F and G, CENELEC EEx d IIC and resists the effects of weather and corrosion per NEMA/CSA Type 4X (equivalent to IP66). Stainless steel is available as an option. Agency Approvals: FM, CSA, CENELEC, ATEX, CE Mark, T4 Rated (System Approval) and CRN. Flow Element Materials of Construction: All-welded 316L stainless steel for all wetted surfaces. Hastelloy C, Monel 400 and Titanium are available as an option. Process Connection: D Standard: 0. 75 inch male NPT. D Optional: 1 inch male NPT, flanges or retractable sensing element. Insertion Length: D 1.2 inch [30 mm] D 2 inches [51 mm] o 4 inches [102 mm] D 6 inches [152 mm] D 9 inches [229 mm] o 12 inches [305 mm] o 18 inches [ 457 mm] Customer specified lengths are available as an option. Operating Temperature: o Standard: -4° to +350° F [ -20° to +177° C) IJ Optional: -100° to +500° F [ -73° to +260° C] or -100° to +850° F [ -73° to
+454° C)
Operating Pressure: To 3500 psig [240 bar(g)] Control Circuit Operating Temperature: -40° to + 140° F [ -40° to +60° C) Input Power: Field selectable 115 +/- 15 Vac or 230 +/- 30 Vac, 50/60 Hz; 21 to 28 Vdc or 18 to 26 Vac; 7 watts maximum. Relay Contacts: Field configurable dual SPDT or single DPDT rated 6 amps at 115 Vac, 240 Vac or 24 Vdc. Hermetically sealed relays are available as an option. Output Signal: Analog DC voltage related to flow or level/interface signal and proportional to temperature. Electrical Connection: 1 inch female NPT Remote Configuration: Available as an option with customer specified interconnecting cable length. Optional N.I.S.T. Flow Calibration Services Factory N.I.S.T. calibration in air or water is available as an option for customer specified setpoint(s) or a flow curve based on the media ranges specified above. Page 2 of3 IPEC00270038
lome I About FCI I Products I Applications I Sales I News/Events I Support I Contact FCI I Search I Site Map ,2011 Fluid Components International LLC. All Rights Reserved Contact Us at 800-854-1993 or 760-744-6950 Legal & Privacy Statements Page 3 of3 IPEC00270039
ENTERGY Conceptual Design
~ ~~;:,~,~~~2!~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -060 Rev. 0 Attachment 4 Cost Estimate IPEC00270040
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL
- EC #: SAMA IP2-060 Conceptual PROJECT TITLE: SWGR Water Intrusion Protection ESTIMATOR: RCMT JOB LOCATION:U1 Superheater Bldg-Stairwell4 PROJECT CODE: TBD
~;;;...t._ _ _ _ ____,
Definitive 0 CAPITAL 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 6-19-2012 ESTIMATE TOTAL $ 715,145 REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-060 in accordance with Entergy design engineering practices. For SAMA IP2-060, resolution is required to prevent flooding at Elevation 15' -0" in stairwell 4 and from entering the adjacent 480VAC Switchgear Room (switchgear room}. The stairwell also serves as a passageway to the entrance of the switchgear room. This package provides for a conceptual design to prevent water from entering the switchgear room in the event of a pipe rupture in the stairwell. The package will provide a design that will exhaust the water from the stairwell to a non-critical area in the event of a pipe rupture. The water needs to be exhausted from this area as quickly as possible before it floods the adjacent electrical switchgear room. Sealing the switchgear room from flooding will be accomplished by replacing the room entry door with a solid door. More essential is the need for exhausting the water from the stairwell in the event of a pipe rupture. This is required to prevent severe flooding in the switchgear room An escape path wil be provided for this constrained water to discharge to a suitable area outside the stairwell. Prepared by: Date: IPEC00270041
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE D Indian Point Nuclear Power Station t:;:, I IlVlA It: LEVEL EC #: SAMA IP2-060 1--- Conceptual PROJECT TITLE: SWGR Water Intrusion Protection ESTIMATOR: RCMT 1--- Preliminary JOB LOCATION:U1 Superheater Bldg-Stai1Well4 PROJECT CODE: TBD 1--- Definitive ORIGINATOR: ORIG. DATE: 6-19-2012 Item Description
- 1. This estimate assumes that this work will not require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all work will be performed by trained contract crafts persons in lieu of station maintenance personnel.
- 5. This estimate assumes that scaffodling will be required for conduit installation and wire pulling in the staiiWell
- 6. This estimate assumes the detection devices mounting bracket will be fabricated in the shop.
- 7. This estimate assumes a blank annunciator panel is available for use in the Unit 2 Control Room.
- 8. This estimate assumes that core boring is required between El. 15'- 0" and 33'- 0" cable spreading area.
- 9. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 10. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary - 30% C. Implementation complexity - 40% D. Inside Containment- 50% IPEC00270042
Page 1 of3 7/5/2012 4:51 PM SAMA IP2-050 ESTIMATE PREVENT WATER INTRUSION OF THE 480 VAC SWG ROOM FROM STAIRWELL 4 (6-1g...12).xls
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-0 EC #: SAMA IP2-060 PROJECT TITLE: SWGR Water Intrusion Protection 0 CAPITAL OO&M TAKEOFF:
JOB LOCATION:U1 Superheater Bldg-Stairwell4 PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: 00liTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 6-19-2012 MANHOURS MATERIALS! MATERIAL LABOR SUB-ITEM OESCRJPTION QTY UOM CFT NO. UNIT FCTR TOTAL S/MH PER UNIT OOLLARS OOLLARS CONTRACT TOTALS
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
f-tF Conceptual MANHOURS DOLLARS
'IT'" Preliminary EO/ ENGINEERING ro- Definitive 01 STUDY, DESIGN, & CLOSEOUT 160 $ 16,000 02 DESIGN ENGR CONST SUPPORT 80 $ 8,000 General Notes: 03 MODS ENGR EOI SUPPORT $
04 SYS ENGR/ S-U ENGR 196 $ 19,600 05 PROJECT MANAGEMENT 300 $ 36,000 06 WORK MANAGEMENT $ 07 TESTING 20 $ 2,000 08 ENGINEERING OCP ACCEPTANCE REVIEW 40 $ 4,000 CONTRACT ENGINEERING 09 DESIGN ENGR CONTRACT SUPPORT 800 $ 96,000 10 SUPL CONTRACT MODS ENGR $ 11 MODS PLAN & SCHED -CONTRACT 20 $ 2,000 12 FIELD ENGRS I PLANNERS 80 $ 9,600 MATERIALS I MISC CONTRACTS 13 MATERIALS $ 7,856 14 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 15 SWEC CRAFT LABORIWALKDOWN 714 $ 80,707 16 LOST TIME 71 $ 9,771 17 SWEC DISTRIBS $ 22,067 PLANT CRAFT LABOR 18 MECH MAINT. $ 19 ELECT MAINT $ 20 I&C 120 $ 12,000 21 CSG $ MISC EOI SUPPORT 22 QUALITY CONTROL 40 $ 4,000 23 TRAINING 12 $ 1,440 24 SIMULATOR CHANGES 120 $ 12.000 25 OPS 80 $ 9,600 26 HP/RP $ IIIISC CONTRACT SUPPORT 27 QUALITY CONTROL 40 $ 3,200 28 NDE $ 29 HP/RP $ 30 RADWASTE $ 31 NURSE $ - 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL CONTRACTOR $ 36 VENDOR STOCKING $ 37 DECONTAMINATION CONTACTOR $ 38 RBC'S $ 39 SECURITY- Wacl<enhut $ 40 FIRE WATCH (Rover) $ 41 SAFETY 17 $ 1,226 CONTINGENCY 42 CONTINGENCY $ 101360 ESTIMATE SUBTOTAL 2,910 s 468,427 SITE ENCUMBRANCE PREMIUM (20%) s 91,685 Loaders (30%) s 166,034 ESTIMATE TOTAL $ 716,146
- 1. Gather and stage tools and materials 1 LT CP 2 12.00 1.00 24 $ 96.00 $ $ 2,304 $ 2,304
- 2. Remove switchgear room louvered door 1 EA CP 2 8.00 1.00 16 $ 96.00 $ $ 1,536 $ 1,536
- 3. Procure, install and align new solid steel fire door 1 EA CP 2 12.00 1.00 24 $ 96.00 $ 450.00 $ 450 $ 2,304 $ 2,754
- 4. Gather hinged mechanical damper for installation in Unit 1 door 1 EA IW 2 20.00 1.00 40 $ 137.33 $ $ 5,493 $ 5,493
- 5. Cut and modify unit 1 door to install hinged mechanical damper 1 EA IW 2 40.00 1.00 80 $ 137.33 $ 300.00 $ 300 $ 10,986 $ 11,286
- 6. Install hinged mechanical damper in Unit 1 door. 1 EA IW 2 20.00 1.00 40 $ 137.33 $ 5,000.00 $ 5,000 $ 5,493 $ 10,493
- 7. Procure & install level detector and support 1 EA EL 2 4.00 1.00 8 $ 123.32 $ 125.00 $ 125 $ 987 $ 1,112
- 8. Stage, erect and modify scaffolding as required 1 LT CP 2 6.00 1.00 12 $ 96.00 $ $ 1,152 $ 1,152
- 9. Stage, erect and modify scaffolding as required 1 LT LB 1 6.00 1.00 6 $ 78.65 $ $ 472 $ 472
- 10. Procure & install conduit to connect level detector 180 LF EL 2 O.o75 2.00 54 $ 123.32 $ 3.00 $ 540 $ 6,659 $ 7,199
- 11. Procure and install Junction Box 1 EA EL 2 6.00 1.00 12 $ 123.32 $ 10.00 $ 10 $ 1,480 $ 1,490
- 12. Procure and intall conduit supports 6 EA EL 2 2.00 1.00 24 $ 123.32 $ 6.00 $ 36 $ 2,960 $ 2,996
- 13. Core boring for routing new conduit and wiring 1 LT EL 2 10.00 1.00 20 $ 123.32 $ $ 2,466 $ 2,466
- 14. Remove Control Room fire seal and route new wiring 2 EA EL 2 10.00 2.00 20 $ 123.32 $ $ 2,466 $ 2,466
- 15. Procure & install wiring from stairwell to Control Room 240 LF EL 2 0.04 1.00 19 $ 123.32 $ 1.25 $ 300 $ 2,343 $ 2,543
- 16. Procure & install new alarm window in Control Panel 1 EA EL 2 12.00 1.00 24 $ 123.32 $ 125.00 $ 125 $ 2,960 $ 3,085
- 17. Replace and test Control Room fire seal as required 1 LT EL 2 6.00 1.00 12 $ 123.32 $ 125.00 $ 125 $ 1,480 $ 1,605
- 18. Terminate Level detector and annunciator wiring 1 EA EL 1 4.00 1.00 4 $ 123.32 $ 493 $ 493
- 19. Dismantle & store scaffolding 1 LT CP 2 4.00 1.00 8 $ 96.00 $ $ 768 $ 768
- 20. Dismantle & store scaffolding 1 LT LB 1 4.00 1.00 4 $ 78.65 $ $ 315 $ 315
- 21. Test level detector and annunciator 1 LT EL 2 16.00 1.00 32 $ 123.32 $ $ 3,946 $ 3,946
- 22. Cleanup and restore area 1 LT EL 2 4.00 1.00 8 $ 123.32 $ $ 987 $ 987
- 23. Cleanup and restore area 1 LT BL 2 4.00 1.00 8 $ 90.09 $ $ 721 $ 721
- 24. Cleanup and restore area 1 LT IW 2 4.00 1.00 8 $ 137.33 $ $ 1,09Q $ 1,099 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP 1 LT PT 1 20.00 1.00 20 $ 95.16 $ 20.00 $ 400 $ 1,903 $ 2,303
- 2. PAINTING & TOUCH-UP PT $ $ $
IPEC00270043
Pa9"2of3 7/5/2012 4:51PM SA.MA IP2..QSO ESTIMATE PREVENT WATER INTRUSION OF THE 480 VAC SWG ROOM FROM ST AlR.WELL 4 (S..19-12}.Xl5
~ ..Q PROJECT TITLE: SWGR Water Intrusion Protection INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2.060
(;21 CAPITAL U OII.M TAKEOFF: JOB LOCATION:U1 Superheater Bldg-Stalrwell4 PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS* OourAGE (;21 NO!HlUTAGE ORIGINATOR: ORIG. DATE: 6-19-2012 IM::'::I~ A.NiiOURS MATERIAL LABOR SUB* ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL .,.H OOLLARS OOLLARS CONTRACT TOTAL$ FIRE WATCH IBOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 60.00 1.00 80 s 53.80 $ . $ 4,288 $ 4,268
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW . $ $ $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ . $
SUBTO AL CRAFT & SUB-CONTRACTOR 607 $ 7,411 :~ 66,061 $ . $ 75,472
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 49 $ 112.13 $ 5,494 $ 5,494 SUBT TAL 656 $ 7,411 $ 73,555 $ $ 80,966
' RELATED COSTS *
- 1. WALKDOWN ALLOWANCE 1 LT EL 7 $ 123.32 $ 863 $ 863
- 2. WORK PACKAGE REVIEW 1 LT EL 26 $ 123.32 $ 3,453 $ 3,453
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 23 $ 123.32 $ 2,836 $ 2,836
- 4. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 7,355.50 $ 7,356
- 5. CRAFT IN PROCESSING (20%) $14,711.00 $ 14,711
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ $ .
- 7. (112 day traininQ, or- 2%)
sUBTOTAL 714 $ 7,411 $ 102,774 $ * ~ 110,1!10 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ $ $
PL $ . $ $ . SUB' OTAL MECH MAINT. $ . $ - $ . $ . 1 ELECT MAINTENANCE PL . $ . $ $ . PL $ $ $ SUBTOTAL ELECT. MAINT. $ $ $ $ .
- 1. I&C (Dev. Calibration & Maintenance Procedures 1 LT PL 1 120.00 1.00 12~ $ 100.00 $ $ 12,000 s 12,000 PL $ . $ $ .
SUBTOTAL I&C MAINT. 120 $ $ 12,000 $ . $ 12,000
- 1. CSG PL $ . $ s .
PL . $ $ $ SUBTOTAL CSG MAINT. . $ . $ $ . $ SUBTOTAL PLANT 120 $ $ 12,000 $ $ 12,000 SUBTOTAL CRAFT/PLANT 834 $ 7,411 $ 114,774 $ * $ 122,185 IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM $ $ .
2 DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 eo.oo 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM $ $ .
- 4. SYSTEMS ENGINEERING *ELECTRICAL 1 LT NM 1 eo.oo 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 5. SYSTEMS EINGINEERING -INSTR & CONTROL 1 LT NM 1 36.00 1.00 36 $ 100.00 $ 3,600 $ 3,600
- 6. SYSTEMS ENGINEERING* CIVIL STRUCTURAL 1 LT NM 1 eo.oo 1.00 80 $ 100.00 $ 8,000 $ 8.000
- 7. PROJECT MANAGEMENT 1 LT NM 1 300.00 1.00 300 $ 120.00 $ 36,000 $ 36,000
- 8. WORK MANAGEMENT (w.o Planning) 1 LT NM $ $ .
- 9. 0A I QC VERIFICATION 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 10. TRAINING 12 LT NM 12 1.00 1.00 12 $ 120.00 $ 1,440 $ 1,440
- 11. HP I RPI A LARA 1 LT NM $ . $ .
- 12. SIMULATOR CHANGES 1 LT NM 2 120.00 1.00 120 $ 100.00 $ 12,000 $ 12,000
- 13. OPS (Procedure davelopment I revision) 1 LT NM 1 60.00 1.00 60 $ 120.00 $ 9,600 $ 9,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $ .
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING
- SWEC (lncl Per Diem) LT NM . $ $ .
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 3. FIELC ENGRSIPLAN- SWEC(Incl Per Diem) 1 LT NM 1 80.00 1.00 80 $ 120.00 $ 9,600 $ 9,600
- 4. 0A I QC VERIFICATION 1 LT NM 1 40.00 1.00 40 $ 80.00 $ 3,200 $ 3,200
- 5. NDE 1 LT NM . $ $
- 6. HPIRP 1 LT NM . $ . $
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURfiY 1 LT SEC
- 17. FIREWATCH {Rover) 1 LT NM $ . $ -
- 18. SAFETY(2%) 1 LT NM 17 $ 72.14 $ 1,226 $ 1,226
- 19. LOST TIME (10%) 1 LT 71 $ 137.62 $ 9,771 $ 9771 SUBTOTAL CRAFT/NON-MANUAL 1,056 $ 7,411 $ 231,211 $ . $ 238,622
- 1. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 445 $ 445 IPEC00270044
Page 3 of 3 7/5/2012 4:51 PM SAMA IPNl60 ESTIMATE PREVENT WATER INTRUSION OF THE 4BO VAC SWG ROOM FROM STAIRWELL 4 (6-19-12).xls
~ .0 PROJECT TITLE: SWGR Water Intrusion Protection INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP2-060 0CAPITAL OO&M TAKEOFF:
JOB LOCATION:U1 Superheater Bldg-Stairwell4 PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS OOUTAGE [2} NON-ouTAGE ORIGINATOR: ORIG. DATE: 6-19-2012 MAN HOURS MATERIAL MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ SUBTOTAL INSTALLATION COST 1,056 $ 7,856.00 $ 231,211 $ $ 239,067
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM $ $
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 40 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. DESIGN ENGINEERING- INSTR. & CONTROL 1 LT NM 1 80 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 4. DESIGN ENGINEERING- CIVIL/STRUCTURAL 1 LT NM 1 40 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 5. TESTING (Instrument Calibration and testing) 1 LT NM 2 10.00 1.00 20 $ 100.00 $ 2,000 $ $ 2,000
- 6. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 800.00 1.00 800 $ 120.00 $ 96,000
- 7. DESIGN ENG. DCP ACCEPTANCE REVIEW 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4000 SUBTOTAL DESIGN COST 1,020 $ 22,000 $ 96,000.00 $ 118,000 SUBTOTAL INSTALLATION & DESIGN COST $ 7,856 $ 253,211 $ 78,800 $ 337,887 1 CONTINGENCY ( 30%) $ 101,360 ESTIMATE SUBTOTAL 2,910 $ 439,227 IPEC00270045
ENTERGY Conceptual Design
~ ~~~"~'~'~:~2~,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-061 Prevent water intrusion of the 480VAC Switchgear Room as a result of flooding in the adjacent Fire Protection Deluge Room Prepared b~ rJ.J{. Approved by:
~/--~~
I ~~~ Date: 1- zo-zot'2 Date: ~* "--- '-- ~ Page 1 of6 IPEC00270046
ENTERGY Conceptual Design
~~~~~~~te: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 ISSUE 3
2.0 BACKGROUND
3 3.0 EXISTING CONDITIONS 3 4.0 DESIGN CONSIDERATIONS 4 5.0 CONFIRMATION OF DESIGN 4 6.0 RECOMMENDED SOLUTION 5 7.0 PRELIMINARY MATERIAL LIST 6 Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page2of6 IPEC00270047
ENTERGY Conceptual Design
~ ;~~,~~~!:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-061:
Prevent water intrusion of the 480VAC Switchgear Room as a result of flooding in the adjacent Fire Protection Deluge Room
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-061 in accordance with Entergy design engineering practices. For SAMA IP2-061, resolution is required to prevent flooding in the Fire Protection Deluge Room (deluge room) from entering the adjacent 480VAC Switchgear Room (switchgear room). The deluge room also serves as the passageway to the entrance of the switchgear room. This package provides for a conceptual design to prevent water from entering the switchgear room in the event of pipe rupture in the deluge room. The package will provide a design that will exhaust the water from the deluge room to a non-critical area in the event of a pipe rupture. The water needs to be exhausted from this area as quickly as possible to avoid flooding of the adjacent electrical switchgear room. The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual final cost estimate for EC development and implementation at the Station. Page 3 of6 IPEC00270048
ENTERGY Conceptual Design
~ ~~~~,~~~E~,:.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 3.0 EXISTING CONDITIONS There is fire protection system piping in the deluge room, immediately adjacent to the switchgear room, which can potentially rupture. The piping varies in size up to ten-inches in diameter.
The entry door to the deluge room is part of the fire zone boundary and is a solid one-piece steel door. In the event of a pipe break in the room, it is assumed that sufficient water cannot escape through that passageway to prevent damage to the 480V Switchgear. Inside the deluge room, there is an entry door to the switchgear room. This door has louvered openings in the lower half and is not able to prevent water resulting from a pipe rupture from entering the room. Resolution for the problem with the existing switchgear room door is required. In addition, once this door has been modified, a solution will be required to remove water accumulation in the deluge room as a result of a pipe rupture. 4.0 DESIGN CONSIDERATIONS The existing solid entry door to the deluge room must be retained since it is part of the current fire zone boundary. The louvered entry door (from the deluge room) to the switchgear room must be replaced with a solid door so that water will be kept from entering the switchgear room. The dual solid-door concept provided here is intended to capture the ruptured pipe water trapped between the two solid doors of the deluge room. In turn, an escape path will need to be provided for this constrained water to discharge to a suitable area outside the deluge room. In the event deluge piping in the Unit 2 Transformer Deluge Room ruptures causing the deluge room to begin filling with water and causing the proposed blow out panels to open, the water will exit via the stair tower #3 and flood the Unit #1 cellar. With a maximum rate of 7,000gpm the accumulated water in one hour would be approximately 400,000 gallons. This will probably fill the cellar and eventually spill up over the south stair way and flow into the 15' yard. This flooding poses no threat to the Unit 2 safe shut down but will require a substantial effort to clean up and return the non essential equipment to service. Page 4 of6 IPEC00270049
ENTERGY Conceptual Design
~ ~~~?,~~E:,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 5.0 CONFIRMATION OF DESIGN "Sealing" the switchgear room from flooding is the first step. This will be done by replacing the room entry door with a solid door. Exhausting the water from the deluge room in the event of a large deluge room pipe rupture also is required to prevent severe flooding of the switchgear room. Considering the size of the pipe being dealt with, a large discharge relief portal is necessary.
This design will install two (2) pressure release (blow-out) panels in the deluge room's south wall (Attachment 2, Figure 2). The blow-out panels will be 3 HR fire rated equal to the removed fire wall section. PSA flooding analysis assumes a flow rate of approximately 5,000GPM as a result of a guillotine type line failure in the 10 inch line with a maximum flow rate of 7,500GPM upon pump activation. Two (2) openings of 24" wide by 24" high will be required based upon this flow rate. The blow-out panels are located vertically in line to minimize the amount of rebar that would be required to be cut, thus minimizing the impact to the structural integrity of the wall in order to install blow out panels. Wiring is required for a new alarm to be routed to the Control Room's annunciator at Elevation 53'-0" to indicate the occurrence of a valve station flood. Wiring is also required for one (1) new flashing strobe light, located in the Unit 2 Turbine Building adjacent to the door to the Fire Protection Deluge Room. Additional steel bracing will be added to areas of the walls as required.
- 6. RECOMMENDED SOLUTION
- 1. Replace the switchgear room's louvered entry door with a solid door.
- 2. Modify and reinforce the deluge room's south wall for installation of the two (2) blow-out panels.
- 3. Install the two 3 HR fire rated blow-out panels as indicated.
- 4. Install two (2) limit switches on each 3 HR fire rated blow-out panel as indicated.
- 5. Provide alarm connection from the limit switches to the annunciator
- Install wiring in conduit raceway from the limit switches in the Deluge Valve Station at Elevation 15'-0" up to the cable spreading area at Elevation 33'-0"
- Continue routing wiring in cable trays at Elevation 33' -0" up to the Page 5 of6 IPEC00270050
ENTERGY Conceptual Design
~ ~:,~?c~2!!: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 annunciator in the Control Room at Elevation 53'-0"
- 6. Connect wiring to new "EL. 15FT- DELUGE VALVE STATION FLOOD" alarm window in the Control Room's Supervisory Panel annunciator
- 7. Install flashing strobe light outside of door entrance to deluge room warning of valve station flood.
- 8. Provide power wiring from the strobe light to the distribution panel
- a. Install wiring in conduit raceway from the strobe light at Elevation 15'-0" up to the cable spreading area at Elevation 33'-0"
- b. Continue routing wiring in cable trays at Elevation 33'-0" up to the distribution panel in the Control Room at Elevation 53'-0"
- 9. Provide procedures for limit switch calibration and setpoint.
- 10. Provide procedure for flashing strobe light testing.
- 11. Provide procedures and training for mitigation relating to this condition.
7.0 PRELIMINARY MATERIAl liST Item Description Quantity
- 1. Solid metal switchgear room entry door and frame 1
- 2. 2' wide x 2' high - 3 HR fire rated pressure release panel 2
- 3. Angle iron to reinforce wall openings As Required
- 4. Anchor bolts As Required
- 5. Limit switches for pressure release panel 4
- 6. 1"- Conduit 250 Feet
- 7. Junction Box with terminal blocks 1
- 8. 125 VDC 2/c Cable 200 Feet 120 VAC 2/c Cable 200 Feet
- 9. Flashing strobe light 1 Page 6 of6 IPEC00270051
ENTERGY Conceptual Design
~ ~~"~,~~~2:~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270052
-===-- Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 96 OF 150 REV.11 ATIACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 1 OF6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. S A P Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentialtmeact Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering DYES (X] NO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering DYES IXJ NO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering .YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES Ot1 NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270053
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS PotentiallmR!ct ASME Section Ill Specifications DYES ~NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES 00NO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES !:I NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES f&1 NO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES i'&T NO
- Does the proposed activity involve Reg. Guide 1.97 {Post Accident Monitoring)
Indications? MAINTENANCE Potential Jm~act Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES !JfNo
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES IE No
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270054
*~Entergy NUCLEAR MANAGEMENT MANUAl QUALITY RELATEO REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmgact Computer Support and Software DYES OD"No
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES 181 NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES ~NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce}
any cobalt containing materials (such as Stellite) into the primary system? Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) DYES jX1 NO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potential lmgact ASME Containment In-service Inspection (IWE /IWL) Program DYES IJI NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES IXJ NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270055
J!t NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS [CONTINUED} Potentiallmeact ASME In-service Inspection (lSI) Program DYES l&iNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES t&f NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as B31.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES JXI NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES IE' NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES fxl NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES IX1 NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES lXI NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES 00 NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES r&1 NO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00270056
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET50F6 PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmeact Flow Accelerated Corrosion (FAC) Program DYES tKfNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES bs.1 NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanQer program?
Predictive Maintenance Program DYES txfNO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES IXJNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES fX!'NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES IXfNO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES (K1 NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves(fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES ~NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270057
QUALITY RELATED EN-DC-115 REV.11
~Entergy NUCLEAR MANAGEMENT I
MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATIACHMENT9.3 IMPACT SCREENING
SUMMARY
SHEET& OF 6 PROGRAMS AND COMPONENTS {CONTINUED} Potential lmgact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process. such as welding, brazing or soldering?
Safety Program .YES 0NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc .* for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES DNO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES 0NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES DJJ' NO I IPEC00270058
~Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE EN-DC-115 I
PAGE 102 OF 145 REV.10 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 6 OF6 PROGRAMS AND COMPONENTS (CONTINUED) PotentrallmQact Welding Program II YES NO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program II YES NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering Ill YES NO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program Ill YES NO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact II YES NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program II YES NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? IPEC00270059
ENTERGY Conceptual Design
~ ;,:~,~~~~~~~,:,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 15'-0"
-PRESSURE RELEASE PANEL
- 2. Figure 2: CONTROL BUILDING FLOOR PLANS & SECTIONS AT EL. 15'-0"
-PRESSURE RELEASE PANEL
- 3. Figure 3: EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL. 33'-0"
-CONDUITS DUMPING INTO CABLE TRAYS IPEC00270060
i a.ITERGY Conc;epiual Design
~TechnQiogies indian Point Nudear Statkm Pad~:a;e IJ.~-d:Sorud~
Unit2 SAMA tP1 -061 Rw"~ 0 I <0
~:t I
.ci I >:Z a::
!fl.
t
-..... - - ""~a..
I/)
..(~t 1-a::r Ill I-;.,
r, I
't
........ ....r:--' ... ~
I t~ i-
-- ("\
~
Q:
~
~
N 0:::
<:(
l.a.J
~
I~
.. l. ... "f 11:
~ ~ .l J_ .
...IL .* -......
- 1- .l
~
l il
"' ~
i./ ~ (/)
. ~ >
0 co l
.t ~ -.:t
-l
""""' ..., -~ N b
.ci .ci 0::
>:Z >Z w a::
I wu..: m: > gj [/)fll
.:z ::>
' ~g 0
' I ......!
L *' ..,. ...,.,
/
DOOR
.*. ..-,. co NTROL PANELS (TYP.}
r- r-1 .1[
-il 'I
..I l DELUGE e. EXISTING STAIRS N0.3
~
t~. VALVE ~PRESSURE RELEASE PANEL
. STATION STROBE.___....-t) UMlT LIGHT fiRE SWITCH DOOR Figure 1 EQUIPMENT ARRANGEMENT CONTROL BUILDING AT EL 15'-<r-PRESSURE RELEASE PANEL (REFERENCE DWG. 9321-F-3052}
(NOT TO SCALE) IPEC00270061
IPEC00270062 If II IPEC00270063
ENTERGY Conceptual Design
~ ~~~~~~~:.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. CENTRIA Architectural Metal Wall and Roof Systems
- Pressure Relief Walls (included here)
IPEC00270064
IPEC00270065 I .
. . -- -~ - .....::.-; The dangerous potential for explosions in power generating facilities mquires
.:'::* *-*-----::::"'~~
design solutions that provide protection. With pressure release panels, only a portion of a wall will ever blow away. This relieves the pressure inside an area and diminishes the amount of overall damage to the facility. The holes in the attachment item, whether it is a panel or a panel attachment clip are larger than the fastener head. A special washer is placed between the oversized hole and fastener head. These washers are designed to fail at certain pressure, thus allowing the attachment item to pass over the head of the fastener. This will allow the section of wall to release from the suppo11s. This section of wall is framed together and held from falling to the ground by restraining cables. I !
-* / .j :: ,".....
IPEC00270066
ENTERGY Conceptual Design
~ ~:~.~,~~~~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -061 Rev. 0 Attachment 4 Cost Estimate IPEC00270067
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL
- EC #: SAMA IP2-061 PROJECT TITLE: SWGR Water Intrusion Protection ESTIMATOR: RCMT JOB LOCATION: Fire Protection Deluge Room PROJECT CODE: TBD D
~;....a.
Definitive D ouTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 06/11/2012 ESTIMATE TOTAL $933,981 0CAPITAL 0o&M REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-061 in accordance with Entergy design engineering packages. For SAMA IP2-061, resolution is required to prevent flooding in the Fire Protection Deluge Room (deluge room) from entering the adjacent 480VAC Switchgear Room (switchgear room). The deluge room also serves as the passageway to the entrance of the switchgear room. This package provides for a conceptual design to prevent water from entering the switchgear room in the event of a pipe rupture in the deluge room. The package will provide a design that will exhaust the water from the deluge room to a non-critical area in the event of a pipe rupture. The water needs to be exhausted from this area as quickly as possible before it floods the adjacent electrical switchgear room. Sealing the switchgear room from flooding will be accomplished by replacing the room entry door with a solid door. More essential is the need for exhausting the water from the deluge room in the event of a large deluge room pipe rupture. This is required to prevent severe flooding in the switchgear room The dual solid-door concept is intended to capture the ruptured pipe water between the two solid doors of the deluge room. In turn, an escape path will be needed for this constrained water to discharge to a suitable area outside the deluge room. The installation of pressure release (blowout) panels is proposed for the south exterior wall of the deluge room. Prepared by: Approved by: Date: IPEC00270068
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE J Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-061 Conceptual rROJECT TITLE: SWGR Water Intrusion Protection ESTIMATOR: RCMT Preliminary JOB LOCATION: Fire Protection Deluge Room PROJECT CODE: TBD Definitive 0 CAPITAL D OUTAGE ORIGINATOR: 0 NON-OUTAGE Do&M ORIG. DATE: 06/11/2012 Item Descriotion
- 1. This estimate assumes that this work will not require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all work will be performed by trained contract crafts persons in lieu of station maintenance personnel.
- 5. This estimate assumes that deluge room south wall (including some rebar) must be cut and reinforced to support new pressure relief panels.
- 6. This estimate assumes that concrete cutting will be performed by bricklayers/cement masons and ironworkers.
- 7. This estimate assumes a blank annunciator panel is available for use in the Unit 2 Control Room.
- 8. This estimate assumes that scaffoldinQ will be rquired for conduit installation and wire pullinQ in the stairwell.
- 9. This estimate assumes that core boring is required between El. 15'- 0" and 33'- 0" cable spreading area.
- 10. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 11. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 12. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 13. and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% I IPEC00270069
~ Page1 of3 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 7/512012 3:33PM IP2-061 Estimate (Rev_6-12-12).xls
-0 EC #: SAMA IP2-061 PROJECT TITLE: SWGR Water Intrusion Protection TAKEOFF:
JOB LOCATION: Fire Protection Delujj Room PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: OUTAGE 0 NON-ouTAGE 0 CAPITAL OO&M ORIGINATOR: ORIG. DATE: 06/11/2012 I MAN HOURS I MATERIAL ~MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOMICFT NO.I UNIT I FCTR TOTAL I $/MH PER UNIT I DOLLARS DOLLARS I CONTRACT TOTAL$
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
1-- Conceptual MANHOURS DOLLARS 1-- Preliminary EO/ ENGINEERING 1-- Definitive 01 STUDY, DESIGN, & CLOSEOUT 120 $ 12,000 02 DESIGN ENGR CONST SUPPORT BO $ B,OOO General Notes: 03 MODS ENGR EOI SUPPORT $ - 04 SYS ENGRI S-U ENGR 196 $ 19,600 05 PROJECT MANAGEMENT 300 $ 36,000 06 WORK MANAGEMENT - $ - 07 TESTING 20 $ 2,000 OB ENGINEERING DCP ACCEPTANCE REVIEW 40 $ 4,000 CONTRACT ENGINEERING 09 DESIGN ENGR CONTRACT SUPPORT BOO $ 96,000 10 SUPL CONTRACT MODS ENGR - $ - 11 MODS PLAN & SCHED -CONTRACT 20 $ 2,000 12 OSG FIELD ENGRS I PLANNERS 100 $ 12,000 MATERIALS I MISC CONTRACTS 13 MATERIALS $ 13,792 14 OTHER CONTRACTS $ - CONTRACT CRAFT LABOR 15 SWEC CRAFT LABOIVWALKDOWN 1,014 $ 11B.~BB 16 LOST TIME 101 $ 14,455 17 SWEC DISTRIBS $ 32,113 PLANT CRAFT LABOR 1B MECH MAINT. - $ - 19 ELECTMAINT - $ - 20 I&C 120 $ 12,000 21 CSG - $ - MISC EO/ SUPPORT 22 QUALITY CONTROL 40 $ 4,000 23 TRAINING 12 $ 1,440 24 SIMULATOR CHANGES 240 $ 24,000 25 OPS BO $ 9,600 26 HP/RP - $ - M/SC CONTRACT SUPPORT 27 QUALITY CONTROL 60 $ 4,BOO 2B NDE $ - 29 HP/RP $ - 30 RADWASTE $ - 31 NURSE $ - 32 ELEVATOR CONTRACTOR $ - 33 WASTE MANAGEMENT - $ - 34 HOUSEKEEPING - $ - 35 EQUIPMENT RENTAL CONTRACTOR - $ - 36 VENDOR STOCKING $ - 37 DECONTAMINATION CONTACTOR - $ 3B RBC'S $ - 39 SECURITY- Wackenhut - $ 40 FIRE WATCH (Rover) - $ - 41 SAFETY 23 $ 1,659 CONTINGENCY 42 CONTINGENCY $ .171,059 ESTIMATE SUBTOTAL 3,366 $ 598,706 SITE ENCUMBRANCE PREMIUM (20%) $ 119,741 LOADERS (30%) $ 215,534 ESTIMATE TOTAL $ 933,981
- 1. Gather and stage tools and materials 1 LT CP 2 12.00 1.00 24 $ 96.00 $ - $ 2,304 $ 2,304
- 2. Remove switchgear room louvered door 1 EA CP 2 B.OO 1.00 16 $ 96.00 $ - $ 1,536 $ 1,536
- 3. Procure, install and align new solid steel fire door 1 EA CP 2 12.00 1.00 24 $ 96.00 $ 250.00 $ 250 $ 2,304 $ 2,554
- 4. Cut & reinforce deluge room wall for blow out panels 1 LT BL 2 40.00 1.00 BO $ 90.09 $ - $ 7,207 $ 7,207
- 5. Cut & reinforce deluge room wall for blow out panels 1 LT IW 2 40.00 1.00 BO $137.33 $ 600.00 $ BOO $ 10,9B6 $ 11,5B6
- 6. Procure & install 3 HR fire rated blow out panel 2 EA IW 2 40.00 1.00 160 $137.33 $5,000.00 $ 10,000 $ 21,973 $ 31,973 Procure & install 2 lim~ switches on 3 HR fire rated blow out
- 7. 4 EA EL 2 4.00 1.00 32 $123.32 $ 125.00 $ 500 $ 3,946 $ 4,44B panel as required B. Stage, erect and modify scaffolding as required 1 LT CP 2 6.00 1.00 12 $ 96.00 $ - $ 1,152 $ 1,152
- 9. Stage, erect and modify scaffolding as required 1 LT LB 1 6.00 1.00 6 $ 7B.65 $ - $ 472 $ 472
- 10. Procure & install condu~ to connect limit switches 1BO LF EL 2 O.OB 2.00 54 $123.32 $ 3.00 $ 540 $ 6,B59 $ 7,199
- 11. Procure and install Junction Box 1 EA EL 2 6.00 1.00 12 $123.32 $ 10.00 $ 10 $ 1,4BO $ 1,490
- 12. Procure and intall conduit supports 6 EA EL 2 2.00 1.00 24 $123.32 $ 6.00 $ 36 $ 2,960 $ 2,996
- 13. Cora boring for routing new conduit and wiring 2 LT EL 2 10.00 1.00 40 $123.32 $ - $ 4,933 $ 4,933
- 14. Remove Fire barriers and seals 1 LT EL 2 10.00 1.00 20 $123.32 $ 125.00 $ 125 $ 2,466 $ 2,591
- 15. Procure & install wiring from deluge room to Control Room 240 LF EL 2 0.04 1.00 19 $123.32 $ 1.25 $ 300 $ 2,343 $ 2,643
- 16. Procure & install new alanm window In Control Panel 1 EA EL 2 12.00 1.00 24 $123.32 $ 125.00 $ 125 $ 2,960 $ 3,0B5
- 17. Procure & install strobe light outside deluge room 1 EA EL 2 20.00 1.00 40 $123.32 $ - $ 4,933 $ 4,933 1B. Replace and Test Seals 1 LT EL 2 6.00 1.00 12 $123.32 $ 125.00 $ 125 $ 1,480 $ 1,605
- 19. Tenminate Devices 6 EA EL 1 4.00 1.00 24 $123.32 $ 2,960 $ 2,960
- 20. Dismantle & store scaffolding 1 LT CP 2 4.00 1.00 B $ 96.00 $ $ 76B $ 76B
- 21. Dismantle & store scaffolding 1 LT LB 1 4.00 1.00 4 $ 7B.65 $ $ 315 $ 315
- 22. Test & secure blow out panels, switches & alanms 1 LT EL 2 16.00 1.00 32 $123.32 $ $ 3,946 $ 3,946
- 23. Cleanup and restore area 1 LT EL 2 4.00 1.00 B $123.32 $ $ 9B7 $ 9B7
- 24. Cleanup and restore area 1 LT BL 2 4.00 1.00 B $ 90.09 $ - $ 721 $ 721
- 25. Cleanup and restore area 1 LT IW 2 4.00 1.00 B $137.33 $ - $ 1,099 $ 1,099 IPEC00270070
~ Page2of3 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 7/512012 3:33PM IP2.001 Estimate {Rev_6-12-12).xls EC #: SAMA IP2-061 PROJECT TITLE: SWGR Water Intrusion Protection TAKEOFF:
JOB LOCATION: Fire Protection Deluge Room PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: 0 OIJTAGE 0 NON-<lUTAGE 0 CAPITAL OO&M ORIGINATOR: ORIG. DATE: 06/11/2012 MANHOURS MATERIAL MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT l-\D;:::O~L;.7LA7.:RS:T-DO:::'='LPilA"f::RS:rl':::co=NT;:RA~C::;T;f-:T;:;O::;T"'A'L"$,.-j PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP LT PT 20.00 1.00 20 $ 95.16 $ 20.00 $ 400 $ 1,903 $ 2,303
- 2. PAINTING & TOUCH-UP PT $ * $ * $
FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH LT FW 80.00 1.00 80 $ 53.60 $ * $ 4,288 $ 4,288
- 2. CRAFT SUPPORT FOR BOTTLE WATCH LT FW $ * $ * $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT LT $ $
SUBTOTAL CRAFT & SUB-CONTRACTOR 871 $ 13,011 $ 99,081 $ * $ 112,092
- 1. jCONSl'RU*CTI!)N l~UPPOFn (1~% I)F LABOR$) $ 7,963 $ 7,963
$ * $ 120,055
' RELATED COSTS'
- 1. WALKDOWN ALLOWANCE LT EL 10 $123.32 $ 1,233 $ 1,233
- 2. WORK PACKAGE REVIEW LT EL 30 $123.32 $ 3,700 $ 3,700
- 3. TOOL ROOM ATTENDANTS (-3.5%) LT EL 33 $123.32 $ 4,070 $ 4,070
- 4. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 10,704 $ 10,704
- 5. CRAFT IN PROCESSING (20%) $ 21,409 $ 21,409
- 6. HUMAN PERFORMANCE & ALARA TRAINING LT $ 2,141 $ 2,141
- 7. (112 dav training, or~ 2%)
SUBTOTAL 1,014 $ 13,011 $ 150,301 $ - $ 163,312 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ * $ $
PL $ * $ . $ SUBTOTAL MECH MAINT. $ * $ * $ - $
- 1. ELECT MAINTENANCE PL PL MAINT.
- 1. I&C (Dev. Calibration & Maintenance Procedures LT PL 1 120.00 1.00 120 $100.00 $ * $ 12,000 $ 12,000 PL $ * $ - $ -
SUBTOTALI&C MAINT. 120 $ - $ 12,000 $ - $ 12,000
- 1. CSG PL $ - $ - $ -
Pl $ - $ * $ SUBTOTAL CSG MAINT. SUBT $ - $ 12,000 $ * $ 12 000 SUBTOTAL CRAFT/PLANT 1,134 $ 13,011 $ 162,301 $ - $ 175,312 IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM $ $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 80.00 1.00 80 $100.00 $ 8,000 $ 8,000
- 3. SYSTEMS ENGINEERING MECHANICAL 1 LT NM $ $
- 4. SYSTEMS ENGINEERING ELECTRICAL 1 LT NM 1 80.00 1.00 80 $100.00 $ 8,000 $ 8,000
- 5. SYSTEMS EINGINEERING INSTR & CONTROL 1 LT NM 1 36.00 1.00 36 $100.00 $ 3,800 $ 3,600
- 6. SYSTEMS ENGINEERING - CIVIL STRUCTURAL 1 LT NM 1 80.00 1.00 60 $100.00 $ 8,000 $ 8,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 300.00 1.00 300 $120.00 $ 36,000 $ 36,000 B. WORK MANAGEMENT (w.o Planning) 1 LT NM 1 $ - $ -
- 9. QA I QC VIERIFICATION 1 LT NM 1 40.00 1.00 40 $100.00 $ 4,000 $ 4,000
- 10. TRAINING 12 LT NM 12 1.00 1.00 12 $120.00 $ 1,440 $ 1,440
- 11. HP /RPI ALARA 1 LT NM $ * $ .
- 12. SIMULATOR CHANGES 1 LT NM 2 120.00 1.00 240 $100.00 $ 24,000 $ 24,000
- 13. OPS (Procedure develOpment I revision) 1 LT NM 1 80.00 1.00 80 $120.00 $ 9,600 $ 9,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING* SWEC (lncl Per Diem) LT NM - $ $
$ 2,000
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) LT NM 1 20.00 1.00 20 $100.00 $ 2.000
- 3. OSG FIELD ENGRSIPLAN- SWEC(Incl Per Diem) LT NM 1 100.00 1.00 100 $120.00 $ 12,000 $ 12,000
- 4. QA I QC VERIFICATION LT NM 1 60.00 1.00 60 $ 80.00 $ 4,800 $ 4,800
- 5. NDE LT NM $ - $
- 6. HP/RP LT NM $ $
- 7. RADWASTE LT NM
- 8. NURSE LT NM
- 9. ELEVATOR CONTRACTOR LT NM
- 10. WASTE MANAGEMENT LT NM
- 11. HOUSEKEEPING LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR LT NM
- 13. VIENDOR STOCKING LT NM
- 14. DECONTAMINATION CONTRACTOR LT NM
- 15. RBC's LT NM IPEC00270071
~ Page3of3 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 71512012 3:33PM IP2-061 Estimate (Rev_6-12-12).xls 0 EC #: SAMA IP2-061 PROJECT TITLE: SWGR Water Intrusion Protection TAKEOFF:
JOB LOCATION: Fire Protection Delu~ Room PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: OUTAGE 0 NON-ouTAGE 0 CAPITAL OO&M ORIGINATOR: ORIG. DATE: 06/1112012 MAN HOURS MATERIAL MATERIAL LABOR SUB* ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 16. SECURITY 1 LT SEC
- 17. FIREWATCH {Rover) 1 LT NM $ - $ .
- 18. SAFETY (2%) 1 LT NM 23 $ 72.14 $ 1,659 $ 1,659
- 19. LOST TIME (10%) 1 LT 101 $143.12 $ 14,455 $ 14,455 SUBTOTAL CRAFT/NON-MANUAL 2,386 $ 13,011 $ 299,855 $ . $ 312,866
- 1. FREIGHT, SALES TAX, & CONSUMABLE$ (6%) $ 781 $ 781 SUBTOTAL INSTALLATION COST 2,386 $ 13,792 $299,855 $ - $ 313,647
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM $ - $ -
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 40.00 1.00 40 $100.00 $ 4,000 $ 4,000
- 3. DESIGN ENGINEERING- INSTR. & CONTROL 1 LT NM 1 40.00 1.00 40 $100.00 $ 4,000 $ 4,000
- 4. DESIGN ENGINEERING- CIVIUSTRUCTURAL 1 LT NM 1 40,00 1.00 40 $100.00 $ 4,000 $ 4,000 5, TESTING (Instrument Calibration and testing) 1 LT NM 2 10,00 1.00 20 $100.00 $ 2,000 $ 2,000
- e. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 800.00 1.00 BOO $120.00 $ 96,000 $ 96,000
- 7. DESIGN ENG. DCP ACCEPTANCE REV1EW 1 LT NM 1 40.00 1.00 40 $100.00 $ 4,000 $ 4,000 SUBTOTAL DESIGN COST 980 $ 114,000 $ - $ 114,000 COST $ 413,855 $ - $ 427,647
- 1. CONTINGENCY ( 40%) $ 171,059 ESTIMATE SUBTOTAL rr:=:r: 3,386 $ 598.700 IPEC00270072
ENTERGY Conceptual Design
~ ~.~,~~~~~~2,~,;- Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-062 Provide Alternate Safe Shutdown System Power to Safety Injection Pump Approved by:
Prepared>>: . t__ / . /;/ ( /!:1:. f}. J/((1~~~ i:/ L
/
Date: '2..o-2orz Date: '; .*
'~
Page 1 of6 IPEC00270073
ENTERGY Conceptual Design
~ ~:~~~~~2~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 ISSUE 3
2.0 BACKGROUND
3 3.0 EXISTING CONDITIONS 3 4.0 DESIGN CONSIDERATIONS 4 5.0 CONFIRMATION OF DESIGN 4 6.0 RECOMMENDED SOLUTION 5 7.0 PRELIMINARY MATERIAL LIST 6 Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00270074
ENTERGY Conceptual Design
~ ~;;~~,?.~~2!:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-062:
Provide Alternate Safe Shutdown System Power to Safety Injection Pump
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-062 in accordance with Entergy design engineering practices. For SAMA IP2-062, resolution is required to make available an alternate source of 480VAC power to a Safety Injection System pump. This is required in the event of flooding in the 480VAC Vital Switchgear Room (switchgear room) at Elevation 15'- 0" that prevents the normal 480VAC power from being available. For this SAMA, Safety Injection Pump 22 (22 Sl) has been selected to be available with the alternative power option. The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material provide the basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. 3.0 EXISTING CONDITIONS The suggested alternate source of 480VAC power to selected Pump 22 Sl is Unit 1 Substation 12FD3. Substation 12FD3, a component of the Alternate Safe Shutdown System (ASSS), is fed from a 13.8kV transformer located in the same area as the substation in the "retired" Unit 1 Station. 12FD3 substation would be an appropriate alternate power source, but it cannot be used because there isn't Page 3 of6 IPEC00270075
ENTERGY Conceptual Design
~ ~~~~'~"~2~,:;: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 sufficient compartment space available for the additional switchgear components required.
In addition to the requirement for an alternate power source to be provided, a device also needs to be added that will be able to switch to the backup power from the normal power supply feeding the pump. 4.0 DESIGN CONSIDERATIONS The existing 1250 kVA at 13.8kV transformer, based upon initial review, does not have available margin sufficient enough to power the additional new MCC for the purpose required here and this transformer will have to be replaced. Since a connection for the new MCC will be required downstream of the existing transformer's relay protection (use relay protection for existing transformer currently installed in Substation 12FD3 for new transformer), locating the new MCC in the existing substation area is preferred. In addition to the alternate power source required, a device capable of switching the alternative power to the designated pump is also required to be installed. Considering the amount of new cable that needs to be installed, the most efficient means of implementing this part of the design change requires the "switch" to be installed in the area local to the pump. 5.0 CONFIRMATION OF DESIGN Pump 22 Sl normal power source is provided from the Unit 2 switchgear room. The design package will install a manually operated transfer switch to transfer the Sl pump's power feed from its normal source to an alternate source. The switch will be located in the Unit 2 Primary Auxiliary Building (PAB) in proximity of the Pump 22 Sl room at Elevation 59"-0". The "alternate" power source will be from a new MCC installed at Elevation 33'-0" in Unit 1 and fed from the new transformer in the same area. The new MCC will provide the compartment and controls necessary for operating the pump locally at the MCC instead of from the Control Room. Page 4 of6 IPEC00270076
ENTERGY Conceptual Design
~ ~:~~~~2~,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 6.0 RECOMMENDED SOLUTION
- 1. Install a new transformer in Unit 1 at Elevation 33'-0" at Substation 12FD3 to replace the existing transformer.
- 2. Install a new MCC in Unit 1 at Elevation 33'-0" in the area of Substation 12FD3 and its associated new transformer.
- Provide an appropriate connection for powering the new MCC's bus downstream of the existing relay protection currently installed in Substation 12FD3.
- 3. Install a manually operated transfer switch located in the Primary Auxiliary Building (PAB) at Elevation 59'-0".
- 4. At Pump 22 Sl, disconnect the existing power cable. Re-route the cable to the new transfer switch and connect it to the "normal" input connection of the new switch.
- 5. At Pump 22 Sl install a new power cable. Route the new cable to outside the room to the new transfer switch and connect it to the "common" output connection of the new switch.
- 6. At the new MCC installed in Unit 1 at Elevation 33' -0" install a new power cable.
Route the new cable to the new transfer switch and connect it to the "alternate" input connection of the new switch at Elevation 59'-0" in the PAB.
- 7. Revise the necessary procedures and conduct training in response to these new operating conditions.
Page 5 of6 IPEC00270077
ENTERGY Conceptual Design
~ ~~~.~~,?~~E~~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. New transformer approximate size 3000 KVA 1
- 2. ASCO Series 386 Non-Automatic Power Transfer Switches or Equivalent 1
- 3. 1"- Conduit 80 Feet
- 4. 2" - Conduit 90 Feet
- 5. 2/c Cable 380 Feet
- 6. 480 VAC- 4/c Power Cable 450 Feet
- 7. Free standing MCC (2 buckets high x 1 bucket wide) with mounting brackets 1
- 8. 480 VAC switchgear to be installed into free standing MCC 1 Page 6 of6 IPEC00270078
I ENTERGY Conceptual Design
~Technologies Indian Point Nuclear Station Package JJH~ ":.vutct* ~JI ),non ~u;uliow)
Unit 2 SAMA IP2 -062 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270079
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. SANA Engineering Change No.: IPl- Rev. No.: E Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallmgact Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil/ structural {including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any oioinQ enQineerinQ desiQn chanQes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES OJjNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES ikl'No
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270080
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potential lm(!act ASME Section Ill Specifications DYES ~NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES Qd NO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES (J1 NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room. and other control panel locations?
Margin Management DYES KINO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97/ PAM (Post Accident Monitoring) DYES C!a'No
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potential lmQact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance DYES IJ1 NO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential Impact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES lXI' No
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundarv or reactor svstem procedures?
IPEC00270081
*"=" Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potential 1m (2act Computer Support and Software DYES !If No
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES }dNa
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact .YES DNO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, traininQ or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallm~act ASME Containment In-service Inspection (IWE /IWL) Program DYES f.XI NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES DQ NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testinQ?
IPEC00270082
*~Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE Engineering Change Process EN-DC-115 j PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS {CONTINUED} PotentiallmRact ASME In-service Inspection (lSI) Program DYES M]No
.. Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES ()JfNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES ~NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
.. Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES lkj NO
.. Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES ~NO
.. Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES fXjNO
.. Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES Q§l' NO
. Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00270083
....-=--Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 100 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 50F6 PROGRAMS AND COMPONENTS (CONTINUED) Potentiallmgact Flow Accelerated Corrosion (FAC) Program DYES r.R1 NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES IX! NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES !XI NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES DJI NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES ill NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES IX! NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program DYES IX1 NO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EO} maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PTCurves DYES ~NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure temperature, reactor materials)?
Relief Valve Program DYES ~NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES tgj NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270084
~Entergy NUClEAR MANAGEMENT MANUAl QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 101 OF 150 REV.11 ATTACHMENT9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES 0NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES 0NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES blfNo
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
IDetailed Impact Screening (Attachment 9.4) Attached? DYES tgNO IPEC00270085
ENTERGY Conceptual Design
~ ~~~~,~~~~::: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: PARTIAL SITE PLAN OF AREAS AFFECTED
- 2. Figure 2: PROVIDE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 22 Sl PUMP IPEC00270086
'"U m () 0 0 N ""'-J 0 0 (X) ""'-J r---- ENTERGY Conceptual Design
~ :~:.~e~r~~*~5~~'~; Indian Point Nuclear Station Unit 2 Package SAMA IP2-062 Rev, 0 CONT/'I,I.'~MENT BLJG_
t-I UNiT N0_2 z~
- So a..z
~* UNIT r\0.2
_;/ IN'AI<E S'RUCTURE U~>JIT N0.2 PF~I~AARY A,JXILiARY 22 Sl PUMP CONTROL BLDG. UNIT 1'10.1 SCREENWEI_L L;NIT NO_ 1 HOUS:C: TURBIN:C: SUPER'-1EATER BLDG. FIGURE 1 PARTIAL SITE PLAN OF AREAS AFFECTED (NOT TO SCALE) 0 NEW MANUAL TRANSFER SWITCH AND OFFICIAL NUMBER DETERMINED LATER
'"U m () 0 0 N ""'-J 0 0 (X) (X) ENTERGY Conceptual Design
~ T.~~.~.~~~~P~.:.~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-062 Rev. 0 CONTROL BLDG. PRIMARY AUXILIARY BLDG.
POWER
.______ TRANSFER SWITCH xxxx CONTROL ROOM UNIT NO. 2 !~~----~I 22 Sl PUMP EL. 53'-0"
(
)
UNIT SUB. COMPT. 12FD3 XXX ~--------------------------------~ EXTENSION EL. 33'-0" UNIT 1 UNIT 2 SUPERHEATER BLDG. 480 VAC SWITCHGEAR FIGURE 2
<> NEW MANUAL TRANSFER SWITCH AND OFFICIAL NUMBER DETERMINED LATER PROVIDE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 22 Sl PUMP (NOT TQ SCALE)
L NEW UNIT SUB. 12FD3 EXTENSION AND OFFICIAL NUMBER DETERMINED LATER
ENTERGY Conceptual Design
~ ~~"~'~,~~2!~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. ASCO Series 386 Non-Automatic Power Transfer Switches or Equivalent IPEC00270089
Power Switching & Controls for Business-Crit ica l Continu it y ASCO SERIES 300 Power Transfer Switches
~+r.,
~ '?~
EMERSON, f\Jet worl< Power IPEC00270090
ASCO' SERIES 386 Non-Automatic Power Transfer Switches User-Initiated Control ASCO 386 non-automatic transfer switches are generally used in applications where operating personnel are available and the load is not an emergency type requiring automatic transfe r of power. The power-switching mechanism and controller is the same hardware used on the highly reliable ASCO SERIES 300 transfer switches. ASCO 386s are furnished as standard with a momentary-type selector switch to initiate transfer andre-transfer. They can also be arranged for remote control via ASCO's connectivity products. Electrical Features:
- Listed under UL 1008, CSA certified:
- UL listed thro ugh 480 VAC.
- CSA certified through 600 VAC.
- Door-mounted selector switch for local, manually initiated electrica I control.
- Sizes from 30 th rough 3000 amps.
Available to 600 VAC. 50 or 60Hz.
- Rated for all classes of load transfer.
100%tungsten load ratings through 400 amps.
- Designed fo r emergency and sta ndby applications.
- Same withstand and close-on rating as SERIES 300.
Standard Selectable Control Features:
- In phase monitor to transfer motor loads between live sources, without any intentiona l off time, to prevent inrush currents from exceeding normal sta rting levels.
- Selective load disco nnect, double-throw contact to operate at an adjustable 0 to 20 second time delay prio r to trans-fer and reset 0 to 20 seconds after tra nsfer.
- High/Low nominal voltage setting. Allows user to adjust for source low reduced voltage conditions in remote areas.
- 60Hz or 50 Hz selectable switch.
- Single/Three-phase selectable switch.
Control Features: Fig. 14: ASCO 386 400 Amp
- Switch position indicating signal lights.
Type 1 Enclosure wfO ptional
- One auxiliary contact closed when transfer switch is Accessories 9C, 9D Source connected to normal and one closed on emergency, Ava ilability Lights standard featu re 14A/ 14B.
Optional Accessories:
- 6Q Key-operated, momenta ry source selector switch furnished instead of the standard selector switch.
ASCI t* SERIES 386
- 9C, 9D Source ava ilability lights to provide operator with a local indication of power source availability.
Power Transfer Switch
- Accessory 14AA/14BA auxiliary contacts to indicate r.- position of ma in contacts. Two (2) for normal position and two
~r......n...r
~
~
.__ (2) for emergency position (one set is standard).
T~t llbwut ..!:.., ~ T*~
- 72A Serial mod ule (5 110) is used to allow loca l or remote communications wit h ASCO POWERQUEST connectivity products.
- Special Enclosures (Specify by appropriate code in catalog number):
Fig. 15: Control and Display Panel Type 3R: Rain-tight Type 4: Weatherproof Type 12: Oil Tight
- 72E Connectivity Module 5150 is used to bring severa l different serial devices that communicate at different baud rates and with different protocols to a common Ethernet media.
9 IPEC00270091
ENTERGY Conceptual Design
~ ~~"~'~,?~~2!~.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -062 Rev. 0 Attachment 4 Cost Estimate IPEC00270092
ENTERGY NUCLEAR NORTHEAST iMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-062 PROJECT TITLE: Safety Injection Pump ASSS Power ESTIMATOR: RCMT JOB LOCATION: Aux, Superheater & Control Bldgs. PROJECT CODE: TBD 0 OLJTAGE 0 NON*OLJTAGE ORIGINATOR: ORIG. DATE: 07/1312012 ESTIMATE TOTAL $1,624,840 0CAPITAL Do&M REVISION 10-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-062 in accordance with Entergy design engineering practices. For SAMA IP2-062, resolution is required to make available an alternate source of 480VAC power to a Safety Injection System pump. This is required in the event of flooding in the 480VAC Vital Switchgear Room (switchgear room) at Elevation 15'-0" that prevents the normai480VAC power from being available. For this SAMA, Safety Injection Pump 22 (22 Sl) has been selected to be available with the alternative power option. This project will also replace the existing 13.8kV transformer with with a larger capacity model. Prepared by: Approved by: Date: IPEC00270093
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE
+/-
Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP2-062 Conceptual PROJECT TITLE: Safety Injection Pump ASSS Power ESTIMATOR: RCMT Preliminary JOB LOCATION. Aux. Superheater & Control Bldgs. PROJECTC[S~~~TBD T Definitive 0 OUTAGE 0 NON-OUTAGE ORIGINATOR 0 CAPITAL O&M ORIG. DATE: 0711312012
~ Description stimate assumes that this work will not require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personneL
- 5. This estimate assumes that core boring is required between El. 53'- 0" and 33' 0" cable spreading area.
This estimate assumes that a new transformer will be installed in Unit 1 at Elevation 33'- 0" to replace existing transformer at Substation 6 . 12FD3. This estimate assumes that a new motor control center will be installed in Unit 1 at Elevation 33' 0" near the new transformer at Substation 7
- 12FD3.
- 8. This estimate assumes that new transformer and MCC will be connected and powered by Station Maintenance personnel.
- 9. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 10. Estimate Classification System (see Attachment3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity - 40% D. Inside Containment - 50% IPEC00270094
~
Page 1 of3 10/4/2012 3:0 8 PM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET IP2-0 62.xls
-0 EC #: SAMA IP2-062 PROJECT TITLE: Safety Injection Pump ASSS Power 0cAPITAL Uo&M TAKEOFF:
JOB LOCATION: Aux, Superheater & Control Bldgs. PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: DourAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 0711312012 MAN HOURS 'MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT !'l0 UNIT FCTR TOTAL $1MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
"'15'"""
o-rr- Conceptual Preliminary Definitive EO/ ENGINEERING 01 STUDY, DESIGN, & CLOSEOUT MANHOURS 600 DOLLARS
$ 60,000 02 DESIGN ENGR CONST SUPPORT 160 $ 16,000 General Notes: 03 MODS ENGR EOI SUPPORT $
04 SYS ENGRI S-U ENGR 160 $ 16,000 05 PROJECT MANAGEMENT 600 $ 60,000 06 WORK MANAGEMENT $ 07 ENGINEERING DCP ACCEPTANCE REVIEW 150 $ 15,000 CO/fl'RACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 1,040 $ 124,800 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 160 $ 16,000 11 FIELD ENGRS I PLANNERS 140 $ 16,800 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 170,459 13 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/\NALKDOWN 1,316 $ 139,400 15 LOST TIME 132 $ 17,673 16 SWEC DISTRIBS $ 37,881 PLA/fl' CRAFT LABOR 17 MECH MAl NT. $ 18 ELECT MAINT 32 $ 3,200 19 I&C $ 20 CSG $ MISC EO/ SUPPORT 21 QUALITY CONTROL 120 $ 12,000 22 TRAINING 48 $ 5,760 23 CHEMISTRY $ 24 OPS I OPS SUPPORT 120 $ 14,400 25 HPIRP 80 $ 6,365 MISC CONTRACT SUPPORT 26 QUALITY CONTROL 130 $ 10,400 27 NDE $ 28 HPIRP $ 29 RADWASTE $ 30 NURSE $ 31 ELEVATOR CONTRACTOR $ 32 WASTE MANAGEMENT $ 33 HOUSEKEEPING $ 34 EQUIPMENT RENTAL CONTRACTOR $ 35 VENDOR STOCKING $ 36 DECONTAMINATION CONTACTOR $ 37 RBC'S $ 38 SECURITY- Wackenhut $ 39 FIRE WATCH (Rover) $ 40 SAFETY 27 $ 1,836 CONTINGENCY 41 CONTINGENCY $ 297,590 ESTIMATE SUBTOTAL 5,015 $ 1,041,564 SITE ENCUMBRANCE PREMIUM (20%) $ 208,313 LOADERS (30%) $ 374,963 ESTIMATE TOTAL $ 1,624,840
- 1. Gather and stage tools and materials 1 LT EL 4 10.00 1.00 40 $ 123.32 $ $ 4,933 $ 4,933
- 2. Determinate at existing MCC and remove substation 12FD3 Transformer 1 EA EL 4 20.00 1.00 80 $ 123.32 $ $ 9,866 $ 9,866
- 3. Procure and set new 3000kVA transformer 1 EA EL 4 20.00 1.00 80 $ 123.32 $ 150,000.00 $ 150,000 $ 9,866 $ 159,866
- 4. Stage, erect & modify scaffolding as required 1 LT CP 2 12.00 1.00 24 $ 96.00 $ $ 2,304 $ 2,304
- 5. Stage, erect & modify scaffolding as required 1 LT LB 1 12.00 1.00 12 $ 78.15 $ $ 938 $ 938
- 6. Core drill as required to route new conduit 2 LT EL 2 20.00 1.00 80 $ 123.20 $ $ 9,856 $ 9,856
- 7. Procure & install new MCC, 2 buckets and 480VAC 1 EA EL 4 30.00 1.00 $ 8,500.00 $ 8,500 $ 14,798 $ 23,298 switchgear as required 120 $ 123.32
- 8. Install a manually operated transfer switch at El. 59' -
1 EA EL 2 24.00 1.00 $ 500.00 $ 500 $ 5,919 $ 6,419 0" in the Primary Auxiliary Building 48 $ 123.32
- 9. Procure and field erect conduit supports 22 EA EL 5 1.00 1.00 110 $ 123.32 $ 6.00 $ 132 $ 13,565 $ 13,697
- 10. Procure and erect 1" conduit as required 80 LF EL 2 0.18 1.00 29 $ 123.32 $ 1.75 $ 140 $ 3,576 $ 3,716
- 11. Procure and erect 2" conduit as required 90 LF EL 2 0.20 1.00 36 $ 123.32 $ 1.75 $ 158 $ 4,440 $ 4,598
- 12. Procure, pull & route 2/c cable as required 456 LF EL 2 0.018 1.00 16 $ 123.32 $ 1.25 $ 570 $ 1,973 $ 2,543 13.
Procure, pull & route 480VAC 4/c cable as required 540 LF EL 2 0.03 1.00 32 $ 123.32 $ 1.50 $ 810 $ 3,946 $ 4,756
- 14. Disconnect existing power cable at 22 Sl 1 LT PL 2 30.00 1.00 60 $ 60.00 $ $ 3,600 $ 3,600
- 15. Connect new power cable to 22 Sl & power cables to transfer switch 1 LT PL 2 20.00 1.00 40 $ 60.00 $ $ 2,400 $ 2,400 16.
Connect power cable to ne\rV MCC's and transformer 1 LT PL 2 60.00 1.00 120 $ 60.00 $ $ 7,200 $ 7,200
- 17. Provide testing as required 1 LT PL 2 4.00 1.00 8 $ 60.00 $ $ 480 $ 480
- 18. Assist with testing as required 1 LT EL 2 20.00 1.00 40 $ 123.32 $ $ 4,933 $ 4,933
- 19. Dismantle scaffolding to storage 1 LT CP 2 12.00 1.00 24 $ 96.00 $ $ 2,304 $ 2,304
- 20. Dismantle scaffolding to storage 1 LT LB 1 12.00 1.00 12 $ 78.15 $ $ 938 $ 938
- 21. Cleanup and restore area 1 LT EL 4 8.00 1.00 32 $ 123.32 $ $ 3,946 $ 3,946 IPEC00270095
Page 4 of 5 7126/2012 8:56 AJ.~ Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET IP2-082 $j Pump Safe Shutdown (Rev_1~22~11! Jds 10-0 PROJECT TITLE: Safety Injection Pump ASSS Power JOB LOCATION Aux< Superheater & Control Bldgs EST STATUS: 0 CJUri\GE 0 NON.Qllfi\GE ITEM DESCRIPTION TOTAL$ PAINTING & TOUCH-UP REQUIREMENTS PAINTING & TOUCH-UP PAINTING & TOUCH-UP FIRE WATCH I BOTTLEWATCH REQUIREMENTS CRAFT SUPPORT FOR FIRE WATCH 2 LT FW 4800 1<00 96 * $ 5<146 5,146 CRAFT SUPPORT FOR BOTTLE WATCH LT FW . 's MISC SUB-CONTRACT MISC SUB-CONTRACT . s
' 27 9,342 1,
- RELATED COSTS
- I WALKDOWN ALLOWANCE LT EL 12 123.32 1,480 ' 1,480 WORK PACKAGE REVIEVV LT EL 31 123.32 3,623 3,623 TOOL ROOM ATTENDANTS [-3 5%) L7 EL 43 123.32 5,303 5,303 4 GENERAL CRAFT OUTAGE DISTRIBS. (10%) 12,627 12,627
- 5. CRAFT IN PROCESSING (20%) 25,254 25,254 HUMAN PERFORMANCE & ALARA TRAINING 2,525 2,525 1.316 160,810 $ 177,261 336091 PLANT SCOPE PL 3.200 3,200 3,200 SUBTOTAL CSG MAINT.
3.200 0,481 $ $ 341.291 IMPLEMENTATION SUPPORT EO/ WELDING ENGINEERING LT NM s DESIGN ENGINEERING SUPT DURING CONST LT NM 16000 1.00 160 100 00 16,000 s 16,000 SYSTEMS ENGINEERING* MECHANICAL LT NM s 4 SYSTEMS ENGINEERING
- ELECTRICAL LT NM 80.00 1.00 eo 100.00 8,000 $ 8.000 5 SYSTEMS EINGINEERING
- INSTR & CONTROL LT NM 40.00 1.00 40 100.00 4,000 $ 4,000 6 SYSTEMS ENGINEERING* CIVIL STRUCTURAL LT NM 40.00 1 00 40 100.00 4,000 $ 4,000
- 7. PROJECT MANAGEMENT LT NM 600.00 1.00 600 100.00 60,000 $ 60.000 8 TRAINING OPS STAFF 12 LT NM 4.00 1.00 48 12o.oo 1 5,780 $ 5,760 9 QA I QC VERIFICATION 1 LT NM 1 120.00 1.00 120 I 12,000 $ 12,000 I~;
10 CHEMISTRY 1 NM ,0000 $ 11 HP I RPI A LARA NM 80.00 1.00 80 79.56 6,385 $ 8,365 12 WORK MANAGEMENT LT NM s OPS I OPS PROCEDURE SUPPORT AND 13 DEVELOPMENT LT NM 120.00 1.00 120 120.00 14,400 14,400
- 14. TRAVEL & LIVING EXPENSES LT CONTRACTOR SUPPORT FIS I MODS ENGINEERING* SWEC (lncl Per Diem) LT NM MODS PLANNING & SCH.- SWEC (lncl Per D*em) LT NM 160.00 1.00 160 s 100.00 16,000 $ 16,000 FIELD ENGRSIPLAN- SWEC LT NM 14000 1.00 140 120.00 16,800 $ 16,800 QA I QC VERIFICATION LT NM 1 130 00 1.00 130 80.00 10,400 $ 10.400 5 NDE LT NM $
6 HPIRP LT NM $ 7 RADWASTE LT NM
- e. NURSE LT NM 9 ELEVATOR CONTRACTOR LT NM 10 WASTE MANAGEMENT LT NM
- 11. HOUSEKEEPING LT I NM
- 12. EQUIPMENT RENTAL CONTRACTOR LT NM 13 VENDOR STOCKING LT NM 14 DECONTAMINATION CONTRACTOR LT NM 15 RBC's LT NM 16 SECURITY LT SEC
- 17. FIREWA TCH (Rover) LT NM SAFETY (2%) LT 27 68.00 LT 132 133.69 FTINON*MANUAL 3,225 160,810 $373,715 $ 534,525 IPEC00270096
~
Page 5 of5 7/261201 2 8:58AM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET lP2-062 Sl Pump Safe Shutdown (R:ev_1 -22*11}-xls 0 EC #: SAMA IP2*062
~
~
1PROJECT TITLE Safety Injection Pump ASSS Power JOB LOCATION: Aux, Superheater & Control Bldgs T CODE TBD T EST STATUS OOUTAGE 0NON<JUTAGE TOR u -"MATERIAL$ m:%1 ITEM DESCRIPTION QTY UO T TOTAL$
- 1. FREIGHT. SALES TAX. & CONSUMABLES (6%) $ 9.649 s 9,649 3,225 $ $ 544, 74 1 DESIGN ENGINEERING* MECHANICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000 2 DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 440,00 100 440 s 100 00 $ 44,000 $ 44,000 3 DESIGN ENGINEERING* INSTR. & CONTROL 1 LT NM s $
4 DESIGN ENGINEERING- CIVIUSTRUCTURAL 1 LT NM 1 8000 1.00 80 s 100.00 $ 8,000 $ 8,000 5 1.()40 s s
=~
CONTRACT ENGR DESIGN SuPPORT 1 NM 1 1,04000 100 120,00 $ 124,800 124,800 6 ENGRG DCP ACCEPTANCE REVIEW 1 NM 1 150 s 100.00 $ 15 000 s 15,000 1. SUBTOTAL DESIGN COST CONTINGENCY (40%) I 1,790 3 170,459 $ 199,800 s $ s 370,259 297,590 ESTIMATE SUBTOTAL 5,015 $ 1,041,564 IPEC00270097
ENTERGY Conceptual Design
~ ~:;,~~,~~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-065 Upgrade Alternate Safe Shutdown System for RCP Seal Cooling Prepared b/Jt !} . , Approved by:
t _y; ;;'}t~we. --- --***- Date: q.~zo-2..orz Date: / {;, Page 1 of6 IPEC00270098
ENTERGY Conceptual Design
~ ~~,~~,~~~2,:~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 ISSUE 3
2.0 BACKGROUND
3 3.0 EXISTING CONDITIONS 4 4.0 DESIGN CONSIDERATIONS 4 5.0 CONFIRMATION OF DESIGN 4 6.0 RECOMMENDED SOLUTION 5 7.0 PRELIMINARY MATERIAL LIST 6 Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00270099
ENTERGY Conceptual Design
~ ~~.~~,~~2~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Kev. u 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-065:
Upgrade Alternate Safe Shutdown System for RCP Seal Cooling
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-065 in accordance with Entergy design engineering practices. Component Cooling Water 23 Pump, Charging Pump 23, and Service Water Pumps 23 and 24 are system pumps powered from the 480VAC Vital Switchgear Room (switchgear room) at Elevation 15'-0". These pumps can provide cooling water for Reactor Cooling Pump (RCP) seal cooling when needed. When necessary, this action needs to be provided in a timely manner. For SAMA IP2-065, resolution is required to provide the ability to switch these pumps to an existing alternative power source more quickly (within 10 to 15 minutes) than is possible using the current available method. The modifications described above are in the event of flooding in the switchgear room that prevents the normai480VAC power from being available. The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. Page 3 of6 IPEC002701 00
ENTERGY Conceptual Design
~ ~~~.~~;::~2:,:.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 3.0 EXISTING CONDITIONS Currently, the selected pumps can be powered from alternative power available at Unit 1 Substations 12FD3 and 12RW3 through the operation of manually operated transfer switches located at the respective pump areas. In the event of loss of RCP seal cooling, it will take an operator too much time under certain circumstances to get to these local devices to switch to alternate power. A provision to enable the alternate source of 480VAC power to be provided in a more timely way than the existing method is required.
4.0 DESIGN CONSIDERATIONS One way to more rapidly activate the alternate source of 480VAC power is to install remotely operated switching devices in place of the locally installed manual switching devices. These emergency power transfer devices will be able to be operated remotely from a new panel installed near (but not in) the Control Room. This philosophy ensures that the new installation maintains appropriate physical separation from the Control Rooms' existing design criteria and its current day to day operation. These remotely located transfer switches will also be able to be operated at their installed locations. The new remotely operated transfer devices will be installed in the locations currently occupied by the manually operated devices. The new switching devices will also have the option of manual transfer from their location in addition to being operated from the remote location. Control power for the new switching device's operating requirements will need to be provided from a source that is not affected by the Switchgear Room water intrusion. 5.0 CONFIRMATION OF DESIGN The normal power source for Component Cooling Water Pump 23 (23 CCW) and Charging Pump 23 (23 CHRG), and Service Water Pumps 23 (23 SW) and (24 SW) is provided from the Unit 2 switchgear room. The alternate power source for pumps 23 CCW and 23 CHRG is Unit 1 Substation 12 FD3 through the operation of manually operated transfer switches. The alternate power source for pumps 23 SW and 24 SW is Unit 1 Substation 12 RW3 through the operation of manually operated transfer switches. This design package retains the existing alternate power sources but accomplishes the transfer with the installation of new transfer switches that can be remotely operated or operated locally. Page 4 of6 IPEC002701 01
ENTERGY Conceptual Design
~ ~~"~~,~~~2:,~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 The new panel located near the Control room will provide the ability to transfer the pumps 480VAC power requirements from the normal source to their respective alternate source. This panel will also include the controls required for operating the pumps from this location instead of the Control room or at Unit 1 Substations 12FD3 and 12RW3.
- 6. RECOMMENDED SOLUTION
- 1. At each of the pump's existing manually operated transfer switches, disconnect the power cables.
- Remove the existing manually operated transfer switches
- 2. In the locations previously occupied by the manual transfer switches, install the new electrically operated transfer switches.
- Re-connect the removed power cables to the new transfer switches
- Connect the transfer switches with a new cable routed from a source that is not affected by the Switchgear Room water intrusion.
- 3. Outside the Control Room area install a new operating panel with power transfer ability and operating controls for 23 CCW Pump, 23 CHRG Pump, and Pumps 23 SW and 24 SW.
- Connect the transfer switches with new control cabling for its operation and route it to the new operating panel located outside the Control Room area.
- Connect the existing two (2) pump motor control compartments at Unit 1 Substation 12FD3 with new control cabling for their operation and route it to the new operating panel located outside the Control Room area.
- Connect the existing two (2) pump motor control compartments at Unit 1 Substation 12RW3 with new control cabling for their operation and route it to the new operating panel located outside the Control Room area.
- 4. Revise the necessary procedures to ensure the requirement for restoration of power within 10 to 15 minutes and conduct training in response to these new operating conditions.
Page 5 of6 IPEC002701 02
ENTERGY Conceptual Design
~ ~;~.~~.~~2:,~,: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. ASCO Series 386 Non-Automatic Power Transfer Switches or Equivalent 4
- 2. Control Switches 8
- 3. 2"- Conduit 250 Feet
- 4. 2/c Cable 900 Feet
- 5. 4/c Cable 1500 Feet
- 6. Hoffman Box 12"x16"x1 0" 4 Page 6 of6 IPEC002701 03
ENTERGY Conceptual Design
~ ~~~~~~~2~,:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC002701 04
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN*DC*115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. SAMA Engineering Change No.: 0b Rev. No.: E Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallm12act Civil/ Structural Design Engineering .YES DNO
- Does the proposed activity involve any civil I structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES ~NO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES (i!No
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC002701 05
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 97 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potentiallmeact ASME Section Ill Specifications DYES Dij'No
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a desi~n specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) DYES IKJNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES l8j NO
- Does the proposed activity involve any new or existing EO components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES lXI NO
- Does the proposed activity impact equipment or materials related to hydrogen contr .....
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES Q£fNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES 't)d'No
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance DYES !)a' NO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES il NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES kJ NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270106
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET30F6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallm~act Computer Support and Software DYES t&fNO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES ~NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES lxrNo
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Ste!lite} into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve anv procurement activities?
PROGRAMS AND COMPONENTS Potentiallm~act ASME Containment In-service Inspection (IWE /IWL) Program DYES 'tg NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES ~NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC002701 07
d** NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F 6 PROGRAMS AND COMPONENTS {CONTINUED} Potential lmgact ASME In-service Inspection (lSI) Program DYES D":§'NO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. {ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES prJ No
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES ~NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES l8f NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES IE' NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES J8rNO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES 1&1NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES !XfNO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC002701 08
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 50F 6 PROGRAMS AND COMPONENTS (CONTINUED) Potentiattmeact Flow Accelerated Corrosion (FAC} Program DYES IX) NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAG Program.?
Heat Exchanger Program DYES rK! NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanaer prooram?
Predictive Maintenance Program DYES li1 NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitorinQ?
Microbiological Induced Corrosion (MIC} Program Impact DYES fBjNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV} Program DYES llf NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES Ql;J' NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program DYES ~NO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EO) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES I]TNO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES f81 NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or ruoture disc?
RPV Internals Program DYES 1'!:f NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270109
~Entergy NUCLEAR MANAGEMENT MANUAl QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 101 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET60F6 PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmeact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process. such as welding, brazing or soldering?
Safety Program .YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc .* for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation. etc.?
Training Program .YES ONO
- Does the. proposed activity involve existing training requirements or create the need for new training?
Simulator Impact .YES 0NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES ixJ NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
IDetailed Impact Screening (Attachment 9.4) Attached? DYES btfNo I IPEC0027011 0
ENTERGY Conceptual Design
~ ~;~?.~~~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: PARTIAL SITE PLAN OF AREAS AFFECTED
- 1. Figure 2: UPGRADE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 23 CHRG AND 23 CCW PUMP
- 2. Figure 3: UPGRADE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 23 SW AND 24 SW PUMP IPEC00270111
'"U m () 0 0 N ""'-J 0 N ENTERGY Conceptual Design
)
~ ~:~~~?~~2!.:,; Indian Point Nuclear Station Unit 2 Package SAMA IP2-065 Rev. 0 CONTAINMENT !3LDG.
1-J: UNIT N0.2 zl:i;:
- io a..z UNIT N0.2 INTAKE STRUCTURE UNIT N0.2 f--~------------------------,
TURBINE PRIMARY AUXILIARY BLDG. '
/ED\ /ED\
~~
12RW3 CONTROL BLD~l UNIT N0.1 SCREENWELL UNIT N0.1 HOUSE TURBINE SUPERHEATER BLDG. (TSC) J FIGURE 1 PARTIAL SITE PLAN OF AREAS AFFECTED (NOT TO SCALE) 0 TRANSFER SWITCH
-u m () 0 0 I'V 0 w ENTERGY Conceptual Design
~ ~~~.~;,;~~~2!.:": Indian Point Nuclear Station Unit 2 Package SAMA IP2-065 Rev. 0 CONTBOL Bl.OQ. PB!MARY AUXILIARY BLDG.
CONTROL POWER I
- TRANSFER - TRANSFER SWITCH SWITCH
- EDC4 '-----
EDF9 23 CHRG PUMP 23 CCW PUMP I err cr:r CONTROL ROOM PUMP TRANSFER PUMP TRANSFER I 123 CHRG PUMP UNIT NO. 2 l]L cr:r I I EL. 53'-0" c) EL. 80'-o"c
)
1M UNIT SUB. 12FD3 2B EL. 33'-o"
~
UNIT 1 UNIT 2 SUPERHEATER BLDG. 480 VAC SWITCHGEAR ( El 68'-0"r J ) FIGURE 2 UPGRADE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 23 CHRG AND 23 CCW PUMP (NOT TO SCALE)
"'U m () 0 0 I'V 0 .j:::o.. ENTERGY Conceptual Design
)
~ ;,;;,,~,~~:~2:,:~ Indian Point Nuclear Station Unit 2 Package SAMA IP2-065 Rev. 0 I
SERVICE WATER CONTROL BLDG. TRANSFER CONTROL POWER SWITCH EDG4 - 24 sw I PUMP I I 23 SW PUMP 24 SW PUMP PUMP TRANSFER PUMP cr:r TRANSFER CONTROL ROOM TRANSFER UNIT NO. 2 SWITCH cr:r cr:r CEr EDG3 I 23 sw I I PUMP II I I EL. 53'-0" EL. 15'-0" INDIAN POINT N0.2 INTAKE STRUCTURE 1M UNIT 2 UNIT 480 VAC SWITCHGEAR SUB. 12RW3 3M EL. 26'-0" INDIAN POINT NO.1 SCREENWELL HOUSE ROOF
)
)
FIGURE 3 UPGRADE ALTERNATE SAFE SHUTDOWN SYSTEM FOR 23 SW AND 24 SW PUMP (NOT TO SCALE)
ENTERGY Conceptual Design
~ ~~"~,~~~~2~,~.: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. ASCO Series 386 Non-Automatic Power Transfer Switches or Equivalent IPEC00270115
II Power Switching & Controls for Business-Critical Continuity ASCO SERIES 300 Power Transfer Switches EMERSON "*'i' Net work Power IPEC00270116
ASCO ~ SERIES 386 Non-Automatic Power Transfer Switches User-Initiated Control ASCO 386 non-automatic transfer switches are generally used in applications where operating personnel are available and the load is not an emergency type requiring automatic transfer of power. The power-switching mechanism and controller is the same hardware used on the highly reliable ASCO SERIES300 transfer switches. ASCO 386s are furnished as standard with a momentary-type selector switch to initiate transfer andre-transfer. They can also be arranged for remote control via ASCO's connectivity products. Electrical Features:
- Listed under UL 1008, CSA certified:
- UL listed through 480 VAC.
- CSA certified through 600 VAC.
- Door-mounted selector switch for local, manually initiated electrical control.
- Sizes from 30 through 3000 amps.
Available to 600 VAC, 50 or 60Hz.
- Rated for all classes of load transfer.
100%tungsten load ratings through 400 amps.
- Designed for emergency and standby applications.
- Same withstand and close-on rating as SERIES 300.
Standard Selectable Control Features:
- In phase monitor to transfer motor loads between live sources, without any intentional off time, to prevent inrush currents from exceeding normal starting levels.
- Selective load disconnect, double-th row contact to operate at an adjustable 0 to 20 second time delay prior to t rans-fer and reset 0 to 20 seconds after transfer.
- High/Low nominal voltage setting. Allows user to adjust fo r sou rce low reduced voltage conditions in remote areas.
- 60Hz or 50 Hz selectable switch.
- Single/Three-phase selectable switch.
Control Features: Fig. 14: ASCO 386 400 Amp
- Switch position indicating signal lights.
Type 1 Enclosure w/Optional
- One auxiliary contact closed when transfer switch is Accessories 9C, 9D Source connected to no rmal and one closed on emergency, Ava ilability Lights standard feature 14A/14B.
Optional Accessories:
- 6Q Key-operated, momentary source selector switch furnished instead of the standard selector switch.
ASCI"' SERIES 386 Power Transf&T SWitch r.~ .!:..r~r.~
- 9C, 9D Source availability lights to provide operator with a local indication of power source availability.
- Accessory 14AA/ 14BA auxiliary contacts to indicate position of main contacts. Two (2) for normal position and two (2) for emergency position (one set is standard).
- 72A Serial module (5 11 0) is used to allow local or re mote Fig. 15: Control and Display Panel communications with ASCO POWERQUEST connectivity products.
- Special Enclosures (Specify by appropriate code in catalog number):
Type 3R: Rain-tight Type 4: Weatherproof Type 12: Oil Tight
- 72E Connectivity Module 5150 is used to bring severa l different serial devices that communicate at different baud rates and with different protocols to a common Ethernet media.
9 IPEC00270117
ENTERGY Conceptual Design
~Tech nolo~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -065 :Rev. 0 i
Attachment 4 Cost Estimate IPEC00270118
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTMIATE LEVEL* EC #: SAMA IP2-065 PROJECT TITLE: RCP Cooling System Safe Shutdown 0CAPITAL Oo&M ESTIMATOR: RCMT JOB LOCATION: Auxiliary, Intake & Turbine Buildings PROJECT CODE: TBD F...a.;;....;;.;.;...........,.........._ ___. OourAGE 0NoN-OUTAGE ORIGINATOR: ORIG. DATE: 11129/10 ESTIMATE TOTAL $1,789,771 REVISION 10-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-054 in accordance with Entergy design engineering practices. Component Cooling Water 23 Pump, Charging Pump 23, and Service Water Pumps 23 and 24 are system pumps powered from the 480VAC Vital Switchgear Room (switchgear room) at Elevation 15' -o*. These pumps can provide cooling water for Reactor Cooling Pump (RCP) seal cooling when needed. When necessary, this action needs to be provided in a timely manner. For SAMA IP2-065, resolution is required to provide the ability to switch these pumps to an existing alternative power source more quickly than is possible using the current available method. The modifications described above are in the event of flooding in the switchgear room that prevents the normal 480VAC power from being available. Prepared by: Approved by: Date: IPEC00270119
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE ln~n Poi'tfluclear Power Station tl:STMIATE LEVEL* ~ Etf'W: tm\ IP2-065 ConceptuaO ou ~JtlJom:J[1fiTLE: RCP Cooling System Safe Shutdown ESTIMATOR: RCMT Preliminary JOB LOCATION: Auxiliary, Intake & Turbine Buildings PROJECT CODE: TBD
- Definitive ORIGINATOR: ORIG. DATE: 11129110 Item DescriPtion
- 1. This estimate assumes that this work will be completed during 2014.
- 2. This estimate assumes that this work will be completed in a single 10 hours per shift, four days per week non-outage schedule.
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold points ..
- 4. This estimate assumes that all installation work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate assumes that all high voltage disconnections and reconnections will be performed by station maintenance personnel.
- 6. This estimate assumes that all conduit will be erected and that all power and control cables will be pulled before disconnectinQ pump power.
- 7. This estimate assumes that core boring will be required in the Auxiliary Building and the Control Room Area (Potential 4 Core Bores).
- 8. This estimate provides for continuous fire watch during fire seal breeching
- 9. Since the added control panels are outside the control room, no changes to the simulator were included in this estimate
- 10. This estimate does not include funding for unreviewed safety Questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost Estimate 11. Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide for 12. anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative and 13. progresses as follows: A. Outside fence boundary- 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00270120
~
Page 1 of 3 10/4/2012 3:10PM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET IP2-065.xls 0 0 CAPITAL Do&M EC #: SAMA IP2-065 PROJECT TITLE RCP Cooling System Safe Shutdown TAKEOFF JOB LOCATION Auxiliary, Intake & Turbine Buildings PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS DouTAGE 0 NON-OUTAGE ORIGINATOR ORIG. DATE 11129110 I MANHOURS !'MATERIAL$ MATERIAL LABOR I SUB* TEM DESCRIPTION QTY UOM I CFT I NO. UNIT FCTR TOTALI $1MH I PERUNIT DOLLARS DOLLARS I CONTRACT TOTAL$ _0 D .Q_
- ESTIMATE LEVEL* ESTIMATE
SUMMARY
Conceptual MANHOURS DOLLARS - Preliminary EO/ ENGINEERING - Definitive 01 STUDY, DESIGN, & CLOSEOUT 480 $ 48,000 02 DESIGN ENGR CONST SUPPORT 160 $ 16,000 General Notes: 03 MODS ENGR EOI SUPPORT $ 04 SYS ENGRI S-U ENGR 280 $ 28,000 05 PROJECT MANAGEMENT 640 $ 76,800 06 WORK MANAGEMENT $ 07 ENGINEERING DCP ACCEPTANCE REVIEW 120 $ 12,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 1,240 $ 148,800 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 170 $ 17,000 11 FIELD ENGRS I PLANNERS 150 $ 18,000 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 60,712 13 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 2,467 $ 255,011 15 LOST TIME 247 $ 32,626 16 SWEC DISTRIBS $ 71,367 PLANT CRAFT LABOR 17 MECH MAINT. $ 18 ELECT MAINT 16 $ 1,600 19 I&C $ 20 CSG $ MISC EO/ SUPPORT 21 QUALITY CONTROL 130 $ 13,000 22 TRAINING 96 $ 11,520 23 CHEMISTRY $ 24 OPS I OPS SUPPORT 320 $ 38,400 25 HPIRP 240 $ 19,094 MISC CONTRACT SUPPORT 26 QUALITY CONTROL 140 $ 11,200 27 NDE $ 28 HPIRP $ 29 RADWASTE $ 30 NURSE $ 31 ELEVATOR CONTRACTOR $ 32 WASTE MANAGEMENT $ 33 HOUSEKEEPING $ 34 EQUIPMENT RENTAL CONTRACTOR $ 35 VENDOR STOCKING $ 36 DECONTAMINATION CONTACTOR $ 37 RBC'S $ 38 SECURITY- Wackenhut $ 39 FIRE WATCH (Rover) $ 40 SAFETY 50 $ 3,400 CONTINGENCY 41 CONTINGENCY $ 264,759 ESTIMATE SUBTOTAL 6,946 $1,147,289 SITE ENCUMBRANCE PREMIUM (20%) $ 229,458 LOADERS (30%) $ 413,024 ESTIMATE TOTAL $1,789,771 Preliminary to Tie-ins
- 1. Gather and stage tools and materials 1 LT EL 4 1000 1.00 40 $111.84 $ $ 4,474 $ 4,474
- 2. Stage, erect and modify scaffolding 1 LT CP 2 6000 1.00 120 $ 96.00 $ 11,520 $ 11,520
- 3. Core drill as required to route new conduits 4 LT EL 2 20.00 1.00 160 $111.84 $ $ 17,894 $ 17,894 Procure & erect conduit supports from 23 CCW, 23
- 4. 250 LF EL 2 0.18 1.00 90 $111.84 $ 2.50 $ 625 $ 10,066 $ 10,691 CHRG, and 23 & 24 SW pumps Procure & erect conduit from 23 CCW, 23 CHRG, and
- 5. 180 23 & 24 SW pumps 250 LF EL 4 0.18 1.00 $111.84 $ 2.50 $ 625 $ 20,131 $ 20,756
- 6. Procure and install Hoffman boxes for switches 4 EA EL 2 1000 1.00 80 $111.84 $ 3,000.00 $ 12,000 $ 8,947 $ 20,947 Procure and install new control switches for 23 CCW,
- 7. 64 23 CHRG, and 23 & 24 SW pumps 8 EA EL 2 4.00 1.00 $111.84 $ 500.00 $ 4,000 $ 7,158 $ 11,158 Determinate & remove existing manual switches 23
- 8. 160 CCW, 23 CHRG, and 23 & 24 SW pumps 4 EA EL 2 20.00 1.00 $111.84 $ $ 17,894 $ 17,894
- 9. Procure and install non-automatic transfer switches at 4 EA EL 2 24.00 1.00 192 $111.84 $ 7,500.00 $ 30,000 $ 21,473 $ 51,473 23 CCW, 23 CHRG, and 23 & 24 SW pumps
- 10. Procure and pull 41c control cable 1,500 LF EL 2 0.04 1.00 120 $111.84 $ 1.25 $ 1,875 $ 13,421 $ 15,296
- 11. Procure and pull 21c control cable 1,000 LF EL 2 0.020 1.00 40 $111.84 $ 1.15 $ 1,150 $ 4,474 $ 5,624 IPEC00270121
Page 4 of 5 7126/2012 9:02AM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 17:1 0 PROJECT TITLE: RCP Cooling System Safe Shutdown 0 CAPITAL DOOM EC #: SAMA IP2-065 IP2-065 {Rev 7-17-12) xis TAKEOFF: JOB LOCATION: Auxiliary, Intake & Turbine Buildings PROJECT CODE: TBD ESTIMATOR RCMT EST. STATUS: OouTAGE 0 NON-OuTAGE OR IGINATOR: ORIG. DATE: 11129110 MAN HOURS 'MATERIAL$ MATERIAL LABOR SUB-
~TEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
Tie-Ins lor New Switches . $ . Connect power feed sand controls to new non-1' 160 automatic transfer switches 1 LT PL 2 80.00 1.00 $ 60.00 $ $ 9,600 $ 9,600 Terminate cables in CR Area and Substations 12FD3
- 2. 160 and 12RW3 2 EA PL 2 40.00 1.00 s 60.00 $ 3,500.00 $ 7,000 $ 9,600 s 16,600
- 3. Test pump switching for proper operation 1 LT PL 2 40.00 100 80 $ 60.00 $ $ 4,800 $ 4,800
- 4. Scaffolding Dismantle 1 LT CP 2 40.00 1.00 80 s 96.00 $ $ 7,680 $ 7,680
- 5. Cleanup and restore work areas 1 LT EL 3 40.00 1.00 120 $123.32 $ $ 14,798 $ 14,798 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT
- 2. PAINTING & TOUCH-UP PT FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 30 LT FW 3 24.00 1.00 720 $ 50.53 $ $ 36,382 $ 36,382
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT
~
SUBTOTAL CRAFT & SU 2,156 $ 57, $ $ 277,587 172~
- 1. CONSTRUCTION SUPPORT (8% OF LABOR$) 1 LT $ 17,577 $ 17,577 SUBTOTAL : 2,328 $ 57,275 $237.889 $ . $ 295,164
- OUTAGE RELATED COSTS *
- 1. OUTAGE WALKDOWN ALLOWANCE 1 LT PF 21 $106.40 $ 2,234 $ 2,234 2 WORK PACKAGE REVIEW 1 LT PF 37 $106.40 $ 3,937 $ 3,937
- 3. OUTAGE TOOL ROOM ATTENDANTS (-3.5%) 1 LT LB 81 $ 76.46 $ 6.193 $ 6,193
- 4. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 23,789 $ 23,789
- 5. CRAFT IN PROCESSING {20%) $ 47,578 $ 47,578
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 4,758 $ 4,758
~OTAL 7.
I I 2,467 $ 57,275 $326,378 $ PLANT SCOPE
- 1. MECH MAINTENANCE PL PL m
SUBTOTAL MECH MAINl . I - $ - $ - $ . $
- 1. ELECT MAINTENANCE 2 8.00 1.00 16 $100.00 $ - $ 1,600 $ 1,600 T. MAINT. I I 16 $ - $ 1,600 I$
- 1. I&C PL I PL SUBTCTAL I&C MAINT. $ - $ - $ - $ -
- 1. CSG PL PL I SUBTOTAL CSG MAINT. $ $ - $ - $
SUBTOTAL PLANT 16 $ $ 1,600 $ . $ 1,600 i
=
- 2.483 $ 57,275 $327,978 $ - $ 385,253 IMPLEMENTATION SUPPORT EO!
- 1. FIS I MODS ENGINEERING (EOI) 1 LT NM 2 DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 160.00 1.00 160 $100.00 $ 16,000 $ 16,000 3 SYSTEMS ENGINEERING* MECHANICAL 1 LT NM
- 4. SYSTEMS ENGINEERING- ELECTRICAL 1 LT NM 1 160.00 1.00 160 $100.00 $ 16,000 $ 16,000
- 5. SYSTEMS EINGINEERING- INSTR & CONTROL 1 LT NM 1 120.00 1.00 120 $100.00 $ 12,000 $ 12,000 6 SYSTEMS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 7 PROJECT MANAGEMENT 1 LT NM 1 640.00 1.00 640 $120.00 ! $ 76,800 $ 76,800
- 8. TRAINING (OPS STAFF) 12 LT NM 1 8.00 1.00 96 $120.00 $ 11,520 $ 11,520
- 9. QA I QC VERIFICATION 1 LT NM 1 130.00 1.00 130 $100.00 $ 13,000 $ 13,000
- 10. WORK MANAGEMENT 1 LT NM $ -
- 11. HP I RPI ALARA 3 LT NM 1 8000 1 00 240 $ 79.56 $ 19,094 $ 19,094
- 12. CHEMISTRY 1 LT NM
- 13. OPS I OPS PROCEDURE SUPPORT & DEVELOPM 1 LT NM 1 320.00 1,00 320 $120.00 $ 38,400 $ 38,400 14 TRAVEL & LIVING EXPENSES 1 LT $ $ .
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per Diem) LT NM 2 MODS PLANNING & SCH.- SWEC (Inc! Per Diem) 1 LT NM 1 170.00 1.00 170 $100.00 $ 17,000 $ 17,000 3 FIELD ENGRSIPLAN- SWEC (lncl Per Diem) 1 LT NM 1 150.00 1.00 150 $120.00 $ 18,000 $ 18,000 4 QA I QC VERIFICATION 1 LT NM 1 140.00 1.00 140 $ 80.00 $ 11,200 $ 11,200 IPEC00270122
~
Page 5 of 5 7/26/2012 902 AM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET IP2-D65 (Rev 7-17-12) xis 0 0 CAPITAL OO&M EC #: SAMA IP2-065
!PROJECT TITLE: RCP Cooling System Safe Shutdown TAKEOFF:
JOB LOCATION: Auxiliary, Intake & Turbine Buildings PROJECT CODE: TBD ESTIMATOR RCMT EST. STATUS: 0 OUTAGE 0 NON-ouTAGE ORIGINATOR: ORIG. DATE: 11/29/10 MANHOURS 'MATERIAL$ MATERIAL LABOR SUB-TEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 5. NDE 1 LT NM
- 6. HP I RP 1 LT NM
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM -
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM 13 VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC -
- 17. FIREWATCH (Rover) 1 LT NM - $
- 18. SAFETY(2%) 1 LT NM 50 $ 68.00 $ 3,400 $ 3,400
- 19. LOST TIME (10%) 1 LT 247 $132.09 $ 32 626 $ 32,626 SUBTOTAL CRAFT/NON-MANUAL 5,106 $ 57,275 $613,018 $ . $ 670,293 1 FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 3,437 $ 3,437 SUBTOTAL INSTALLATION COST 5,106 $ 60,712 $613,018 $ . $ 673,730
- 1. DESIGN ENGINEERING* MECHANICAL 1 LT NM
- 2. DESIGN ENGINEERING* ELECTRICAL 1 LT NM 1 400.00 1.00 400 $100.00 $ 40,000 $ 40,000
- 3. DESIGN ENGINEERING* INSTR & CONTROL 1 LT NM
- 4. DESIGN ENGINEERING* CIVIL/STRUCTURAL 1 LT NM 1 80.00 1.00 80 $100.00 $ 8,000 $ 8,000
- 5. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,240.00 1.00 1,240 $120.00 $ 148,800 $ 148,800
- 6. ENGINEERING DCP ACCEPTANCE REVIEW 1 LT NM 1 120.00 1.00 120 $100.00 $ 12,000 $ 12,000 SUBTOTAL DESIGN COST 1,840 $ 48,000 $ 160,800 $ 208,800 SUBTOTAL INSTALLATION & DESIGN COST 6,946 $661,018 $ 160,800 $ 882,530
- 1. CONTINGENCY ( 30%) $ 264,759 ESTIMATE SUBTOTAL $ 1,147,289 IPEC00270123
ENTERGY Conceptual Design
~ ~;,:~~,?.~~'~'~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 2 CONCEPTUAL DESIGN PACKAGE For SAMA IP2-GAG Provide a device for manually closing a Main Steam Safety Valve (MSSV) that fails to reseat closed following a Steam Generator Tube Rupture by/} tJ
.P<*::t Prepared Approved by:
/~~
' 1 f
**~~* J Date:
{ q_ 20-2o1Z Date: .*'
/.
Pagel of5 IPEC00270124
ENTERGY Conceptual Design
~ ~;,~"~'~:::~2~.~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 ISSUE 3
2.0 BACKGROUND
3 3.0 EXISTING CONDITIONS 4 4.0 DESIGN CONSIDERATIONS 4 5.0 CONFIRMATION OF DESIGN 4 6.0 RECOMMENDED SOLUTION 5 7.0 PRELIMINARY MATERIAL LIST 5 Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of5 IPEC00270125
ENTERGY Conceptual Design
~ ;;~,~?,~2~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP2-GAG:
Provide a device for manually closing a Main Steam Safety Valve (MSSV) that fails to reseat closed following a Steam Generator Tube Rupture
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-GAG in accordance with Entergy design engineering practices. For SAMA IP2-GAG, resolution is required for returning a "stuck-open" (failed to reseat closed) MSSV to its normally closed position after its operation resulting from a steam generator tube rupture. This package will provide for a "valve gagging" device to be temporarily installed on the valve to provide manual assistance if needed when a MSSV fails to reseat closed upon reduction of pressure. The design considerations that follow will address the application's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list will be the informal basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. Page3of5 IPEC00270126
ENTERGY Conceptual Design
~ ~~~.~?,?.~~~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 3.0 EXISTING CONDITIONS This is a new application for use of the valve gag at IP2. Currently, the purpose of the valve gag for MSSVs at IP2 is only in conjunction with Procedure 2-PT-R006, Main Steam Safety Valve Setpoint Determination.
4.0 DESIGN CONSIDERATIONS The MSSVs at IP2 are Crosby HC-65W ISOFLEX Safety Valves. Crosby Engineering Doc #IS-V3147A, page 9, provides instruction for installing a valve gag to be used for hydrostatic testing purposes. It cautions not to overload the valve spindle or damage to the valve may result. It provides instructions for this device to be installed only when testing at pressures no greater than 10 percent above the nameplate (lifting) pressure. The original purpose for this device at IP2 during testing is as the name infers; to "gag the valve", meaning to keep it in a passive closed status. In the proposed resolution to the issue (MSSV fails to reseat closed after operation) the valve gag will be installed temporarily and used for the purpose of closing the valve. Prior to installing this device, accessibility for installation requires that certain parts be removed from the valve assembly. These parts are the lever (27), the forked lever (30), the top cap (25), and the spindle nut (23) shown in Attachment 2, Figure 1. The valve gag, and the tools needed to remove the parts indicated, along with the tool required to install the valve gag, need to be made available on the Turbine Floor elevation and located in an area close to the vicinity of the MSSVs. 5.0 CONFIRMATION OF DESIGN The device will be used to close a valve that fails to reseat when the pressure has dropped below the lifting pressure. The gagging application will be utilized within the same pressure limits specified in Crosby's Manual (pressure at the valve after release will be no greater than 10 percent above the nameplate (lifting) pressure). To further ensure use of the gagging device is adequate, confirmation will be provided by the valve manufacturer or, if needed, a finite element analysis for this specific application will be performed. This will confirm that use of the gag is appropriate and adequate for this purpose and also determine its operating limitations. Page4of5 IPEC00270127
ENTERGY Conceptual Design
~ ~~2.~~,~.~~.:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 By adhering to the valve gag's specific use limitations, reseating the valve closed by this method will be similar to the current use of the gag for the valve-test installation (Attachment 2, Figure 2).
6.0 RECOMMENDED SOLUTION
- 1. Provide a cabinet (in the vicinity of the MSSVs) to be used for storage of the valve gag and the associated tools needed (Attachment 2, Figure 3)
- 2. Provide training for installation of this device
- 3. Prepare the necessary installation procedure(s) for installing the gag and identify the circumstances other than testing for when this device is to be used 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Wall mounted cabinet approximately 30" x 30" x 10" deep 1
- 2. Hilti mounting bolts 4
- 3. Valve gag for style HC ISOFLEX safety valve 1
- 4. Socket wrench and socket for installing valve gag 1
- 5. Lubricant for valve gag threads and end point 1
- 6. Tools required for removal of valve parts 1 set (includes pliers, hammer, screwdrivers, and wrenches)
- 7. Torque wrench set 1
- 8. Tote-bag for valve gag and required tools 1 Page 5 of5 IPEC00270128
ENTERGY Conceptual Design
~ ;:;,~,?,~~~2!~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG IRe. "
Attachment 1 Entergy Impact Screening Summary IPEC00270129
. _.,_ QUALITY RELATED EN-DC-115 REV.11
~Entergy NUCLEAR MANAGEMENT I
MANUAL REFERENCE USE PAGE 96 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET1 OF 6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. 5 A f Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potential lmeact Civil/ Structural Design Engineering DYES ~NO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering DYES tRf NO
" Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering DYES (KJ'No
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES f81No
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering II YES NO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis DYES ~NO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES t!t1 NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270130
**b NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 97 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS Potentiallmr;tact ASME Section Ill Specifications DYES Ill NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program DYES (81 NO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) DYES (XI NO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES IKf NO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES r2!f NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program DYES ~NO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES [gJ NO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97/ PAM (Post Accident Monitoring) DYES ~NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance DYES ~NO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance DYES imNo
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES iXt NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270131
~Entergy NUClEAR MANAGEMENT MANUAl QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET30F6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmeact Computer Support and Software DYES IXf NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES IXJ NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES IXJ NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce {or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations DYES !XI NO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) DYES ~NO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory} DYES 18fNO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering DYES 181 NO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS PotentiallmJ;!act ASME Containment In-service Inspection (IWE I IWL) Program DYES jgf NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES ill No
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270132
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmgact ASME In-service Inspection (lSI) Program DYES 00No
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES ~NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES tgf NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program DYES CiJ NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES Qs) NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES li3J NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES 110 NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES I)C NO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00270133
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Flow Accelerated Corrosion (FAC) Program DYES ~NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES tlfNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES IE NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitorinQ?
Microbiological Induced Corrosion (MIC) Program Impact DYES ~NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES 18No
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES l8f NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program DYES ~NO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PTCurves DYES l8f NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials}?
Relief Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270134
..'!. NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallm(2act Welding Program DYES !XfNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES DNO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc .* for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES rxtNo
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES b1:j NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES tz(No IPEC00270135
ENTERGY Conceptual Design
~ ~~:~~?~~:: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Style HC ISOFLEX Safety Valve
- 2. Figure 2: Gag installed on valve bonnet
- 3. Figure 3: Turbine Bldg Floor Plan at El. 53'-0"- storage cabinet location IPEC00270136
ENTERGY Conceptual Design
~ ~;,~~,~},~E~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 PARTS LIST Part Part Name Spare Parts*
1A Body 1B Nozzle 3 Nozzle Ring 3 4 Nozzle Ring Set Screw 5 Disc Insert 6 Disc Holder 2 7 Disc Holder Retaining Nut 8 Disc Holder Retaining Cotter 1 9 Guide 3 10 Guide Ring 3 11 Guide Ring Set Screw 12A Spindle Point 3 12B Spindle Rod 3 12C Spindle Rod Pin 3 13 Bonnet 14 Bonnet Stud 15 Bonnet Stud Nut 16 Spring 3 17 Bottom Spring Washer 3 18A Top Spring Washer 3 18B Bearing Pin 3 18C Locking Pin 3 19 Bearing Adapter 20 Bearing'
- 21A Adjusting Bolt 21B Adjuslhig Bolt. Beadng .***
22 Adjusting Bolt Nut 23 Spindle Nul 24 Spindle Nut Cotter 25 Cap 26 Cap Set Screw 27 Lever 28 Lever Pin 29 Lever Pin Cotter 30 Forked Lever 31 . Forked Leiier Pin. 32 Forked Lever Pin Cotter 34 Tes{Ciahip
- 36 Test Rod 37 seal. and Wire
- 38 Protective Hood 39 main Plu9 40 Hydro Test Plug Assembly 41 Nam~plaie * * **** **
42 Drive Screw 43** Cooling Spool 44 .. Cooling Spool Stud 45" cooling Spoof stud Nut .
*Spare Parts Designation (See Notes 1, 2, 3 on Page 4)
- For Crosby Style HCA ISOFLEX only Figure 1 STYLE HC ISOFLEX SAFETY VALVE IPEC00270137
ENTERGY Conceptual Design
~ ~~~,~~.~~~~ Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 Figure 2 GAG INSTALLED ON VALVE BONNET IPEC00270138
ENTERGY Conceptual Design
~ :~;"~~'~2"i':: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System -As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix IPEC00270139
ENTERGY Conceptual Design
~ ~~~"~'~,~~~:,~: Indian Point Nuclear Station Unit 2 Package SAMA IP2 -GAG Rev. 0 Attachment 4 Cost Estimate IPEC00270140
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
- ESTIMATE LEVEL* EC #: SAMA IP2
- GAG PROJECT TITLE: Unit 2 MSSV Gag OcAPrr 0o&I ESTIMATOR: RCMT JOB LOCATION: IP2 Turbine Building PROJECT CODE: TBD Definitive 0 OUTA* 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 7/17112 ESTIMATE TOTAL $458,617 REVISION 10-4 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP2-GAG in accordance with Entergy design engineering practices. For SAMA IP2-GAG, resolution is required for returning a "stuck-open" (failed to reseal closed) MSSV to its normally closed position after its operation resulting from a steam generator tube rupture. This estimate provides for the procurement of an MSSV Gag, gagging tools, lubricant and tote bag, procurement and installation of a wall hung storage cabinet, design engineering for development of the engineering change for the cabinet installations, costs for development of new procedures and/or revision of existing procedures and the cost of training station maintenance personnel to the new or existing procedures. Prepared by: Date: IPEC00270141
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station Ef!IMATE LEVEL
- EC #: SAMA IP2
- GAG
~ Conceptual PROJECT TITLE: Unit 2 MSSV Gag 0CAPITA ['Jo&M ESTIMATOR: RCMT Preliminary JOB LOCATION* IP2 Turbine Building PROJECT CODE: TBD Definitive 0 OUTAG ['JNON-OUT.A.GE ORIGINATOR: ORIG. DATE: 7/17112 Item Descriotion 1' This estimate assumes that this work will be completed during 2014
- 2. This estimate assumes that this work will be peliormed on a single 1o hours per shift, 4 days per week non-outage schedule.
- 3. This estimate assumes that mock-up training for gagging a failed MSSV will be provided to Station Maintenance personnel.
- 4. This estimate assumes that a mockup "failed" MSSV will be provided for training purposes.
- 5. This estimate assumes that all work will be peliormed by IP in-house Maintenance personneL
- 6. The estimates assumes training for 12 people 7 Th1s es!lmate does not mclude fund1n~ NRC submittals, but if reqUired the addi!lonal cost will be added This est1mate is based on the project's nd 1s classified Class 4 as defined per the AACE International Cost 8
~" Atl"hmoot3. "'"re~ 2) projected 2014 costs based on current 2012 craft billmg rates at Indian Pomt The projected costs provide for of 3% per year des a contmgency factor related to the complexity and location of the work reqUired The factor IS cumulative 10 and progresses as follows:
A. Outside fence boundary- 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00270142
Page 1 of 4 10/3/2012 5:06PM IP2-GAG Estimate.xls ~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-4 EC #: SAMA IP2 -GAG PROJECT TITLE Unit 2 MSSV Gag DouTAGE 0 NON-OUTAGE DcAPITAL 100&M TAKEOFF JOB LOCATION IP2 Turbine Building PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS ORIGINATOR ORIG. DATE 7/17112 MAN HOURS MAT'L $ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOMCF11 NO. UIR FCTR TOTAL $1MH I I UNIT I DOLLARS DOLLARS CONTRACT I TOTAL$
*ESTIMATE LEVEL* ESTIMATE
SUMMARY
-=- Conceptual ~ MANHOURS DOLLARS D Preliminary ENGINEERING o Definitive 01 02 STUDY, DESIGN, & CLOSEOUT DESIGN ENGR CONST SUPPORT 80 24 8,000 2,400 General Notes: 03 MODS ENGR SUPPORT $ 04 SYS ENGR/ S-U ENGR $ All work associated with preparation and training for 05 PROJECT MANAGEMENT 120 $ 14,400 installation of MSSV gags will be provided by I P Station 06 WELDING ENGR $ Mechanical Maintenance personnel. 07 CONTRACT FOR APPLICATION ANALYSIS $ 120,000 08 ENGR'G DCP ACCEPTANCE REVIEW 20 $ 2,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 320 $ 38,400 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 40 $ 4,000 11 OSG FIELD ENGRS I PLANNERS 20 $ 2,400 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 1,590 13 OTHER CONTRACTS $ PLANT CRAFT LABOR 14 IPEC CRAFT LABOR/WALKDOWN 180 $ 14,000 15 LOST TIME $ 16 DISTRIBUTABLE COSTS $ MISCELLANEOUS SUPPORT 17 QUALITY CONTROL 40 $ 4,000 18 NDE $ 19 OPS TRAINING 24 $ 2,880 20 OPS- PROCEDURES 60 $ 7,200 21 HP/RP $ MISC CONTRACT SUPPORT 22 QUALITY CONTROL 40 $ 3,200 23 NDE $ 24 HP/RP $ 25 RADWASTE $ 26 NURSE $ 27 ELEVATOR CONTRACTOR $ 28 WASTE MANAGEMENT $ 29 HOUSEKEEPING $ 30 EQUIPMENT RENTAL CONTRACTOR $ 31 VENDOR STOCKING $ 32 DECONTAMINATION CONTRACTOR $ 33 RBC'S $ 34 SECURITY $ 35 FIRE WATCH (Rover) $ 36 SAFETY 4 $ 272 37 LOST TIME 18 $ 1,400 CONTINGENCY 37 CONTINGENCY $ 67,843 ESTIMATE SUBTOTAL 990 $ 293,985 SITE ENCUMBRANCE PREMIUM (20%) $ 58,797 LOADERS (30%) $ 105,835 ESTIMATE TOTAL $ 458,617 Non-Outage Storage Preparation
- 1. Procure one 30" X 30" X 12" storage cabinets 1 EA PL 2 4.00 100 8 $ 60.00 $250.00 250 $ 480.00 $ 73000
- 2. Hang one 30" X 30" X 12" storage cabinets 1 EA PL 2 40.00 100 80 $ 60.00 $ 4,800.00 $ 4,800.00
- 3. Procure MSSV gag 1 EA PL 2 2.00 100 4 $ 60.00 $750.00 750 $ 240.00 $ 990.00
- 4. Procure gagging tools, lubricant & tote bags 1 LT PL 2 4.00 100 8 $ 60.00 $500.00 500 $ 480.00 $ 980.00 Non-Outage Training $ $
- 1. Gather and stage gag, tools and materials 1 LT PL 2 2.00 100 4 $ 100 00 $ 400.00 $ 400.00
- 2. Disassemble mock-up valve per procedure 1 LT PL 12 4.00 100 48 $ 100 00 $ 4,800.00 $ 4,800.00
- 3. Tag and store removed parts for restoration 1 LT PL 2 100 100 2 $ 100 00 $ 200.00 $ 200.00
- 4. Install and adjust gag per specification 1 LT PL 12 2.00 100 24 $ 100 00 $ 2,400.00 $ 2,400.00
- 5. Cleanup work area and return tools to storage 1 LT PL 2 100 100 2 $ 100 00 $ 200.00 $ 200.00 IPEC00270143
Page 4 of 5 7/2512012 11:33 AM IP2-GAG Estimate (Rev_?-17-121
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-4 EC #: SAMA IP2 -GAG PROJECT TITLE: Unit 2 MSSV Gag JOB LOCATION: IP2 Turbine Buiiding
~~:CAPITAL ROJECT CODE: TBD WOOM TAKEOFF:
ESTIMATOR: RCMT EST. STATUS: 00UTAGE 0NON-CXJTAGE RIGINATOR ORIG. DATE: 7117112 MANHOURS MArL$ MATERIAL LABOR SUB-ITEM DESCRIPTION i QTY,UOM CF NO. U!R FCTR TOTAL $1MH I UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 1. CONSTRUCTION SUPPORT (8% OF LABOR$) 1 LT $
SUBTOTAL 180 1,500 $ 14,00000 $ $ 15,500.00
- OUTAGE RELATED COSTS * '
- 1. OUTAGE WALKDOWN ALLOWANCE 1 LT s - $ - $ -
- 2. WORK PACKAGE REVIEW 1 LT $ - $ $
- 3. OUTAGE TOOL ROOM ATIENDANTS (-3.5%) 1 LT $ $ $ -
- 4. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ $
- 5. CRAFT IN PROCESSING (20%) $ $
- 6. HU11.1AN PERFORMANCE & ALARA TRAINING 1 LT $ $
- 7. ( 112 day training, or - 2%)
180 ~ 1:>,:>UU.UU PLANT SCOPE
- 1. MECH MAINTENANCE PL - $ $
I PL - $ - $
~~
- 1. ELECT MAINTENANCE PL $ - $
PL $ $ - c
- 1. I&C PL $ $
Pl $ $ -
- 1. CSG - $ $
- ~ - ~~ :j; -
SUBTOTAL PLANT 0 $ 0 SUBTOTAL CRAFT/PLANT 180 I 1,500 14000 $ - 15,500 IMPLEMENTATION SUPPORT
- 1. FIS I MODS ENGINEERING 1 LT NM - $ - $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 24.00 1.00 24 $ 100.00 $ 2,400.00 s 2,400.00
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 $ - $
- 4. SYSTEMS ENGINEERING - ELECTRICAL 1 LT NM - $ $
- 5. SYSTEMS EINGINEERING- INSTR & CONTROL 1 LT NM - $ $
- 6. SYSTEMS ENGINEERING- CIVIL STRUCTURAL 1 LT NM - $ $
- 7. PROJECT MANAGEMENT 1 LT NM 1 120.00 1.00 120 $ 120.00 $ 14,400.00 $ 14,400.00
- 8. WELDING ENGR (Program Engr) 1 LT NM - $ $
- 9. QA I QC VERIFICATION 1 LT NM 1 40.00 100 40 s 100.00 $ 4,000.00 $ 4,000.00
- 10. NDE 1 LT NM s - $
11. 12. HP I RP/ ALARA OPS TRAINING 12 1 LT LT NM 1 1 1.00 24 $ 120.00
$ 2,880.00
$ 2.880.00 NM 2.00
- 13. OPS- DEVELOP/REVISE PROCEDURES 1 LT NM 1 60.00 100 60 $ 120.00 s 7,200.00 $ 7,200.00 14 TRAVEL & LIVING EXPENSES 1 LT 15 LOST TIME (10%) 1 LT $ $ -
CONTRACTOR SUPPORT 1 FIS I MODS ENGINEERING- SWEC (lncl Per Diem) 1 LT NM - $ $
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000.00 $ 4,000.00 3 FIELD ENGRSIPLAN- SWEC 1 LT NM 1 20.00 1.00 20 $ 120.00 $ 2,400.00 $ 2,400.00
- 4. QA I QC VERIFICATION 1 LT NM 1 40.00 1,00 40 $ 80.00 $ 3,200.00 $ 3,200.00
- 5. NDE 1 LT NM $ $
- 6. HPIRP 1 LT NM - $ $
- 7. RADWASTE CONTRACTOR 1 LT NM 8, NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL SUPPLIER 1 LT NM -
- 13. VENDOR STOCKING 1 LT NM -
14. 15. DECONTAMINATION CONTRACTOR RBC's 1 LT NM - 1 LT NM
- 16. SECURITY 1 LT SEC -
- 17. FIREWATCH (Rover) 1 LT LB - $ $ - $ -
- 18. SAFETY(2%) 1 LT NM 4 $ 68.00 $ 272.00 $ 272.00
- 19. LOST TIME (10%) 1 LT 18 $ 7778 $ 1400.00 $ 1 400.00 I ~. 90 $ 90.00 I 570 1,590 $
IPEC00270144
Page 5 of 5 7/25/2012 11:33 AM IP2-GAG Eslimate (RevJ-17-12)
~
INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET
-4 EC #: SAMA IP2
- GAG PROJECT TITLE: Unit 2 MSSV Gag ~~CAPITAL l:cJO&M TAKEOFF:
JOB LOCATIOI\I: !P2 Turbine Builc!ing ROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: QOliTAGE (!]NON-OlJTAGE RIGINATOR: ORIG. DATE: 7/17112 MANHOURS ~L$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CF NO. U/R FCTR TOTAL UNIT DOLLARS DOLLARS CONTRACT TOTAL$ 1 DESIGN ENGINEERING MECHANICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000.00 $ 8,000.00
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM " s $
3 DESIGN ENGINEERING- INSTR: & CONTROL 1 LT NM $ $ -
- 4. DESIGN ENGINEERING - CIVIUSTRUCTURAL 1 LT NM $ - $
- 5. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 320.00 1.00 320 $ 120.00 $ 38,400 $ 38,400.00
- 6. CONTRACT FOR APPLICATION ANALYSIS 1 LT NM $ 120,000 $ 120,000.00 7 ENGR'G DCP ACCEPTANCE REVIEW 1 LT NM 1 20.00 100 20 $ 100.00 $ 2,000 $ 2.000.00 420 00 SUBTOTAL INSTALLATION & DESIGN COST I I $ 102,552.00 $ 120,000 s 226,142.00
- 1. CONTINGENCY ( 30%) $ 67,843.00 ESTIMATE SUBTOTAL 990 $ 293,985.00 IPEC00270145
ENTERGY Conceptual Design
~ ~~~"~~~~~2.:.~: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 3 CONCEPTUAL DESIGN PACKAGE For SAMA IP3-007 Install a Reactor Cavity Flooding System Prepared by~}_ , Approved by:
!Xt.,~~..x.
1
- ---~~
//
Date: '1~z.0,.20("Z Date: Page 1 of7 IPEC00270146
ENTERGY Conceptual Design
~ ~~~~~2~2!,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST- Mechanical
- 8. PRELIMINARY MATERIAL LIST- Electrical/Instrumentation Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of7 IPEC00270147
ENTERGY Conceptual Design
~ ~~~.~.?m~~2~,:,: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP3-007:
Install a Reactor Cavity Flooding System
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-007 in accordance with Entergy design engineering practices. For SAMA IP3-007, resolution is required to reduce potential containment damage as a result of concrete-core interaction from molten debris following core damage and vessel failure. This package will provide an installation using a standby pump and fire water to flood the reactor cavity in the event this emergent action is necessary. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. 3.0 EXISTING CONDITIONS IP3 does not contain a reactor cavity flooding system specifically designed to protect the containment structure from the impact of molten debris resulting from core damage and vessel failure. Page 3 of7 IPEC00270148
ENTERGY Conceptual Design
~ ~?~.~~,~~,:;: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 4.0 DESIGN CONSIDERATIONS A permanently installed and readily available core cavity flooding mechanism would serve to limit damage to the containment's integrity. There is a fire water supply header routed underground in an area near the Fuel Storage Building that can be utilized for this purpose. In addition, the Hudson River is a source for a backup water supply that is also available. The proposed design will provide an alternative connection so that this option can be utilized if needed.
5.0 CONFIRMATION OF DESIGN The existing fire water supply header near the Fuel Storage Building area can be accessed and connected to a pump for flooding the containment. Calculations will be performed to verify the proposed 1OOOGPM pump flow rate is adequate The new pump will be permanently installed with a suction connection from the underground fire water supply piping. Also, an additional connection will be provided on the suction line to allow for an alternate water source such as the Hudson River. The pump will be diesel-driven to further ensure availability in the event of station blackout. The pump and a small diesel fuel oil day tank (with supply capacity to operate 72 hours) will be installed in a new outdoor weather proof enclosure in the immediate area of the Fuel Storage Building. The discharge of the pump will be connected to piping routed to Penetration #Y-Y in the containment structure, an elevation suitable for flooding the reactor cavity. A permanent Containment Isolation Valve (CIV) will be installed at this penetration. In support of this new configuration, the appropriate analysis and Technical Specification/FSAR changes to make this addition will be provided. Heat tracing, if required for any outdoor piping, will need to be provided. Page 4 of7 IPEC00270149
ENTERGY Conceptual Design
~ :~~.~~,~~~2~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 6.0 RECOMMENDED SOLUTION
- 1. Diesel-Driven Pump Outdoors in the area of the Fuel Storage Building Area provide for the installation of the diesel-driven backup pump.
- At the southeast corner, install a concrete pad for mounting the pump and its weather proof enclosure.
- Mount and permanently install the pump.
- Install the weatherproof enclosure.
- Excavate and modify the fire water line with a tie-in of required valves and new pipe routed to the pump's suction connection.
- Construct an oil spill containment berm around the weatherproof enclosure.
- Route and install conduit and cable and terminate from distribution cabinet to enclosure to provide electrical power required for heating, ventilation, lighting and heat tracing.
- 2. Piping Connection to Containment From the pump's discharge connection, install required valves and new pipe routed to the containment piping penetration Y-Y at Elevation 59' -6" (Figures 1 and 1A).
- 3. Install required pipe supports
- 4. Provide heat tracing and insulation for any outdoor pump supply header piping.
- 5. Provide procedures and training to operate, test, and perform maintenance on the components of the newly installed system.
Page 5 of7 IPEC00270150
ENTERGY Conceptual Design
~ ;~,~~~~~2~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 7.0 PRELIMINARY MATERIAL LIST- Mechanical Item Description Quantity
- 1. 8"- 150# Check Valve, Butt Weld, C.S., A216-WCB, 2 Mfr. VELAN or equal
- 2. 6"- 150# Check Valve, Butt Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 3. 8"- 150# Gate Valve, Butt Weld, C.S., A216-WCB, 2 Mfr. VELAN or equal
- 4. 6"- 150# Gate Valve, Butt Weld, C.S., A216-WCB, 3 Mfr. VELAN or equal
- 5. 1"- 3000# Globe Valve, Socket Weld, C.S., A216-WCB, 1 Mfr. VELAN or equal
- 6. Pump, 1OOOGPM, Self-Contained Diesel-Driven Skid with Industrial 1 Weatherproof Enclosure (detailed specification to follow)
- 7. Day Tank, diesel fuel oil storage (72 hour capacity) 1
- 8. 8" Schedule 40 Seamless pipe, Carbon Steel, A-106 Grade B 300 Feet
- 9. 6" Schedule 40 Seamless pipe, Carbon Steel, A-106 Grade B 50 Feet
- 10. 1" Schedule 40 Seamless pipe, Carbon Steel, A-1 06 Grade B 5 Feet
- 11. 3/4" Schedule 40 Seamless pipe, Carbon Steel, A-1 06 Grade B 10 Feet
- 12. 6" Schedule 40 B.W. Tee, A-106 Grade B 2
- 13. 6" 150# R. F. WN Flange, A-1 06 Grade B 3
- 14. 6" 150# R.F. Blind Flange, A-106 Grade B 2
- 15. 3/4"- 3000# Globe Valve, Socket Weld, C.S., A216-WCB, 4 Page 6 of7 IPEC00270151
ENTERGY Conceptual Design
~ ~~~~~~2~~,: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 8.0 PRELIMINARY MATERIAL LIST - Electrical/Instrumentation
- 1. 1"- Conduit and Supports 200 Feet
- 2. 120 VAC - 3/c Power Cable 200 Feet
- 3. 3/4" Stainless Steel tubing 40 Feet
- 4. Pressure Gauge 2
- 5. Differential Pressure Gauge 1 Page 7 of7 IPEC00270152
ENTERGY Conceptual Design
~ ~~~.~~.~2~.:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270153
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE Use Engineering Change Process EN-DC-115 I
PAGE 96 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET1 OF6 INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potentia! impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. SAHA ~o..J Engineering Change No.: '"I P:J.! .. Oo1 Rev. No.: 04ZSt Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallmgact Civil/ Structural Design Engineering .YES ONO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES DNO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers or settings chan~:~es or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES DNO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering .YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis DYES /il[No
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical ReQuirements Manual, or reQuire a full50.59 Evaluation?
FERC I NERC Impact DYES P!!No
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS*PL-158, ENS-DC-199, etc.)
IPEC00270154
"'='Entergy NUCLEAR MANAGEMENT ~
QUALITY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 97 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potentiallm~act ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) I] YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) II YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES )XNo
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program DYES t(No
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management BYES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES 'P(No
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallm~acl Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and reQuired training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and reQuired training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmcact Nuclear Fuel Design DYES j)(No
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program .YES DNO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270155
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET30F6 PROCESS OR PROgRAM IMPACT SCREENING CHECKLIST Potentiallmeact Computer Support and Software DYES )(No
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES ~NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES }(No
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENT§ Potentiallmeact ASME Containment In-service Inspection (IWE /IWL) Program .YES DNO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program Ill YES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270156
--=-Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 l
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS (CONTINUED} PotentlallmR!ct ASME In-service Inspection (lSI) Program Ill YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program II YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings}. .
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES ]8(No
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program .YES DNO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES Ji(No
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program aves DNO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker relay or electrical equipment?
IPEC00270157
*-=-Entergy NUCLEAR MANAGEMENT MANUAL QUAUTY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 100 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET50F6 PROGRAMS AND COMPONENTS (CONTINUED} Potential lm!;!act Flow Accelerated Corrosion {FAC) Program DYES )(No
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES )(No
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program .YES DNO
- Does the proposed activity impact or involve any aspect ofthe storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES }if No
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES Ji{'No
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thennal Perfonnance Program DYES ~NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s} maintains its qualification status?
PTCurves DYES 'll(No
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES )i(No
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270158
~Entergy NUCLEAR MANAGEMENT MANUAL QUAI..ITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 101 OF 150 REV.11 AnACHMENT9.3 IMPACT SCREENING
SUMMARY
SHEET60F6 PROGRAMS AND COMPONENTS {CONTINUED) Potential lmgact Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES I ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES ~NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES ONO
- Does the proposed activity result in a change to the Fire Protection Program (induding 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES !(No IPEC00270159
ENTERGY Conceptual Design
~ ~~~-~,~~2~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Reactor Cavity Flooding System- Flow Diagram
- 2. Figure 1A: Reactor Cavity Flooding System- Flow Diagram
- 3. Figure 2: Reactor Cavity Flooding System - Fire Water Tie-In
- 4. Figure 3: Reactor Cavity Flooding System - General Arrangement IPEC00270160
ENTERGY ' Conceptual Design
~:~~~~ tndian Point Nuclear Station UNIT 3 Package SAMA IP3-007 Rev. o INSIDE OUTSIDE MECH MECH PENET. PEN AREA AREA VENT
** '.i *
.:..*.* 1" CONT.
ON 1
* ..
- FIGURE 1A
....;** ~
6" EXISTING
........... I CONTAINMENT LEAK RATE TEST CONN.
PENET #Y-Y OPEN INSIDE OUTSIDE CONTAIN. CONTAIN. FIGURE . 1 REACTOR CAVITY FLOODING SYSTEM FLOW DIAGRAM IPEC00270161
ENTERGY Conceptual Design
~Technologies Indian Point Nuclear Station Package Plot~oiSmatl~
UNIT 3 IP3-007 Rev. o CONT. ON FIGURE 1. ENCLOSED SELF -CONTAINED PUMP SKID 8" 6" ALTERNATE
..-.---.....~o~l WATER I SOURCE CONN .
.2" 8" 4 6"
PUMP 1000 GPM
) 6"EXIST. F.P. )
( FIGURE 1A REACTOR CAVITY FLOODING SYSTEM FLOW DIAGRAM IPEC00270162
ENTERGY Conceptual Design
~~:~~~~2lj:: Indian Point Nuclear Station Unit 3 Package SAMA IP 3-007 Rev. o 1 oFo t f PIVJ:6 S"FP PiV~~
LP~N~-~7--2----~-4~----~~~~r-~ .. ----~tr--pty---4-"-.~~
- FUEL STORAGE PIV-15-22 r 4":!: - P~i-2o-s 21..=-6 suNfl s"FP~
B!JILDiNG fOR CO!'<'T.OF LINES INSIDE THE PIV-38 b" ( BUND FLANGE 4"FP L---....;;..-------.....;;..----- I F'..ANGE t ~
~ _.l~-- PN;7 ~
BLDG.SEE DWG. 9321-F-40913 SI*U 4"FP Fh".J HOUSE PAS. FOR CONT.OF LINES INSIDE T.-JE BLDG.SEE OWG. 9321-F-40913 Srl.1 f-osal"56e-+-_...;:....:...:.. t...-{:<l-*f.., 4"FP_____, OR CAVITY NG SYSTEM LZ ~ ELECTRICAL. POi=< CONT. OF LINES INS;DE THE BL::lG., --.../'~ FO~OF SEE DWG. NC. 9321-F-40913 SH. 1 (ZONE f4) W/cJ~B6 BOX LINES iNSIDE THE 8LDG.SEE DWG. 8"FP 9321 F 40913 SH.1 8"FP tl I J_ PIV-28-4
.t 4"FP 6"FP SERV'CE AQMIN!STRATION PIV--24-3 TURBINE GENERATOR BUILDING .fLU!LDING L 4 "F?
PIV-27-3 I
~6-4 4 FIGURE 2 REACTOR CAVITY FLOODING SYSTEM FIRE WATER TIE-IN DWN CHK'D 1-o-s.s-su-P*~-...,- - i INDIAN POINT NO. 3 NUCLEAR POWER PLANT DISCIPLINE ENG
- JfSClPUNE MGR. FLOW DIAGRAM OF PLANT PROJ APPROVAL FIRE PRCTECTION SYSTEM SHEET ~~0. 1 DATE SCALE f\JONE DWG NO REV 9.321-F-40903 3C SHEEr IPEC00270163
ENTERGY Conceptual Design tndian Point Nuclear Station Package 1-----1 Unit 3 SAMA IP3-007 Rev. 0 N * < r-164 RADIOACTI V[ MACHIN!:. SHOP BUILDING
<RAMS)
- 13. 8 KV SWlTCHYARD 69 I REACTOR CONTAINMENT
- **" ____ T _____ _
~
BUILDING <VC)
~~
59 5~ Q: .... [I] !:! 1-Q
~~
u:::l
~
FIGURE 3 REACTOR CAVITY FLOODING SYSTEM GENERAL ARRANGEMENT NOT NUCLEAR SAFETY RELATED CIWD
~DE=s=SUP~v----l INDIAN POINT NCI. 3 NUCLEAR PD\IER PLANT Dl$Cll't..!N£ Ef<<<
INDIAN POINT NO. 3 PLOT PLAN FOR DATI: VILLAGE OF BUCHANAN St"A~ ' NONE DIIG NO M:V 9321-F-11146 1 SHEE:T Ill' IPEC00270164
ENTERGY Conceptual Design
~ ~:,:~.~,~~~2~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (MCE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. Typical Self Contained Diesel-Driven Pump (attached here)
IPEC00270165
.:tlf
~~~ (;©rruv©Jou=u©l ErFU~U[FD [Q)wow&rFU ll>>rruo~
Hale offers a variety of standard and custom self contained engine driven pumping modules with features designed to meet demanding applications. Our units can be mounted direct, bolted down, or set up as trailers for transportable firefighting protection at dock side. Varying in size and capability from small open chassis units to custom trailer pumping modules1 they span a wide range of applications including marine firefighting pumps and industrial trailers. Hale builds water and foam pumping skids to meet the needs of government, forestry, and industrial customers. Units have been constructed for hurricane relief, fire protection at nuclear power sites, oil field fire fighting, hydrant systems, marine fire boats, dock protection, and more. These units ore equipped with heavy duty fan forced radiator cooling. HALE Products Class11 IPEC00270166
ENTERGY Conceptual Design
~ ;:~"~'~,~~~~:;_~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -007 Rev. 0 Attachment 4 Cost Estimate IPEC00270167
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
~TIMATE LEVEL* EC #: SAMA IP3-007 0 Conceptual PROJECT TITLE: Install a Reactor Cavity Flooding System 0CAPITAL Do&M ESTIMATOR: RCMT D Preliminary JOB LOCATION: Containment Building, Yard near FSB PROJECT CODE: TBD u- Definitive 00UTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 07-12-2012 ESTIMATE TOTAL $1,869,811 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C. F. R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-007 in accordance with Entergy design engineering practices. For SAMA IP3-007, resolution is required to reduce potential containment damage as a result of concrete-core interaction from molten debris following core damage and vessel failure conditions. This package will provide an installation using a standby pump and fire water to fiood the reactor cavity in the event this emergency action is necessary. Pffipoffidb' jJL B.Jf~ ,.k!. Approved by:
- ~~ ~'~_kl. ::;.;;..::: --:* ~
Date: q-zo-zor Date: t ,. 2 <: z !/Z,_ IPEC00270168
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
!~IMAII:.LI:.VI:.L Conceptual Preliminary EC #: SAMA IP3-007 PROJECT TITLE: Install a Reactor Cavity Flooding System JOB LOCATION: Containment Building, Yard near FSB 0 CAPITAL Oo&M PROJECT CODE: TBD ESTIMATOR: RCMT D Definitive 0 OUTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 07-12-2012 Item Descriotion
- 1. This estimate assumes that this work will require outage conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, Six days per week schedule.
- 3. This estimate assumes that a Prefabricated building will be purchased for erection on site by skilled local craft.
- 4. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate provides for continuous fire watch during welding activities.
- 6. This estimate assumes training for 12 Plant Ops.Personnel.
- 7. This estimate assumes that the safety class for piping and valves will only require a C of C.
- 8. This estimate assumes that weld inspections will be limited to visual and LP testing.
- 9. The bulk of the work in this estimate is non outage and is assumed to occur in 2011 on a 4 day per week, 10 hour per day schedule.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 10. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 11. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00270169
Page 1 of 3 10/4/2012 9:32AM IP3-007.xlsx INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP3-007 PROJECT TITLE: Install a Reactor Cavity Flooding System TAKEOFF JOB LOCATION: Containment Building, Yard near FSB []oUTAGE D NON-OUTAGE PROJECT CODE TBD [::;:]CAPITAL 0 o&M ESTIMATOR RCMT EST. STATUS I I ORIGINATOR ORIG. DATE 07-12-2012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-
~T UOMI CFT I NO.I UNIT I FCTR TOTAL I $1MH 7 C;:;:T:;:--t--I::;TO=TA"'L:-;;:-$--I I PER UNIT 11-'::D2::02i-L.:;:L';iA';;R.;::S=-t-;:;:D;;oO-C'LLA;:-7,R:O:S::-+-I---;:;C;:;:07,N,;T;;RA ITE~ DESCRIPTION D
*ESTIMATE LEVEL* ESTIMATE
SUMMARY
Conceptual MANHOURS DOLLARS Preliminary ENGINEERING Definitive 01 STUDY, DESIGN, & CLOSEOUT 160 $ 16,000 02 DESIGN ENGR CONST SUPPORT 40 $ 4,000 General Notes: 03 MODS ENGR SUPPORT 04 SYS ENGRI S-U ENGR 100 $ 10,000 05 PROJECT MANAGEMENT 200 $ 24,000 06 TESTING (Calibration & Testing) 40 $ 4,000 07 TECH SPECIFSAR, CALCS, ANALYSIS 675 $ 81,000 08 ENGINEERING DCP ACCEPTANCE REVIEW 40 $ 4,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 1,200 $ 144,000 09 SUPL CONTRACT MODS ENGR 10 MODS PLAN & SCHED -CONTRACT 160 $ 16,000 11 OSG FIELD ENGRS I PLANNERS 140 $ 16,800 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 121,900 13 OTHER CONTRACTS CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 2,446 $ 333,032 15 LOST TIME 245 $ 33,357 16 SWEC DISTRIBS PLANT CRAFT LABOR 17 MECH MAl NT. $ 18 ELECT MAINT $ 19 I&C $ 20 CSG $ MISC SUPPORT 21 QUALITY CONTROL 180 $ 18,000 22 PLANNING & SCHEDULING $ 23 TRAINING 36 $ 4,320 24 CHEMISTRY $ 25 OPS 100 $ 12,000 26 HPIRP $ MISC CONTRACT SUPPORT 27 QUALITY CONTROL 130 $ 10,400 28 NDE $ 29 HPIRP $ 30 RADWASTE $ 31 NURSE $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL $ 36 VENDOR STOCKING $ 37 DECONTAMINATION CONTRACTOR $ 38 RBC'S $ 39 SECURITY $ 40 FIRE WATCH (Rover) $ 41 SAFETY 49 $ 3,332 CONTINGENCY 42 CONTINGENCY $ 342,456 ESTIMATE SUBTOTAL 5,941 $ 1,198,597 Site Encumbrance Loaders (20%) $ 239,719 Loaders (30%) $ 431,495 ESTIMATE TOTAL $ 1,869,811 IPEC00270170
Page 2 of 3 10/4/2012 9:32AM IP3-007.xlsx ~- INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP3-007 PROJECT TITLE Install a Reactor Cavity Flooding System TAKEOFF JOB LOCATION: Containment Building, Yard near FSB []oUTAGE D NON-OUTAGE PROJECT CODE TBD []CAPITAL Do&M ESTIMATOR RCMT EST. STATUS ORIGINATOR ORIG. DATE 07-12-2012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEJ DESCRIPTION bT UOM CFT I NO.I UNIT I FCTR TOTAL I $/MH I PER UNIT I DOLLARS DOLLARS I CONTRACT I TOTAL$ Non-outage Work
- 1. Gather and stage tools and materials 1 LT LB 2 2.00 1.00 4 $ 78.15 $ $ 313 $ 313
- 2. Perform walkdown of work area. 1 LT LB 2 4.00 1.00 8 $ 78.15 $ $ 625 $ 625
- 3. Perform walkdown of work area. 1 LT OP 1 4.00 1.00 4 $ 115.00 $ $ 460 $ 460
- 4. Excavate to existing Fire Water Line 1 LT OP 1 24.00 1.00 24 $ 115.00 $ $ 2,760 $ 2,760
- 5. Excavate to existing Fire Water Line 1 LT LB 2 24.00 1.00 48 $ 78.15 $ $ 3,751 $ 3,751
- 6. Perform tie in to existing fire line 1 LT PF 3 20.00 1.00 60 $ 120.71 $ $ 7,243 $ 7,243
- 7. Backfill and compact excavation 1 LT OP 1 15.00 1.00 15 $ 115.00 $ $ 1,725 $ 1,725
- 8. Backfill and compact excavation 1 LT LB 2 15.00 1.00 30 $ 78.15 $ $ 2,345 $ 2,345
- 9. Excavate, form and pour slab with oil berm 1 LT OP 1 1000 1.00 10 $ 115.00 $ $ 1,150 $ 1,150
- 10. Excavate, form and pour slab with oil berm 1 LT LB 3 30.00 1.00 90 $ 78.15 $ 1,500 $ 7,034 $ 8,534 11 Excavate, form and pour slab with oil berm 1 LT CP 2 1000 1.00 20 $ 96.00 $ $ 1,920 $ 1,920
- 12. Obtain and erect insulated steel building. 1 LT MW 3 20.00 1.00 60 $ 134.00 $ 10,000.00 $ 10,000 $ 8,040 $ 18,040
- 13. Provide Light, Heat and Ventilation 1 LT EL 2 30.00 1.00 60 $ 123.32 $ 4,000.00 $ 4,000 $ 7,399 $ 11,399
- 14. Set Diesel Pump Skid 1 LT MW 2 20.00 1.00 40 $ 134.00 $ 50,000.00 $ 50,000 $ 5,360 $ 55,360
- 15. Excavate and pour Pipe Support Piers 1 LT LB 2 60.00 1.00 120 $ 78.15 $ 4,000.00 $ 4,000 $ 9,378 $ 13,378
- 16. Excavate and pour Pipe Support Piers 1 LT CP 1 60.00 1.00 60 $ 96.00 $ $ 5,760 $ 5,760
- 17. Excavate and pour Pipe Support Piers 1 LT OP 1 60.00 1.00 60 $ 115.00 $ $ 6,900 $ 6,900
- 18. Obtain Material and Erect Pipe Supports on Piers 1 LT PF 3 60.00 1.00 180 $ 120.71 $ 2,000.00 $ 2,000 $ 21,728 $ 23,728
- 19. Cut, Fit and Weld Piping from Diesel to Pene.Y-Y 1 LT PF 3 150.00 1.00 450 $ 120.71 $ $ 54,320 $ 54,320
- 20. Tie in Piping at Pump and at Penet. Y-Y 1 LT PF 3 20.00 1.00 60 $ 120.71 $ $ 7,243 $ 7,243 21 Mount and tie in diesel day tank 1 LT PF 3 1000 1.00 30 $ 120.71 $ 1,000.00 $ 1,000 $ 3,621 $ 4,621
- 22. Prefabricate Containment spool piece for outage. 1 LT PF 2 20.00 1.00 40 $ 120.71 $ $ 4,828 $ 4,828
- 23. Support testing as required 1 LT PF 2 20.00 1.00 40 $ 120.71 $ $ 4,828 $ 4,828
- 24. Clean-up area and restore 1 LT PF 2 1000 1.00 20 $ 120.71 $ $ 2,414 $ 2,414
- 25. Clean-up area and restore 1 LT LB 2 1000 1.00 20 $ 78.15 $ $ 1,563 $ 1,563 OUTAGE WORK
- 1. Obtain tools and material 1 LT PF 2 5.00 1.70 17 $ 120.71 $ $ 2,052 $ 2,052
- 2. Perform job brief and walk down are 1 LT PF 2 5.00 1.70 17 $ 120.71 $ $ 2,052 $ 2,052
- 3. Install prefabricated spool in containment 1 LT PF 2 1000 1.70 34 $ 120.71 $ $ 4,104 $ 4,104
- 4. Clean up and restore area 1 LT PF 2 5.00 1.70 17 $ 120.71 $ $ 2,052 $ 2,052 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP- PRIME 1 LT PT 2 60.00 1.00 120 $ 95.16 $ 1,500 $ 11,419 $ 12,919
- 2. PAINTING & TOUCH-UP 1 LT PT 2 60.00 1.00 120 $ 95.16 $ 3,000 $ 11,419 $ 14,419 FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 120.00 1.70 204 $ 53.60 $ $ 10,934 $ 10,934
- 2. CRAFT SUPPORT FOR BOTTLE WATCH MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT SUBTOTAL CRAFT & SUB-CONTRACTOR 2,082 $ 77,000 $ 216,740 $ $ 293,740
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 167 $ 104.10 $ 17,385 $ 17,385 SUBTOTAL 2,249 $ 77,000 $ 234,125 $ $ 311,125
*RELATED COSTS*
- 1. WALKDOWN ALLOWANCE 1 LT PF 20 $ 120.71 $ 2,414 $ 2,414
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT PF 98 $ 120.71 $ 11,830 $ 11,830
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 79 $ 123.32 $ 9,742 $ 9,742
- 4. GENERAL CRAFT DISTRIBS. (1 0%) $ 23,413 $ 23,413
- 5. CRAFT IN PROCESSING (20%) $ 46,825 $ 46,825
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 4,683 $ 4,683
- 7. (1/2 day training, or- 2%)
SUBTOTAL 2,446 $ 77,000 $ 333,032 $ $ 410,032 PLANT SCOPE
- 1. MECH MAINTENANCE PL PL SUBTOTAL MECH MAINT. $ $ - $ $
- 1. ELECT MAINTENANCE PL PL SUBTOTAL ELECT. MAINT. $ $ - $ $
- 1. I&C (Dev. Instrument Calibration Procedures) 0 LT PL PL SUBTOTAL I&C MAINT. $ $ $ $
IPEC00270171
Page 3 of 3 10/4/2012 9:32AM IP3-007.xlsx ~- INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP3-007 PROJECT TITLE: Install a Reactor Cavity Flooding System TAKEOFF JOB LOCATION: Containment Building, Yard near FSB []oUTAGE D NON-OUTAGE PROJECT CODE TBD []CAPITAL Do&M ESTIMATOR RCMT EST. STATUS ORIGINATOR ORIG. DATE 07-12-2012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITE~ DESCRIPTION ~T UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 1. CSG PL PL SUBTOTAL CSG MAINT. $ $ - $ $
SUBTOTAL PLANT $ $ - $ $ SUBTOTAL CRAFT/PLANT 2,446 $ 77,000 $ 333,032 $ $ 410,032 IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000
- 4. SYS ENGINEERING- ELECTRICAL 1 LT NM 1 20.00 1.00 20 $ 100 00 $ 2,000 $ 2,000
- 5. SYS ENGINEERING -INSTR & CONTROL 1 LT NM $ $
- 6. SYS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 200.00 1.00 200 $ 120.00 $ 24,000 $ 24,000
- 8. TRAINING (OPS Staff) 1 LT NM 12 3.00 1.00 36 $ 120.00 $ 4,320 $ 4,320
- 9. QA I QC VERIFICATION 1 LT NM 1 180.00 1.00 180 $ 100 00 $ 18,000 $ 18,000
- 10. PLANNING & SCHEDULING 1 LT NM 11 HP I RP/ ALARA 1 LT NM
- 12. CHEMISTRY 1 LT NM
- 13. OPS (DEVELOP/REVISE PROCEDURE(S)) 1 LT NM 1 10000 1.00 100 $ 120.00 $ 12,000 $ 12,000
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per Diem) LT NM $ $
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 160.00 1.00 160 $ 100 00 $ 16,000 $ 16,000
- 3. OSG FIELD ENGRS/PLAN- SWEC(Incl Per Diem) 1 LT NM 1 140.00 1.00 140 $ 120.00 $ 16,800 $ 16,800
- 4. QA I QC VERIFICATION 1 LT NM 1 130.00 1.00 130 $ 80.00 $ 10,400 $ 10,400
- 5. NDE 1 LT NM 1
- 6. HP/RP 1 LT NM 1
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM 11 HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIRE WATCH (Rover) 1 LT NM
- 18. SAFETY (2%) 1 LT NM 49 $ 68.00 $ 3,332 $ 3,332
- 19. LOST TIME (10%) 1 LT 245 $ 136.15 $ 33 357 $ 33,357 SUBTOTAL CRAFT/NON-MANUAL 3,826 $ 77,000 $ 485,241 $ $ 562,241
- 1. 6" and 8" Sch 40 pipe Safety Class 1 LT MT $ 18,000 $ 18,000
- 2. 8", 6" and 1", 150# class, Safety Related 1 LT MT $ 20,000 $ 20,000
- 3. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 6,900 $ 6,900 SUBTOTAL INSTALLATION COST 3,826 $ 121,900 $ 485,241 $ $ 607,141
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000
- 3. DESIGN ENGINEERING- INSTR & CONTROL 0 LT NM
- 4. DESIGN ENGINEERING- CIVIL/STRUCTURAL 1 LT NM 1 80.00 1.00 80 $ 100 00 $ 8,000 $ 8,000
- 5. TESTING (Instrument Calibration and testing) 1 LT NM 2 20.00 1.00 40 $ 100 00 $ 4,000 $ $ 4,000
- 6. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,200.00 1.00 1,200 $ 120.00 $ 144,000 $ $ 144,000
- 7. TECH SPEC/ FSAR, CALCS, ANALYSIS 1 LT NM 1 675.00 1.00 675 $ 120.00 $ 81,000 $ 81,000
- 8. ENGRG DCP ACCEPTANCE REVIEW 1 LT NM 1 40.00 1.00 40 $ 100 00 $ 4,000 $ 4,000 SUBTOTAL DESIGN COST 2,115 $ 164,000 $ $ 249,000 SUBTOTAL INSTALLATION & DESIGN COST $ 649,241 $ $ 856,141
- 1. CONTINGENCY ( 40%) $ 342,456 ESTIMATE SUBTOTAL 5,941 $ 1,198,597 IPEC00270172
ENTERGY Conceptual Design
~ ~~~"~'~,~~~2~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 3 CONCEPTUAL DESIGN PACKAGE For SAMA IP3-018 Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products Prepared by: Approved by:
!Jl:fl~~...(\-v-Y*
(/ , / '" i /// Date: 1* z o~z z Date: ~,_> .' Page 1 of 11 IPEC00270173
ENTERGY Conceptual Design
~ ~:,:~,~,~~2.!;: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST- Mechanical 8.0 PRELIMINARY MATERIAL LIST - Electrical Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of 11 IPEC00270174
ENTERGY Conceptual Design
~ ~:~.~~,~~~~~,~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP3-018:
Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-018 in accordance with Entergy design engineering practices. For SAMA IP3-018, resolution is required to reduce the resulting consequences from a Steam Generator Tube Rupture (SGTR). This package will capture and route discharge from the Main Steam Safety Valves (MSSVs) through a structure where water will be used to condense the exhausted steam and remove potential fission products. The design considerations that follow will address the resolution's adequacy and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for EC development and implementation at the Station. Page 3 of 11 IPEC00270175
ENTERGY Conceptual Design
~ ~~~,~~,?.~~~~~.~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 3.0 EXISTING CONDITIONS Indian Point 3 is a pressurized water reactor, which uses steam generators to transfer the heat generated by the reactor from the primary ("Reactor Coolant"}
system to the secondary ("Main Steam") system, which drives the turbine. This SAMA deals with the potential effects of a rupture of one or more of the tubes in one of those generators, allowing primary system fluid to enter the secondary system and potentially be released to atmosphere. The Main Steam System is provided with protection. In the event of a Steam Generator Tube Rupture (SGTR}, the Main Steam Isolation Valves (MSIVs) close and the Main Steam Safety Valves (MSSVs) may open at a pre-determined setpoint to protect the steam line. The steam line isolation provided by the MSIVs, coupled with the relief provided by opening the MSSVs, provides for the integrity of the main steam system, but should the secondary side release not be terminated, the release to atmosphere may include fission products for postulated scenarios leading to core damage. This potential radioactive release needs to be captured and mitigated. 4.0 DESIGN CONSIDERATIONS An installation is required that will capture the steam released from the MSSVs and process the steam to remove fission products. There are four steam lines each of which contains five MSSVs for a total of 20 MSSVs. Any one, or multiples, of the valves has to be considered a potential release path open under the conditions described above. A connection of piping from each 14 inch diameter MSSV stack needs to be routed and connected to a facility equipped to "scrub" the steam being discharged. This will require approximately 200 feet of pipe per stack. Each stack will require monitoring to detect if a steam discharge has occurred and to initiate the scrubbing system. The proposed modification consists of four large vessels, one for each main steam line, each enclosed in its own structure. Each vessel will require a piped water supply and pumps to spray the steam with water in order to condense the steam. Additional controls for maintaining the water level and its recirculation will also be needed. Drainage and disposal provisions for the contaminated condensate will also be required. Electrical power will be required for pumps, controls, heaters, & exhaust fans. Page 4 of 11 IPEC00270176
ENTERGY Conceptual Design
~ ~;~~~,~~~2~,:.: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 5.0 CONFIRMATION OF DESIGN New piping connections will be added to the existing MSSV discharge stacks to capture potentially contaminated steam from being discharged to the atmosphere as a result of a SGTR. The connected piping from each main steam line, will, in turn, be routed to an enclosed vessel. The vessel, equipped with nozzles and a pumped water supply for spraying the entering steam, will condense the steam and scrub any included fission products.
Analysis and/or calculations will be performed to:
- establish physical design conditions or boundary conditions such as flow rate for the design steam generator tube rupture and rated discharge capacity of each MSSV.
- evaluate if backpressure created by the new discharge and quenching system will exceed the current design level.
- determine the resulting discharge flow rate, pressure drop and resulting conditions in the b!owdown vessel. These calculations will determine final blowdown vessel and spray pump sizing and quench water flow rate required to condense the MSSV discharge and what equilibrium pressure and temperature conditions will result in the vessel.
- determine the exit flow rate of quenched water that will be discharged from the blowdown vessel drain line.
- determine the dimensions of the blowdown vessels to include the total volume, aspect ratio of length and diameter and vertical orientation along with the co-current spray pattern of admitted MSSV discharge flow and quench water.
- determine city water or fire protection system capacity to provide water supply for quenching system
- determine the physical protection for blowdown vessels to prevent damage from tornado generated missiles
- determine the amount of potential radioactive fluid leakage and develop a system to contain this fluid In addition, with the spray pump suction coming from both an outside source and the bottom of the vessel, a calculation to establish outside source water verses flow recalculated from the blowdown vessel needs to be performed. An active flow control system may need to be added to control and maintain these proportions and prevent one from dominating the other as conditions inside the blowdown vessel Page 5 of 11 IPEC00270177
ENTERGY Conceptual Design
~ ~~~?.~~2~~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 change during the discharge transient.
The proposed discharge piping system, quench vessel and their support systems will be analyzed to determine their ability to withstand the transient shock loads that occur when one or more MSSVs opens and exposes the flow path components to dynamic stresses and thermal changes. The MSSV blowdown vessel will be an ASME code pressure vessel and will require overpressure protection in the form of a safety/relief valve discharging to an appropriate location. There is the possibility for the quenching process to liberate a significant quantity of non-condensable gases (ex. C02, H2, etc) resulting from condensation and cooling of steam water flow. 6.0 RECOMMENDED SOLUTION A MECHANICAL
- 1. Install City Water/ Fire Protection Water Supply Piping This will require excavating at the East wall of the house service boiler building and connection of the new piping to the existing 4 inch connection (Ref. Dwg. 9321-F-40903). This piping run is to have an underground isolation valve with a curb box located close to the house service boiler building.
- 2. Install Slowdown Vessel Support Structure
- The blowdown vessels and spray pumps are to be located north of the Unit 3 Containment Building (see Attachment 2, figures 1, 2, and 14).
A steel structure is provided for support and protection for the vessels and pumps.
- Prior to the design of the structure, locate support foundations around existing piping and conduits in the area (new reinforced concrete foundations to be 3000 PSI compressive strength @ 28 days). Steel to be galvanized ASTM A500 GR B. All channels, angles, plates, and bars to be A36.
- Install intermediate steel, platforms and required ladders as not to impede on existing piping and conduits, etc.
The following applicable codes, standards, and specifications shall apply: A 2009 International Building Code B. ASCE 7, Minimum Design Loads for Building and Other Structures Page 6 of 11 IPEC00270178
ENTERGY Conceptual Design
~ ::~~,~~~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 C. AISC Steel Construction Manual D. AWS D1.1 Structural Welding Code-Steel E. AISI Specification for Design of Cold-Formed Steal Structural Members F. ACI 301 Specification for Structural Concrete G. ACI 315 Detail and Detailing of Concrete Reinforcement H. ACI 318 Building Code for Structural Concrete
- 3. Install Slowdown Vessels
- Lift blowdown vessels into place on the support structure using a heavy crane.
- Secure the vessels support lugs to the steel structure by welding or mechanical means.
- 4. Install Spray/Recirculation Pumps and Related Piping
- Install the spray/recirculation pump on the intermediate platform located just above the existing piping and conduits and below the blowdown vessel drain.
- Install the pump suction piping, discharge piping, and valves.
- Install sample and level connections, root valves, level transmitter, tubing, tray, hardware and supports.
- 5. Install 14 inch DIA. Main Steam Relief Valve (MSSV) Stack Extension Piping
- Prepare ends of existing stack pipes for welding.
- Install new piping from each main steam line relief valve (five MSSV's per main steam line) and run to its related Nozzle connection on the appropriate blowdown vessel.
- Utilize "five diameter Bends" where possible.
- Install supports as required.
- Install flow switch on each MSSV Stack Extension Piping downstream of MSSV (five MSSV per main steam line - thus five flow switches per main steam line).
Page 7 of 11 IPEC00270179
ENTERGY Conceptual Design
~ ;;~~~,~~~E~:;: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0
- Install pressure switch connection, root valve, pressure switch, tubing, tray, and supports.
- 6. Install Building Siding and Roof
- Install siding and roof by attaching to the blowdown vessel support structure.
- Install space heaters and exhaust wall units.
B. ELECTRICAL
- 1. Install a new MCC extension in Unit 3 in Turbine Bldg. at Elevation 15'-0" at MCC 312A.
- Power the new MCC extension from the existing MCC 312A.
- 2. In MSSV Slowdown building on the intermediate platform install a 480/120 Volt transformer.
- 3. Conduit and Wiring
- Route and support conduit from new MCC extension in Unit 3 Turbine Bldg. at Elevation 15'-0" to 480/120 Volt transformer in MSSV Slowdown building.
- Install and connect wiring from the new MCC extension to 480/120 Volt transformer in MSSV Slowdown building.
- 4. Install Hoffman junction box with terminal blocks.
- 5. Install Hoffman Panel and Related Components
- Install the Hoffman panel on the intermediate platform.
- Install the loop power supply and local controller into Hoffman panel.
- 6. Conduit and Wiring A. Instruments
- Route and support conduit from each flow switch to the new junction box fitted with terminal blocks.
- Route and support single conduit from flow switch junction box to the new Hoffman panel.
Page 8 of 11 IPEC00270180
ENTERGY Conceptual Design
~ ~'~"~'~?.~?2:~.: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0
- Install and connect wiring from the flow switches to the new junction box.
- Install and connect wiring from the junction box to the new Hoffman panel.
- Route and support conduit from each level transmitter and pressure switch to the new Hoffman panel.
- Install and connect wiring from each level transmitter and pressure switch to the new Hoffman paneL B. Pump and Valves
- Route and support conduit from pump and valves to the new Hoffman panel.
- Install and connect wiring from pump and valves to the new Hoffman panel.
C. GENERAL
- 1. Testing Perform a functional test by running pump in a spray mode until level in the vessel signals valving to switch to recirculation mode.
- 2. Additional Requirements The condensed steam co!Hded in the blowdown vessel must be sampled for fission products and disposed of at plant operation's discretion.
- 3. Provide procedures and training for operating, testing, and performing maintenance on the components of the newly installed system.
- 4. Provide preventive maintenance procedures and parts for all blowdown vessels and recirc/spray system components.
Page 9 of 11 IPEC00270181
ENTERGY Conceptual Design
~ ~~~.~~,~~~~:~.~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 7.0 PRELIMINARY MATERIAL LIST - Mechanical Item Description Quantity 1 14 inch Dia Schedule 40 Seamless pipe A 106 Grade B 4000 feet
- 2. Pump-300GPM, Griswold Pump Co (or equal) 4
- 3. Slowdown Vessel, ASME Section VIII, per sketch 4
- 4. Structural Steel-12 x 12 x 190 lb/ft Wide Flange, A500 GR B 1,500 feet 10 x 10 x 112 lb/ft Wide Flange, A500 GR B 1,000 feet 8 x 8 x 67 lb/ft Wide Flange, A500 GR B 1,000 feet 4 x 4 x %"Angle, A500 GR B 2,500 feet
- 5. Spray Nozzles 80
- 6. 4 inch Gate Valve, 150# Carbon Steel 12
- 7. 4 inch Check Valve, 150# Carbon Steel 4
- 8. 8 inch Dia Schedule 40 Seamless pipe A 106 Grade B 600 feet
- 9. 3 inch Dia Schedule 40 Seamless pipe A106 Grade B 600 feet
- 10. 1 inch Dia Schedule 40 Seamless pipe A 106 Grade B 40 feet 11 4 inch Dia Schedule 40 Seamless pipe A 106 Grade B 500 feet
- 12. 4 inch Gate Valve, 150# Carbon Steel, with curb box 1
- 13. 4 inch Air operated gate valve, 150# Carbon Steel 8
- 14. 8 inch Air operated gate valve, 150# Carbon Steel 4
- 15. Unit Heaters- Large Capacity lndustriai-280V-15000 W 50000-BTU/HR- 1342 CFM 2
- 16. Shutter Mounted Exhaust Fan, 36" Blade, 1 Speed, 12,000 CFM 2
- 17. Metal Siding-Ryerson Great Rib Style or Equal 20,000 Sq. Ft.
- 18. Metal Roofing-Ryerson RY-Lock Style or Equal 2,400 Sq. Ft.
- 19. Double Door w/Frame-Metal w/Hardware 1
- 20. 1"-Globe Valve Carbon Steel 12
- 21. 2" x 3" Relief Valve (setpoint data pending calculation) 4 Page 10 of 11 IPEC00270182
ENTERGY Conceptual Design
~ ~:~,~,~~~E:,~;: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 8.0 PRELIMINARY MATERIAL LIST - Electrical Item Description Quantity
- 1. FCI Flow Switch Model FLT93f FlexSwitch or Equivalent 20
- 2. Rosemount 3051 Pressure Transmitter for level measurement or Equivalent 4
- 3. Allen-Bradley 836-- 836-C12 Pressure Switch or Equivalent 4
- 4. Loop Power - Power Supply 1
- 5. Local Controller 1
- 6. Hoffman Junction Box with terminal blocks 4
- 7. Hoffman Wall Mounted Panel and enclosure, with 1 terminal blocks, 36" x 36" x 16"
- 8. Instrument Tubing- 0.375" x 0.065- 316 SS Tubing 300 Feet
- 9. 3"- Conduit and supports 1200 Feet
- 10. 1"- Conduit and supports 3000 Feet
- 11. 10/c - Cable 1200 Feet
- 12. 2/c- Cable 2600 Feet
- 13. One Pair- Twisted Shielded Pair Cable 400 Feet
- 14. MCC extension (2 buckets high x 1 bucket wide) with mounting brackets to connect to existing MCC 312A 1
- 15. 480 VAG switchgear to be installed into MCC extension 2
- 16. 480/120 volt Transformer 1
- 17. 2"- Conduit and supports 500 Feet
- 18. 480 VAG- 4/c Power Cable 500 Feet Page 11 of 11 IPEC00270183
ENTERGY Conceptual Design
~ ~~,~~,~~~~:,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270184
d'l&. NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 96 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. AMA Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potential lm12act Civil/ Structural Design Engineering .YES ONO
- Does the proposed activity involve any civil/ structural {including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES ONO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? {SOER 10-1)
Instrumentation and Controls Design Engineering
- Does the proposed activity involve any I&C design or settings changes or activities?
- ONO Mechanical Design Engineering .YES ONO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact .YES ONO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270185
'"'='Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
Sheet 2 of6 DESIGN ENGINEERING PROGRAMS Potentiallmeact ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES !X1 NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) .YES DNO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential Impact Nuclear Fuel Design DYES DG NO
- Does the proposed activity impact or involve the design, performance or storage of <
nuclear fuel? Reactivity Management Program DYES DC] NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270186
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmgact Computer Support and Software .YES DNO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact .YES DNO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact .YES DNO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and <.'
installation information? MP&C (Inventory) .YES ONO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS PotentiallmJ2act ASME Containment In-service Inspection (IWE /IWL) Program .YES DNO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program .YES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270187
.'1'6 NUCLEAR QUALITY RELATED EN*DC*115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 99 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallm~act ASME In-service Inspection (lSI) Program .YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel wa!ls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program .YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST proQram documents?
Air Operated Valve (AOV) Program .YES DNO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T) Program .YES DNO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES IX! NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES I![ NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00270188
!1.. NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
"'!:="Entergy MANAGEMENT REFERENCE USE PAGE 100 OF 150 MANUAL Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallm(;!act Flow Accelerated Corrosion (FAC) Program .YES DNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES IX[ NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact .YES DNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES til' NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program .YES DNO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains itsqualification status?
PTCurves DYES f81No
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES ~NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270189
....Entergy
-===-
NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I PAGE 101 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEETS OF6 PROGRAMS AND COMPONENTS {CONTINUED} PotentiallmJ2act Welding Program .YES ONO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program .YES ONO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES ONO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES ONO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator impact .YES ONO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program .YES ONO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES [1Cl NO IPEC00270190
ENTERGY Conceptual Design
~ :::~"~'~,~~~~~,~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Partial Site Plan of Areas Affected
- 2. Figure 2: General Arrangement- Blowdown Vessels Location
- 3. Figure 3: General Arrangement- Proposed Piping Routing
- 4. Figure 4, Sheet 1: Partial Flow Diagram- S.G. No. 31, Ref Dwg 9321-F-20173
- 5. Figure 4, Sheet 2: Partial Flow Diagram- S.G. No. 31, Ref Dwg 9321-F-20173
- 6. Figure 5, Sheet 1: Partial Flow Diagram- S.G. No. 32, Ref Dwg 9321-F-20173
- 7. Figure 5, Sheet 2: Partial Flow Diagram- S.G. No. 32, Ref Dwg 9321-F-20173
- 8. Figure 6, Sheet 1: Partial Flow Diagram- S.G. No. 33, Ref Dwg 9321-F-20173
- 9. Figure 6, Sheet 2: Partial Flow Diagram- S.G. No. 33, Ref Dwg 9321-F-20173
- 10. Figure 7, Sheet 1: Partial Flow Diagram- S.G. No. 34, Ref Dwg 9321-F-20173
- 11. Figure 7, Sheet 2: Partial Flow Diagram- S.G. No. 34, Ref Dwg 9321-F-20173
- 12. Figure 8: Partial Flow Diagram- Fire Protection System, Ref Dwg 9321-F-40903
- 13. Figure 9: MSSV Blowdown Vessel
- 14. Figure 10: MSSV Blowdown Vessel and Support Elevation IPEC00270191
ENTERGY Conceptual Design
~ ~~~"~~.~.~~E.i.:.: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 FIGURE 1 PARTIAL SITE PLAN OF AREAS AFFECTED UNIT 3 CONTAINMENT
* *-- BUILDING MSSV BLOWDOWN VESSEL ;,,.~
I -:.:: I
. l & SUPPORT STRUCTURE LOCATION IPEC00270192
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit3 SAMA IP3-018 Rev. 0
........_ . PLANT NORTH I
I I I I I _....---, I
/"" "-._.J I
I COND. I STORAGE I TANK \ I
\
\ I REACTOR
' ' '--::1_ I 1 CONTAINMENT rol I
I I I UNIT N0.3 LT~ I NEW MSSV BLOWDOWN VESSEL W/VESSEL I
& PIPING SUPPORT I STRUCTURES AT GRADE ELEV. 18'-6" I I
I I 14 "0 MSSV VENT STACKS tTYP. 20) I 1 r------4--~--------~---------------- I FIGURE 2 GENERAL ARRANGEMENT SLOWDOWN VESSEL LOCATION IPEC00270193
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0
......._ . PLANT NORTH APPENDIX "R" DIESEL BLDG.
UNIT 3 CONTAINMENT NEW MSSV BLDG. SLOWDOWN VESSELS & SUPPORT STRUCTURE .--+-14'0 MSSV DISCHARGE STACK PIPING EXISTING (TYP. 20 PIPES) MSSV DISCHARGE VENT STACK CLUSTER 4'0 ROOF EL. 86' -6" FIRE PROT./ CITY WATER SUPPLY - - - / TIE IN LOCATION !"""\____- TURBINE~ BLDG. DWG. 9321 -F-40063 G APPRO X ELEV. 13' -0" FIGURE 3 GENERAL ARRANGEMENT PROPOSED PIPING ROUTING IPEC00270194
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 14" 14" CONTINUE 14" ON FIGURE 4 SHEET 2 14" 14" 4 (SHEET 1)
._DES_SUP.'.....___. INDIAN PUINT NO.3 NUCLEAR POWER PLANT FLOW DIAGRAM MAIN STEAM DWG NO f£V 9321-F-20173 71 IPEC00270195
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA 1P3-018 Rev. 0
~~---
I I r::----
--------~~~
--------, I 1 I r-----------
1111 FS FS FS 1 I I I II II CONTINUED I II II FROM I II II FIGURE 4 I II II SHEET 1 1 OUT OF 5 LOGIC
~~
1 I TO ...., I PROCESSING I I I MSSV I I SLOWDOWN I 4" VESSEL NO. 31 I I I I I I I I I I I I I SAMPLE I CONN I _ _ _ _ _ ...JI I I DRAIN SPRAY & RECIRC TO PROCESSING PUMP NO. FP/CITY ., 4 WATER --...l..---lllililiao-J FIGURE 4 (SHEET 2) FLOW DIAGRAM MAIN STEAM DWG NO RE.V 9321-F-20173.71 IPEC00270196
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 14" 14" CONTINUE ON FIGURE 5 SHEET 2 14" 14" FLOW DIAGRAM MAIN STEAM DWG NO 9321-F-20173 71 IPEC00270197
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 1 rr:---- I I ~--------------~
.--- -------- I I llj r - - - - - - - - - - -
1 I Ill FS I I Ill CONTINUED I I Ill FROM I I Ill FIGURE 5 I I Ill SHEET 1 1 OUT OF 5 LOGIC
~I 1
I TO I PROCESSING I I MSSV I SLOWDOWN VESSEL NO. 32 I I I I I I I SAMPLE CONN I _ _ _ _ _ _ _ ..J I I DRAIN SPRAY & RECIRC TO PROCESSING PUMP NO. 32 L_ _ _ _ _j FP/CITY .. WATER _ 4 __;;!:,__-IIII...,J FIGURE 5 (SHEET 2)
~DES"""'"'!""SUPY~--IINDIAN PUINT ND. 3 NUCLEAR POWER PLANT FLOW DIAGRAM MAIN STEAM DWG NO 9321-F-20173 71 IPEC00270198
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 cO M 9
~ ::::J ""0 e
o._ c 0
*v; Vl ii:
Q) 0 E
~ 14" E
~
"' 14" Q) e> CONTINUE 14"
..c"'u ON FIGURE i5 Vl 14" SHEET 2 Oi Vl 14"
~
- J 0.
a
.8 c
0
.!E ~ .s c
00 9
~ <( ;Vl UJ ~ ~
z lD Vi UJ 0
<(
'{'
t UJ u I z 0 I u I
<(
i7i L __ M
~
Vl Q) en
~
u FIGURE 6 (SHEET 1)
"'c o._
en
*v; 0
Q)
~DES~SIJP.I~--1 INDIAN POINT NO.3 NUCLEAR POWER PLANT -ro::::J 0. ~
s: FLOW DIAGRAM MAIN STEAM SCR.E: NONE DWG NO 9321-F-20173 71 IPEC00270199
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0
~~-=--=-----=--=--=--=--=--=--=---=--=--=-~
I I r:::r: - - _:-_:-_:-_:-_:-_:-_:-- - - -, I I 1 I r- ------- ' 1 1 1 I 1I 1 FS FS FS I I Ill I I Ill I I Ill CONTINUED FROM I I Ill FIGURE 6 OUT OF 5 LOGIC
~~ SHEET 1 1
I TO I PROCESSING I I MSSV BLOWDOWN I VESSEL NO. 33 I I I I I I I SAMPLE I I CONN
...)
I DRAIN SPRAY &: RECIRC TO PROCESSING PUMP NO. 33 L_ _ _ _ _j FIGURE 6 (SHEET 2) FLOW DIAGRAM MAIN STEAM DWG NO 9321-f-2017 IPEC00270200
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 I 00 9 M CL
~ ::J ""0 CL 2
c 0
"tR u:::
ClJ 0 E ClJ cr: 14" E: t;"' ClJ
~
CONTINUE
"'u .t::
ON FIGURE 0"' SHEET 2
<Jl <Jl ~
- J 0.
a
.8 c
0
~ ~ .s c
_w 00 9M 8::;
<( <(
- 0-
<Jl Ll.J ~ ~
CL z l? tn Ll.J 0
<( ~
Ll.J
~
II 11
.N
;----L----
L~:-~~-3 J L --4" u z STEAM>'") TO MST-13 0 II u GEN TO MST-14
<(
II
- N0.34 IL-- _
tf, r~-, 1
§_ I \1 1/2" "'0\
ClJ I u FIGURE 7 (SHEET 1)
"'c CL 0\ *v; ClJ 0
10
- J 0.
- l C"
FLOW DIAGRAM
~
MAIN STEAM
"'E ~
Ll.J
<(
- DWG NO REV
<(
<Jl
' 9321-F-20173 71 IPEC00270201
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 I r==...:-- ...:-...:-...:- -.:::-...:-...:-...:-...:-...:- - -, I I r::- r:: -------------- ------, - 1 lllr- -------- 1 II II I II II I II II CONTINUED I I Ill FROM I I Ill FIGURE 7 OUT OF 5 LOGIC
~I SHEET 1 1
I TO I --------, PROCESSING I I I I MSSV I I 4" SLOWDOWN I I VESSEL NO. 34 I I I I I I I I I I I SAMPLE I CONN I I _ _ _ _ ...J I DRAIN SPRAY & RECIRC TO PROCESSING PUMP NO. 34 L_ _ _ _ _j FP/CITY .. 4 WATER ---'----~ FIGURE 7 (SHEET 2) FLOW DIAGRAM MAIN STEAM DWG NO 9321-F-2017 IPEC00270202
RCM) " Technologies ENTERGY Indian Point Nuclear Station Conceptual Design Package Unit 3 SAMA IP3-018 I rR"ev. 0
...._....,..-_;).... Power System Services 4"
SEE FIGURE 4 SHEET 2 4" SEE FIGURE 5 SHEET 2 4" SEE FIGURE 6 SHEET 2 4" 4" SEE FIGURE 7 SHEET 2 4" VALVE W/CURB BOX NEW TIE-IN 16-21 W/CURB BOX / KJ-t><J-~---_,___T_ _ !-
!:a 6-5 W/CURB X w
8:: BOX
*(.0 HOUSE SERVICE m BOILER a:::x BUILDING
- lO om 3:
I en
#34 FIGURE 8 IIWII lllltK"P
~OES~SUPV~--1 INDIAN P[JJNT ND. 3 NUCLEAR POWER PLANT FLOW DIAGRAM OF PLANT FIRE PROTECTION SYSTEM SHEET 1 DWG NO iWI 9321-F-40903. 30 IPEC00270203
~ r-------------------------------~------------------~-----------------T--------~ ~ ;:;, ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-018 Rev. 0 d:,
8 r-------------------------------~------------------~----------------~----------;
~ ~::I -o e
0.. c: 0
*ta u::
(J) Ei E E: Sl"' 14"0 NOZZLE
~ RELIEF VALVE DISCHARGE £"' HEADERS INLET 0"' (TYP.5)
(;; Vl
- 3" RELIEF VALVE 2
- ! CONN.
~
a
.8 c:
0
- 14"0 DISCHARGE
.!l1 HEADER INLET ~ (TYP. 5) .s c:
T OJ 4"0SPRAY NOZZLE___...- 1" PRESSURE SWITCH CONN. INLET SPRAY SPRAY 20 SPRAY_____, RING RING NOZZLES {EQUALLY SPACED) LEVEL 50'-0" CONN. SUPPORT LUGS (TYP. 4) 1"0SAMPLE CONN. 8"0DRAIN CONN. 4"0 OUTLET 16'-0" DIA. CONN. to E
~
UJ
<(
FIGURE 9
;7i MSSV SLOWDOWN VESSEL B' ~c: ~------------------------------------------------------------------------------~ ~
IPEC00270204
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-0 18 Rev. 0 r~4"0MSSV DISCHARGE
~ STAC:PIPING APPRO X. ELEV. 100'-0" I ! I -+-I -+-- ~::6-::::H--
SLOPED~ ~~ v ROOF \ rWf(( 11 .,.. SUPPORT AS REQ'D I I I ( \ I II I \ ELECTRIC SPACE
--H--IPHW ~ I ~~~~g " I' 1"-----
HEATER r ' t I \
\
I( 1/ VENCLOSURE SIDING
\_._/
II
......... ::~------~
MSSV
... ..... I h /1111 SLOWDOWN I VESSEL I \
'\
'\
!'\
\_
I "\ ""----TEM PERATURE CON TROLLED I ...... _'- 4"0 EXH AUST FAN I I LT "
.-~
A I 8" DRAIN TO PROCESSING PLATFORM ELEV. 40'-0" EXISTING PIPING{~
& ELECTRICAL ~
CONDUIT I I GRADE ELEV. I I I APPROX. 18'-6" I c-..l-1-- FOOTINGS I FIGURE 10 I MSSV SLOWDOWN VESSEL
& SUPPORT ELEVATION IPEC00270205
ENTERGY Conceptual Design
~ ~;~"~~,~~~~~~,: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. ENTERGY- Main Steam Safety Valve Setpoint Data from Procedure 3-PT-R006A (attached here)
- 4. Typical Water Spray Pump (attached here)
- 5. Flow Switch Model FLT93F Flexswitch (attached here)
- 6. Rosemount 3051 Pressure Transmitter (attached here)
- 7. Allen-Bradley Bulletin 836 Pressure Switch (attached here)
IPEC00270206
"'U m () 0 0 I'V MAIN STEAM SAFETY VALVES SETTING TEST No: 3-PT -R006A Rev:8 0 USING SET PRESSURE VERIFICATION DEVICE I'V Page 33 of 36 0 ATTACHMENT 1, SAFETY VALVE DATA SHEETS (Page 9 of 12) SG 33 REQUIRED AS FOUND AS FOUND AS LEFT AS LEFT VALVE NO. INITIALS SETTING PSIG REQUIRED+/- 3% ACTUAL* REQUIRED+/- 1% ACTUAL** 1 MS-45-3 1065 1034 TO 1096 1055 TO 1075 2 MS-46-3 1080 1048 TO 1112 1070 TO 1090 3 MS-47-3 1095 1063 TO 1127 1085 TO 1105 4 MS-48-3 1110 1077 TO 1143 1099TO 1121 5 MS-49-3 1120 1087 TO 1153 1109 TO 1131
- As Found: First Initial Actuation
** As Left: Last Actuation Performed
[1;14j] Customer Name
- DATA I ESTIMATE SHEET I Quote Attention To:
Phone# Total Price for 1 UniUs Griswold Pump Co. Fax #---------------1 7,477 107 Plantation Oak Drive Quoted By Peter Glauber Total Estimated Weight Thomasville, GA 31792 Email pwg@glauber..com 497 800-843-9222ph 800-752-2929fax Quote# Estimated Lead-Time
~~~~~F~I~u~id~l~nf-o~rm~M~Io~n~~~--~--------~~~-------- 8weeks Liquid Fuel oil unloading Curve# G-3610 Driver Info: F.O.B. Thomasville, GA Temperature _ _ _ _ 8o_ _ _ _
Specific Gravity _ _ _ _ _1_ _ _-t
._F-I Impeller Dia.
NPSHr 9.1 8.1 HP
---- 5 Frame _ __;1~8..;.4T.:.__
Today's Date February 14, 2008 Project Name I Reference Viscosity _ _ __..;2;;..1;..__ _-t Coupling Info: TEFC GPM _____~30;;..0;.._____-I TB Woods Type SC7 TDH 370 Sheet 1 of 1 Be-::weer: rlT --~- ---~~----- CP ------*--*----*-;
*-- r X
j r 1 I I I -- Pump End Dimensions Modell Pump Size & Desi~uction I 150# Drilling I Discharge 150# Drilling I D I X CP E1 I E21 F y 811MI 4x3-10A7~ 4 I(8}3/7Holeson7.50BC 3 (4) 3/4 Holes on 6 .OBC 18.251 11 23.5 4 718135/8112.5 4 Steel Base Plate Dimensions Max Nema Frame I ANSI Baseplate# I ~ ~ I HT (min) I I HD max (D+HG) I ~. 1-.t!!:..l
~..-_ _,;..;;8_4T'----' I 139 I L.21.J ~ I 3.5 I I 12 I ~ ~
Materials of Construction Case I Impeller I Stuffing Box I Sleeve Shaft I Seal/ Packing Gland I Seal Type I Material Code I 316 ss I 316 ss I 316 ss I I 316 ss I cs 414o I 316ss I CSSN I Car/Sic I Construction Details Shaft Diameter Bearings Impeller Case Corrosive At Under Under Under Maximum Thickness Allowance Coupling Impeller Seal Sleeve Ov;rhang Radial Thrust Span Eye Area Diameter Solids 112 118 1.125 1 1-3/4 1-112 8-3/8 SKF 6309 SKF 5309NC3 15-3/4 12.5 518 B.H.P. Limits RPM BHP Sealing Std. Stuffing Box Oversized Sluffing Box 3600 200 Mechanical Lantern Distance end of box to Distance end of box to 1800 100 Seal Size Ring Width LD. Depth nearest obstruction I.D. Depth nearest obstruction 1200 66.4 1-314 5/8 2-112 2-518 2-13116 3-112 2-5/8 2-13/16 880 49.5 I IPEC00270208
Flow Switch Model FL T93L - Inline Flexswitch I Fluid Components International (FCI) Page 1 of2 Language: Search FCI i-:r l*c-Home 1 Contact FCI 1 Site Map I Search Tips Flow Switch Model FLT93F FlexSwitch Products Flow Switches FLT93B FL T93S Download literature FLT93F for this product FL T93L Flow Switch Summary The FLT93F insertion type FlexSwitch for flow and temperature monitoring represents the first true technological breakthrough in thermal technology in over a decade. This product was designed for heavy industrial FLT93C environments including high temperatur-e and high pressure. FCI is the only thermal manufacturer providing temperature compensation to ensur*e set point accuracy for process temperatures that vary up to+/- 100° F. FSlOA The FLT93F offers fast response time and is suitable for small process connections. This product is easily field-configured or factory pr*eset, providrng unparalleled flexibility, accuracy and stability for all multiple process FS2000 sensing and switching requirements. For an operational demonstration of FCI's FLT93 FlexSwitch Series, please follow this lmk. FS2000H Applications II Pump protection
- Safety spray nozzle monitoring FS2000l II Cooling water/heat exchangers II Oil well system testing II Drain line flow II Relief valve monitoring 12-648 Specifications For Flow Service- Setpoint Range:
II Water-based Liquids: 0.01 to 3.0 fps [0.003 to 0.9 mps] fvlust be validated a Hydrocarbon-based Liquids: 0.01 to 5.0 fps [0.003 to 1.5 mps] Must be validated II Air/Gas: 0.25 to 120 sfps [0.08 to 37 smps] at standard conditions of 70° F [21.1 ° C] and 14.7 psi a [1.013 bar(g)]. Accuracy: (whichever reading is higher) II Liquids: +/- 0.5% reading or+/- 0.04 fps [+/- 0.012 mps] II Gases:+/- 0.5% reading or+/- 2 sfps [+/- 0.06 nmps] For Temperature Service: Accuracy:+/- 2° F [+/- 1 o C] Repeatability: +/- 1° F [ +/- 0.6° C] Response Time: As low as 0.5 seconds
Enclosure:
Powder coated aluminum enclosure is rated for hazardous location use Groups B, C, D, E, F and G, CENELEC EEx d IIC and resists the effects of weather and corrosion per NEfviA/CSA Type 4X (equivalent to IP66). Stainless steel is available as an option. Agency Approvals: FM, CSA, CENELEC, ATEX, CE Mark, T4 Rated (System Approval) and CR~J. Flow Element Materials of Construction: All-welded 316L stainless steel for all wetted surfaces. Hastelloy C, Monel 400 and Titanium are available as an option. Process Connection: II Standard: 0.75 inch male NPT. II Optional: 1 inch or 0.25 inch male NPT, flanges or retractable sensing element. Insertion Length: II 1.2 inch [30 mm] II 2 inches [51 mm]
- 4 inches [102 mm]
II 6 inches [152 mm] II 9 inches [229 mm] II 12 inches [305 mm] http://www.fluidcomponents.com/Industrial/Products/FlowSwitches/ProdFLT93F_FS.asp 3/29/2011 IPEC00270209
Flow S\vitch Model FLT93L - Inline Flexswitch I Fluid Components International (FCI) Page 2 of2 Iii 18 inches [ 457 mm] Customer specified lengths are available as an option. Operating Tempera'cure:
- Standard: *4° to +350° F [-20" to +177° C]
II Optional: -100° to +500° F [-73° to 7260° C] II Operating Pressure: To 3500 ps:g [2.40 bac(g)] Control Circuit Operating Temperature: -40° to +140° F [-40° to +60° C] Input Power: Field selectab e 115 +/- 15 Vac or 230 30 Vac (50/60Hz); 21 to 28 Vdc or 18 to 26 Vac; 7 watts maxi',~um. Relay Contacts: Field configurable dual SPDT or single DPDT rated 6 amps at 115 Vac, 240 Vac or 24 Vdc. Hermetcally sealed relays are available as an opt;or. Output Signal: Ana og DC voltage related to flow or level/interface signal and proportional to temoerature. Electrical Connection: 1 inch female NFT Remote Configuration: Availab'e as an opt'on with custe>mer specified intercornectmg cab e lengtr. Optional N.I.S.T. Flow Calibration Services Factory N.I.S.T. calibration ir air* or* v.:ater ava:lable as ar optoon customer spe:ified nt(s) or flow curve based on the media ranges specified above. Home About FCJ Products Applications ' Sales I News/Events I Sl!pport 1 Fluid Componerts All Rigrts Reserved Contact Us 2~ legal & Privacy Statements http://wv..w.fluidcomponents.com/Industrial/Products/FlowSwitches/ProdFLT93F_FS.asp 3/29/2011 IPEC0027021 0
Product Data Sheet 00813-0100-4001, Rev LA November 2010 Rosemount 3051 Rosemount 3051 Pressure Transmitter THE PROVEN INDUSTRY LEADER IN PRESSURE MEASUREMENT
- Best-in-Class petformance with up to 0.04%
reference accuracy
- Industry first installed five-year stability Unmatched Dynamic Petformance
- Coplanar' platform enables integrated pressure, flow, and level solutions
- Advanced PlantWeb Functionality to increase plant productivity
- ..;i CE Contents Setting the Standard for Pressure Measurement. ........................... page 2 Ordering Information Rosemount 3051C Coplanar Pressure Transmitter. . . . . . . . . . . . . . . . .... page 3 Rosemount 3051 T In-Line Pressure Transmitter ...................... page 10 Rosemount 3051 CF Flowmeter Series . . . . . . . ..................... page 14 Rosemount 3051 L Liquid Level Transmitter ......................... page 29 Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... page 35 Product Certifications. . . . . . . . . . . . . . . . . . . . . . . ....................... page 44 Dimensional Drawings. . . . . . . . . . . . . . . . . . . . . . . . . . .................... page 49 ROSEMOUNT" www.rosemount.com EMERSON . .
Process Management IPEC00270211
Product Data Sheet 00813-01 00-4001, Rev LA Rosemount 3051 November 2010 Setting the Standard for Pressure Measurement Proven best-in-class performance, reliability and safety Over 4 million installed Meet your application needs with extensive offering Real world total performance of +/-0.15% c;. Flow Reference accuracy of +/-0.04% I C::<'
* }li Pressure Maximize Installation Flexibility with Coplanar Platform
- Improve reliability and performance with integrated DP Flowmeters, DP Level and manifolds
- Easy installation with all solutions fully assembled. leak-tested and calibrated
- Meet your application needs with an unsurpassed offering .£~. *
;;;1-"t' Level r * . l' Unlock the Value of Devices with the Smart Wireless THUM' Adapter c.
- Gain access to field intelligence and improve quality, safety, availability,
...'. operations and maintenance costs
- Remotely manage devices and monitor health
- Enable new wireless measurement points
- Utilize existing loop power Innovative, Integrated DP Flowmeters
- Fully assembled and leak tested for out-of-the-box installation
- Reduce straight pipe requirements, lower permanent pressure loss and achieve accurate measurement in small line sizes
- Up to 1.65% volumetric flow accuracy at 8:1 turndown Proven, Reliable and Innovative DP Level Technologies
- Connect to virtually any process with a comprehensive offering of process connections, fill fluids, direct mount or capillary connections and materials
- Quantify and optimize total system performance with QZ option
- Operate at higher temperature and in vacuum applications
- Optimize level measurement with cost efficient Tuned-System rM Assemblies 7.
Instrument Manifolds- Quality, Convenient, and Easy t i
- Design and engineered for optimal performance with Rosemount transmitters Save installation time and money with factory assembly
- Offers a variety of styles, materials and configurations 2
IPEC00270212
Product Data Sheet 00813-0100-4001, Rev LA November 2010 Rosemount 3051 Rosemount 3051C Coplanar Pressure Transmitter Industry's best total performance, a flexible Coplanar platform, and installed
,e,~'
five-year stability has made Rosemount 3051 the standard for Differential, Gage, and Absolute pressure measurement. Select from the following capabilities for seamless integration:
- Performance up to 0"04% accuracy
" .'
- Manifolds, Primary Elements and Seal Solutions
- 4-20 rnA HART, 1-5 Vdc HART low power, FOUNDATION fieldbus, and Profibus PA protocols
- Calibrated spans/ranges from 0" 1 inH20 to 4000 psi (0,25 mbar to 276 bar) 3051C Coplanar Pressure Transmitter
- 316 SST, Alloy C-276, Alloy 400, Tantalum, Gold-Plated Alloy 400 or 316L SST wetted materials Additional Information Specifications: page 35 Certifications: page 44 Dimensional Drawings: page 49 Table 1" 3051C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. 3 IPEC00270213
Product Data Sheet 00813-0100-4001, Rev LA Rosemount 3051 November 2010 Table 1. 3051 C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. M Low-Power, 1-5 V de with Digital Signal Based on HART Protocol (See Option C2 for 0.8-3.2 V de)
. *****-~"~~~-*~-------
IVIQLCIICll<> Construction Process_~la~~e_Type Flange Material DrainNent
'-'LaiiUCU U Standard fi~~~
~00 2 Coplanar 3(3) Coplanar 4 Coplanar Alloy 400fK-500 *__ ___
-----~
5 Coplanar Plated CS SST
- 7(3) Coplanar SST Alloy C-276 8(3) Coplanar Plated CS Alloy C-276 0 Alternate Process Connection
- l;oVlClLIIIl:j ~
"""'"'" ... --~~---
Standard 2(3) 316L SST
- 3(3) Alloy C-276
- c:,
-Af"""~v~
4 Alloy400 Tantalum 1A ,,;l::~hl<> on 3051 CD and CG, Ranges 2-5 only. Not available on 3051 CA) 1-s. G<.,.u-,..*"'"u Alloy 400 (Us* in combination with O~ringOption Code B.)
*:., Gold-plated SST Standard Standard A Gl ""* PTFE B Gla..,,;it~:-filicu PTFE 1-- ----
Sensor Fill Fluid Standard Standard 1 Silicone
- 2 Inert (Differential and Gage only)
- Housing Material Conduit Entry Size Standard Standard A Aluminum %-14 NPT :
- B Aluminum M20 X 1.5
- r-J~- SST %-14 NPT
- iK SST M20x1.5 I * - ----
Expanded D Aluminum G% M SST G% FouNDATION fieldbus Advanced Control Function Block Suite Suite 4 IPEC00270214
Product Data Sheet 00813-01 00-4001, Rev LA November 201 0 Rosemount 3051 Table 1. 3051 C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. C-276 DrainNent 400/K-500 DrainNent Orifice CS Bolts 5 IPEC00270215
Product Data Sheet 00813-0100-4001, Rev LA Rosemount 3051 November 2010 Table 1. 3051 C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. 6 IPEC00270216
Product Data Sheet 00813-0100-4001, Rev LA November 2010 Rosemount 3051 Table 1. 3051 C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. Calibration Certificate Standard Standard Q4 Calibration Certificate *
"a<3- Calibration Certificate and GOST Verification Certificate *
'(ip- Calibration certification and tamper evident seal
- Material Traceability Certification Standard .................
Q8 Material Traceability Certification per EN 10204 3.1.B
- Quality Certification for Safety Standard Standard
-~~~J~~or-use certificate of FMEDA data
- Hardware Adjustments '
Standard <>**
~*~**w~*w J 1(16)(17) Local Zero Adjustment Only
- J3(16)(17) No Local Zero or Span Adjustment * *-----*-*
Transient Protection Terminal Block Standard <>**
~~"WUOW T1(18) Transient Protection Terminal Block
- Software Configuration Standard Standard C1(16) Custom Software Configuration (l;Omptetea CDS 00806-0100-4001 required with order)
- Low Power Output Expanded I~;
0.8-3.2 V de Output with Digital Signal Based on HART Protocol (Output Code M only) Standard Standard C3 Gage Calibration (Model 3051 CA4 only)
- Alarm Limit Standard ~t,.nrl::.;rl* .
16 C4< 16l?~-+~~:~~~~i;_~f~~~Compliant with NAMUR Recommendation NE 43, Alarm High
- CN< lC Compliant with NAMUR Recommendation NE 43. Alarm Low
- Pressure Testing FYn<'lnrl~rl P1 Hydrostatic Testing with Certificate Cleaning Process Area Expanded P2 C1eanmg for Special Service Cleaning for <1 PPM Chlorine/Fluorine .....
Pressure Calibration Expanded P4 ~..,;auorate at Line Pressure (Specify Q48 on order for correvfJVITdf;,l:! vv!t!!!vO!vJ Performance Standard ca,.nA::.r.-1
*~*
,_r=>a< 20 l _ j_~iil_h_r='erformance Option
- 7 IPEC00270217
Product Data Sheet 00813-0100-4001, Rev LA Rosemount 3051 November 2010 Table 1. 3051 C Coplanar Pressure Transmitters Ordering Information
*The Standard offering represents the most common options. The starred options(*) should be selected for best delivery.
The Expanded offering is subject to additional delivery lead time. Flange Adapters Standard Standard Without DrainNent Ports Standard Process Connection
-SST Standard
! 4500 psig (31 0 Static Pressure Limit Standard External Ground Screw Standard Surface finish certification for Toolkit Total System Performance Reports
**~**~*******~**************************************~****
Standard Conduit Electrical Connector
**~****************************************************************
Standard Standard (1) 3051CDO is available only with Output Code A, Process Flange Code 0 (Alternate Flange H2, H7, HJ, or HK), Isolating Diaphragm Code 2, 0-ring Code A, and Bolting Option L4. (2) Option code M4 LCD Display with Local Operator Interface required for local addressing and configuration. (3) Materials of Construction comply with recommendations per NACE MR0175/JSO 15156 for sour oil field production environments. Environmental limits apply to certain materials. Consult latest standard for details. Selected materials also conform to NACE MR0103 for sour refining environments. (4) Requires 0 code in Materials of Construction for A/female Process Connection. (5) Not valid with optional code P9 for 4500 psi Static Pressure. (6) Process Flange limited to Coplanar (codes 2, 3, 5, 7, 8) or Traditional (H2, H3, H7). (7) Not valid with optional code 09 for RC1/2 Adaptors. (8) Not valid for optional codes OF and 09 for Adaptors (9) "Assemble-to" items are specified separately and require a completed model number. (10) Available only with output codes A- 4-20 HART and F- FOUNDATION fieldbus. (11) Not available with Low Power code M. (12) Available only with 3051CD and 3051CG and output code A- 4-20 mA HART 8 IPEC00270218
Product Data Sheet 00813-01 00-4001, Rev LA November 201 0 Rosemount 3051 (13) Not available with Alloy C-276 isolator (3 code), tantalum isolator (5 code), all cast C-276 flanges, all plated CS flanges, all DIN flanges, all Level flanges, assemble-to manifolds (S5 and S6 codes), assemble-to seals (S1 and S2 codes), assemble-to primary elements (S3 and S4 codes), surface finish certification (016 code), and remote seal system report (QZ code). (14) Available only with output code W- Profibus PA. (15) Only available with HART 4-20 mA output (output code A). (16) Not available with Fieldbus (output code F) or Profibus (output code IN). (17) Local zero and span adjustments are standard unless Option Code J1 or J3 is specified (18) The T1 option is not needed with FISCO Product Certifications; transient protection is included in the FISCO product certification codes /A and IE. (19) NAMUR-Compliant operation is pre-set at the factory and cannot be changed to standard operation in the field. (20) High Performance Option includes 0.04% Reference Accuracy See Performance Specifications for details. (21) Not valid with Alternate Process Connection options S3, S4, S5, and S6. (22) Transmitter is shipped with 316 SST conduit plug (uninstalled) in place of standard carbon steel conduit plug. (23) Not available with Alternate Process Connection; DIN Flanges and Level Flanges. (24) The V5 option is not needed with the T1 option; external ground screw assembly is included with the T1 option. 9 IPEC00270219
Allen-Bradley I Rockwell Automation 1201 South Second Street Milwaukee, WI 53204-2496 USA Phone: (800) 230-4787 Contact Allen-Bradley I Rockwell Automation
- J' Request 2 Ouo:,
* ../ S2nd an Ern?il
* . / SL~Pf~-:;*!i:;(s \f/eb::::its Bulletin 836 Pressure Controls
- Operating ranges from 30 in. Hg vacuum ... 900 psi
- Independently adjustable range and differential
- Copper alloy and stainless steel bellows
- 7/16-20 S.A.E. and 1/4 in. N.P.T. connections
- Variety of contact blocks available
- Open Type, Type 1, Type 4& 13, Type 4X and Type 7&9 and 4& 13 combination enclosures Specifications Sensor Technology Mechanical Deflection Pressure Gauge Measurement Switch Point Range 98.24 to 900 psi Switch Characteristics Tech Electro-mechanical IPEC00270220
ENTERGY Conceptual Design
~ ~~~~~~:~.: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -018 Rev. 0 Attachment 4 Cost Estimate IPEC00270221
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP3-018 PROJECT TITLE: Install a Facility to Capture MSSV Discharge Steam and Remove ESTIMATOR: RCMT Fission Products.
JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE: TBD 00UTAGE 0NON-OUTAGE ORIGINATOR: 0CAPITAL 0o&M ORIG. DATE: 07/24/12
~_.----------~
ESTIMATE TOTAL $35,676,701 REVISION 11-0 Summary of Change: In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-018 in accordance with Entergy design engineering practices. For SAMA IP3-018, resolution is required to reduce the resulting consequences from a Steam Generator Tube Rupture (SGTR). This package will capture and route discharge from the Main Steam Safety Valves (MSSVs) through a structure where water will be used to condense the exhausted steam and remove potentialfission products. Prepared by: Approved by: Date: IPEC00270222
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL
- EC #: SAMA IP3-018 0CAPITAL 0o&t1
[J] Conceptual PROJECT TITLE: Install a Facility to Capture MSSV Discharge Steam and Remove FESTIMATOR: RCMT LJ Preliminary JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE: TBD u Definitive 0olffAGE 0 NON-OLffAGE ORIGINATOR ORIG. DATE: 07124112 Item Descriotion
- 1. This estimate assumes that this work will not require outage conditions to complete
- 3. This estimate assumes that Sheet Prodtuct for sidinq will be Installed bv Sheet Metal Craft Using Man lifts with assistance from a crane.
- 4. This estimate assumes that all work will be performed bv trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate provides for continuous fire watch durinq weldinq cutting and qrindinQ activities.
- 6. This estimate assumes training for 12 Plant Ops.Personnel.
- 7. This estimate assumes that the safety class for piping and valves and tanks will be Safety Class 1.
- 8. This estimate assumes that weld inspections will be for Safety Class 1 Piping.
The work in this estimate is non outage except for final connections to the steam lines and is assumed to occur in 2014 on a 4 day per week, 9. 1 o hour per day schedule. 10. This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost Estimate Classification Svstem (see Attachment 3, Reference 2).
- 11. Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide for anticipated billing rate increases of 3% per vear.
This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is 12. cumulative and progresses as follows: A Outside fence boundarv - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00270223
~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP3-018 PROJECT TITLE Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products. [J CAPITAL Do&M TAKEOFF JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS: []OUTAGE [J NON-OUTAGE I ORIGINATOR ORIG. DATE 07/24/12 MAN HOURS MATERIAL$ I MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT I NO. UNIT IFCTR TOTAL I $/MH PER UNIT I DOLLARS DOLLARS CONTRACT TOTAL$
*ESTIMATE LEVEL* ESTIMATE
SUMMARY
~ Conceptual MANHOURS DOLLARS ~ Preliminary ENGINEERING "0 Definitive 01 STUDY, DESIGN, & CLOSEOUT 1,600 $ 160,000 02 DESIGN ENGR CONST SUPPORT 200 $ 20,000 General Notes: 03 MODS ENGR SUPPORT $ 04 SYS ENGR/ S-U ENGR 220 $ 22,000 05 PROJECT MANAGEMENT 900 $ 108,000 06 TESTING (Calibration & Testing) 160 $ 16,000 07 ENGINEERING DCP ACCEPTANCE REVIEW 200 $ 20,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 7,800 $ 936,000 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 960 $ 96,000 11 OSG FIELD ENGRS I PLANNERS 800 $ 96,000 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 7,432,190 13 OTHER CONTRACTS $ 180,000 CONTRACT CRAFT LABOR 14 SWEC CRAFT LABOR/WALKDOWN 37,920 $ 4,152,773 15 LOST TIME 3,792 $ 531,600 16 SWEC DISTRIBS $ 1,167,945 PLANT CRAFT LABOR 17 MECH MAl NT. $ 18 ELECT MAINT $ 19 I&C 120 $ 12,000 20 CSG $ MISC SUPPORT 21 QUALITY CONTROL 600 $ 60,000 22 PLANNING & SCHEDULING $ 23 TRAINING 72 $ 8,640 24 CHEMISTRY 40 $ 4,000 25 OPS 200 $ 24,000 26 HP/RP 40 $ 3,182 MISC CONTRACT SUPPORT 27 QUALITY CONTROL 720 $ 57,600 28 NDE 120 $ 10,184 29 HP/RP 20 $ 1,591 30 RADWASTE $ 31 NURSE $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL $ 50,000 36 VENDOR STOCKING $ 25,000 37 DECONTAM INATl ON CONTRACTOR $ 38 RBC'S $ 39 SECURITY $ 40 FIRE WATCH (Rover) $ 41 SAFETY 761 $ 51,748 CONTINGENCY 42 CONTINGENCY $ 7,623,227 ESTIMATE SUBTOTAL 57,245 $ 22,869,680 SITE ENCUMBRANCE PREMIUM (20%) $ 4,573,936 LOADERS (30%) $ 8,233,085 ESTIMATE TOTAL $ 35,676,701 Non-Outage Work Protect existing infrastructure
- 1. Gather and stage tools and materials 1 LT LB 2 20.00 100 40 $ 78.15 $0 $ 3,126 $ 3,126
- 2. Gather and stage tools and materials 1 LT IW 4 20.00 100 80 $137.33 $ 10,000.00 $10,000 $ 10,986 $ 20,986
- 3. Perform walkdown of work area. 1 LT LB 2 1000 100 20 $ 78.15 $0 $ 1,563 $ 1,563
- 4. Perform walkdown of work area. 1 LT OP 1 1000 100 10 $115.00 $0 $ 1,150 $ 1,150
- 5. Perform walkdown of work area. 1 LT IW 5 1000 100 50 $137.33 $ 6,867 $ 6,867
- 6. Erect barriers, platforms, walkways, stairs, supports 1 LT IW 5 80.00 100 400 $137.33 $ 54,932 $ 54,932 Erect barriers, platforms, walkways, stairs, supports 1 LT OP 1 80.00 100 80 $115.00 $ 9,200 $ 5,000 $ 14,200
- 7. Erect barriers, platforms, walkways, stairs, supports 1 LT LB 2 80.00 100 160 $ 78.15 $ 12,504 $ 12,504 Tie Into City Water
- 1. Excavate to existing City Water Line 1 LT OP 1 32.00 100 32 $115.00 $ $ 3,680 $ 3,680
- 2. Excavate to existing City Water Line 1 LT LB 2 32.00 100 64 $ 78.15 $ $ 5,002 $ 5,002
- 3. Perform tie in to existing City Water line 1 LT PF 3 40.00 100 120 $120.71 $ 5,000.00 $ 5,000 $ 14,485 $ 19,485
- 4. Backfill and compact excavation 1 LT OP 1 20.00 100 20 $115.00 $ $ 2,300 $ 2,300
- 5. Backfill and compact excavation 1 LT LB 2 20.00 100 40 $ 78.15 $ $ 3,126 $ 3,126 IPEC00270224
~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP3-018 PROJECT TITLE Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products. [J CAPITAL Do&M TAKEOFF JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS: []OUTAGE [J NON-OUTAGE I ORIGINATOR ORIG. DATE 07/24/12 MAN HOURS MATERIAL$ I MATERIAL LABOR SUB-ITEJ DESCRIPTION QTY UOM CFT I NO. UNIT IFCTR TOTAL I $/MH PER UNIT I DOLLARS DOLLARS CONTRACT TOTAL$ Slowdown Vessel Supports Excavate, form and pour Slowdown Vessel Support 1. piers 1 LT OP 1 120.00 100 120 $115.00 $0 $ 13,800 $ 10,000 $ 23,800 Excavate, form and pour Slowdown Vessel Support 2. piers 1 LT LB 3 120.00 100 360 $ 78.15 $ 6,000.00 $6,000 $ 28,134 $ 34,134 Excavate, form and pour Slowdown Vessel Support 3. piers 1 LT CP 2 80.00 100 160 $ 96.00 $0 $ 15,360 $ 15,360 Obtain and erect steel support structure for vessel 3. support and enclosure siding. 1 LT IW 5 200.00 100 1,000 $137.33 $ 353,000.00 $353,000 $ 137,330 $ 490,330 Obtain and erect steel support structure for vessel 4. support and enclosure siding. 1 LT OP 2 200.00 100 400 $115.00 $0 $ 46,000 $ 30,000 $ 76,000 Set Slowdown Vessels
- 1. Perform walkdown of work area. 1 LT BM 5 1000 100 50 $130.83 $0 $ 6,542 $ 6,542
- 2. Perform walkdown of work area. 1 LT OP 2 1000 100 20 $115.00 $0 $ 2,300 $ 2,300
- 3. Obtain and Set (4) ASME Pressure Vessels. 4 LT BM 5 100 00 100 2,000 $130.83 $ 500,000.00 $2,000,000 $ 261,660 $ 2,261,660
- 4. Obtain and Set (4) ASME Pressure Vessels. 4 LT OP 2 50.00 100 400 $115.00 $0 $ 46,000 $ 25,000 $ 71,000
- 5. Clean Up and Restore Area/De mob 1 LT BM 5 20.00 100 100 $130.83 $0
- 6. Clean Up and Restore Area/De mob 1 LT OP 2 20.00 100 40 $115.00 $0 Excavate and Pour Piping Support Piers
- 1. Perform walkdown of work area. 1 LT LB 6 1000 100 60 $ 78.15 $0 $ 4,689 $ 4,689
- 2. Perform walkdown of work area. 1 LT CP 3 1000 100 30 $ 96.00 $ 2,880 $ 2,880
- 3. Perform walkdown of work area. 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 1,150
- 4. Gather and stage tools and materials 1 LT LB 6 20.00 100 120 $ 78.15 $ 20,000.00 $10,000 $ 9,378 $ 19,378
- 5. Gather and stage tools and materials 1 LT CP 3 20.00 100 60 $ 96.00 $ 4,000.00 $4,000 $ 5,760 $ 9,760
- 6. Gather and stage tools and materials 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 5,000 $ 6,150
- 7. Excavate, form and pour Piping Support piers 1 LT LB 6 200.00 100 1,200 $ 78.15 $ 93,780 $ 93,780
- 8. Excavate, form and pour Piping Support piers 1 LT CP 3 200.00 100 600 $ 96.00 $ 57,600 $ 57,600
- 9. Excavate, form and pour Piping Support piers 1 LT OP 1 200.00 100 200 $115.00 $ 23,000 $ 23,000
- 10. Clean Up and Restore Area/De mob 1 LT LB 6 20.00 100 120 $ 78.15 $ 9,378 $ 9,378 11 Clean Up and Restore Area/De mob 1 LT CP 3 20.00 100 60 $ 96.00 $ 5,760 $ 5,760
- 12. Clean Up and Restore Area/De mob 1 LT OP 1 20.00 100 20 $115.00 $ 2,300 $ 2,300 Erect Yard Area Pipe Supports From MSSV Slowdown Pipes to New Vessels
- 1. Perform walkdown of work area. 1 LT IW 5 1000 100 50 $137.33 $ 6,867 $ 6,867
- 2. Perform walkdown of work area. 1 LT LB 2 1000 100 20 $ 78.15 $ 1,563 $ 1,563
- 3. Perform walkdown of work area. 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 1,150
- 4. Gather and stage tools and materials 1 LT IW 5 20.00 100 100 $137.33 $ 13,733 $ 13,733
- 5. Gather and stage tools and materials 1 LT LB 2 20.00 100 40 $ 78.15 $ 3,126 $ 3,126
- 6. Gather and stage tools and materials 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 10,000 $ 11,150
- 7. Erect Piping Supports 1 LT IW 5 200.00 100 1,000 $137.33 $90,000 $ 137,330 $ 227,330
- 8. Erect Piping Supports 1 LT LB 2 200.00 100 400 $ 78.15 $ 31,260 $ 31,260
- 9. Erect Piping Supports 1 LT OP 1 200.00 100 200 $115.00 $ 23,000 $ 23,000
- 10. Prime and paint Pipe supports 1 LT PT 4 80.00 100 320 $ 95.16 $4,000 $ 30,451 $ 34,451 (OUTAGE) Prep, Install and Weld 14" Blow Down Pipe from Existing Pipe to New Vessels
- 1. Perform walkdown of work area. 1 LT PF 6 1000 1.70 102 $120.71 $ 12,312 $ 12,312
- 2. Perform walkdown of work area. 1 LT OP 1 1000 1.70 17 $115.00 $ 1,955 $ 1,955
- 3. Perform walkdown of work area. 1 LT CP 4 1000 1.70 68 $ 96.00 $ 6,528 $ 6,528
- 4. Gather and stage tools and materials 1 LT PF 6 20.00 1.70 204 $120.71 $ 2,000,000.00 $2,000,000 $ 24,625 $ 2,024,625
- 5. Gather and stage tools and materials 1 LT OP 1 1000 1.70 17 $115.00 $ 1,955 $ 1,955
- 6. Gather and stage tools and materials 1 LT CP 4 20.00 1.70 136 $ 96.00 $ 13,056 $ 13,056
- 7. Erect Scaffolding as Required 4 LT CP 4 80.00 1.70 2,176 $ 96.00 $ 208,896 $ 208,896
- 8. Erect Scaffolding as Required 4 LT LB 2 80.00 1.70 1,088 $ 78.15 $ 85,027 $ 85,027 Cut, Fit and Weld Piping from existing MSSV Stack 9.
Pipes to New Slowdown Vessel Nozzles (5 Pipes). 4 LT PF 6 140.00 1.70 5,712 $120.71 $ 110,000.00 $440,000 $ 689,496 $ 50,000 $ 1,179,496
- 10. Prime and Paint and touch up 14' Pipe 4 LT PT 4 40.00 1.70 1,088 $ 95.16 $ 6,000.00 $24,000 $ 103,534 $ 127,534 11 Remove Scaffolding and Store 4 LT CP 4 40.00 1.70 1,088 $ 96.00 $ 104,448 $ 104,448
- 12. Remove Scaffolding and Store 4 LT LB 2 40.00 1.70 544 $ 78.15 $ 42,514 $ 42,514 Install Spray/Recirc Pump, Piping and Related Hardware
- 1. Perform walkdown of work area. 1 LT MW 2 1000 100 20 $134.00 $ 2,680 $ 2,680
- 2. Perform walkdown of work area. 1 LT PF 6 1000 100 60 $120.71 $ 7,243 $ 7,243
- 3. Perform walkdown of work area. 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 1,150
- 4. Gather and stage tools and materials 1 LT MW 2 20.00 100 40 $134.00 $ 5,360 $ 5,360
- 5. Gather and stage tools and materials 1 LT PF 6 20.00 100 120 $120.71 $ 14,485 $ 14,485
- 6. Gather and stage tools and materials 1 LT OP 1 1000 100 10 $115.00 $ 1,150 $ 5,000 $ 6,150
- 7. Install the Spray/Recirc Pump on the platform. 4 LT MW 2 1000 100 80 $134.00 $ 25,000.00 $100,000 $ 10,720 $ 110,720
- 8. Install the Spray/Recirc Pump on the platform. 4 LT OP 1 5.00 100 20 $115.00 $0 $ 2,300 $ 2,300
- 9. Install, Fit and Weld 8" Drain Line and Valve 4 LT PF 2 40.00 100 320 $120.71 $ 78,000.00 $312,000 $ 38,627 $ 350,627 Install, Fit and Weld 4" Recirc line from Pump to 10.
Vessel Spray Nozzle connection, including Valves. 4 LT PF 2 20.00 100 160 $120.71 $ 68,750.00 $275,000 $ 19,314 $ 294,314 Install, Fit and Weld 4" Recirc line from Pump Inlet to 11 Vessel recirc. connection, including Valves. 4 LT PF 2 16.00 100 128 $120.71 $ 68,750.00 $275,000 $ 15,451 $ 290,451 Install, Fit and Weld 4" Pipe from City Water previous! 12. installed to new tee in Pump Suction Line. 4 LT PF 2 8.00 100 64 $120.71 $ 20,000.00 $80,000 $ 7,725 $ 87,725 Install Fit and Weld 1" lines and Install instrument
- 13. isolation vavles for sample, relief valve , Level and Pressure Switch. 4 LT PF 2 12.00 100 96 $120.71 $ 20,000.00 $80,000 $ 11,588 $ 91,588 Install and tie in Level Transmitter, Relief Valve, 14.
Pressure and Flow Switches. 4 LT PF 2 20.00 100 160 $120.71 $ 100,000.00 $400,000 $ 19,314 $ 419,314
- 15. Clean up Area 1 LT PF 6 1000 100 60 $120.71 $ 7,243 $ 7,243 IPEC00270225
~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP3-018 PROJECT TITLE Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products. [J CAPITAL Do&M TAKEOFF JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS: []OUTAGE [J NON-OUTAGE I ORIGINATOR ORIG. DATE 07/24/12 MAN HOURS MATERIAL$ I MATERIAL LABOR SUB-ITEJ DESCRIPTION QTY UOM CFT I NO. UNIT IFCTR TOTAL I $/MH PER UNIT I DOLLARS DOLLARS CONTRACT TOTAL$ Install Conduit, Cable, Power Supply and Local Controllers and Make Connections to Switches/Transmitters
- 1. Perform walkdown of work area. 1 LT EL 4 1000 100 40 $123.32 $0 $ 4,933 $ 4,933
- 2. Gather and stage tools and materials 1 LT EL 4 20.00 100 80 $123.32 $0 $ 9,866 $ 9,866
- 3. Install Hoffman Junction Box with Terminal Blocks 4 LT EL 2 20.00 100 160 $123.32 $ 3,000.00 $12,000 $ 19,731 $ 31,731 Install Hoffman Panel, then Install loop power supply 4.
and local controler in the panel. 1 LT EL 2 20.00 100 40 $123.32 $ 12,000.00 $12,000 $ 4,933 $ 16,933 Run and Support Conduit from Flow Switches to each 5. new Hoffman Box 4 LT EL 2 80.00 100 640 $123.32 $ 50,000.00 $200,000 $ 78,925 $ 278,925 Pull Cable from flow switches to Hoffman boxes and 6. terminate. 4 LT EL 2 80.00 100 640 $123.32 $ 4,000.00 $16,000 $ 78,925 $ 94,925 Run and Support Conduit from Junction Boxes to new 7. Hoffman panel. 4 LT EL 2 80.00 100 640 $123.32 $ 12,000.00 $48,000 $ 48,000 Install and connect wiring from Junction boxes to 8. Hoffman Panel. 1 LT EL 2 40.00 100 80 $123.32 $ 6,000.00 $6,000 $ 9,866 $ 15,866 Run and support conduit from level and pressure 9. switches to new Hoffman Panel. 4 LT EL 2 80.00 100 640 $123.32 $ 12,000.00 $48,000 $ 78,925 $ 126,925 Pull Cable from Level and Pressure switches to new 10. Hoffman Panel and terminate. 4 LT EL 2 60.00 100 480 $123.32 $ 6,000.00 $24,000 $ 59,194 $ 83,194 Route and support Conduit from the Pump and valves 11 to the new Hoffman Panel. 4 LT EL 2 80.00 100 640 $123.32 $ 78,925 $ 78,925 Install and connect wiring from Pump and valves to 12. new Hoffman Panel. 4 LT EL 2 60.00 100 480 $123.32 $ 59,194 $ 59,194 Erect Scaffolding to support Electrical work of cable, 13. conduit and box installations. 1 LT CP 4 80.00 100 320 $ 96.00 $ 30,720 $ 30,720 Erect Scaffolding to support Electrical work of cable, 14. conduit and box installations. 1 LT LB 2 80.00 100 160 $ 78.15 $ 12,504 $ 12,504
- 15. Remove/dismantle and store Scaffolding 1 LT CP 4 40.00 100 160 $ 96.00 $ 15,360
- 16. Remove/dismantle and store Scaffolding 1 LT LB 2 40.00 100 80 $ 78.15 $ 6,252
- 17. Support testing and calibration as required 1 LT EL 2 40.00 100 80 $123.32 $0 $ 9,866 $ 9,866
- 18. Clean-up area and restore 1 LT EL 4 20.00 100 80 $123.32 $0 $ 9,866 $ 9,866
- 19. Clean-up area and restore 1 LT LB 2 20.00 100 40 $ 78.15 $0 $ 3,126 $ 3,126 Install New MCC Extension and 480/120
- 1. Perform walkdown of work area and job brief 1 LT EL 3 1000 100 30 $123.32 $0 $ 3,700 $ 3,700
- 2. Perform walkdown of work area and job brief 1 LT OP 1 1000 100 10 $115.00 $0 $ 1,150 $ 1,150
- 3. Gather Materials and tools and transport to areas 1 LT EL 3 20.00 100 60 $123.32 $ 14,000.00 $14,000 $ 7,399 $ 21,399
- 4. Gather Materials and tools and transport to areas 1 LT OP 1 20.00 100 20 $115.00 $0 $ 2,300 $ 5,000 $ 7,300 Install New MCC extension in Unit 3 Turbine bldg at 5.
Elev. 15' at existing MCC312A 1 LT EL 3 20.00 100 60 $123.32 $0 $ 7,399 $ 7,399 Power new MCC Extension from Existing MCC 312A 6. 1 LT EL 3 1000 100 30 $123.32 $0 $ 3,700 $ 3,700 Install New 480/120V Transformer in MSSV building 7. on intermediate platform 1 LT El 3 1000 100 30 $123.32 $0 $ 3,700 $ 3,700 Install New 480/120V Transformer in MSSV building 8. on intermediate platform 1 LT OP 1 5.00 100 5 $115.00 $0 $ 575 $ 575 Erect scaffolding as required to support conduit/cable 9. installation. 1 LT CP 4 40.00 100 160 $ 96.00 $0 $ 15,360 $ 15,360 Erect scaffolding as required to support conduit/cable 10. installation. 1 LT LB 2 40.00 100 80 $ 78.15 $0 $ 6,252 $ 6,252 Install and Support Conduit from new MCC extension 11 to new Transformer 1 LT EL 3 50.00 100 150 $123.32 $0 $ 18,498 $ 18,498 Pull Cable from new MCC extension to new 12. Transformer and connect. 1 LT EL 3 15.00 100 45 $123.32 $0 $ 5,549 $ 5,549 Run local conduit from new transformer to equipment 13. as required. 1 LT EL 3 20.00 100 60 $123.32 $0 $ 7,399 $ 7,399 Pull cable from new transformer to equipment as 14. required and terminate. 1 LT EL 3 20.00 100 60 $123.32 $0 $ 7,399 $ 7,399
- 15. Dismantle and Store Scaffolding. 1 LT CP 4 20.00 100 80 $ 96.00 $0 $ 7,680 $ 7,680
- 16. Dismantle and Store Scaffolding. 1 LT LB 2 20.00 100 40 $ 78.15 $0 $ 3,126 $ 3,126 SIDING, ROOFING AND BUILDING UTILITIES INSTALLATION
- 1. Perform walkdown of work area and job brief 1 LT SM 4 1000 100 40 $106.94 $0 $4,278 $4,278
- 2. Perform walkdown of work area and job brief 1 LT OP 1 1000 100 10 $115.00 $0 $1,150 $1,150
- 3. Gather Materials and tools and transport to areas 1 LT SM 4 30.00 100 120 $106.94 $120,000.00 $120,000 $12,833 $132,833
- 4. Gather Materials and tools and transport to areas 1 LT OP 1 30.00 100 30 $115.00 $0 $3,450 $25,000 $28,450
- 5. Install Siding on Tank Support Structure 1 LT SM 4 250 100 1000 $106.94 $0 $106,940 $106,940
- 6. Install Siding on Tank Support Structure 1 LT OP 1 250 100 250 $115.00 $0 $28,750 $28,750
- 7. Install Sheet metal roofing 1 LT RF 4 60 100 240 $ 87.92 $20,000.00 $20,000 $21,101 $41,101
- 8. Support Roofing Installation and Bldg. Elec. Work. 1 LT OP 1 80 100 80 $115.00 $0 $9,200 $10,000 $19,200
- 9. Install Unit Heaters 1 LT EL 3 20 100 60 $123.32 $11,500.00 $11,500 $7,399 $18,899
- 10. Install Exhaust fans with dampers 1 LT EL 3 20 100 60 $123.32 $4,000.00 $4,000 $7,399 $11,399 11 Install Lighting 1 LT EL 3 20 100 60 $123.32 $4,000.00 $4,000 $7,399 $11,399
- 12. Demob and clean area 1 LT EL 3 20 100 60 $123.32 $7,399 $7,399
- 13. Demob and clean area 1 LT SM 4 20 100 80 $106.94 $8,555 $8,555
- 14. Demob and clean area 1 LT OP 1 20 100 20 $115.00 $2,300 $2,300 IPEC00270226
~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP3-018 PROJECT TITLE: Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products. [J CAPITAL Do&M TAKEOFF JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS: []OUTAGE [J NON-OUTAGE I ORIGINATOR ORIG. DATE 07/24/12 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ PAINTING & TOUCH-UP REQUIREMENTS $
- 1. PAINTING & TOUCH-UP 1 LT PT 4 160.00 1.00 640 $ 95.16 $4,000 $ 60,902 $ 64,902
- 2. PAINTING & TOUCH-UP PT $ $
FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 600.00 100 600 $ 53.60 $ 32,160 $ 32,160
- 2. CRAFT SUPPORT FOR BOTTLE WATCH $
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ $
SUBTOTAL CRAFT & SUB-CONTRACTOR 33,744 $ 3,673,000.00 $7,011,500 $3,604,710 $ 180,000 $10,796,210
- 1. CONSTRUCTION SUPPORT (8% OF LABOR $) 1 LT 2,700 $106.83 $ 288,441 $ 288,441 SUBTOTAL 36,444 $ 7,011,500 $3,893,151 $ 180,000 $11,084,651
*RELATED COSTS*
- 1. WALKDOWN ALLOWANCE $ $
WALKDOWN ALLOWANCE $ $
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT PF 100 $120.71 $ 12,071 $ 12,071 2a. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT EL 100 $123.32 $ 12,332 $ 12,332
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 1,276 $123.32 $ 157,356 $ 157,356
- 4. GENERAL CRAFT DISTRIBS. (1 0%) $ 389,315 $ 389,315
- 5. CRAFT IN PROCESSING (20%) $ 778,630 $ 778,630
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 77,863 $ 77,863
- 7. (1/2 day training, or- 2%)
SUBTOTAL 37,920 $ 7,011,500 $5,320,718 $ 180,000 $12,512,218 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ $ $
PL $ $ $ SUBTOTAL MECH MAINT. $ $ $ $
- 1. ELECT MAINTENANCE PL $ $ $
PL $ $ $ SUBTOTAL ELECT. MAINT. $ - $ $ $
- 1. I&C (Dev. Instrument Calibration Procedures) 1 LT PL 1 120.00 100 120 $100 00 $ $ 12,000 $ 12,000 PL $ $ $
SUBTOTAL I&C MAINT. 120 $ - $ 12,000 $ $ 12,000
- 1. CSG PL $ $ $
PL $ $ $ SUBTOTAL CSG MAINT. $ - $ $ $ SUBTOTAL PLANT 120 $ $ 12,000 $ $ 12,000 SUBTOTAL CRAFT/PLANT 38,040 $ 7,011,500 $5,332,718 $ 180,000 $12,524,218 IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING 1 LT NM $ $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 200.00 100 200 $100 00 $ 20,000 $ 20,000
- 3. SYSTEMS ENGINEERING- MECHANICAL 1 LT NM 1 40.00 100 40 $100 00 $ 4,000 $ 4,000
- 4. SYS ENGINEERING- ELECTRICAL 1 LT NM 1 40.00 100 40 $100 00 $ 4,000 $ 4,000
- 5. SYS ENGINEERING -INSTR & CONTROL 1 LT NM 1 60.00 100 60 $100 00 $ 6,000 $ 6,000
- 6. SYS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 80.00 100 80 $100 00 $ 8,000 $ 8,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 900.00 100 900 $120.00 $ 108,000 $ 108,000
- 8. TRAINING (OPS Staff) 1 LT NM 12 6.00 100 72 $120.00 $ 8,640 $ 8,640
- 9. QA I QC VERIFICATION 1 LT NM 1 600.00 100 600 $100 00 $ 60,000 $ 60,000
- 10. PLANNING & SCHEDULING 1 LT NM 1 $ $
11 HP I RP/ ALARA 1 LT NM 1 40.00 100 40 $ 79.56 $ 3,182 $ 3,182
- 12. CHEMISTRY 1 LT NM 1 40.00 100 40 $100 00 $ 4,000 $ 4,000
- 13. OPS (DEVELOP/REVISE PROCEDURE(S)) 1 LT NM 1 200.00 100 200 $120.00 $ 24,000 $ 24,000
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
IPEC00270227
~ INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0 EC #: SAMA IP3-018 PROJECT TITLE: Install a Facility to Capture MSSV Discharge Steam and Remove Fission Products. [J CAPITAL Do&M TAKEOFF JOB LOCATION: Yard North and East of MSSV Vent Stacks PROJECT CODE TBD ESTIMATOR RCMT EST. STATUS: []OUTAGE [J NON-OUTAGE I ORIGINATOR ORIG. DATE 07/24/12 MAN HOURS MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$ CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lncl Per Diem) LT NM $ $
- 2. MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 960.00 100 960 $100 00 $ 96,000 $ 96,000
- 3. OSG FIELD ENGRS/PLAN- SWEC(Incl Per Diem) 1 LT NM 1 800.00 100 800 $120.00 $ 96,000 $ 96,000
- 4. QA I QC VERIFICATION 1 LT NM 1 720 00 100 720 $ 80.00 $ 57,600 $ 57,600
- 5. NDE 1 LT NM 1 120.00 100 120 $ 84.87 $ 10,184 $ 10,184
- 6. HP/RP 1 LT NM 1 20.00 100 20 $ 79.56 $ 1,591 $ 1,591
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM 11 HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR-Crane 1 LT NM 1 $ 50,000
- 13. EQUIPMENT RENTAL CONTRACTOR-Welding 1 LT NM 1 $ 25,000
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM
- 16. SECURITY 1 LT SEC
- 17. FIRE WATCH (Rover) 1 LT NM $ $
- 18. SAFETY (2%) 1 LT NM 761 $ 68.00 $ 51,748 $ 51,748
- 19. LOST TIME (10%) 1 LT 3,792 $140.19 $ 531,600 $ 531,600 SUBTOTAL CRAFT/NON-MANUAL 47,485 $ 7,011,500 $6,502,263 $ 180,000 $13,693,763
- 3. FREIGHT, SALES TAX, & CONSUMABLES (6%) $ 420,690 $ 420,690 SUBTOTAL INSTALLATION COST 47,485 $ 7,432,190 $6,502,263 $ 180,000 $14,114,453
- 1. DESIGN ENGINEERING- MECHANICAL 1 LT NM 2 200.00 100 400 $100 00 $ 40,000 $ 40,000
- 2. DESIGN ENGINEERING- ELECTRICAL 1 LT NM 2 200.00 100 400 $100 00 $ 40,000 $ 40,000
- 3. DESIGN ENGINEERING- INSTR & CONTROL 1 LT NM 2 200.00 100 400 $100 00 $ 40,000 $ 40,000
- 4. DESIGN ENGINEERING- CIVIL/STRUCTURAL 1 LT NM 2 200.00 100 400 $100 00 $ 40,000 $ 40,000
- 5. TESTING (Instrument Calibration and testing) 1 LT NM 2 80.00 100 160 $100 00 $ 16,000 $ $ 16,000
- 6. CONTRACT ENGR DESIGN SUPPORT (CALCULATIONS AND ELECTRICAL LOAD STUDY) 1 LT NM 3 2,600.00 100 7,800 $120.00 $ 936,000 $ 936,000
- 7. ENGINEERING DCP ACCEPTANCE REVIEW 1 LT NM 4 50.00 100 200 $100 00 $ 20,000 $ 20,000 SUBTOTAL DESIGN COST 9,760 $ 176,000 $ 936,000 $ 1,132,000 SUBTOTAL INSTALLATION & DESIGN COST $6,678,263 $ 1,116,000 $15,246,453
- 1. CONTINGENCY (50%) $ 7,623,227 ESTIMATE SUBTOTAL 57,245 $22,869,680 IPEC00270228
ENTERGY Conceptual Design
~ ~;,~~,~~~2!,~: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 3 CONCEPTUAL DESIGN PACKAGE For SAMA IPJ-019 Install Leak Monitoring Instrumentation for ISLOCA Pathway Isolation Valves Prepare4/;Ld ~
44 Approved by: Date: Pagel of6 IPEC00270229
ENTERGY Conceptual Design
~ ~~~~.~~~:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of6 IPEC00270230
ENTERGY Conceptual Design
~;;~~~~~:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP3-019:
Install Leak Monitoring Instrumentation for ISLOCA Pathway Isolation Valves
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-019 in accordance with Entergy design engineering practices. For SAMA IP3-019, resolution is required to provide remote monitoring of any potential fluid leakage past the isolation valves in ISLOCA pathways. This package will provide the piping connections and transmitters required to interface with the monitoring instrumentation located outside containment. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. Page3of6 IPEC00270231
ENTERGY Conceptual Design
~ ~~~"~~~~~~'~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 3.0 EXISTING CONDITIONS In containment, the pathways of the Safety Injection (SI) System piping need to be monitored for potential leaks of liquid from the interfacing Reactor Cooling System (RCS) and Auxiliary Cooling System (ACS) piping. There are 32 check valves and 2 motor operated valves (MOV) installed in the Sl piping that interface with these systems to provide this isolation.
In each ISLOCA pathway there are redundant "blocking valves" that provide isolation from interfacing systems. The effectiveness of the valves blocking function to provide an isolation boundary needs to be monitored. 4.0 DESIGN CONSIDERATIONS Check Valve Pathways Each of the "blocked" piping sections within an isolation boundary has an existing piping connection that may be adapted as a monitoring point. (Ref. Attachment 2- Figure 2- all sheets) MOV Pathway The "blocked" piping section within this isolation boundary will require modification of piping to include a connection that can be adapted as a monitoring point. (Ref. Attachment 2 - Figure 2 - sheet 1) Monitoring for pressure change within each of the isolated boundaries will need to be transmitted to a remote location outside containment. 5.0 CONFIRMATION OF DESIGN There are fifteen (15) separate ISLOCA paths with blocked isolation boundaries that potentially can allow fluid to leak by. As stated above, there are proposed connections located in each piping path for a sensing device to be applied to monitor them. Installation of a pressure transmitter at each of these piping connections will provide the means of measuring changes within an isolation boundary. In addition, the transmitter will enable this information to be electronically transmitted to a location outside containment for remote display and monitoring. Page 4 of6 IPEC00270232
ENTERGY Conceptual Design
~ ~?~.~'~'~2~:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0
- 6. RECOMMENDED SOLUTION
- 1. Check Valves A. For each isolation boundary listed in Attachment 2, Figure 1, perform the following:
- At the existing piping connection install small bore pipe, instrument root valves, instrument tubing, pressure transmitter and required supports.
- 2. MOVs
- For the isolation boundary listed in Attachment 2, Figure 1, perform the following:
- Within the "blocked" piping section that forms the isolation boundary, install a new connection to be adapted as a monitoring point.
- At the piping connection install small bore pipe, instrument root valves, instrument tubing, pressure transmitter and required supports.
- 3. Remote Leakage Monitoring Install new instrumentation outside containment, to display leakage data for each isolation boundary listed in Attachment 2, Table 1.
- 4. Conduit and Wiring A. Transmitters
- Route and support conduit from each transmitter to the two new junction boxes fitted with terminal blocks located in containment.
- Route and support a single conduit from each junction box, via containment penetration, to the new ISLOCA leak status monitoring panel outside containment.
- Install and connect wiring from the pressure transmitters to the new junction boxes.
- Install and connect wiring from the junction boxes to the new ISLOCA leak status monitoring panel.
B. Remote Leakage Monitor Panel
- Route and connect 120VAC power supply to the new monitor panel located in the Control Building at Elevation 33'- 0".
- 5. Provide procedures and training to operate, test, and perform maintenance on the components of the newly installed system.
Page5of6 IPEC00270233
ENTERGY Conceptual Design
~ ~::.~~.~~~~.~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. Rosemount 1153 Series D Alphaline Nuclear 15 Pressure Transmitter
- 2. Valve -Valve Manifold 15
- 3. Yokogawa - DXAdvanced R4 - DX2000 Recorder 1
- 4. Loop Power- Power Supply 1
- 5. Hoffman Junction Box with terminal blocks 2
- 6. Hoffman Wall Mounted Panel and enclosure, with 1 terminal blocks, 36" x 36" x 16"
- 7. Instrument Tubing- 0.375" x 0.065-316 SS Tubing 1500 Feet
- 8. 1" - Conduit 450 Feet
- 9. 2" - Conduit 350 Feet
- 10. Two Pair- Twisted Shielded Pair Cable 350 Feet
- 11. Eight Pair- Twisted Shielded Pair Cable 1100 Feet
- 12. 2/c Cable 100 Feet
- 13. %" -1500# Socket Weld Globe Valve 46 CONVAL Model No. 12G3J-3163D or equal
- 14. %"Schedule 160 Seamless Pipe, A376 Type 316 80 Feet
- 15. %"-6000# Socket Weld Tee, A182 F316 15
- 16. %"-6000# Screwed Cap, A182 F316 15
- 17. %"-6000# Sockolet, A 182 F316 1 Page 6 of6 IPEC00270234
ENTERGY Conceptual Design
~ ~:~~.~,~~~~.:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270235
*-===-- Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 96 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. A Rev. No.: A Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallm(:!act Civil/ Structural Design Engineering .YES ONO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities?
Electrical Design Engineering .YES ONO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering .YES ONO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering .YES ONO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis .YES ONO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES l)f NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270236
~Entergy NUCLEAR MANAGEMENT QUALITY RELATED EN-DC-115 I REV.11 REFERENCE USE PAGE 97 OF 150 MANUAL Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS Potentiallmeact ASME Section Ill Specifications .YES DNO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program .YES DNO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) .YES DNO
- Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) .YES DNO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (1 0 CFR 50.44) (if applicable) DYES (g'No
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program .YES DNO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management .YES DNO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) .YES DNO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeact Electrical Maintenance .YES DNO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance .YES DNO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program .YES DNO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270237
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET 30F 6 PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallm~act Computer Support and Software DYES IX[ NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Quality Assurance (SQA)?
Chemistry and Environmental Impact DYES (Z[NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or any changes to the environment?
Radiation Protection (RP) Program Impact DYES MNo
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce {or reintroduce) any cobalt containing materials (such as Stellite} into the primary system?
Operations .YES DNO I
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) .YES DNO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS Potentiallm~act ASME Containment In-service Inspection (IWE /IWL) Program .YES DNO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program .YES DNO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270238
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS (CONTINUED} Potentiallm(lact ASME In-service Inspection (lSI) Program .YES DNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program .YES DNO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program .YES DNO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES 1&1 NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T} Program DYES IXj NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Pipin!1 & Components?
Boric Acid Corrosion (BAC) Program DYES ~NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES IXJ'NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES mNo
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing .YES DNO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical equipment?
IPEC00270239
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I REV.11 PAGE 100 OF 150 Enaineering Chanae Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEETS OF6 PROGRAMS AND COMPONENTS (CONTINUED} PotentiallmQact Flow Accelerated Corrosion (FAC) Program .YES DNO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES (XfNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanaer oroaram?
Predictive Maintenance Program DYES IE! NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitorina?
Microbiological Induced Corrosion (MIC) Program Impact DYES ~NO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES L'8f NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program t!SNo
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program .YES DNO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EO) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES 1)1' NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES IX] NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES [gj NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270240
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 101 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmgact Welding Program .YES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazinQ or solderinQ?
Safety Program .YES DNO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering .YES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES 00NO
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES ilrJ NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES 1):1 NO IPEC00270241
ENTERGY Conceptual Design
~~~~~~~.:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: Existing Valve Tie-In Chart
- 2. Figure 2, Sheet 1 - 9321-F-27353: Safety Injection System Flow Diagram (partial)
- 3. Figure 2, Sheet 2- 9321-F-27353: Safety Injection System Flow Diagram (partial)
- 4. Figure 2, Sheet 3- 9321-F-27353: Safety Injection System Flow Diagram (partial)
- 5. Figure 2, Sheet 4- 9321-F-27353: Safety Injection System Flow Diagram (partial)
- 6. Figure 3 Typical Leak Detection Piping Connection at Check Valves
- 7. Figure 4: Leak Detection Piping Connection at MOVs IPEC00270242
ENTERGY Conceptual Design
~ ::~~2~~~.:~ Indian Point Nuclear Station Unit 3 Package SAMA IP3-19 Rev. 0 Existing Boundary Location Valve No.
SI-162 Test Connection between Valves SI-857U & SI-857W SI-158 Test Connection between Valves SI-857S & SI-857T
' SI-161 Test Connection between Valves SI-857Q & SI-857R SI-159 Test Connection between Valves SI-857B & SI-857H SI-154 Test Connection between Valves SI-857 A & SI-857G SI-163 Test Connection between Valves SI-857C & SI-857J SI-157 Test Connection between Valves SI-857D & SI-857K SI-153 Test Connection between Valves SI-857E & SI-857L SI-160 Test Connection between Valves SI-857F & SI-857M SI-156 Test Connection between Valves SI-857N & SI-857P SI-113 Test Connection between Valves Sl-897A & SI-838N SI-895N SI-857A SI-120 Test Cmmection between Valves SI-897B & SI-838B/ SI-895B/ SI-857S SI-123 Test Connection between Valves SI-897C & SI-838C/ SI-895C/ SI-857Q SI-130 Test Connection between Valves SI-897D & SI-838D/ SI-895D/ Sl-8570 NEW Test Connection between Valves AC-731 & AC-730 FIGURE 1 EXISTING VALVE TIE-IN CHART IPEC00270243
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-019 Rev. 0 FOR CONT. SEE l ABOVE (TYPICAL) 0-SI-2501 R LOOP 1 COLD LEG (Rcs)..- 3 4-SI-2501R 1 9321-F-27383 FC 112 839D L.!J 1501R v 2"-#845-----...._ LOOP 2 COLD LEG (Res)..-~ 9321-F-27383 3 4-SI-2501R FC 119 839D L.!J v v 2" -#844-----...._ 1501R 3/4-SI-2501R FC 839F CONTINUED ON FIGURE 2 { SHEET 4 FIGURE 2 (SHEET 1) IPEC00270244
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-019 Rev. 0 RED . LOOP 4 COLD LEG 142 9321-F-27383 LN #16 1/2-RC-2501 R L.O. 3/4"-#3001
~ -- -- --
9321-F-27233
--+---~~~~----~~
NNE-104 -** INSIDE MISSILE OUTSIDE MISSILE FLOWllU~ SAFETY IHJ.Etr!ON 'SYSTEM BARRIER BARRIER StEET tiD. 1 FIGURE 2 (SHEET 2) IPEC00270245
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-019 Rev. 0 857U 857W L.O. LOOP 2 2" COLD LEG LOOP 3 2" COLD LEG LOOP 1 2" COLD LEG 897A 857G
.....,.._ -----')
--10"-#351 2"
145 L!...l D 2501R 1501R (TYP) (TYP) FIGURE 2 (SHEET 3) IPEC00270246
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-019 Rev. 0
---3/4-SI-2501 R (FE\
~ 6"-SI-2501 R 6"-#358 L!..J v D lt-a~lllllll---1 2501R 1501R I 132
- J 3/:"
c--1:---l 2174
~
~
I 3/4" 10" 2175
',~;§~,"~ }
SHEET 1 II "----3/4-S I 3/4"-#605
-~--- ----------- -----------------------------------
FIGURE 2 (SHEET 4) IPEC00270247
ENTERGY Technologies Indian Point Nuclear Unit 3
""""'"'""' Services SAMA IP3-019 Rev 0 2--------9--G--2 EXISTING ~
VALVE ~v I1 ~~
~
x SEE FIG.2 _w--'----- 3/4" NEW 3/4"
/VALVE NEW---.!
PIPING 3/4" SCH 160 LJ/ NEW TEST CONN NEW 3/4" VALVES 3/8"SS TUBING VALVE MANIFOLD FIGURE 3 TYPICAL LEAK DETECTION PIPING CONNECTION AT CHECK VALVES
""" Sf.PV INDIAN POINT NO. 3 NUCLEAR POWER PLANT FLOW DIAGRAM SAFETY INJECTION SYSTEM SHEET NO.1 D\.IG NO REv 9321-F-27353 40 S>£ET IPEC00270248
ENTERGY Conceptual Design Indian Point Nuclear Station Package Unit 3 SAMA IP3-019 Rev. 0
,.----NEW 3/ 4" -6000 # SOCKOLET (DRILL THRU 14" PIPE)
M ~EXISTING
~(}---
.. [Ml / MOV 14
-----o-----!)lCJ EXISTING ~C-731 AC-730 MOV NEW 3/4" VALVE ~ NEW 3/4" VALVE 3/4" NEW PIPING-II /NEW TEST CONN 3/4" SCH 160 LJ NEW 3/4" VALVES~ MISSLE CONTAINMENT BARRIER PENETRATION LOCAL * **
TRANSMITIER
- I 3/B"ss--
TUBING I
* ---:---2 SEE FIGURE 3 I
LEAK DETECTION PIPING CONNECTION AT MOV'S IPEC00270249
ENTERGY Conceptual Design
~ ~~~,~,~~2~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. ENTERGY Material Specification Indian Point Unit No. 3, NYPA Spec. TS-MS-024
- 4. Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitter (attached here)
- 5. Yokogawa- DXAdvanced R4- DX1 000 Recorder (attached here)
IPEC00270250
Product Data Sheet 00813-0100-4388 Rev BA January 2008 Rosemount 1153 Series D Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitter INDUSTRY LEADING PERFORMANCE
- Qualified per IEEE Std 323-1974 and IEEE Std 344-1975
- 5.0 x 107 rads TID gamma radiation
- 7 g ZPA seismic
- 420 OF (215.6 °C} steam temperature
- 0.25% accuracy CE Contents Introduction ......................................... 0 0 * * * * * ******* page 2 Transmitter Description ............................................... page 2 Operation. . . . . . . . . . . . . . . . . . . . . . . . . . . ................. 0 * * * * ****** page 2 Dimensional Drawings .. 0 * * * * * * * * * * * * * *************** 0 *************** page 3 Nuclear Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... page 4 Performance Specifications ........................... 0 **************** page 5 Functional Specifications ............................. 0
- 0 ****** 0 ******* page 6 Physical Specifications ........ 0 ********* 0 ***** 0 **** 0 0 0 0 ** 0 ****** 0 0
- 0
- page 8 Ordering Information. 0 *** 0 0 0 0 *** 0. 0 0 0. 0 0 0 0 0 0 0 0 0 0 0 0
- 0 0. 0 *** 0. 0
- 0 0 0 0 0 0 page 11
~
ROSEMOUNT' ~ Nuclear EMERSON" Process Management IPEC00270251
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 Results Driven by Proven Measurement Introduction The Rosemount 1153 Series D Alphaline Nuclear FIGURE 1 The 6 -Cell. Pressure Transmitters are designed for precision Rosemount 1153DD, HD, GD pressure measurements in nuclear applications which Lead require reliable performance and safety over a specified qualified life. These transmitters were qualified per IEEE Std 323-1974 and IEEE Std Capacitor 344-1975 to radiation levels of 50 megarads TID Plates gamma radiation, seismic levels of 7 g, and for steam pressure performance. Stringent quality control during Sensing Diaphragm the manufacturing process includes traceability of pressure-retaining parts, special nuclear cleaning, Rigid
*..--~+----Insulation and hydrostatic testing.
Transmitter Description Silicone Oil Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitters are uniquely built for Class 1E nuclear service while retaining the basic design of the Rosemount 1151 Series that has become a standard of reliable service. Units are available in absolute (A), gage (G), differential (D), and high-line differential (H) configurations, with up to eight pressure range Rosemount 1153AD options. Direct electronic sensing with the completely sealed 6 -Cell' capacitance sensing element (see Figure 1) Capacitor Plates eliminates mechanical force transfer and problems associated with shock and vibration. Installation and Sensing commissioning are simplified by the compact design Diaphragm and 2-wire system compatibility. Wiring terminals and electronics are in separate compartments, so the .._-ff-__ Rigid Insulation electronics remain sealed during installation. Silicone Oil Operation The completely sealed 6 -Cell capacitance sensing element is the key to the unequalled performance and reliability of the Rosemount 1153 Series D Pressure Transmitter. Process pressure is transmitted through an isolating diaphragm and silicone oil fill fluid to a Reference sensing diaphragm in the center of the 6 -Cell (see Figure 1). A reference pressure is transmitted in the same manner to the other side of the sensing diaphragm. Displacement of the sensing diaphragm, a maximum motion of 0.004 inches (0.1 mm), is proportional to the pressure differential across it. The position of the sensing diaphragm is detected by capacitor plates on both sides of the sensing diaphragm. Differential capacitance between the sensing diaphragm and the capacitor plates is converted electronically to a 2-wire, 4-20 rnA de signal. 2 IPEC00270252
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D DIMENSIONAL DRAWINGS ROSEMOUNT 1153DD AND 1153HD 0.75 (19) Clearance 4.72 Max. (119.9) L for Cover Removal 1/2-14 NPT I. (Typical) Conduit Connection Nameplate (1 place) (Remove for (228.6) Zero and Span Adjust)--tr----111 Transmitter Circuitry (this Sid Terminal Connections 1.63 (this Side) (41.3) Welded
- dJ I DrainNent Valve J__ I ~2) (Optional LJ t
/4-18 NPT 3.4 _j Available)
(86.4) 0.8 (20) to End of Mating Tubing ompression Fittings (2) Swagelok for 3/s-in. Tubing (Optional 1/4-18 NPT Available) Pressure Dimension Range Code A 3,4,5 2.13(54) 6, 7 2.19 (55.6)
/s-in. 8 2.25 (57.2)
Mating Tubing 9 2.28 (57.9) ROSEMOUNT 1153AD AND 1153GD 0 2.33 (59.1) DETAIL A 0.75 (19) Clearance L_for Cover Removal r (Typical) Nameplate (Remove for (228.6) Zero and Span Adjust) 7
/16-20 UNF (Typical)
Terminal Connections 1.63 (this Side) (41.3) [ Wetaed low Side 1 I DrainNent Valve (1) Vent
/J (GD only)
~/4-18 34 Optional 711&-14 UNC (8G.4)- NPT Available) (4 Places) 0.8 (20) to End of Mating Tubing NOTE Compression Fittings (1)
All dimensions are nominal In inches (millimeters). Swagelok for 3/s-in. Tubing (Optional 114-18 NPT Available) 3 IPEC00270253
Product Data Sheet 00813-01 00-4388, Rev BA Rosemount 1153 Series D January 2008 SPECIFICATIONS Steam Pressure/Temperature: Accuracy within +/-(4.5% upper range limit + 3.5% Nuclear Specifications span) during and after exposure to steam at the following temperatures and pressures: Qualified per IEEE Std 323-1974 and IEEE Std 344-1975 as stated in Rosemount Report 08300040. 420 OF (215.6 oc), 95 psig for 3 minutes 350 OF (176.6 oc), 120 psig for 7 minutes Output Code P 320 OF (160 oc), 70 psig for 8 hours 265 OF (129.4 oc), 24 psig for 67 hours Radiation: Accuracy within +/-6% of upper range limit during Range Code 0: +/-(6.7% of upper range limit+ and after exposure to 5.19 x 107 rads, total 3.5% of span). integrated dosage. Additional Radiation: Range Code 0: +/-8.2% of upper range limit. After completion of the above tests, the transmitters were exposed to an additional Seismic: 5.5 x 10 7 rads TID. Accuracy within +/-0.5% of upper range limit during and after a disturbance defined by a required Performance: +/-(1.5% of upper range limit + 1.0% response spectrum with a ZPA of ?g. span). Range Code 0: +/-0.75% of upper range limit. Range Code 0: +/-(2.3% of upper range limit+ 1.0% of span). Steam Pressure/Transmitter: Accuracy within +/-(4.5% upper range limit +3.5% Post DBE Operation: span) during and after exposure to steam at the Accuracy at reference conditions shall be within following temperatures and pressures: +/-3% of upper range limit (4.5% for Range Code
- 0) for one year following DBE.
420 OF (215.6 oc), 95 psig for 3 minutes 350 OF (176.6 oc), 85 psig for 7 minutes Both Output Codes 320 OF (160 oc), 60 psig for 3 hours 240 OF (115.5 oc), 27 psig for 21 hours Chemical Spray: 176 OF (80 oc), 3 psig for 30 days simulating one Composition is 0.28 molar boric acid, 0.064 molar year post-DBE operation. sodium thiosulfate, and sodium hydroxide as required to make an initial pH of 11.0 and a Range Code 0: +/-(6.7% of upper range limit+ subsequent pH ranging from 8.5 to 11.0. 3.5% of span). Chemical spray is sprayed at a rate of 0.25 Post DBE Operation gal/minlft2 . Accuracy at reference conditions shall be within Quality Assurance Program:
+/-1.5% of upper range limit (2.25% for Range In accordance with NQA-1, 10CFR50 Appendix Code 0) for one year following DBE. B, and ISO 9001:2000 Output Code R Nuclear Cleaning:
Radiation: To 1 ppm maximum chloride content. Accuracy within +/-(1.5% of upper range limit + Hydrostatic Testing: 1.0% span) during and after exposure to 5.5 x To 150% of maximum working pressure or 2,000 107 rads, total integrated dosage. psi, (13.8 MPa), whichever is greater. Range Code 0: +/-(2.3% of upper range limit+ Traceability: 1.0% of span). In accordance with NQA-1 and 10CFR50 Seismic: Appendix B; chemical and physical material Accuracy within +/-0.5% of upper range limit during certification of pressure-retaining parts. and after disturbance defined by a required response spectrum with a ZPA of ?g. Range Code 0: +/-0.75% of upper range limit. 4 IPEC00270254
Product Data Sheet 00813-0100-4388, Rev SA January 2008 Rosemount 1153 Series D Qualified life: Overpressure Effect Dependent on continuous ambient temperature at the installation site (see Figure 2). Replacement Rosemount 1153DD: of the amplifier and calibration circuit boards at Maximum zero shift after 2,000 psi (13.8 MPa) the end of their qualified life permits extension of overpressure: the transmitter qualified life to the module qualified life. Details of the test are in the Rosemount Report D8300040. Rosemount 1153HD Maximum zero shift after 3,000 psi (20.68 MPa) overpressure: Range Code Overpressure Effect 4 +/-1.0% of upper range limit 5 +/-2.0% of upper range limit 6,7 +/-5.0% of upper range limit Rosemount 1153GD and 1153AD 100 110 120 130 140 150 Maximum zero shift after 2,000 psi (13.8 MPa) Temperature (°F) overpressure: PERFORMANCE SPECIFICATIONS Based on zero-based ranges under reference conditions. Maximum zero shift after 4,500 psi (31.0 MPa) overpressure: Accuracy
+/-0.25% of calibrated span; includes combined effects of linearity, hysteresis, and repeatability.
Maximum zero shift after 6,000 psi (41.34 MPa) Dead Band overpressure: None Drift
+/-0.2% of upper range limit for 30 months (+/-0.3% of Static Pressure Zero Effect upper range limit for Range Code 0).
Rosemount 1153DD: Temperature Effect Per 1,000 psi (6.89 MPa): Per 100 *F (55.6 *c) ambient temperature change. Range Code Temperature Effect 3 +/-(1.5% of upper range limit+ 1.0% span) 4-9 +/-(0.75% of upper range limit+ 0.5% span) 0 +/-(1.13% of upper range limit+ 0.5% span) Rosemount 1153HD: Per 1,000 psi (6.89 MPa): 5 IPEC00270255
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 Static Pressure Span Effect Power Supply The effect is systematic and can be calibrated out for Load limits are as shown in Figure 3 and Figure 4. a particular pressure before installation. Correction uncertainty equals +/-0.5% of input reading/1 ,000 psi FIGURE 3. Output Code P (6.89 MPa). 2000 -.----4_-_2_o_m_A_D_c_ _ _ _ __, Power Supply Effect 1650--- -------------------------- 1500 Less than 0.005% of output span per volt 1325 ------ Load Effect g: 1000 Cll No load effect other than the change in the voltage 0 c:: Design supply to the transmitter J!! 1/) 500 Region
*u; Cll Mounting Position Effect 0::
"C 0 No span effect; zero shift of up to 1.5 in H20 (372 "'
0
..J 45 Pa), which can be calibrated out 13.5 Power Supply (V DC)
Response Time FIGURE 4. Output Code R Fixed time constant (63%) at 100 oF (37.8 oC) as follows: 4-20 mADC 1825-r-------------------- Range Code Response Time 1575--fsoii-3 2 seconds or less 4 0.5 seconds or less g: 5-9,0 0.2 seconds or less Cll 0 c:: Design Adjustable damping is available through a special N J!! 1/)
*u; 50 Region Option. Cll 0::
"C FUNCTIONAL SPECIFICATIONS "'
0
..J 0 12 35 45 Service 13.5 Power Supply (V DC)
Liquid, gas, or vapor Span and Zero Output Continually adjustable externally 4-20 rnA de Zero Elevation and Suppression Maximum zero elevation: 600% of calibrated span (400% of calibrated span for Range Code 0) Maximum zero suppression: 500% of calibrated span (300% of calibrated span for Range Code 0) Zero elevation and suppression must be such that neither the calibrated span nor the upper or lower range value exceeds 100% of the upper range limit. Temperature Limits Normal Operating Limits: 40 to 200 oF (4.4 to 93.3 OC) Qualified storage limits: -40 to 120 oF (-40 to 48.9 oc) 6 IPEC00270256
Product Data Sheet 00813-01 00-4388, Rev BA January 2008 Rosemount 1153 Series D Humidity Limits Rosemount 1153HD: 0.5 psia to 3,000 psig (3.4 kPa abs to 20.7 MPa) 0-100% relative humidity (NEMA 4X) maximum rated static pressure for operation Volumetric Displacement within specifications; overpressure limit is 3,000 psig (20.7 MPa) on either side without damage to Less than 0.01 in 3 (0.16 cm 3 ) the transmitter Turn-On Time Overpressure Limits 2 seconds maximum. No warm-up required. Rosemount 1153GD and Rosemount 1153AD: Pressure Ranges Operates within specifications from 0.5 psia Rosemount 115300 and 1153HD: (3.4 kPa abs) to upper range limit. Overpressure Range Code Pressure Ranges limits without damage to the transmitter are: Range Code Overpressure Limit 3 0-5 to 0-30 in H20 (D units only) (0-1.24 to 0-7.46 kPa) 3-8 2,000 psig (13.8 MPa) 4 0-25 to 0-150 in H20 (0-6.22 to 0-37.3 kPa) 9 4,500 psig (31.0 MPa) 5 0-125 to 0-750 inH20 0 6,000 psig (41.34 MPa) (0-31.08 to 0-186.4 kPa) 6 0-17 to 0-100 psi (0-0.12 to 0-0.69 MPa) 7 0-50 to 0-300 psi (0-0.34 to 0-2.07 MPa) 8 0-170 to 0-1,000 psi (D units only) (0-1.17 to 0-6.89 MPa) Rosemount 1153GD and 1153AD Range Code Pressure Ranges 3 0-5 to 0-30 inH20 (G units only) (0-1.24 to 0-7.46 kPa) 4 0-25 to 0-150 inH20 (G Units Only) (0-6.22 to 0-37.3 kPa) 5 0-125 to 0-750 inH20 (0-31.08 to 0-186.4 kPa) 6 0-17 to 0-100 psi (0-0.12 to 0-0.69 MPa) 7 0-50 to 0-300 psi (0-0.34 to 0-2.07 MPa) 8 0-170 to 0-1,000 psi (0-1.17 to 0-6.89 MPa) 9 0-500 to 0-3,000 psi (G units only) (0-3.45 to 0-20.68 MPa) 0 0-1,000 to 0-4,000 psi (G units only) (0-6.89 to 0-27.56 MPa) Maximum Working Pressure Rosemount 115300 and 1153HD: Static pressure limit Rosemount 1153GD and 1153AD: Upper range limit Static Pressure and Overpressure Limits Rosemount 115300: 0.5 psia to 2,000 psig (3.4 kPa abs to 13.8 MPa) maximum rated static pressure for operation within specifications; overpressure limit is 2,000 psig (13.8 MPa) on either side without damage to the transmitter 7 IPEC00270257
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 PHYSICAL SPECIFICATIONS Flange Bolts and Nuts: Plated alloy steel, per ASTM A-540 Materials of Construction Electronics Housing: Isolating Diaphragms: 316 SST 316L SST Mounting Bracket: DrainNent Valves: 316L SST 316 SST Mounting Bolts (Bracket to Transmitter}: Process Flanges: SAE J429 Carbon steel, Grade 2 or Grade 5 CF-8M (cast version of 316 SST) Process Connections Process 0-rings: 3/s-in. 316L SST Swagelok compression fitting, 316 SST (1/4-18 NPT optional) Electronics Housing 0-rings: Ethylene propylene Electrical Connections 1/:c-14 NPT conduit with screw terminals Fill Fluid: Silicone oil Weight 24 lb (1 0.9 kg) including mounting bracket. FIGURE 5. Rosemount 1153 Series D Pressure Transmitter. Exploded view. Electronics Circuit Boards Cover Process Flange (Optional) 3 -Cell Sensing Module Process Flange (optional) 8 IPEC00270258
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D FIGURE 6. Electric Block Diagram Sensor~ Demodulator Current Detector Current A~~-0 Test ~ I Limiter ~+
+
o"'~-
~~
Signal j - Control I Voltage Regulator Reverse 1-- Amp. Polarity
~*
Protection Current
... Control FIGURE 7. Transmitter Wiring Diagram
~+ -[))
+
-----+
Power Supply
+ ~
0 9 IPEC00270259
Product Data Sheet 00813-0100-4388, Rev SA Rosemount 1153 Series D January 2008 FIGURE B. Transmitter Mounting Configurations Center of Gravity (Bracket Included) 2.3 1.8 (45.7) 2.81 (71.4) Tl I f$l ---. I 3/a-in. 2.81 ~ Bolts (4) (71.4) (Customer Supplied) 5 (127) MOUNTING BRACKET FOR ACCEPTABLE ALTERNATE PANEL MOUNT SHOWN IN MOUNTING PANEL MOUNTING TYPICAL MOUNTING HOLE PATTERN CONFIGURATION (BACK SIDE) NOTES
- 1. Orientation with respect to gravity is not critical.
- 2. Units can alternately be mounted with process connection adjacent to bracket.
- 3. All dimensions are nominal in inches (millimeters}.
Standard Accessories Documentation All models are shipped with a mounting bracket. One Certification is provided for each Rosemount 1153 instruction manual is included with each shipment. Series D Pressure Transmitter for accuracy, special cleaning, hydrostatic testing, and traceability. Calibration Chemical and physical reports and identification of pressure retaining parts are on file at Rosemount Transmitters are factory calibrated to the customer's Nuclear Instruments, Inc. specified range. If calibration is not specified, transmitters are calibrated at maximum range. Calibration is at reference conditions (ambient temperature and pressure). Options Consult the N-Options Product Data Sheet 00813-0100-2655 or call Rosemount Nuclear Instruments, Inc. for special transmitter needs. Tagging The transmitter will be tagged, at no charge, in accordance with customer requirements (96 characters maximum). All tags are SST. The standard tag is permanently attached to the transmitter. Standard tag character height is 0.125 in. (3.18 mm). A wire-on tag is available on request. 10 IPEC00270260
Product Data Sheet 00813-0100-4388, Rev BA January 2008 Rosemount 1153 Series D ORDERING INFORMATION Model Product Description Code Pressure Measurement D Differential Pressure; 2,000 psig (13.8 MPa) Static Pressure Rating H Differential Pressure; 3,000 psig (20.68 MPa) Static Pressure Rating A Absolute Pressure G Gage Pressure 3 0-5 to 0-30 in H2 0 N/A N/A 0-5 to 0-30 inH20 (0-1.24 to 0-7.46 kPa) (0-1.24 to 0-7.46 kPa) 4 0-25 to 0-150 in H2 0 0-25 to 0-150 inH 2 0 N/A 0-25to 0-150 inH 2 0 (0-6.22 to 0-37.3 kPa) (0-6.22 to 0-37.3 kPa) (0-6.22to 0-37.3 kPa} 5 0-125 to 0-750 inH 2 0 0-125 to 0-750 inH2 0 0-125 to 0-750 inH 20 0-125 to 0-750 inH 2 0 (0-31.08 to 0-186.4 kPa) (0-31.08to 0-186.4 kPa) (0-31.08 to 0-186.4 kPa) (0-31.08 to 0-186.4 kPa} 6 0-17 to 0-100 psi 0-17 to 0-100 psi 0-17 to 0-100 psia 0-17 to 0-100 psi (0-0.12 to 0-0.69 MPa) (0-0.12 to 0-0.69 MPa) (0-0.12 to 0-0.69 MPa} (0-0.12to 0-0.69 MPa} 7 0-50 to 0-300 psi 0-50 to 0-300 psi 0-50 to 0-300 psia 0-50 to 0-300 psi (0-0.34 to 0-2.07 MPa) (0-0.34 to 0-2.07 MPa) (0-0.34 to 0-2.07 MPa) (0-0.34 to 0-2.07 MPa} 8 0-170 to 0-1,000 psi N/A 0-170 to 0-1,000 psia 0-170 to 0-1,000 psi (0-1.17 to 0-6.89 MPa) (0-1.17 to 0-6.89 MPa) (0-1.17 to 0-6.89 MPa) 9 N/A N/A 0-500 to 0-3,000 psi (0-3.45 to 0-20.68 MPa) 0 N/A N/A N/A 0-1,000 to 0-4,000 psi (0-6.89 to 0-27.56 MPa} A Welded . Swagelok Compression Fitting Process Connection and Welded DrainNent Valve s<2l 1/4-18 NPT Process Connection and Welded DrainNent Valve c<2l 1/4-18 NPT Process Connection and Drain Hole (DrainNent Valve Not Included) D One Flange Option Code A and one Remote Seal E(2 l One Flange Option Code B and one Remote Seal F(2 l One Flange Option Code C and one Remote Seal G Two Remote Seals H Welded 3/s-in. Swage/ok Compression Fitting on Process Connection and DrainNent Connection J(2 l Welded 3/s-in. Swagelok Compression Fitting Process Connection and 1/4-18 NPT Drain Hole L One Flange Option Code H and one Remote Seal M(2 l One Flange Option Code J and one Remote Seal Typical Model Number:1153 D D 4 R A (1) The Rosemount 1153 Series D with the Output CodeR Electronics is a/so available with adjustable damping. Specify this option by adding "N0037" to the end of the complete model number. For example: 1153DD4RAN0037. (2) Customer assumes responsibility for qualifying connection interfaces on this option. Contact Rosemount Nuclear Instruments, Inc. for details. 11 IPEC00270261
Product Data Sheet 00813-0100-4388, Rev BA Rosemount 1153 Series D January 2008 The Emerson logo is a trade mark and service mark of Emerson Electric Co. Rosemount, the Rosemount logotype, and Alphaline are registered trademarks of Rosemount, Inc. a-Cell is a trademark of Rosemount, Inc. Swagelok is a registered trademark of Swagelok Co. Emerson Process Management Rosemount Nuclear Instruments, Inc. /!: Rosemount Nuclear lnstuments, Inc. satisfies all obligations coming from
~ legislation to harmonize product requirements in the European Union.
8200 Market Boulevard Chanhassen, MN 55317 ( Tel (952) 949-5210 Fax (952) 949-5201 Copyright 2008 Rosemount Nuclear Instruments, Inc. http://www.rosemountnuclear.com 1111111111111111111111111111111111111111111111111111111 00813-0100-4388, Rev BA ROSEMOUNT" Nuclear 111111111111111111111111111111111111111111111111111111 EMERSON'" f www.rosemountnuclear.com Process Management IPEC00270262
T.,
;~-..~{
r,.,*~~~~
\. '*.
;--~
l' Bulletin 04L41 801-01 E IPEC00270263
"'U m 0 0 0 I\.) v1gdant ...... The dear path to operational excellence 0 I\.) (J) -ll>- The evolution of the global standard in paperless recorders has reached the next stage
-the DAQSTATION DXAdvanced series R4 (release 4)./ts basic functions have been further enhanced with an expanded security function option providing FDA 21 CFR Part 11 compliance, making it ideal for a broadening range of applications, such as in pharmaceutical manufacturing.
- Up to 48 channels of input
- User can stattlstop recording by batch, and create data files<
- Expandable to up to 348 channels With the MW100 automatic connection function
-**~~--**~~
- Arrange the your way with a custom display function!
- Review historical data with date and time calendar search functions
- Standard Ethernet interface
- Supports the PROFIBUS-DP and EtherNe!JlP protocols!
- Expanded Web and networking functions!
- Dust- and splash-proof front panel (IP65, NEMA4 compliant)
- Highly reliable lntemal memory with error-<::orrection funcUon
*Front panel door lock and login funcl>on
*-:ortlt.':"' *
- Software for a variety of tasks including analysis, settings, and acquisition DAQSTANDARO:
Supports settings and data file analysis DAQStudlo: Builder software lor custom displays DAQWORX: Integrated Data Acquisition Software Suite DAQManager: Data management Software
/ lt.<:it Opti Driy§_
Standard-equipped internal memory greatly A USB flash drive can be used to transfer data to increased (to 400 MB). Even longer recording your PC. The optional front panel USB port also durations, and multichannel recording. allows an external PC keyboard to be used with the DXAdvanced to facilitate setting and text entry. Measurement CH- 30 channels Computation CH = 0 channels DX2000 (400 MB) Display update {minute/div) 30 minutes Save interval (s) 60s Total sample time Approx. 5 years Meas urement CH - 30 channels Computation CH = 0 channels DX2000 (400MB) Save interval (s) 1s Total sample time Approx. 2 months CO((P, **;'/F) f) L ,*cion All DXAdvanced models include a CompactFiash drive. This function provides control of the input value Rugged and readily available CompactFiash cards (CF correction schedule. Following a predetermined cards) serve as the removable media, and are available schedule, DXAdvanced displays a message as optional accessories. Up to 2 GB CF card supported. prompting the user to perform input value correction. This is convenient, for example, in Nadcap"' related heat treatment applications.
'Nadcap: National Aerospace and Defense Contractors Accreditation Program Calibration schedule setting Message to prompt calibration This function ensures that the CF card always retains the latest data when files are saved to it automatically. \c j ,;f t *.'
When the CF card is full, the oldest files are deleted Reports can be created automatically using a to make room for the newest files. The media FIFO spreadsheet template created in Excel. Reports are function allows you to use the OX continuously for long created in Excel format, greatly reducing time and periods of time without having to change the CF card. effort spent on making spreadsheets. Overview of the Media FIFO Function Saved File4 Medium Excel report IPEC00270265
Capacity: 400MB
,'vlaximum number of files can be saved:
400 files (total number of display data file and event data file) Mounting: mounting {on a vertical plane)
*Alarm Function may be inclined downward up to 30 Number of a-arrn levels* Up to four levels for each channel a horizontal plane.
Alarm types: High and low limits, differential high and low iimits, high and low rate-of-change limits and delay high Front Panel: Water and and low (based on and NEMA I*Jo 250 TYPE4*)
- Alarm annunciator function:
*Input Alarm display based on alarm sequence, and relay output operation Number of Inputs:
Supported alarm sequences: 3 (ISA-A-4, ISA-A, ISA-M) DX1000: 2, 4, 6, 12 channels
- Event adion function DX2000: 4, B, 10, 20, 30, 40, 48 channels General: Particular action can be executed by particular event.
tl!easurement Interval: Number of event action: 40 actions can be set DX1002, DX1004, DX2004, DX2008:
- Security funclions
- 125 ms, 250 .ms, 25 ms sampling mode')
General: function or key loc~ function can be set for DX1006, DX1012, DX2010, DX2020, DX2030, DX2048: key operat'on or communication operation. 1 s (Not available when ND integration time is set to Koy lock function: On/off and password can be set For each operatioc 100 ms), 2 s, 5 s, 125 ms (fast samp'ing mode*)
""AJD integration time is fixed to 1.67 case of fast key and FUN C operation.
samp!ing Login function: User name and to login can be set
*Please security f:~nction opt:on (/AS1)
Inputs: DCV (20, 60, 200 mV, 2, 6, 20, 50 V, 1-5 V) for t'-e models with the /AS1 option TC (R, S, B, K, E, J, T. N, W, L, U, \NRe) RTD (Pt100, JPt100)
- Cloci<
Dl (Contact input, TIL level) Clock: With calendar function (year of grace) DCA external shunt C!ock accuracy: +/-10 excluding a delay (of 1 second, maximum) each time the power is turned on. DST function (summer/winter lime): The time at which the daylight savings time adjustment is actomatically calculated acd configured.
- Communication Functions Connection: Ethernet
~ Doe-s not inciude the accuracy of reference junction compensation Protocols: TCP, IP, ICMP, ARP, DHCP, HTIP, FTP.
*Display SMTP, SNTP, Modbus, DX private Display unit: E-mail inform function:
DX1000 5.5-inch TFT co: or LCD FTP client function: DX2000: 1OA-inch TFT color Transferred data file, FTP server function, Web server function, SNTP client Display group: function, SNTP server function, DHCP client function, Modbus client function, Number of display: DX 1000: 10 groups, DX2000: 36 groups Mod bus server function I*Jumber of assignable channels for one EtherNetiiP server Connects to EtherNet/IP networks as an Adapter DX1000: 6 DX2000: 10 channels (Server). Display color:
- Balch function Trend/Bargraph* Selectable from 24 colors General: Data batch
Background:
White or black selectable name, Trend are available. Trend type: Vertical, horizontal, landscape, horizontal split or
- Power Supply circular* selectable Rated power supply: 100 to 240 VAG (automatic switching)
~ Circular display is only for DX20JO Allowable power supply voltage range:
Bargraph display: 90 to 132 or 180 to 264 VAC Direction: Vertical or horizontal selectable Rated power Digital indication: Hz (automatic switching) Display renewal rate: 1s Power consumption: Overview display: DX1000: 60 VA (max., for 240 VAC power supply) Number of indication channels: DX2000 100 VA (max., for 240 VAC power supply) Measuring values and alarm status of all channels Information display* Alarm summa!)', message sum mal)', memory information, report information, relay status, Mod bus status Power voltage: 90 lo 132 or 180 to 250 VAC Tag display: Power supply frequency: 50 Hz +/-2%, 60Hz +/-2% Tag number and comment Ambient temperature* 0 to 50 'C No. characters Ambient humidity: 20% to 80% RH (at 5 to 40 'C) Tag no max Tag corr.ment :32max SPECIFICATIONS OF OPTIONAL FUNCTIONS Displayable characters* Tag no.: Alphanumerics comments: Alphanumerics, Japanese, and *Alarm Output Relays (IA1, IA2, IA3, IA4*, 1/'.5') An alarm signal is output from the rear panel as contact signal. Number or output: Select from 2, 4, 6, 12' points of characters: 32 characters maximum
- Only for DX2030.
Number of messaged: 100 messages 10 free messages)
- Serial Communication Interface (IC2, Data referencing function: Display the data (display data or event Connection: EIA RS-232 or RS-422N485 (IC3) data) from internal or external me mol)'. Protocols: DX private protocol, Modbus(master/slave) protocol
- Custom display fundion: Setting/measurement server function:
User can change object (trend, numeric, and bar graphs, etc) sizes Operation, setting or output of measurement data and attributes, and freely to create screens. are available by protocoL No. of screens: (3 from internal memory, 25 from external media (CF)) Mod bus communication: Reading or writing data on other Max no. of placeable display objeds: instruments are available by Mod bus protocoL' 134 (normal: 80, scale: 4, trend: 4, Jist: 4, graphic: 40, " i:V11 option or /MC1 option is required to :ead da7a fror1 o!i1er instrument bitmap: 2)
- Data Saving Function
- VGA Video Output (IDS)
External storage medium: Resolution: 640 x 480 pixels (VGA) Medium: Corr,pactFiash memory card (CF card)
- Fail/Status (/F1)
Internal me mol)': The relay output on the rear panel indicates the occurrence of CPU Medium: Flash memo!)' failure or selected status. IPEC00270266
- Fail & Alarm 22 points (IF2, only for DX2000) PROFIBUS-DP master devices can access the following internal data.
Combination output function" and "Alarm output relays 22 Load measurement channel data Load MATH channel data (IH2) Write communication input channel data term'nal (detachable type) is used for input terminaL Node address setting range: 0 to 125 Type (IH5[ ], IH5*) Interface: PROFIBUS-DP-VO Slave Provides carrying handle and power cord. Transmission medium* 2 dedicated cables
~ iH5 is only for 24 VDC/AC power supply model {!P1), and does not include power code Transmission speedldlslance* 9.6 kbps/1200 m to 12 lvlbps/1 00 m
- Mathematical Functions (/M1) Termination resistance: None (requires external tenmi~ation resistance)
Used for data, displaying trends and digital values, and recording *Advanced security function (lASt) to channels. Security and electronic record/signature functions have been added thai are Channel to calculated data: compliant with the USA's FDA. title 21 CFR Part 11. DX1002, 12 channels, DX1006, DX1012: 24 channels Data anti-tamper function:Setlings and measured data are saved as encrypted DX2004, DX2008: Up to 12 channels binary files. DX201 0, DX2020, DX2030, DX2040, DX2048: 60 channels Login function: Using the login func<ion (user user ID and password), you can enter security settings on tile anthmetic operations, Statistical operations, operations, instrument Conditional operation User level and number of users: Con slant: Up to 60 constants (K01 to K60) System admin:strator: 5 users (ail can be operated) Report functions: General user: 90 users Report type: Hourly, daily, hourly+ daily, daily +wee~ly and dai'y Electronic signature function:
+monthly A'ter checking data that has finis1ed being recorded.
Operation: Max. 4 types are selectable from average. maximum, you can add three levels of elecoronic signatu:e, minimum, instantaneous and summation select a pass/fail, and enter comments
- Cu10, Cu25 RTD lnput/3 leg Isolated RTD Input (/N1) Audit Trail Function: The settings change log and the operation log when This option allows Cu10 and Cu25 inputs to be added to the standard input the change was made are saved.
t;1pes. Password management function:
- 3 legs lso:ated RTD Input (/N2*) Logins are verified by a Kerberos aul~enticalion server A, B, b legs are of isolated input type.
*Only fo:DX1006, DXc012, DX2010, DX2020, :JX2030, DX2048.
*Extended Input Types Thrs option inputs l'fpes as below to be added to the standard ......
DX1000 PQ1!!1 C@i l Wr,g Unit mm vs Ao7Fe, PLATINEL, PR40-20. NiNiMo, W/Wre26, (approx inch) Pt50, Ni100 (SAMA), Ni100 (DIN), Ni120, ~ E83*~ Pt46, Pt20C
- 24 VDC/AC Power Supply (/P1)
Rated power supply: 24 VDC or 24 VAG (50/60Hz) Allowable power supply voltage range: 21.6 to 26.4 VDC/AC Max. power consumption: DX100C: 28 VA (24 VDC), 45 VA (24 VAG (50/60Hz)) DX2000: 45 VA (24 VDC), 70 VA (24 VAG (50160 Hz)) allows functions to be controlled remotely by a co1tact in pel. transmitter power supply (!TPS2*, !TPS4, /TPS8*) voltage: 22.8 to 25.2 VDC (rated load current) output current 4 to 20 mADC
'ITPS2 is only for DX1000, ITPSB only for DX2000
- Easy text /KB2) DX2000 Remote terminal is available to operate the OX Number of units that can be co.1tro'led.
Max 32 ucits by JD setting sp*~ficatior1: Based on Rev1.1, host function Number of 2 ports (Front and rear panel) Available Keyboard: 104/89 keyboard (US) based on USB HID Class Ver.1.1 External medium: USB flash d.ive {Some of the USB flash drive may not be suppo.ied by DXAdvanced.)
*Pulse Pulse oplion includes mathematical functions option (/lvl1) and remote control option (/R 1).
Number of inputs: 3 points (8 points are available in case of using remote inputs) Input format: Photocoupler isolation Isolated power supply 5V)
*Calibration correction function (ICC1)
Corrects the measurement value of each channel using segment linearizer approximation. Number of segment points: 2 to 16 Two panel brackets are used in panel-mounting the DX1 000 and DX2000. They
- External input function (/MC1, only for DX2000) may be used either on the left and right or top and bottom. See Yokogawa's Digital input channels via communication are extended to input data from General Specification (GS 04L41 801-01 E) for information on cutting other instruments. dimensions for DX1 000 vertical or horizontal attachments. otherwise Number of external input channels: indicated, tolerance is +/-3% (or +/-0.3 mm for dimensions under 10 mm).
Up to 240 channels (channel number: 201 to 440) Daqs1ation and DXAdva;,ced are registered traderr:ar't:: of Yokogawa Electri:::: Corporation DX2030, DX2040 and DX2048 Microsoft, MS, and Windows are registered tradema,1\s or ~rademarks of Microscft available when e>ctema! Input option equipped. Corporation in the United States and other countries Pentium are registered trademarks of lntel Corporation. Ethernet is a registered trademark of Xerox Corporation, 2 to 6 Modbus is a registered trademark of AEG Schneider Automation DX2000: 2 to 12 Other company names and product names appearing in this document are registered (DX201 O,DX202C ,Dx2030 ,DX2040,DX2048 only) trademarks or trademarks of their respective holders.
- PROFIBUS-DP communication interface function (/CP1) ?ROFIBUS~D? 1s a registered t"ademarks of PROFIBUS User Organizat,on, EtherNet!IP is a registered t""ademarks of ODVA(Open DevlceNet Vendor Associatic1},
tt IPEC00270267
DX2000 r..1odel cede
~~~~ og~g~el Description DX2004 4Ch 125'Tls(Fest samplioq mcde: 25ms DX2008 8ch. 125'Tls1Fast samolino mode: 25ms DX2010 10ch 1 s!Fasl sa'Tlolinq mode* '25ms)
DX2020 20C~I. 1s/Fastsamolino mode: 125ms DX2030 30ch. Is/Fast samolirc mode: i25ms\ DX2040 40ch 1sfFasl samoH:"',o mode* 125rr.s DX2048 48ch 1s(Fast samolina mode* 125msl Internal memorv 3 400MB
~
=xtemal med'a -4 Dlsclav larcuaqe 12 merlwintertime)
Optior;s IA1 A!arm out:Jvt 2 ocints *1 IA2 A arm outout 4 ooints "'1 IIA3 Alaru outcut 6 ooinls '1 IA4 Alarm cutout 12 oo!nts ~'!
/.A5 Alar'll output ?4 points '1 '2
~ ~S~422~A/485 IDS 3
VGAoutoJt int:rface "'3 IF1 cAIUStatus ou: ui'2 '4 IF2 FAIL+ Alarm ouioui22 ooints '1 '4 lrc2 c:amoed inout :erminal detachable\ IH5 Das~toptype_ (for /Pt;;~~~~;'itcou! power code, screw !voe oower terminall
/H5 1 Desktop lvoe '6 IM1 Mathematical functions
!N1 Cu10.Cu25 RTD in 'uti31eq isolated RTD IN2 3 leo iso'ated RTD '7
/N3 Extended inout tvoe (PR40-2.J. Pt50 etc l
~ 1 ITPS4 24VDC transmitter oower suool* 14loocs '8 ITPS8 24VDC transmitter pewee suppl** (8 loops) '9 IKB1 Easv text ertrv (with in out terminal ... 1 0
- 11
/KB2 Eas" text entrv (w:thout i1out terminal' "*10 IUSB1 USB :rterfece IPM1 Pulse inp~t {inc!udi~g re<note cor:trol and funct:ons)'12 ICC1 ca;ibration correction function
/MC1 Extemal !nout function *13
/BT2 Muiti-batch furtctions "14 ICP1 PRCFIBUS-DP 'unctions '3 lASt Advanced securitv functions
'1 tA5. /F2 cannot :::e
., '~1~~6bM~gg'g~d. ~~~~:3J4s APPLICATION SOFTWARE Model code Descriol;oo OS
)XA12Q DAQST!\NC:ARD I Windows 200Q/Xf'N:s:a I lXA'I70 DAQSiudio 'vVindows XP/Visla DXA.250 DAOManaaer IMncows XPNista ACCESORIES Product Model code (part number) Specification Shur.t resister 415920 250Q+/-O 1%
(for screw input terminal) 415921 1000+0.1% 415922 100+/-0.1% Shunt resister 438920 250Q+/-O.t% DXAdvanced Removable Chass1s Model f) '. t iJ i} U J\f (for clamped input termmal) 438921 438922 1QQQI{) 1% 100+/-0.1% Removable Chassis Model featuring easy maintenance. _...-.:;,;......,1
.(. __ - _ .<~'..,, _
CF card adapter CF card 772090 772093 772094 T 512MB
*This model enebles y*ou to pu.iilhe inner chassis out from *1j the case without having to remove the supply
- til!j' I 'GB communication, and input winng on panel Mcuntinq bracket I B99008X Door look kev B8706FX Remote control terminal 438227 Far IK81, /K82 ootion Validation documents 438230 For IAS1 ootion read the lnstructior 1nanual thoroughly for VigilontPiont is Yokogowa 1s automation concept for safe, reliable, ond profitable v1gtlant pfont operations. VlgilontPianf aims to enable an ongoing state of Operational Excellence where plant personnel ere watchful and attenttve, we!l*inforrned, The clear path to opel'<ltional excellence and ready to toke odions that optimize plant and business: performance.
YOKOGAWA ELECTRIC CORPORATION Network Solutions Business Div./Phone: (81 )-422*52-7179, Fax: (81 )-422-52*6619 *} ]etSOL Online Sign up lor our free e-mail newsletter E-mail: ns@cs,jp,yokogawa,com YOKOGAWA CORPORATION OF AMERICA Phone: 800*258*2552, Fax: (1)-n0-254..()928 YOKOGAWA EUROPE B.V. Phone: (31)*88*4641000, Fax: (31)*88-4641111 Vig-RS-4E YOKOGAWA ENGINEERING ASIA PTE. LTD. Phone: (65)*62419933, Fax: (65)*62412606 Printed in Japan, ooi(KP) [Ed: os!bJ IPEC00270268
ENTERGY Conceptual Design
~ ~;~.~~,~~~2:,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -019 Rev. 0 Attachment 4 Cost Estimate IPEC00270269
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP3-019 0 PROJECT TITLE: Install Leak Monitoring ESTIMATOR: RCMT Instrumentation for ISLOCA Pathway Isolation Valves PROJECT CODE: TBD 1--,__,.______... JOB LOCATION: Containment & Control Bldgs. ORIG. DATE: 06-25-2012 0 OUTAGE 0 NON-OUTAGE ORIGINATOR; 0 CAPITAL D O&M ESTIMATE TOTAL $6,462,470 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package responds to the issue identified in the NRC's staff review of SAMA IP3-019 and provides the technical resolution and associated costs required for implementation. For SAMA IP3-019, resolution is required to provide remote monitoring of any fluid leakage past the isolation valves in ISLOCA pathways. Prepared Approved by: Date: IPEC00270270
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
~IMATE LEVEL* EC #: SAMA IP3-019 Conceptual PROJECT TITLE: Install Leak Monitoring Instrumentation for ISLOCA Pathway lsolati ESTIMATOR: RCMT Preliminary JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD 1---- Definitive ORIGINATOR: OR IG. DATE: 06-25-2012 Item Oescriotion
- 1. This estimate assumes that this work will require both non-outage and outage conditions to complete.
2
- This estimate assumes that the non-outage work work will complete during 2014 working a 10 hours per shift, four days per week schedule.
- 3. This estimate assumes that the outage work will be completed in 2014 working (2 ) 10 hour shifts 6 days per week.
- 4. This estimate assumes that the non-outage work will not suffer productivity loss due to radiation or hazardous conditions ..
- 5. This estimate assumes that all work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 6. This estimate assumes that adequate penetrations exist for routing of wiring from the pressure transmitter junction boxes to the external panel location such that no new containment oenetrations will be reouired.
- 7. This estimate assumes that the Outage work will involve radiological conditions requiring additional briefing times. dressout times and reduced oroduction due to dressout reouirements.
- 8. This estimate assumes that a comercial dedication effort will be required to qualify the Yokogawa Recorder for use in this application.
- 9. This estimate assumes that the piping/tubing components and instrumentation will be Safety Class 1 and the Electrical components will be Safety Class Electrical.
- 10. This estimate is based on the project's current level of scope definition and is classified Class 5 as defined per the AACE International Cost Estimate Classification System (see Attachment 3, Reference 2).
- 11. Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide for anticipated billing rate increases of 3% per year.
This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 12. and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity - 40% D. Inside Containment - 50% IPEC00270271
Page 3 of 5 BJ112012 912 AM SAMA IP3*0191NSTALL LEAK MONITORING INSTRUMENTATION FOR ISLOCA PATHWAY ISOLATION VALVES 06*25-12 B 0 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0CAm 001 EC #: SAMA IP3-019 PROJECT ~j!T II;WJ!f'l:!?..k Monitoring Instrumentation for ISLOCA Pathway Isolation Valves TAKEOFF JOB LOCATION. Containment & Control Blogs. EST STATUS I PROJECT CODE: TBD ORIGINATOR: ESTIMATOR RCMT ORIG. DATE 06-25-2012 MAN HOURS MATERIAL$ MATERIAL LABOR SUB* HM DESCRIPTION OTY UOM CFT I NO.I UNIT FCTR TOTAL $/MH I PER UNIT DOLLARS DOLLARS I CONTRACT TOTAL$
-
- ESTIMATE LEVEL' ESTIMATE
SUMMARY
- Conceptual Preliminary MANHOURS DOLLARS - Definitive EO/ ENGINEERING 01 STUDY, DESIGN, & CLOSEOUT 360 $ 36.000 02 DESIGN ENGR CONST SUPPORT 120 $ 12.000 General Notes: 03 WELDING ENGR EOI SUPPORT 120 $ 12.000 04 SYS ENGRI S*U ENGR 180 $ 18,000 05 PROJECT MANAGEMENT 700 $ 84.000 06 WORK MANAGEMENT 200 $ 20,000 07 TRAVEL & LIVING EXPENSES $
08 ENGINEEWRING DCP ACCEPTANCE REVIEW 120 $ 12,000 CONTRACT ENGINEERING 09 DESIGN ENGR CONTRACT SUPPORT 1.700 $ 204,000 10 SUPL CONTRACT MODS ENGR - $ 11 MODS PLAN & SCHED -CONTRACT 300 $ 30,000 12 FIELD ENGRS I PLANNERS 320 $ 38,400 MATERIALS I M/SC CONTRACTS 13 MATERIALS $ 763,200 14 OTHER CONTRACTS $ 20,880 CONTRACT CRAFT LABOR 15 SWEC CRAFT LABOR!WALKDOWN 6,547 $ 968,114 16 LOST TIME 655 $ 122,085 17 SWEC DISTRIBS $ 272,669 PLANT CRAFT LABOR 18 MECHMAINT. $ 19 ELECTMAINT - $ 20 I&C 240 $ 24,000 21 CSG - $ MISC EOI SUPPORT 22 QUALITY CONTROL 300 $ 30.000 23 TRAINING 48 $ 5,760 24 CHEMISTRY $ 25 OPS I OPS SUPPORT 120 $ 14,400 26 HP IRP 200 $ 20,000 MISC CONTRACT SUPPORT 27 QUALITY CONTROL 240 $ 19,200 28 NDE . $ 29 HPIRP $ 30 RADWASTE - $ 31 NURSE . $ 32 ELEVATOR CONTRACTOR $ 33 WASTE MANAGEMENT - $ 34 HOUSEKEEPING . $ 35 COMMERCIA $ 36 CGD CONTRACT - $ 25,000 37 DECONTAMINATION CONTACTOR - $ 38 RBC'S $ 39 SECURITY
- Wackenhul $
40 FIRE WATCH (Rover) $ 41 SAFETY 136 $ 9,811 CONTINGENCY 42 CONTINGENCY $ 1,380,870 ESTIMATE SUBTOTAL 12,606 $ 4,142,609 SITE ENCUMBRANCE PREMIUM (20%} $ 828,522 LOADERS (30%) $ 1,491,339 ESTIMATE TOTAL $ 6,462,470 NON OUTAGE WORK
- 1. Gather material and stage tools and materials 1 LT EL 2 10.00 1 00 20 $ 123.32 $ 18,00000 $ 18.000 $ 2,466 $ 20,466 2 Mount new monitoring panel with recorder and power supply 1 LT EL 2 40.00 100 80 $ 123.32 $ 35,000 $ 9,866 $ 44,866 3 Run conduit and as required to area of containment MnQI;;~;, 1 LT EL 2 40.00 1.00 80 $ 123.32 $ 9,866 $ 9,866 4 Prefabricate new spool/valve/cap assembhes (15 sub assemblies) 15 LT PF 2 25.00 1.00 750 $ 120.71 $ 250,000 $ 90,533 $ 340,533
- 5. Perform visual and LP examination on socket welds on new spool/valve assemblies 15 LT NM 1 16.00 1.00 240 $ 87.00 $ $ 20,880 $ 20,880 IPEC00270272
Page 4 of 5 811/2012 9:12AM SAMA IPJ.Q191NSTALL LEAK MONITORING INSTRUMENTATION FOR ISLOCA PATHWAY ISOLATION VALVES 05-25-12 r-- Rev. INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 11.0 0CAPIT Do EC #: SAMA IP3-019
~ i!;.lt~ll'l:el.k Monitoring Instrumentation for ISLOCA Pathway Isolation Valves I
I PRO.IECT TAKEOFF: JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD ESTIMATOR RCMT EST STATUS: ORIGINATOR: ORIG. DATE: 06-25-2012 MANHOURS MATERIAL$ MATERIAL LABOR SUB-UNIT I FCTR TOTAL I DOLLARS I CONTRACT I 1 HM DESCRIPnON QTY UOM CFT NO. $/MH I PER UNIT I DOLLARS TOTAL$ OUTAGE WORK
- 1. Gather and stage tools and materials, Perfonn walkdO\\,'n and briefing 1 LT PF 2 10.00 uo 34 $ 120.71 $ 6.977 $ 6,977
- 2. Gather and stage too!s and materials, Perform wa!kdown and brief1na 1 LT EL 2 10.00 1.70 34 $ 123.32 $ 7,128 $ 7,128 3.
Stage, erect & modify scaffolding as required 1 LT CP 2 80.00 1.70 272 $ 96.00 $ - $ 44,390 $ 44,390 4, Stage, erect & modify scaffolding as required 1 LT LB 1 80.00 1.70 136 $ 78.65 $ $ 18,184 $ 18,184
- 5. Remove ex:isting cap and install new pipe/valve/cap sub assembley(14 valve locations). 14 EA PF 2 10.00 1.70 476 $ 120.71 $ 97,679 $ 97.679
- 6. Mount new transmiter, valve manifold and support 15 EA PF 2 10.00 1.70 510 $ 120.71 $ 375,000 $ 104,656 $ 479.656 7, Route and support new tubing between valve manifold and new pipina 14 EA PF 2 15.00 uo 714 $ 120.71 $ 18,000 $ 146,518 $ 164,518
- 8. Weld new sockole1 to 14" existing pipe. 1 EA PF 2 12.00 1.70 41 $ 120.71 $ 8,413 $ 8,413
- 9. Mount Prefabricated piping/valve sub assemblie to socklet. 1 EA PF 2 10.00 1.70 34 $ 120.71 $ 6,977 $ 6,977
- 10. Route and support new tubing between valve manifold and new piping 1 EA PF 2 15.00 170 51 $ 120.71 $ 10,466 $ 10,466
- 11. NDE containment welds welds 60 EA NM 1 1.00 1.70 102 $ 87.00 $ 15,086 $ 15,086
- 12. Support testing as requested 1 LT PF 2 20.00 1.70 68 $ 120.71 $ 13,954 $ 13,954
- 13. Mount Hoffman boxes in containment 2 EA EL 2 6.00 1.70 41 $ 123.32 $ 8,595 $ 8,595
- 14. Route & Support Conduit from each Transmitter in containment to containment Hoffman Enclosure. 450 LF EL 2 0.18 170 275 $ 12332 $ 4.000 $ 33.913 $ 37,913 15.
Route and support conduit from {2] Hoffman boxes 2 LT EL 2 40.00 1.70 272 $ 3,000 $ 33,543 $ 36,543 to penetration and tie in with external conduit $ 123.32
- 16. Pull cable from each transmitter to Hoffman boxes and terminate at transmitter and Hoffman box l LT EL 2 100.00 uo 340 $ 8,000 $ 41,929 $ 49,929 terminal stnps. $ 123.32 Pufl cable from 2 Containment boxes to external
- 17. 1 LT EL 2 80.00 1.70 272 $ 9,000 $ 33,543 $ 42,543 Hoffman Panel and enclosure and terminate. $ 123.32 18 Provide testrng as required. 1 LT OP 2 100.00 1.00 200 $ 100.00 $ - $ 20,000 $ 20,000
- 19. Assist with testing as required 1 LT EL 2 40.00 uo 136 $ 123.32 '$ - $ 16,772 $ 16,772 20 Dismantle scaffolding to storage 1 LT CP 2 40.00 1.70 136 $ 96.00 $ - $ 22,195 $ 22,195 21.
Dismantle scaffolding to storage 1 LT LB 1 40,00 uo 68 $ 78.65 $ $ 9.092 $ 9,092 22 Cleanup and restore area 1 LT EL 4 10.00 uo 68 $ 123.32 $ - $ 8,386 $ 8,386 23, Cleanup and restore area 1 LT PF 4 10.00 uo 68 $ 120.71 $ - $ 8,208 $ 8,208 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP PT - $ $ $
2 PAINTING & TOUCH-UP PT - $ - $ - $ FIRE WATCH I BOTILEWATCH REQUIREMENTS 1 2. CRAFT SUPPORT FOR FIRE WATCH CRAFT SUPPORT FOR SO TILE WATCH 2 1 lT LT FW FW 1 120.00 1.00 240 $ 53.60 $ 12,864 $ 12,864 MISC SUB-CONTRACT MISC SUB-CONTRACT Commercial Grade 1. Dedication 1 LT NM $ 25,000 $ 25,000 SUBTOTAL CRAFT & SUB-CONTRACTOR 5}58 $ 720,000 $ 842,199 $ 45,880 $ 1,608,079 LT 461 $ 146.27 $ $ 67,430 $ 67,430
$ 720,000 $
' RELA TEO COSTS'
- 1. WALKDOWN ALLOWANCE 1 LT EL 20 $ 123.32 $ 2,466 $ 2,466
- 2. WALKDOWN ALLOWANCE 1 lT PF 30 $ 120.71 $ 3,621 $ 3,621 3, WORK PACKAGE REVIEW 1 LT EL 30 $ 123.32 $ 3,700 $ 3,700
- 4. WORK PACKAGE REVIEW 1 LT PF 30 $ 120.71 $ 3,621 $ 3,621
- 5. TOOL ROOM ATIENDANTS (-3.5%) 1 lT EL 218 $ 123.32 $ 26,884 $ 26,884 6, GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 90.963 $ 90,963
- 7. CRAFT IN PROCESSING (20%) $ 181,926 $ 181,926
- 8. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 18,193 $ 18,193 (1/2 day training, or- 2%)
SUBTOTAL 6,547 $ 720,000 $ 1,241,003 $ 45.880 $ 2,006,883 PLANT SCOPE
- 1. MECH MAINTENANCE PL $ $ $
PL $ $ $ SUBTOTAL MECH MAINT. $ $ $ $
- 1. ELECT MAINTENANCE EL $ - $ - $ -
PL $ $ - $
- 1. I&C Dev. Calibration and Maintenance Procedures 1 lT PL 2 120.00 1.0J 240 $ 100.00 $ - $ 24,000 $ 24,000 SUBTOTAL I&C MAINT. 240 $ $ 24,000 $ - $ 24,000 IPEC00270273
Page 5 of 5 B/112012 9:12AM SAMA IP3*0191NSTALL LEAK MONITORING INSTRUMENTATION "OR ISLOCA PATHWAY ISOLATION VALVES 06-25-12 3 0 INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET 0CAPIT 001 EC #: SAMA IP3-019 PROJECT ~T ll;:lW/'ti'ak Monitoring Instrumentation for ISLOCA Pathway Isolation valvr TAKEOFF: JOB LOCATION: Containment & Control Bldgs. PROJECT CODE: TBD ESTIMATOR RCMT EST STATUS ORIGINATOR: ORIG. DATE 06-25*2012 HM 1. DESCRIPTION QTY I.IOM CFT NO. UNIT MANHDURS FCTR TOTAL $/MH MATERIAL$ PER UNIT MATERIAL DOLLARS LABOR DOLLARS SUB* CONTRACT TOTAL$ CSG PL $ - $ $ SUBTOTAL CSG MAINT. - $ $ $ $ - ffi 240 $ 24.000 I$ s 24.00 SUBTOTAL CRAFT/PLANT 6,787 $ 720,000 $ 1,265.003 $ 45,880 $ 2,030,883 IMPLEMENTATION SUPPORT EO/
- 1. WELDING ENGINEERING 1 LT NM 1 120.00 1.00 120 $ 100.00 $ 12,000 $ 12,000
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 120.00 1.00 120 $ 100.00 $ 12,000 $ 12,000
- 3. SYSTEMS ENGINEERING -MECHANICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4.000 $ 4,000
- 4. SYSTEMS ENGINEERING ELECTRICAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 5. SYSTEMS EINGINEERING
- INSTR B. CONTROL 1 LT NM 1 60.00 1.00 60 $ 100.00 $ 6,000 $ 6,000
- 6. SYSTEMS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 700.00 1.00 700 $ 120.00 $ 84,000 $ 84,000 8 TRAINING OPS STAFF 12 LT NM 1 4 00 1.00 48 $ 120.00 $ 5,760 $ 5,760
- 9. QA I OC VERIFICATION 1 LT NM 1 300.00 1.00 300 $ 100.00 $ 30.000 $ 30.000 10.
11 CHEMISTRY HP I RPI ALARA 1 1 LT LT NM NM 20000 1.00 200 10000 20,000 20,000 1 $ $ $
- 12. WORK MANAGEMENT 1 LT NM 1 200.00 1.00 200 $ 100.00 $ 20.000 $ 20,000
- 13. OPS I OPS PROCEDURE SUPPORT AND DEVELOPMENT 1 LT NM 1 120.00 1.00 120 $ 12000 $ 14,400 $ 14,400
- 14. TRAVEL & LIVING EXPENSES CONTRACTOR SUPPORT 1 LT $ - $
- 1. FIS I MODS ENGINEERING - SWEC (lncl Per Diem) 1 LT NM $ - $
2 MODS PLANNING & SCH.- SWEC (lncl Per Diem) 1 LT NM 1 300.00 1.00 300 $ 100.00 $ 30.000 $ 30,000
- 3. FIELD ENGRSIPLAN* SWEC(Incl Per Diem) 1 LT NM 1 320.00 1.00 320 $ 120.00 $ 38,400 $ 38,400 4 QA I QC VERIFICATION 1 LT NM 1 24000 1.00 240 $ 80.00 $ 19,200 $ 19,200
- 5. NDE 1 LT NM $ - $
6 HPIRP 1 LT NM $ $ -
- 7. RADWASTE 1 LT NM
- 8. NURSE 1 LT NM
- 9. ELEVATOR CONTRACTOR 1 LT NM -
- 10. WASTE MANAGEMENT 1 LT NM -
11 HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RENTAL CONTRACTOR 1 LT NM
- 13. VENDOR STOCKING 1 LT NM -
- 14. DECONTAMINATION CONTRACTOR 1 LT NM
- 15. RBC's 1 LT NM -
- 16. SECURITY 1 LT SEC -
- ~
FIREWATCH (Rover) 1 LT NM $ SAFETY(2%) 1 LT NM 136 $ 72.14 $ 9,811 $ 9.811 LOSTTIME ~ 1 LT 655 $ 186.39 $ 122,085 $ 122.085 10,426 $ 720,000 $ 1,700,659 $ 45.880 $ 2,466,539 I I
~
1 FREIGHT, SALES TAX, & CONSUMABLE$ (6%) SUBTOTAL INSTALLATION COST 10,426 *$ 1, 4o,55l ~ 2,509,739
- 1. DESIGN ENGINEERING MECHANICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 2. DESIGN ENGINEERING ELECTRICAL 1 LT NM 1 100.00 1.00 100 $ 100.00 $ 10,000 $ 10.000
- 3. DESIGN ENGINEERING* INSTR & CONTROL 1 LT NM 1 100.00 1.00 100 $ 100.00 $ 10,000 $ 10,000
- 4. DESIGN ENGINEERING CIVIUSTRUCTURAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
~
- 5. CONTRACT ENGR DESIGN SUPPORT 1 LT NM 1 1,700.00 1.00 1,700 $ 120.00
- 6. DESIGN EGN. DCPACCEPTANCE REVIEW 1 LT NM 1 120.00 1.00 120 $ 100.00 SUBTOTAL DESIGN COST .
1. SUBTOTAL INSTALLATION & DESIGN COST CONTINGENCY (50%)
~ '
$ 1,380,870 ESTIMATE SUBTOTAL 12,606 $ 4,142,609 IPEC00270274
ENTERGY Conceptual Design
~ ~~,:~~'~"~~,~~.:,: Indian Point Nuclear Station Unit 3 Package SAMA IP3-052 Rev. 0 ENTERGY INDIAN POINT NUCLEAR STATION UNIT 3 CONCEPTUAL DESIGN PACKAGE For SAMA IP3-052 Open City Water Supply Valve for Alternate AFW Pump Suction Prepared by: Approved by:
ILfLI~.R* r- --...._ ~
~p?-_-- ~~
7
/"
Date: 1- '2. 0-2 0('2. Date: ~~t ~ '0, -'~ "> ( .;., Page 1 of 5 IPEC00270275
ENTERGY Conceptual Design
~~~~~2~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate Page 2 of5 IPEC00270276
ENTERGY Conceptual Design
~ ~~~'~'~"~~~: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP3-052:
Open City Water Supply Valve for Alternate AFW Pump Suction
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy petiormed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-052 in accordance with Entergy design engineering practices. For SAMA IP3-052, resolution is required to determine the changes necessary to provide city water as an alternative backup supply to the Auxiliary Feed Water (AFW) Pumps. This is required should any unanticipated blockage occur in the normal supply line connecting the Condensate Storage Tank (CST) outlet to the AFW Pumps. This package will assess revising as a minimum the applicable Station's operating procedures as the potential solution for the proposed change. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also supportive sketches as required. These descriptive details and sketches provide the basis for initiating the all inclusive conceptual cost estimate for Engineering Change (EC) development and implementation at the Station. Page 3 of5 IPEC00270277
ENTERGY Conceptual Design
~ ;;~,~,~~"~~~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 3.0 EXISTING CONDITIONS Feedwater Supply Normally, feedwater is provided to the AFW pumps from the CST supply header via Isolation Valve CT -64 in the CST's outlet piping. This supply header valve is required to be open during the Station's operation. Any failure of this valve to remain open during the Station's operation, or any blockage condition in the supply line from the CST, will require resolution to restore feedwater to the AFW pumps.
Although it is not a desired supply option to be employed, backup water can be made available from the city water header to the AFW pumps. The city water header is connected to each of the three feedwater pumps suction piping by system block valves that can be opened to allow city water flow to its respective pump: It is available to be used in the event a condition arises when the normal condensate source is unavailable. Control Room In the Control Room there is an existing common alarm, "AUX B.F.P. LOW FLOW", for monitoring pump flow. There is also existing instrumentation displaying "AUX FWP SUCTION PRESSURE" for each pump. 4.0 DESIGN CONSIDERATIONS In an emergent situation, connecting the backup city water supply to AFW pump(s) will require the appropriate "valve lineup" from the city water header to the respective pump. Should this action be necessary, an approved procedure must be available to use for this requirement. 5.0 CONFIRMATION OF DESIGN No physical modification to the Station will be needed for implementing the requirements of this proposed SAMA. This package will revise, or if necessary provide, the appropriate Station actions and operating procedure(s) required for responding to this condition. The package will identify the applicable valves, procedures, and steps required for re-configuring the valve-lineup. The equivalent requirements necessary for restoration of the system to its normal configuration will also be addressed. Page 4 of5 IPEC00270278
ENTERGY Conceptual Design
~ :~~'~'~;,~~,;,: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0
- 6. RECOMMENDED SOLUTION
- 1. Alarm Response Procedure 3-ARP-006 needs to be revised to provide the solution to the issue discussed here. The revision should indicate the considerations and work steps to be employed when it is indicated that city water may be needed as an alternate water source.
Revise the response to alarm "AUX B.F.P. LOW FLOW" to include provisions necessary to resolve the potential issue discussed in this SAMA. The response, as a minimum, should reflect the usage of this alarm in conjunction with the information available on the "AUX FWP SUCTION PRESSURE" indicators.
- 2. Also, necessary changes should be made to any other Station procedures that require actions when implementing this backup option.
- 3. Provide the required training to support implementation of all revised and any new procedures.
Page 5 of5 IPEC00270279
ENTERGY Conceptual Design
~ ~~~~?,~~~E:,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev.O Attachment 1 Entergy Impact Screening Summary IPEC00270280
$Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 96 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required.
~
Engineering Change No.: I P 3- o '; '2 Rev. No.: e: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES Potentiallml!act Civil/ Structural Design Engineering DYES 181 NO
- Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any pipinA engineering design changes or activities?
Electrical Design Engineering DYES Ci(1 NO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settings changes or activities? (SOER 10-1)
Instrumentation and Controls Design Engineering DYES DZ] NO
- Does the proposed activity involve any I&C design or settings changes or activities?
Mechanical Design Engineering DYES I2CJ NO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve anv mechanical desiQn chanQes or activities?
PSA Engineering .YES DNO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis DYES !:it NO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full50.59 Evaluation?
FERC I NERC Impact DYES ~NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
IPEC00270281
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATEO REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS Potentiallmeact ASME Section Ill Specifications DYES IKJ NO
- Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program DYES ~NO
- Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) DYES l'iJ NO
- Does the proposed activity involve anv changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES fill NO
- Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) DYES iZJ NO
- Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program DYES f&l NO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES [RI'NO
- Does the proposed activity impact or involve any change to design, licensing or operations margins?
Reg. Guide 1.97/ PAM (Post Accident Monitoring) DYES D!1 NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE Potentiallmeac~ Electrical Maintenance DYES i8l NO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance DYES l)!l NO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance DYES KJ NO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potential lmoact Nuclear Fuel Design DYES ~NO
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES 181 NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270282
*~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 98 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallm~act Computer Support and Software DYES t'iNO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software Qualitv Assurance (SQA)?
Chemistry and Environmental Impact DYES IRI NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures, or anv changes to the environment?
Radiation Protection (RP) Program Impact DYES ~NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce (or reintroduce) any cobalt containing materials (such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, training or operator actions?
Planning, Scheduling and Outage (PS&O) DYES IXJ NO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) DYES It! NO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering DYES IK] NO
- Does the activity impact or involve anv procurement activities?
PROGRAMS AND COMPONENTS Potentiallm~act ASME Containment In-service Inspection (IWE /IWL) Program DYES gj NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES ~NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270283
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY REL.ATED REFERENCE USE Engineering Change Process EN*DC-115 I
PAGE 99 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potential lm~act ASME In-service Inspection (lSI) Program DYES IEJ NO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES ~NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES 1&1 NO
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve {AOV) Program DYES fi! NO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP&T} Program DYES fll NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES 181 NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid formation or corrosion?
Check Valve Program DYES fiJ NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES ~NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES ~NO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relav or electrical equipment?
IPEC00270284
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 f REV.11 PAGE 100 OF 150 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED} Potentiallm~act Flow Accelerated Corrosion (FAC) Program DYES ~NO
- Does the proposed activity involve any changes (e.g.: configuration, velocity, flow rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAG Program.?
Heat Exchanger Program DYES ~NO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES r8J NO
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES i&fNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES .BJ NO
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program EJ NO
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program DYES J1No
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its Qualification status?
PT Curves DYES ~NO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program DYES KJ NO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES gj NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270285
~Entergy NUCLEAR MANAGEMENT QUALITY RELATED EN-DC-115 I REV.11 MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET60F6 PROGRAMS AND COMPQNENTS (CONTINUED) Potentlallmgact Welding Program DYES ZNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program DYES i:l NO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering DYES )ll NO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
- Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program .YES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES }gNo
- Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES KINO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? I DYES IPEC00270286
ENTERGY Conceptual Design
~ ~~;,~,~,~~~2,,i'~": Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: AFW Pump Suction Flow Arrangement (simplified for clarity)
Page 7 of9 IPEC00270287
ENTERGY Conceptual Design
~ ~~~.~~~~~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 EXJSTlNC 1rcnv 8"-11074 WATER _IUWIT ~*I)
~~~!~--;.. . . .~~~
8J21-F-2DJ4J SH.1 oil SH.2 8 CT-1300 r; ;J I I
~I tl CT-1J01 CT-IJIIZ I t, II' 11'1-111~ ~
4 ,a
#lll2ll 2"
2"SAMPl.E CT-117 CT-111
' wJ/8"
'I.OCATIOH AUX. I "DRAIN F.W.PUWPIJ2 CT-12-11 lURB.CNJilE I!OMD
~ a 0
N I I I I 1..- CT-JJ L-@-- QIE; FC-IIJSS,FC-1 IJIIS SET TO OPEN Figure 1 LcT-64
.FEED PUMPS RECIRC.VAL'IIES FCV-1121,
-1 123 AT 40GPW DECREASING FC-11 JliAS,
'C-11311AS ARE SET TO a.o5E RECIRC.
~ALVES AT 170 GPW INCREASING AND TO ALARM AT 75GPW DECREASING.
AFW Pump Suction Flow Arrangement (simplified for clarity) Ref. Dwg: 9321-F-20183 FLOW DIAGRAM CONDENSATE & BOILER FEED PUMP SUCTION IPEC00270288
ENTERGY Conceptual Design
~ ~:~~~~~,:,~: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4- Estimate Checklist & Maturity Matrix
- 3. FLOW DIAGRAM 9321-F-20183 ............. Condensate & Boiler Feed Pump Suction
- 4. Alarm Response Procedure 3-ARP-006 ..... Panel SCF - Condensate and Feedwater
- 5. Drawing. 9321-F-33613 ............. Front View of Control Board Section B, Panel SCF Page 8 of9 IPEC00270289
ENTERGY Conceptual Design
~ ~~;;"~'~'~,~~,~~,:,: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -052 Rev. 0 Attachment 4 Cost Estimate Page 9 of9 IPEC00270290
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP3-052 PROJECT TITLE: IP3 AFW Pump Backup Water Supply 0CAPITAL 0o&M ESTIMATOR: RCMT JOB LOCATION: IP3 AFW Pump Building PROJECT CODE: TBD Definitive 0 OUTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 06*22*2012 ESTIMATE TOTAL $ 138,378 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C. F. R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-052 in accordance with Entergy design engineering practices. For SAMA IP3-052, resolution is required to determine the changes necessary to provide city water as an alternative backup supply to the Auxilliary Feedwater (AFW) pumps. This package provides for the costs for development of new procedures and/or revision of existing procedures and the cost of training Station Operating Personnel for the use of these procedures. Prepared by: Date: q ~ z o ,...z. o rz IPEC00270291
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
- ESTIMATE LEVEL* EC #: SAMA IP3-052
~- Conceptual PROJECT TITLE: IP3 AFW Pump Backup Water Supply ESTIMATOR: RCMT
- Preliminary JOB LOCATION: IP3 AFW Pump Building PROJECT CODE: TBD
!; - Definitive ORIGINATOR: ORIG. DATE: 06-22-2012 Item Description
- 1. This estimate assumes that this work will be completed during 2014
- 2. This estimate assumes that all work will be performed by IP in-house personneL
- 3. The estimates assumes training for 12 people
- 4. This estimate does not include funding for unreviewed safety questions or NRC submittals, but if required the additional cost will be added.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 5. Estimate Classification System (see Attachment 3, Reference 2). Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The projected costs provide 6. for anticipated billing rate increases of 3% per year. This estimate allows for and includes a contingency factor related to the complexity and location of the work required. The factor is cumulative 7. and progresses as follows: A. Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity - 40% D. Inside Containment - 50% IPEC00270292
~
2 Page 3 of 4 INDIAN POINT IMPLEMENTATION ESTIMATE WORK ~lstimateAFWPpBackup~~~ c:~:~~l~~
-0 EC #: SAMA IP3-052 PROJECT TITLE: IP3 AFW Pump Backup Water Supply CAPITAL l::JO&M TAKEOFF:
JOB LOCATION: IP3 AFW Pump Building PROJECT CODE: TBD ESTIMATOR: RCMT EST. STATUS: 0 OUTAGE 0 NOfHlUTAGE ORIGINATOR: ORIG. DATE: 06-22-2012 MAN HOURS 'MATERIAL$ MATERIA LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT COLLARS COLLARS CONTRACT TOTAL$
- ESTIMATE LEVEL
- rrn-ro- Conceptual Preliminary ENGINEERING ESTIMATE
SUMMARY
NIANHOURS DOLLARS ltr Definitive 01 STUDY, DESIGN, & CLOSEOUT . $ . 02 DESIGN ENGR CONST SUPPORT . $ - General Notes: 03 MODS ENGR SUPPORT - $ . 04 SYS ENGRI S-U ENGR . $ - 05 PROJECT MANAGEMENT 120 $ 14,400 06 TESTING (Calibration & Testing) $ . 07 TRAVEL & LIVING EXPENSES CONTRACT ENGINEERING oa DESIGN ENGR CONTRACT SUPPORT - $ . 09 10 SUPL CONTRACT MODS ENGR MODS PLAN & SCHED .CONTRACT 11 CONTRACT ENGR
- TRAINING SUPPORT ao $ 9,600 NIA TERIALS I NI/SC CONTRACTS 12 MATERIALS $ -
13 OTHER CONTRACTS $ . CONTRACT CRAFT LABOR 14 SWEC CRAFT LABORIWALKDOWN $ - 15 LOST TIME . $ - 16 SWEC DISTRIBS PLANT CRAFT LABOR 17 18 MECH MAINT. ELECTMAINT 19 I&C . $ . 20 CSG . $ . NI/SC SUPPORT 21 QUALITY CONTROL - $ - 22 PLANNING & SCHEDULING - $ - 23 TRAINING 96 $ 11,520 24 CHEMISTRY $ - 25 OPS 320 $ 38,400 26 HP/RP . $ . NIISC CONTRACT SUPPORT 27 QUALITY CONTROL . $ - 28 NDE . $ - 29 HP/RP - $ . 30 RADWASTE - $ . 31 NURSE . $ . 32 ELEVATOR CONTRACTOR . $ . 33 WASTE MANAGEMENT $ - 34 HOUSEKEEPING $ - 35 36 EQUIPMENT RENTAL VENDOR STOCKING 37 38 DECONTAMINATION CONTRACTOR RBC'S 39 SECURITY $ 40 FIRE WATCH (Rover) $ . 41 SAFETY . $ . CONTINGENCY 42 CONTINGENCY $ 14 '784 ESTIMATE SUBTOTAL 616 $ 88,704 Site Encumbrance Premium (20%) $ 11,741 Loaders (30%) $ 31,933 ESTIMATE TOTAL $ 138,378 CON"RUC,KmSUP>OR,(0%0PW>OR~ 1. SUBTOTAL
- RELATED COSTS
- 1 d+/- j$ *
- 1. WALKDOWN ALLOWANCE 1 LT EL $ . $ .
- 2. WORK PACKAGE REVIEW & CRAFT TRAINING 1 LT EL $ . $ .
- 3. TOOL ROOM ATTENDANTS (~3.5%) 1 LT EL $ . $ .
- 4. GENERAL CRAFT DISTRIBS. (10%) $ . $
- 5. CRAFT IN PROCESSING (20%) $ . $
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ - $
~
7. PLANT SCOPE
- 1. MECH MAINTENANCE $ $ $
I =t I . $
- 1. ELECT MAINTENANCE PL . $ - $ . $ .
PL . $ * $ . $ . SUBTOTAL ELECT. MAINT. . $ . $ . $ . $ . IPEC00270293
~
Page4ot4 INDIAN P0 INT IMPLEMENTATION ESTIMATE WORK ~lstimate AFW Pp Backup sp1y 71512012 2:55PM (06-22-12).xts
-0 EC #: SAMA IP3-052
~~cmTAL ROJECT CODE:~~
PROJECT TITLE: IP3 AFW Pump Backup Water Supply TAKEOFF: JOB LOCATION: IP3 AFW Pump Building TBD ESTIMATOR: RCMT EST. STATUS: 0 OUTAGE 0 NON-ouTAGE RIGINATOR: ORIG. DATE: 06-22-2012 MANHOURS 'MATERIAL$ MATERIAL LABOR SUB-ITEM DESCRIPTION QTY UOM CFT NO. UNIT FCTR TOTAL $/MH PER UNIT DOLLARS DOLLARS CONTRACT TOTAL$
- 1. I&C IOev. Instrument Calibration Procedures) 1 LT PL - $ - $ - $ -
SUBTOTAL I&C MAINT. - $ - $ - $ . $ .
- 1. CSG PL $ - $ . $ .
PL . $ * ! $ - $ - SUBTOTAL I -I $ - ! $ -! $ - $ . ttij SUBTOTAL PLANT $ SUBTOTAL CRAFT/PLANT - $ * !$ * $
- I$ .
IMPLEMENTATION SUPPORT
- 1. MODS ENGINEERING LT NM . $ - $
- 2. DESIGN ENGINEERING SUPT DURING CONST LT NM . $ . $
- 3. SYSTEMS ENGINEERING - MECHANICAL LT NM - $
- 4. SYS ENGINEERING- ELECTRICAL LT NM - $ $
- 5. SYS ENGINEERING -INSTR & CONTROL LT NM - $ $
- 6. SYS ENGINEERING- CIVIL STRUCTURAL LT NM - $ $
- 7. PROJECT MANAGEMENT 1 LT NM 1 120.00 1.00 120 $120.00 $ 14,400 $ 14,400
- 8. TRAINING (OPS Staff) 1 LT NM 12 8,00 1.00 96 $120.00 $ 11,520 $ 11,520
- 9. QA I QC VERIFICATION LT NM . $ . $
- 10. PLANNING & SCHEDULING LT NM -. $ - $ .
- 11. HP I RP/ ALARA LT NM $ - $ .
- 12. CHEMISTRY LT NM $ - $
- 13. OPS (DEVELOP/REVISE PROCEDURE($)) 1 LT NM 1 320.00 1.00 320 $120.00 $ 38,400 $ 38,400
- 14. TRAVEL & LIVING EXPENSES LT $ . $ .
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (incl Per Diem) LT NM . $ - $ -
- 2. MODS PLANNING & SCH.* SWEC (Inc! Per Diem) LT NM - $ -
- 3. OSG FIELD ENGRSIPLAN* SWEC(Incl Per Diem) LT NM - $ $
- 4. QA I QC VERIFICATION LT NM . $ - $ .
- 5. NDE LT NM . $ - $ .
- 6. HP/RP LT NM . $ . $ .
- 7. RADWASTE LT NM .
- 8. NURSE LT NM .
- 9. ELEVATOR CONTRACTOR LT NM -
- 10. WASTE MANAGEMENT LT NM .
- 11. HOUSEKEEPING LT NM .
- 12. EQUIPMENT RENTAL CONTRACTOR LT NM
- 13. VENDOR STOCKING LT NM
- 14. DECONTAMINATION CONTRACTOR LT NM -
- 15. RBC's LT NM
- 16. SECURITY LT SEC
- 17. FIRE WATCH (Rover) LT NM $ - $ .
- 16. SAFETY(2%) LT NM $ . $ .
19. LO~ LT $ 536 $ -
- 1. FREIGHT, SALES TAX, & CONSUMABLE$ (6%) $ .
T 536u $ * $ 64,320 $ - $ 64,320 I
- 1. DESIGN ENGINEERING - MECHANICAL 1 LT NM - $ . $ .
- 2. DESIGN ENGINEERING - ELECTRICAL 1 LT NM - $ - $ -
- 3. DESIGN ENGINEERING* INSTR. & CONTROL 1 LT NM -
- 4. DESIGN ENGINEERING* CIVIUSTRUCTURAL 1 LT NM $ $
- 5. TESTING (Instrument Calibration and testing) 1 LT NM . $ . $ . $ -
6. 7. CONTRACT ENGR DESIGN SUPPORT RT 1 1 LT LT NM NM 1 80.00 1.00
.00
$ 9600
~ -
SUBTOTAL INSTALLATION & DESIGN COST 616 $ 73,920 $ -$ 73,920 1, CONTINGENCY ( 20%) $ 14,764 ESTIMATE SUBTOTAL 616 $ 88,704 IPEC00270294
I IPEC00270295
ENTERGY Conceptual Design
~ ~~~"~'~,~~~2,~= Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 TABLE OF CONTENTS SECTION TITLE 1.0 ISSUE
2.0 BACKGROUND
3.0 EXISTING CONDITIONS 4.0 DESIGN CONSIDERATIONS 5.0 CONFIRMATION OF DESIGN 6.0 RECOMMENDED SOLUTION 7.0 PRELIMINARY MATERIAL LIST Attachment 1 Entergy Impact Screening Summary Attachment 2 Conceptual Design Sketches Attachment 3 References Attachment 4 Cost Estimate 2 of5 IPEC00270296
ENTERGY Conceptual Design
~ ~~,~~~,~~:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 1.0 ISSUE Severe Accident Mitigation Alternative (SAMA) IP3-053:
Install a Hydrogen Excess-Flow Supply Valve to Reduce Station Explosion Risk
2.0 BACKGROUND
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-053 in accordance with Entergy design engineering practices. For SAMA IP3-053, resolution is required to shut down hydrogen supply to piping that is leaking. This package provides for a conceptual design to install a non-electric excess flow valve in the Station's hydrogen supply system. The design considerations that follow will address the adequacy of the proposed resolution and the basis for the recommendation to resolve the identified potential issue. The recommended solution will include descriptive details of the proposed design change and also conceptual design sketches as required. These descriptive details, sketches, and the preliminary material list provide the basis for initiating the all-inclusive conceptual cost estimate for engineering change (EC) development and implementation at the Station. 3.0 EXISTING CONDITIONS There are two hydrogen supply piping sources to the Unit 3 Station. A 1-1/2" pipe supplies the Turbine Building and a 1" pipe supplies the Primary Auxiliary Building (PAS). Page 3 of5 IPEC00270297
ENTERGY Conceptual Design
~ ~?;"~'~,~~~~,:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 Once supply valves are opened, any undetected and unconfined piping damage in the hydrogen supply system will result in leaks. In the absence of a hydrogen leak detection system, leaks in the Station's hydrogen supply piping may occur undetected before the unanticipated hydrogen discharge is determined. Any release and accumulation of hydrogen in confined areas creates the possibility of ignition and explosion. For maximum effectiveness, leak detection and resolution is needed immediately at the hydrogen sources supplying the piping systems.
4.0 DESIGN CONSIDERATIONS The two hydrogen supply sources to the Unit 3 Station require a means to detect and prevent hydrogen piping from continuing to leak and accumulate. Installation of a device in the supply piping that will detect this situation and stop the leakage is proposed. 5.0 CONFIRMATION OF DESIGN MALEMA FLOW SENSORS manufactures a hydrogen rated Safety Excess Flow Valve (flow valve) that is installed in a piping system to monitor flow rate. At a preset flow rate the valve will measure flow in the piping and detect for an un-prescribed change of flow. Any pressure differential resulting from a change of flow offsets the spring-loading of the valve's piston and shuts the valve closed. It can be installed so that set-point can be reset by manual intervention only. Once the reason for the occurrence has been determined and addressed, the valve can be manually reset
- 6. RECOMMENDED SOLUTION
- 1. Install a 1-1/2" M-XF Series Safety Excess Flow Valve manufactured by MALEMA FLOW SENSORS in the 1-1/2" pipe that supplies the Turbine Building. Specify the valve to be provided with the Reset built-in. This will eliminate installation of additional piping and hardware that would be needed for the reset feature to be added (see Attachment 3, Reference 3). The built-in reset will ensure that reset can only be done manually at the flow valve's location.
- 2. Install a 1" M-XF Series Safety Excess Flow Valve manufactured by MALEMA FLOW SENSORS in the 1" pipe that supplies the PAS. Specify the valve to be provided with the Reset built-in. This will eliminate installation of additional piping and hardware that would be needed for the reset feature to be added (see Attachment 3, Reference 3). The built-in reset will ensure that reset can only be done manually at the flow valve's location.
Page 4 of5 IPEC00270298
ENTERGY Conceptual Design
~ ~~~~;::.~2.~:: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0
- 3. Provide flow valve calibration and set-point procedure requirements.
- 4. Provide OPS training and procedures required for this addition to the hydrogen supply system.
7.0 PRELIMINARY MATERIAL LIST Item Description Quantity
- 1. MALEMA M-XF Series Excess Flow Valve with built-in Reset, 1 1-1/2"- 300# Flanged, S.S., or equal
- 2. Slip-on Flange, R.F., 1-1/2"- 300#, C.S. 2
- 3. Flange Insulation Kit, R.F., 1-1/2"- 300# 2
- 4. MALEMA M-XF Series Excess Flow Valve with built-in Reset, 1 1"- 300#, Socket Weld, S.S., or equal Page 5 of5 IPEC00270299
ENTERGY Conceptual Design
~ ~?~~~~~~~;: Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 Attachment 1 Entergy Impact Screening Summary IPEC00270300
!I. NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT REFERENCE USE MANUAL PAGE 96 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
INSTRUCTIONS: Identify the potentially impacted and the unaffected areas by checking the appropriate Yes or No block on the Impact Screening Criteria. If a direct determination cannot be made based on the impact screening questions, the detailed questions in Attachment 9.4 may be used to identify potential impacts. The completion of detailed questions in Attachment 9.4 is recommended but not required. Contact potentially impacted groups if assistance is required. S A Rev. No.: Prepared by: Date: DESIGN ENGINEERING DISCIPLINES PotentiallmQact Civil/ Structural Design Engineering .YES DNO e Does the proposed activity involve any civil/ structural (including seismic) design changes, activities or affect coatings? OR Does the proposed activity involve any piping engineering design changes or activities? Electrical Design Engineering DYES lXJ NO
- Does the proposed activity involve any station or switchyard electrical design, large power transformers, or settinQs chanQes or activities? (SOER 10-1}
Instrumentation and Controls Design Engineering DYES lX! NO
- Does the proposed activity involve anv I&C desiQn or settinQs chanQes or activities?
Mechanical Design Engineering .YES DNO
- Does the proposed activity add/remove/replace insulation, aluminum or other metallic/non-metallic sources of debris in the reactor/containment building or involve any mechanical design changes or activities?
PSA Engineering .YES NO
- Does the proposed activity impact or involve changes to plant evaluations or probabilistic safety assessments?
- Does the proposed activity impact or involve changes to the Emergency Operating Procedures, Abnormal Operating Procedures, or Severe Accident Procedures or does it add, remove or modify SSCs included in a Maintenance Rule function?
Nuclear Analysis DYES D(f'NO
- Does the proposed activity impact or involve changes to plant evaluations, Technical Specifications, Technical Requirements Manual, or require a full 50.59 Evaluation?
FERC I NERC Impact DYES Os:f NO
- Does the proposed activity impact or involve change to FERC I NERC or Regional Entity compliance documents? (ex. MOU, ENN/ENS-PL-158, ENS-DC-199, etc.)
.~ ....
IPEC00270301
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE Engineering Change Process EN-DC-115 I
PAGE 97 OF 150 REV.11 ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
DESIGN ENGINEERING PROGRAMS PotentiallmQact ASME Section Ill Specifications DYES lK] NO
. Does the proposed activity add, delete, or modify information required by ASME Section Ill to be contained in a design specification?
Cable and Raceway Program DYES (X1 NO
. Does the proposed activity involve any changes to cable trays, raceways or the associated documentation?
Electronic Databases (EDB) DYES ~NO
. Does the proposed activity involve any changes to electronic databases?
EQ Program (10CFR50.49, NUREG 0588, Reg Guide 1.89) DYES ~NO
. Does the proposed activity involve any new or existing EQ components?
Hydrogen Control Program (10 CFR 50.44) (if applicable) .YES DNO
.. Does the proposed activity impact equipment or materials related to hydrogen control?
Human Factors Program DYES 1X] NO
- Does the proposed activity involve control panel design including layout and labeling, visual displays, operator aids, auditory signals or environment in the control room, cable spreading room, and other control panel locations?
Margin Management DYES (gf NO
- Does the proposed activity impact or involve any change to design, licensing or operations marQins?
Reg. Guide 1.97 I PAM (Post Accident Monitoring) DYES ~NO
- Does the proposed activity involve Reg. Guide 1.97 (Post Accident Monitoring)
Indications? MAINTENANCE PotentiallmQact Electrical Maintenance DYES ~NO
- Does the proposed activity require an Electrical Maintenance review to identify affected procedures, required actions and required training?
I&C Maintenance DYES (X! NO
- Does the proposed activity require an I&C Maintenance review to identify affected procedures, required actions and required training?
Mechanical Maintenance .YES DNO
- Does the proposed activity require a Mechanical Maintenance review to identify affected procedures, required actions and required training?
NUCLEAR ENGINEERING Potentiallmoact Nuclear Fuel Design DYES rxlNo
- Does the proposed activity impact or involve the design, performance or storage of nuclear fuel?
Reactivity Management Program DYES !Xi NO
- Does the proposed activity impact or involve the reactor system, reactor controls, reactor chemistry, related systems, potential core and spent fuel damage, spent fuel, reactor coolant pressure boundary or reactor system procedures?
IPEC00270302
e-- Entergy NUCLEAR MANAGEMENT QUALITY RELA TEO REFERENCE USE EN-OC-115 I PAGE 98 OF 150 REV.11 MANUAl Engineering Change Process ATIACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROCESS OR PROGRAM IMPACT SCREENING CHECKLIST Potentiallmi!act Computer Support and Software DYES tgj' NO
- Does the proposed activity impact or involve changes to plant computer software or firmware or impact Software QualityAssurance (SQA)?
Chemistry and Environmental Impact DYES rzJ NO
- Does the proposed activity impact or involve any changes to plant chemistry requirements, operations or procedures. or any changes to the environment?
Radiation Protection (RP) Program Impact DYES 1KJ NO
- Does the proposed activity impact or involve any changes to the RP program?
- Does the proposed activity involve the potential to introduce {or reintroduce) any cobalt containing materials {such as Stellite) into the primary system?
Operations .YES DNO
- Does the proposed activity impact or involve changes to Operations procedures, traininQ or operator actions?
Planning, Scheduling and Outage (PS&O) .YES DNO
- Does the proposed activity require a PS&O review to identify required design and installation information?
MP&C (Inventory) DYES D!Jl NO
- Does the proposed activity impact or involve any addition or removal of equipment from the inventory?
- Does the proposed activity impact or involve any Procurement of Quality or Augmented Quality material from non-qualified suppliers?
Procurement Engineering .YES DNO
- Does the activity impact or involve any procurement activities?
PROGRAMS AND COMPONENTS PotentiallmJ;!act ASME Containment In-service Inspection (IWE /IWL) Program DYES ~NO
- Does the proposed activity impact or involve the containment pressure boundary or associated moisture barriers or a support for the containment pressure boundary?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures to include changes to documented information on these items or additional documented information for these items.
- Does the proposed activity limit access to containment surfaces for inspection?
- Involve disassembly of a bolted connection which forms a portion of the containment boundary?
ASME Appendix J (Primary Containment Leak Rate Testing) Program DYES Q!T NO
- Does the proposed activity impact or involve any changes to primary containment leak rate testing?
IPEC00270303
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED REFERENCE USE EN-DC-115 I
PAGE 99 OF 150 REV.11 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET40F6 PROGRAMS AND COMPONENTS (CONTINUED} Potentiallmeact ASME In-service Inspection (lSI) Program DYES !XfNO
- Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? This includes "software only" changes that do not physically change the hardware like such as re-rating of pressures or temperatures. (ASME Section XI items include ASME Class 1, 2, 3, or 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings.
ASME Section XI Repair I Replacement Program DYES ~NO
- Does the proposed activity involve any mechanical component within the ASME XI program I boundaries? Does the proposed activity add, delete, or modify an ASME Section XI pressure boundary item or a support for an ASME Section XI pressure boundary item? (ASME Section XI items include ASME Class 1, 2, 3, MC, and CC, as well as 831.1 treated as lSI Class 2 or 3 (T2 and T3) components, parts, or appurtenances such as pipe or pressure vessel walls, valve bodies and pump casings).
ASME In-service Testing Program DYES !XrNo
- Does the proposed activity impact or involve any item (safety related or non safety related) that may affect the performance or testing of a safety related pump or valve?
- Does the proposed activity impact the function or functional classification of any pump or valve as stated in the 1ST program documents?
Air Operated Valve (AOV) Program DYES tifNO
- Does the proposed activity impact or involve the design, operation or testing of AOVs?
Buried Piping and Tanks (BP& T) Program DYES f&l NO
- Does the proposed activity impact or involve any changes to piping, coatings, or cathodic protection of Buried Piping & Components?
Boric Acid Corrosion (BAC) Program DYES ~NO
- Does the proposed activity impact or involve any increase in the likelihood of boric acid fonmation or corrosion?
Check Valve Program DYES D!1 NO
- Does the proposed activity impact or involve the design, operation or testing of check valves?
Control Room Habitability Program DYES fRr NO
- Does the proposed activity impact or involve changes that affect the temperature or radiological environmental conditions in the Main Control Room?
Electrical Circuit Breaker, Relay and Electrical Equipment Testing DYES Q{i NO
- Does the proposed activity impact or involve changes to the functional testing of circuit breaker, relay or electrical eQuipment?
IPEC00270304
A NUCLEAR QUALITY RELATED EN-DC-115 I REV.11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 100 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
PROGRAMS AND COMPONENTS {CONTINUED) Potential lmeact Flow Accelerated Corrosion (FAC) Program DYES lxfNo Does the proposed activity involve any changes (e.g.: configuration, velocity, flow
"' rate, pressure, temperature, material, weld location, etc.) to piping systems included in the FAC Program.?
Heat Exchanger Program DYES !XfNO
- Does the proposed activity impact or involve the design, operation or testing of a component in the heat exchanger program?
Predictive Maintenance Program DYES MNo
- Does the proposed activity impact or involve any aspect of the storage, use and testing of lubricants?
- Does the proposed activity involve thermography?
- Does the proposed activity involve vibration monitoring?
Microbiological Induced Corrosion (MIC) Program Impact DYES t&fNO
- Does the proposed activity involve piping containing untreated or stagnant water or open to the atmosphere?
Motor Operated Valve (MOV) Program DYES D!a'No
- Does the proposed activity impact or involve the design, operation or testing of MOVs?
Plant Thermal Performance Program DYES DnNo
- Does the proposed activity impact or involve plant thermal performance?
Preventive Maintenance Program DYES ~NO
- Does the proposed activity impact or involve periodic testing or performance of SSCs? or
- Does the proposed activity add, modify or delete any Environmental Qualification (EQ) maintenance requirement or replacement frequency to ensure the component(s) maintains its qualification status?
PT Curves DYES (MNO
- Does the proposed activity add, delete, or modify the basis (as contained in each sites reactor vessel surveillance material testing program) for the Pressure I Temperature Limit Curves (fluence, pressure, temperature, reactor materials)?
Relief Valve Program .YES DNO
- Does the proposed activity impact or involve the design, operation and testing of relief valves, safety valves, vacuum breaker valves or rupture disc?
RPV Internals Program DYES lit NO
- Does the proposed activity impact or involve any change to the reactor internals?
This includes "software only" changes that do not physically change the hardware such as re-rating of pressures or temperatures.
- Does the proposed activity impact or involve or related documentation to include neutron fluence or neutron fluence calculations?
- Does the proposed activity impact or involve or changes to core flow characteristics or core flow characteristics?
IPEC00270305
!!\ NUCLEAR QUALITY RELATED EN-DC-115 I REV. 11
~Entergy MANAGEMENT MANUAL REFERENCE USE PAGE 101 OF 150 Engineering Change Process ATTACHMENT 9.3 IMPACT SCREENING
SUMMARY
SHEET60F 6 PROGRAMS AND COMPONENTS {CONTINUED} Potentiallmeact Welding Program BYES DNO
- Does the proposed activity impact or involve a special process, such as welding, brazing or soldering?
Safety Program BYES DNO
- Does the proposed impact or activity involve personnel or industrial safety?
System Engineering BYES DNO
- Does the proposed activity impact or involve any changes to system configuration, function or performance, etc., for Maintenance Rule or other system?
. Does the proposed activity impact or involve any changes to system procedures, maintenance or operation, etc.?
Training Program BYES DNO
- Does the proposed activity involve existing training requirements or create the need for new training?
Simulator Impact DYES lXI NO
. Does the proposed activity impact or involve changes to the Simulator?
Fire Protection Program DYES fXI NO
- Does the proposed activity result in a change to the Fire Protection Program (including 10CFR50 Appendix R) where the impact is more than negligible?
Detailed Impact Screening (Attachment 9.4) Attached? DYES 11! NO IPEC00270306
ENTERGY Conceptual Design
~ ~:;:~~~£~,~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 Attachment 2 Conceptual Design Sketches
- 1. Figure 1: PAB Hydrogen Supply- Flow Diagram
- 2. Figure 2: PAB Hydrogen Supply- Shed Location
- 3. Figure 3: PAB Hydrogen Supply Shed Excess Flow Valve Location
- 4. Figure 4: Turbine Building Hydrogen Supply- Flow Diagram
- 5. Figure 5: Turbine Building Hydrogen Supply- Crib Location
- 6. Figure 6: Turbine Building Hydrogen Supply- Crib Excess Flow Valve Location IPEC00270307
ENTERGY I Conceptual Design Indian Point Nuclear Station l Package Unit 3 SAMA IP3-053 Rev. 0 NEW PAB HYDROGEN SUPPLY EXCESS FLOW VALVE FILL NON-CONSERVATION _B.e_M~ ARRES~I3_
--....1--- __
1" l "-~758 VOLUME COI,TROL TANK (CVCS) HS-: 882F P..-\1:3 PT ---o 5 -- I "-t758 31 4 l"l--i* f-*-*....J'\._3!4-IJD-2503 HS-18630 9 R 1-WD-2503 3/4" I /2 HS-35 I /2"-~758 31 4" HS-32 r:l 112" 1/2" l/2"-ti7S8 t*S-36 1S-31 I I 3/4"_} HYDROGEN MANIFOLD ENCLOSURE (FUEL STORAGE BLDG
-- --- ~------ --~-- -- *- *----*---- _ _I FIGURE 1 PAB HYDROGEN SUPPLY FLOW DIAGRAM IPEC00270308
ENTERGY Conceptual Design I
~ ~;~~n.,~',~,?,~,:~ tndian Point Nuclear Station Unit 3 SAMA IP3-053 Package Rev. 0 i---***- "----*----"--'-- -*---**- *- ****-~--***-
, *~'"" ~---'
-*~*--*****--** -*****-**- .. ---~~--**~***'"-'-
.,;'-'h..._
~J\-IA) fl_..,
...i .,.,,~:*! *.
!: -"i' I
\
\ f
't i
..t_-;": .. ..:.,.
"** '!\ '. ' }'::t -* ~ *r- > :. 5 4' <r<,H '
*r:J..J:y~*~~;~::-~rx~-~t;.,:,~~--**':~::**:*~:~~-*~*.
.~~~~~~~
FIGURE 2 PAB HYDROGEN SUPPLY SHED LOCATION IPEC00270309
ENTERGY Conceptual Design Indian Point Nuclear Station Package ~--..-. . . . . . . .- - 1 Unit 3 SAMA IP3 -053 Rev, 0 INSTAtL NEW HYDROGEN SUPPLY EXCESS FLOW VALVE
£!.~URE 3 PAB HYDROGEN SUPPLY SHED IPEC00270310
I ENTERGY ConceptuaJ Design tndian Point Nuclear Station Package I Unit 3 SAMA IP 3-053 Rev. 0
/ EXP:...CSION PROOF
~- & ALARM
___.--- M:JUNTED ON
~---- TOP OF CABINET.
\ r
\/ .518"
\r
\\
rfu
~_:.;-4 n~'tiI LCl',.J ?RESSURE SWIT:H MCUNTED O'J SIDES OF CABINET (TYP. )
I
'I
~~~~---.~~-- ~~~~~
I SET i
?SW'P I 870 i
HS-25
- HS-87 HS-6 HS-8 _j c..
~CROSS HS-7B lL I w;uN:T tl! :::J >-
__j
/ CON-ED DWG. (J)
!L 1 A~2Q038l w !L
/ >
H
- )
(f) 1-(.) u..: TO TURBINE BLDG a: > cJ.J 1-(.)
/ 3" GUARD PIPE > a:
[ oc 1 1/2' l 112" w
~ HYDROGEN STORAGE CONTROL IP3V C288-0007
~ABINET ~I -....
N1 NEW TURBINE BLDG (Y"\RD "\REA) HYDROGEN SUPPLY "' EXCESS FLOW VALVE FIGURE 4 TURBINE BUILDING HYDROGEN SUPPLY FLOW DIAGRAM IPEC00270311
TechnoloQies Indian Point N Jhi~ Shuf\t' .:;f s~-:..-n~ S*)lUfi.:~.*i~ unit 3 WATER fACTORY TURBINE GENERATOR BUILDING HEATER BAY DISCHARGE POWER CANAL CCNVERSlON EQUIPMENT BUlLDlNG CONDENSATE POLISHER INTAKE STRUCTURE ~ c:.=J! =:J! ---,c:.;.:r..:...::.Jc.:.Jw FIGURE 5 URBINE BUILDING HYDROGEN SUPPLY CRIB LOCATION IPEC00270312
ENTERGY indian *PointNuclear Siath:m Unit 3 Co*r*. ,c-.*.Package SAMA IP3AJ53 e**p * . *.a.*I*.*D* e**.s.* igh
.***.*.tu !*. *. * * ~
R6v. 0
.* .*. ..! [*. .
NSTALl NEVV 4YDROGEN SUfPLY
- XCESS FLOW VALVE FIGURES TURBINE*BuiEDING HYDROGEN SUPPLY CFUB IPEC00270313
ENTERGY Conceptual Design
~ ~~~,~~,~~~2!,:~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 Attachment 3 References
- 1. ENTERGY Nuclear Management Manual, Engineering Change Process, Rev 11
- 2. Association for the Advancement of Cost Engineering (AACE),
Cost Estimate Classification System- As Applied In Engineering, Procurement, and Construction for the Process Industries
- TCM Framework: 7.3- Cost Estimating and Budgeting
- Figure 4 - Estimate Checklist & Maturity Matrix
- 3. Resolution of Generic Safety Issues: Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (NRC NUREG-0933 with Supplements 1-33)
(attached here)
- 4. MALEMA FLOW SENSORS Model M-XF Series Safety Excess Flow Valves (attached here)
- 5. MALEMA Excess Flow Valve with built-in Reset (attached here)
IPEC00270314
Resolution of Generic Safety Issues: Issue 106: Piping and the Use of Highly Combustible Gases in Vital reas (Rev. 2) (NUREG-0933, Main Report with Supplements 1-33) DESCRIPTION Historical Background Combustible gases such as H2 , propane, and acetylene are used during normal operations of nuclear power plants in limited quantities and for relatively short periods of time. the most prevalent these gases in nuclear plants, is used as a coolant for electric generators in both BWRs and PWRs, for the control reactor water chemistry and waste gas disposal in PWRs, and in the volume control tank (VCT) which is usually located in the auxiliary building of PWRs. It is stored as high pressure in vessels and is supplied to the various systems in the auxiliary building through standard piping, usually 3/4-inch in diameter. As a result, H 2 piping is field-run and its location is plant-specitlc. The concern in this issue is that leaks or breaks in the H2 piping and supply system could result in the accumulation of a combustible or explosive mixture of air and H 2 within the auxiliary building. Inasmuch as the auxiliary building is a safety-related structure which houses most of the components of the safety-related systems of a plant, the accumulation of combustible or explosive mixtures of gas represents a threat to plant safety by virtue of the potential disablement of safety-related equipment, in the event that the combustible gases are inadvertently ignited. H 2 detectors can signal the presence and accumulation of gas, but these are not qualified as safety-grade equipment and do not have an emergency power source. Thus, they are not regarded as sufficient protection against the development of H~ leakage and subsequent uncontrolled combustion or explosion. This issue primarily affected operating reactors licensed prior to the issuance of SRPlL Section 9. 1, "Fire Protection," which addresses the safe use of combustible gases on site. This was identit1ed in NURE0-07051'1 and is related to Issue 136, "Storage and Use of Large Quantities of Cryogenic Combustibles on Site." Whereas Issue 106 addressed normal process system use of relatively small amounts of combustible gases on site, Issue 136 addressed the considerably greater hazards of much greater amounts of combustible materials introduced by new needs at sites, solid waste processing and BWR H2 water chemistry control and the unique hazards associated with the transport and storage of large quantities of combustibles on site in a cryogenic liquid state. Safety Significance IPEC00270315
The auxiliary building is a safety-related structure housing safety-related system components. Inasmuch as the most frequently used combustible gas (H 2 ) is piped into this building for use in the VCT, there is the potential for leakage and the inadvertent ignition of the ensuing combustion or explosion can cause damage or failure of safety-related equipment, thereby contributing to a possibly significant increase in the core-melt probability of the plant Possible Solution In the event of a piping system break or large leak, large releases of combustible gas and the accumulation of combustible or explosive mixtures in air can be prevented by the installation of excess-flow check valves located close to the source ofthe combustible gas. SRP 11 Section 9.5-1 recommends the use of excess-f1ow check valves. Other measures are needed to reduce the frequency of, or cause of~ combustible gas accumulation accidents from such events as valve malfunctions or leaks, connection or fitting leaks, operations errors, material failures, etc. Plants licensed in accordance with the guidelines of SRP11 Section 9.5-1 were assumed to be not affected by this issue; however, the backfitting of excess-flow check valves at all plants not licensed in accordance with SRP11 9. 5-l plants was assumed. Excess-f1ow check valves were an effective "fix tor piping system breaks, but other such as installation or upgrading of detection systems, changes, procedural changes, etc., will be required for other types of accidental releases. The risk and cost analyses performed for the installation of excess-flow check valves as a fix were extrapolated to develop a proper perspective. PRIORITY DETERMINATION Assumptions It was assumed that, of all the combustible gases routinely used in a nuclear power plant the most significant safety concern was associated with the use ofl-h. Unlike most other used in small quantities at nuclear power plants, H2 is used almost continuously while most other are used intermittently and, most likely, in the presence of trained personnel such as during welding operations. H 2 leaks could continue unnoticed as a result of leaks or pipe breaks that go undetected for a sufficient time to accumulate a combustible mixture. It was assumed that H2 detectors were either not provided (as was the case in an event at Vogtle /ll)l or were inoperative. In addition, it was assumed that operating plants licensed prior to the issuance of SRP11 Section 9.5-1 did not have excess-t1ow check valves in place. This latter assumption was a conservative element in this analysis because it was likely that some the plants licensed prior to SRP11 Section 1 may have already had excess-flow check valves in place. The auxiliary building is a safety-related structure that contains most of the components of the safety systems of a plant. However, the design of this structure and the location of safety-related components within the structure are plant-specit1c. In addition, location of the source and, in particular, the H 2 field-run piping layout are also plant-specific. In view of this, it was not possible to identify a particular damage scenario that represented a bounding IPEC00270316
sequence for the purposes of a analysis. Therefore, a reasonable but not necessarily bounding damage scenario was assumed in order to evaluate this issue. This scenario entailed the assumption of an H 2 piping system leak or break, the accumulation of a combustible mixture within a room or space containing safety-related equipment, an ignition source, and damage contained within that room or space. A PN L analysis 64 of this issue based on a pipe break \Vas extrapolated to estimate the frequency of all events that might result in the release and accumulation of combustible in the auxiliary building. It was assumed that the pipe break frequency (for%" pipe) may be obtained from WASH-1400, 111 but that the probability ofthe accumulation of a combustible mixture. the probability of the availability of an ignition source, and the probability of total demolition of the safety-related redundant equipment are 1 in each instance. This latter assumption was conservative. The scenario that was selected as a reasonable one for this analysis was the loss of both RHR heat exchangers (complete loss of heat sink). Resolution of this issue vvould affect operating plants H 2 and not already in compliance with SRP11 Section 9.5-1 with respect to tb gas piping. Specifically, resolution was anticipated to include all operating PWRs. Therefore, the number affected plants was 4 7 PWRs with an average remaining lifetime of about years. Frequency Estimate H 2 piping is standard piping generally thought to be%" in diameter. Based on the results of WASH-140010 (Tables III 2-1, 2-2), the pipe break frequency for piping less than 3" in diameter was l o- 9/hour per section. In general, it was assumed that the H 2 piping in nuclear plants is comprised of about 25 sections. With 8,760 hours/year and an assumed plant utilization factor of 70%, the frequency of Ib release due to pipe break (t~) was estimated to be: (10-9 )(25 sections)(8760 hours/year)(0.7) = (1.5)(10-4) pipe breaks/RY A review of 96 H 2 accidents by NASA 1030 indicated that about 52% could have been attributed to causes that relate to use of 1-h in a gaseous state and about 48% to causes that relate to the use of l-h in its liquid (cryogenic) state; only about 2% was attributed to piping breaks. Therefore. it was assumed that an accident from a gaseous state cause was ( 52°Al 2%) or 26 times more likely to occur than an H 2 accident due to a pipe break. The probability (P) of an 1-h release (leak) was given by: P (26 )(Probability of Pipe Break) (26)(1.5 X 10-4 ) 3.9 X 10-3 The probability of failing both RHR heat exchangers, t{RHR), is the product of the probability IPEC00270317
of an H 2 leak, the probability of obtaining a combustible mixture, the probability of ignition, and the probability of being in the blast zone. Thus, f(RHR) = (3. 9 x 10"3 )(1 )(1 )(1) 3. 9 x 10-3 . When both trains of the RHR system are inoperable, the TS require plants to proceed to the hot shutdown condition within 12 hours; this requirement was modeled in this analysis as a T3 (PWR) transient. Therefore, an H 2 explosion was modeled as an additional initiating transient (with a frequency of 3. 9 x 10- 3 /year as calculated above). All other initiating transients and LOCA parameters were scaled by (12/8,760 hours/RY) in order to model the occurrence of other random initiators during the 12 hours that the reactor is proceeding to hot shutdown. Finally, using the Oconee 3 PRA as representative of all PWRs, the RHR heat exchangers were modeled as inoperative by setting their representative system unavailabilities to 1. The Oconee PRA was then altered to incorporate the modified initiating event frequencies and the RHR systems unavailability in the affected minimal cut sets for each affected accident sequence. All affected Boolean equations were solved to calculate new core-melt frequencies for all containment failure modes and the affected core-melt frequencies were summed for each of the 7 distinct PWR core-melt categories. Public risk was then determined by summing the products of core-melt frequency and their respective release category dose factor for each release category. The analysis was repeated for a period of 96 hours (4 days) as an approximation of the time necessary to achieve cold shutdown by alternate means such as feed-and-bleed. Based on these details, the following core-melt frequency results were calculated: PWR Base Case = 5.46 X 10-6/RY Adjusted Case = 2.26 X 10-7/RY Reduction in Core-melt =5.20xlo* 6 Frequency /RY Consequence Estimate 6 For the time required to come to hot shutdown (12 hours), the results of a PNL analysis -J indicated that resolution of this issue would result in a risk reduction of 8. 8 man-rem/R Y for PWRs. The total public risk reduction was estimated to be approximately 11,500 man-rem. The estimated occupational risk reduction due to accident avoidance was approximately 13 5 man-rem. Cost Estimate Industry Cost: The cost of installing excess-f1ow check valves in the H 2 lines outside ofthe safety-related areas was estimated.(J'l It was assumed that these valves would be installed during scheduled reactor shutdown periods so that there would be no additional power replacement cost incurred. Based on two vendor quotations, the average cost of one excess-f1ow valve was approximately $870. The costs for the implementation, maintenance, and IPEC00270318
operation of the excess-flow check valve "fix" was detailed as follows: (a) Implementation Hardware Design and = 2 days Review Procurement = 1 day Pre-Installation Check = 0.5 hour/valve Installation = 2 days/valve [1 man-day/valve (welder), 1 man-day/valve (fitter)] Post-Installation Check = 1.5 hours/valve Documentation = 0.5 day Total Labor Time (PWR) = 3.5 days+ 2.25 days/valve
= 8 days Labor Cost (PWR) = (8 days)($2,270/man-week)/(5 days/man-week)
= $3,632/plant (b) Equipment Valve Cost (PWR) = (2)($870)
= $ 1,740/plant The total implementation cost/plant was $(3,632 + 1,740) or $5,372; for all47 affected plants, this cost was approximately $255,000.
Operation and maintenance would include a semi-annual check of the installation to ensure that the valve shaft was not "frozen" and replacement of the valve diaphragm as needed; the frequency of this replacement would depend upon the valve environment. For this analysis, the diaphragm was assumed to require replacement every 7 years with an associated labor requirement of 0.5 man-day. (a) Labor for Maintenance and Operation Semi-annual Check = 2 hours/valves Diaphragm replacement required (average plant life/7-year replacements) over the remaining lifetime at 4 hours per replacement. Labor (PWR) = (2 hours/valve )(2 valves )(2 checks/year)
+ (27.7 years/7 years)( 4 hours/valve)(2 valves)/(27.7 years)
= 8 hours/year( checks) + 1.14 hours/year (average diaphragm replacement) 9.14 hours/RY Labor Cost = (9 .14 hours/RY)($2,270/man-week)/( 40 hours/man-week)
= $519/RY.
IPEC00270319
Thus, the operation and maintenance cost was ($519/RY)(47 plants)(27.7 years) or $675,686 and the total industry cost for the resolution of this issue was approximately $(255,000 + 675,000) or $930,000. NRC Cost: Development of the implementation of the solution, including the formulation of guidelines and documentation requirements, and review and inspection of the final installation were estimated to cost (4 man-weeks) ($2,270/man-week) or $9,080. Implementation costs were estimated to be (0.6 man-week/plant)($2,270/man-week) or $1 ,362/plant; for the 4 7 affected plants, this cost was $64,000. Review and inspection of plant operation and maintenance activities were estimated to be (0.5 day/plant-test)(2 tests/year) or 1 day/RY; at a daily rate of [($2,270/man-week)/(5 days/man-week)], this cost was $454/RY. For 47 plants with an average remaining life of 27.7 years, the operation and maintenance cost was estimated to be (47 reactors)(27.7 years)($454/RY) or $591,000. Thus, the total NRC cost was estimated to be $(9,080 + 64,000 + 591,000) or $664,000. Total Cost: The total industry and NRC cost associated with the possible solution was estimated to be $(930,000 + 656,000) or approximately $1.5M. Installation of excess-flow check valves was considered a satisfactory "fix" for the possibility of sudden accumulation of combustible or explosive mixtures of H2 resulting from a piping system break, but it was not a solution for H2 accidents arising from slow leaks in valves or fittings, purging errors, material degradation problems, contamination, etc. Other "fixes" are required to reduce or preclude H2 accidents from scenarios other than pipe breaks. These other "fixes" would include the installation or upgrading of existing H 2 detection and alarm systems, completion of combustible gas system design reviews and modifications to plant design and hardware, operating procedure reviews and modifications, improved preventive maintenance programs, and major modifications to the auxiliary building ventilation system. For an assumed population of 47 plants, the total industry cost of these other "fixes" would be very much more than the costs estimated for the very restrictive "fix" (excess-flow check valves) estimated by PNL. Therefore, the cost of the other "fixes" was assumed to be an order of magnitude greater than that calculated for the installation of excess-flow check valves. Thus, the total estimate for complete resolution of the issue was at least $15M. Value/Impact Assessment Based on a potential public risk reduction of 11,500 man-rem a cost of $15M for a possible solution, the priority score was given by: Other Considerations 6 Based on the potential reduction in core-melt frequency of 5.2 x 10- /RY for PWRs, the cost IPEC00270320
savings from accident avoidance was ($1.65 billion)(5.2 x 10-6 /RY) (47 reactors)(27.7 years) or approximately $11.4M. 64 CONCLUSION For the potential reduction in both public risk and core-melt frequency, a medium priority was appropriate, regardless of potential cost, unless the value/impact score was greater than 3,000 man-rem/$M, in which case, a high priority would be appropriate. For the value/impact score to be $3,000 man-rem/$M, the total industry resolution cost could not exceed about $3.8M. Based on the relatively detailed estimate of the cost of excess-flow check valve installation (~$1.6M), which was only a small portion of the total "fix," and extrapolation, it appeared very unlikely that this issue could be completely resolved for less than $4M. Therefore, the issue was given a medium priority (See Appendix C). The staffs technical findings and regulatory analysis were reported in NUREG/CR-5759F+/-l and NUREG-1364, 154 ~ respectively. The issue was RESOLVED with no new requirements1 "*4
- 6 1547 and Generic Letter 93-06 was issued to inform OLs and CPs. However, RES recommended that the SRP11 be revised to: (1) include the information contained in Generic Letter 93-06 15-41 ;
and (2) reference EPRI NP-5283-SR-A, 154 x "Guidelines for Permanent BWR Hydrogen Water Chemistry Installations- 1987 Revision"; the latter recommendation was consistent with the RES recommendation made with the resolution of Issue 136. Consideration of a 20-year license renewal period would not affect the resolution of Issue 106. Privacy Policy I Site Disclaimer Wednesday, November 03, 2010 IPEC00270321
excess IPEC00270322
Oft IPEC00270323
IPEC00270324 IPEC00270325 IPEC00270326 ENTERGY Conceptual Design
~ ~:'~"~'~,~~~~ Indian Point Nuclear Station Unit 3 Package SAMA IP3 -053 Rev. 0 Attachment 4 Cost Estimate IPEC00270327
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
*ESTIMATE LEVEL* EC #: SAMA IP3-053 PROJECT TITLE: Hydrogen Excess-Flow Valve Installation " CAPITAL 0 O&M ESTIMATOR: RCMT JOB LOCATION: Fan Room, Yard Area PROJECT CODE: TBD Definitive OUTAGE 0 NON-OUTAGE ORIGINATOR: ORIG. DATE: 06/22/2012 ESTIMATE TOTAL $340,790 REVISION 11-0 Summary of Change:
In accordance with NRC environmental regulations in 10 C.F.R. Part 51, Entergy performed SAMA analyses for both Indian Point Nuclear Generating Units 2 and 3 as part of its license renewal application. Those analyses identified a number of potentially cost-beneficial SAMAs for each unit. In its license renewal application and related correspondence with the NRC Staff, Entergy indicated that it would submit the potentially cost-beneficial SAMAs for further internal engineering project cost-benefit analysis, even though none of the potentially cost-beneficial SAMAs is related to aging management under 10 C.F.R. Part 54. Entergy contracted RCM Technologies to assist it in this effort. This package provides a conceptual design and implementation cost estimate for SAMA IP3-053 in accordance with Entergy design engineering practices. For SAMA IP3-053, resolution is required to shut down hydrogen supply piping that is leaking. This package provides for a conceptual design to install a non-electric excess flow valve in the Station's hydrogen supply system. Prepared Approved by: Date: 1-2 0- 2 0 12 IPEC00270328
ENTERGY NUCLEAR NORTHEAST IMPLEMENTATION ESTIMATE Indian Point Nuclear Power Station
- ESTIMATE LEVEL
- EC #: SAMA IP3-053
~ Conceptual PROJECT TITLE Hydrogen Excess-Flow Valve Installation ESTIMATOR RCMT D
Preliminary JOB LOCATION Fan Room. Yard Area PROJECT CODE TBO D Definitive ORIGINATOR: ORIG. DATE: 06/22/2012 Item Description
- 1. This estimate assumes that this work will reauire outaoe conditions to complete
- 2. This estimate assumes that this work will complete during 2014 working a 10 hours per shift, tour days per week schedule
- 3. This estimate assumes that this work will not suffer productivity loss due to radiation, hazardous conditions or QC hold_Q_oints.
- 4. This estimate assumes that ail work will be performed by trained contract craftspersons in lieu of station maintenance personnel.
- 5. This estimate provides for continuous fire watch during cable tray breechina
- 6. This estimate assumes training for 24 Plant Ops. Personnel
- 7. This estimate assumes that the Appendix R Evaluation will be performed by a Contract person for a cost of $250,000.
This estimate is based on the project's current level of scope definition and is classified Class 4 as defined per the AACE International Cost 8. Estimate Classification System (see Attachment 3. Reference 2) Labor dollars in this estimate are projected 2014 costs based on current 2012 craft billing rates at Indian Point. The proJected costs provide for 9. anticipated billing rate increases of 3% per year This estimate aliO'NS for and includes a contingency factor related to the complexity and location of the work required The factor is cumulative 10. and proqresses as follows: A Outside fence boundary - 20% B. Inside fence boundary- 30% C. Implementation complexity- 40% D. Inside Containment- 50% IPEC00270329
s -0 Page 3 of s INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET EC #: SAMA IP3-053 71512012 2:57PM SAMA IP~053 H)'drogen E,)r;ess-Flow Va.* (6-22-12).>ds
~u-~
PROJECT TITLE: Hydrogen Excess-Flow Valve Installation JOB LOCATION: Fan Room, Yard Area DE: TBD ESTIMATOR: RCMT EST. STATUS: 0ourAGE OootHlllfl<iE ORIG. DATE: oel22/2012
'MATERIAL$
ITEM DESCRIPTION QTY UOM MH PER UNIT CT TOTAL$
- ESTIMATE LEVEL
- ESTIMATE
SUMMARY
~ Conceptual Preliminary MANHOURS DOLLARS EO/ ENGINEERING Definitive 01 STUDY, DESIGN, & CLOSEOUT 180 $ 18,000 02 DESIGN ENGR CONST SUPPORT 40 $ 4,000 General Notes: 03 MODS ENGR EOI SUPPORT $
04 SYS ENGRI S.U ENGR 160 $ 1e.ooo 05 PROJECT MANAGEMENT 80 $ 9,600 06 TRAVEL & LIVING EXPENSES $ 07 ENGINEERING DCPACCEPTANCE REVIEW 20 $ 2,000 CONTRACT ENGINEERING 08 DESIGN ENGR CONTRACT SUPPORT 200 $ 24,000 09 SUPL CONTRACT MODS ENGR $ 10 MODS PLAN & SCHED -CONTRACT 40 $ 4.000 11 FIElD ENGRS I PLANNERS 40 $ 4,800 MATERIALS I MISC CONTRACTS 12 MATERIALS $ 9,498 13 OTHER CONTRACTS $ CONTRACT CRAFT LABOR 14 SWEC CRAFT LABORIWALKDOWN 345 $ 35,513 15 LOST TIME 35 $ 4,232 16 SWEC DISTRIBS s 8,922 PLANT CRAFT LABOR 17 MECHMAINT. 10 $ 1,000 1e ELECTMAINT $ 19 l&C 120 $ 12,000 20 CSG $ 111/SC EO/ SUPPORT 21 QUALITY CONTROL 10 $ 1,000 22 NDE 10 $ 1,000 23 OPS fOPS SUPPORT 80 $ 9,600 24 HP/RP eo $ 8,000 25 TRAINING OPS STAFF 48 $ 5,780 MISC CONTRACT SUPPORT 28 QUALITY CONTROL 30 s 2,400 27 NDE $ 28 HP/RP $ 29 WORK MANAGEMENT $ 30 RADWASTE $ 31 NURSE s 32 ELEVATOR CONTRACTOR s 33 WASTE MANAGEMENT $ 34 HOUSEKEEPING $ 35 EQUIPMENT RENTAL CONTRACTOR $ 36 VENDOR .STOCKING $ 37 DECONTAMINATION CONTACTOR $ 38 RBC'S s 39 SECURITY- Waekenhut $ - 40 FIRE WATCH (Rover) $ 41 SAFETY 10 $ 721 CONTINGENCY 42 CONTINGENCY i 36,409 ESTIMATIE SUBTOTAL 1,538 $ 218,455 SITE ENCUMBRANCE PREMIIUM (20%) $ 43,691 LOADERS j30%) s 78,644 ESTIMATE TOTAL $ 340790
- 1. Gather and stage tools and materials 2 LT PF 2 10.00 1.00 40 $ 120.71 $ $ 4,828 $ 4,826 2 Ta~ (close) required valves 2 LT OP 1 2.00 1,00 4 $ 100.00 $ $ 400 $ 400
- 3. Purge or Vent 1"1ine of an Ga.s 1 LT OP 1 8.00 1.00 6 $ 100.00 $ 800 $ BOO
- 4. Purge or Vent 1 1/Z* lin& of ell Gas 1 LT OP 1 8.00 1.00 6 s 100.00 $ $ 800 $ BOO
- 5. Cut and Remove required Section of 1' pipe 1 LT PF 2 8.00 1.00 16 $ 120.71 $ $ 1,931 $ 1,931
- 6. Cut and Remove required Sadion of 1 112 "pipe 1 LT PF 2 B.OO 1.00 18 $ 120.71 $ s 1,931 $ 1,931
- 7. Procure and install new 1" Excess FICW~ Valve 1 LT PF 2 20.00 1.00 40 $ 120.71 $ 4,200.00 $ 4,200 $ 4,828 $ 9,028
- 8. Procure and install new 1 112" Excess Flow Valve, 11,843 1 LT PF 2 30.00 1.00 4,800.00 $ 4,800 $ 7,243 $
Two Flanges and Isolation Ktt eo $ 120,71 $
- 9. Provide testing as required 2 LT OP 1 8.00 1.00 1e $ 100.00 $ $ 1,800 s 1,eoo
- 10. Assist with testing as required 2 LT EL 1 8.00 1.00 16 $ 123.32 $ - $ 1,973 $ 1,973
- 11. Retum Systems to service 2 LT OP 1 4.00 1.00 8 s 100.00 $ $ 800 $ 600
- 12. Cleanup and restore area 2 LT LB 2 4.00 1.00 18 $ 78.85 $ $ 1,256 $ 1,258 PAINTING & TOUCH-UP REQUIREMENTS
- 1. PAINTING & TOUCH-UP 2 LF PT 1 4.00 1.00 8 $ 95.16 $ 20.00 $ 180 $ 761 $ 921
- 2. PAINTING & TOUCH-UP PT $ - $ s .
FIRE WATCH I BOTTLEWATCH REQUIREMENTS
- 1. CRAFT SUPPORT FOR FIRE WATCH 1 LT FW 1 70.00 70 $ 53.80 $ - $ 3,752 $ 3,752
- 2. CRAFT SUPPORT FOR BOTTLE WATCH 1 LT FW $ s s -
MISC SUB-CONTRACT
- 1. MISC SUB-CONTRACT 1 LT $ $
LA~T 282 $ 8.980 $ 27,677 $ $ 36,637 s
;;:h:
- 11. CONSTRUCTION SUPPORT (8% OF 21 $ 98.15 $ $ 2,061 I
SUBTOTAL - ~ ae,~u& IPEC00270330
~
Page 4 of 5 71512012 2:57 PM INDIAN POINT IMPLEMENTATION ESTIMATE WORK SHEET SAMA 11'3-053 H)<lrooen El!r:os>-Fiow V*. - (&-22-12).>05
.() EC #: SAMA IP3~53 PROJECT TITLE: Hydrogen Excess-Flow Valve lnstallaijon Cd CN'IT"- UO&M TAKEOFF:
JOB LOCATION: Fan Room, Yard Area PROJECT CODE: TBD ESTIMATOR: RCMT O=TE~ EST. STATUS: 0C<JTAGE 0NON-ooTAGE ORIGINATOR: MANHOURS 'MATERIAL ITEM OESCRI!'TION QTY UOM CFT NO. UNIT FCTR TOTAL $1MH PER UNIT OOu.ARS C TOTAL$
- RELATED COSTS *
- 1. WALKDOWN ALLOWANCE 1 LT EL 4 $ 123.32 $ 493 $ 493
- 2. WORK PACKAGE REVIEW 1 LT EL 27 $ 123.32 $ 3,330 s 3,330
- 3. TOOL ROOM ATTENDANTS (-3.5%) 1 LT EL 11 $ 123.32 $ 1,357 $ 1,357
- 4. GENERAL CRAFT OUTAGE DISTRIBS. (10%) $ 2,974 $ 2,974
- 5. CRAFT IN PROCESSING (20%) $ 5,946 $ 5,948
- 6. HUMAN PERFORMANCE & ALARA TRAINING 1 LT $ 595 $ 595
- 7. (112 day training, or- 2%)
SUBTOTAL 345 $ 8,960 $ 44.435 $ s 53395 PLANT SCOPE
- 1. MECH MAINTENANCE SUBTOTAL MECH MAINT.
1 LT PL I 1 10.00 1.00 10 $ 100.00 $ 1 1 -
- 1,000 IHfEi
- 1. ELECT MAINTENANCE 1 $ - $ s
!s -Is - s -
~
~ -: ~ -: ~
- ~
- 1. $ $ 12,000 $ 12,000
~
1-140 Is $
- 1. CSG PL $ $ $
SUBTOTAL CSG MAINT. s $ Ct SUBTOTAL PLANT 130 - $ 13000 SUBTOTAL CRAFT/PLANT 475 IMPLEMENTATION SUPPORT EO/
- 1. FIS I MODS ENGINEERING 1 LT NM $ $
- 2. DESIGN ENGINEERING SUPT DURING CONST 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. SYSTEMS ENGINEERING* MECHANICAL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 4. SYSTEMS ENGINEERING- ELECTRICAL 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 s 8,000
- 5. SYSTEMS EINGINEERING
- INSTR & CONTROL 1 LT NM 1 20.00 1.00 20 $ 100.00 $ 2,000 $ 2,000
- 6. SYSTEMS ENGINEERING- CIVIL STRUCTURAL 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 7. PROJECT MANAGEMENT 1 LT NM 1 80.00 100 eo $ 12000 $ 9,600 $ 9,600 B. TRAINING OPS STAFF 12 LT NM 1 4.00 1.00 48 $ 120.00 $ 5.760 $ 5,760
- 9. OA I QC VERIFICATION 1 LT NM 1 10.00 1.00 10 $ 100.00 $ 1,000 $ 1,000
- 10. NDE 1 LT NM 1 10.00 1.00 10 $ 100.00 $ 1,000 $ 1,000
- 11. HP I RPI ALA RA 1 LT NM 1 80.00 1.00 80 $ 100.00 $ 8,000 $ 8,000
- 12. WORK MANAGEMENT 1 LT NM $ - $ -
OPSIOPSPROCEDURESUPPORTAND 13. DEVELOPMENT 1 LT NM 1 eo.oo 1.00 eo $ 120.00 $ 9,600 $ 9,600
- 14. TRAVEL & LIVING EXPENSES 1 LT $ $
CONTRACTOR SUPPORT
- 1. FIS I MODS ENGINEERING- SWEC (lnel Par Diem) 1 LT NM $ $
2. MODS PLANNING & SCH.- SWEC (Inc! Per Diem) 1 LT NM 1 40.00 1.00 40 $ 100.00 $ 4,000 $ 4,000
- 3. FIELD ENGRSIPLAN* SWEC(Inel Per Diem) 1 LT NM 1 40.00 1.00 40 $ 120.00 $ 4,800 $ 4,800
- 4. QA I QC VERIFICATION 1 LT NM 1 30.00 1.00 30 $ 80.00 $ 2,400 $ 2,400
- 5. NDE 1 LT NM $ $
- 6. HPIRP 1 LT NM $ $
- 7. RADWASTE 1 LT NM B. NURSE 1 LT NM 9 ELEVATOR CONTRACTOR 1 LT NM
- 10. WASTE MANAGEMENT 1 LT NM
- 11. HOUSEKEEPING 1 LT NM
- 12. EQUIPMENT RE"'TALCONTRACTOR 1 LT NM 13.
14. VENDOR STOCKING DECONTAMINATION CONTRACTOR 1 1 LT LT NM NM 15. 16. RBC's SECURITY 1 1 LT LT NM SEC
- 17. FIREWATCH (Rover) 1 LT NM .
- ~
- 18. SAFETY (2%) 1 LT NM 10 $ 72.14 $ 721
' Irn"o~. M~ ~,.', ~~~~ im'ro~
1 LT $ 4232 f}}