ML101940236

Instrumentation and Controls Staff Information Requests

ML101940236
Person / Time
Site:	Watts Bar
Issue date:	06/18/2010
From:	Bajestani M Tennessee Valley Authority
To:	Document Control Desk, Office of New Reactors
References
Download: ML101940236 (194)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, TN 37381-2000 June 18, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 10 CFR 50.4 NRC Docket No. 50-391

Subject:

WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - INSTRUMENTATION AND CONTROLS STAFF INFORMATION REQUESTS

Reference:

Licensee Open Items to be Resolved for SER Approval List The purpose of this letter is to provide TVA's responses to NRC's information requests on the "Licensee Open Items to be Resolved for SER Approval List." Enclosure 1 to this letter provides TVA's responses to the information requested by NRC.

The Attachments for Enclosure 1 are contained on the Optical Storage Media (OSM). , Attachment 4, contains the proprietary Sorrento/GA Version 1.1 Software V&V Report. TVA requests that this proprietary Software V&V report be withheld from public disclosure in accordance with 10 CFR § 2.390. In accordance with TVA's agreement with NRC, the proprietary.documents attached to this response are provided for NRC review without affidavits. TVA will provide the non-proprietary version and the withholding affidavit by July 14, 2010. provides the regulatory commitments contained in this letter. I declare under the penalty of perjury that the foregoing is true and correct. Executed on the 1 8 th day of June, 2010.

If you have any questions, please contact William Crouch at (423) 365-2004.

Sincerely, Masoud Bajesa ni Watts Bar*/t 2 Vice President Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 June 18, 2010

Enclosures:

1. Responses to Licensee Open Items To Be Resolved For SER Approval

2. Regulatory Commitments cc (Enclosures):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

U.S. Nuclear Regulatory Commission Page 3 June 18, 2010 GPA: ETK:CLH bcc (Enclosures):

Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Stephen Campbell U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Patrick D. Milano, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08H4 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 G. P. Arent, LP 5A-C*

M. Bajestani, EQB 1B-WBN*

R. R. Baron, EQB 1B-WBN*

A. S. Bhatnagar, LP 6A-C*

M. K. Brandon, ADM I L-WBN*

W. D. Crouch, EQB 1B-WBN D. E. Grissette, ADM 1V-WBN*

S. A. Hilmes, EQB 1B-WBN*

R. M. Krich, LP 3R-C*

D. T. Langley, OSA 1A-BLN*

A. L. Sterdis, LP 5A-C*

E. J. Vigluicci, WT 6A-K*

K. W. Whittenburg, SP 2B-C*

EDMS, WT 3B-K

• These CCs did not receive the attached documents. The attached documents can be obtained by contacting the WBN Unit 2 Licensing office.

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval This enclosure provides TVA's responses to NRC's information requests contained in the "Licensee Open Items to be Resolved for SER Approval List." Each of the following NRC information requests is identified by the unique numbering system utilized in the aforementioned NRC list of open actions.

1. NRC Request (Item No. 19)

Verify that the containmentpurge isolation radiationmonitor is the same as used in Watts Bar Unit 1, or identify any hardware changes.

TVA Response:

TVA letter dated April 27, 2010 (Reference 5--see Reference list on page 23) responded to this request for information (Enclosure 1, Item No. 6) for the ratemeter.

Unit 2 uses a Model RD-52 detector assembly, which is the replacement for the obsolete RD-32 detector assembly used in Unit 1. The detector assembly upgrade is due to component obsolescence and to improve reliability.

2. NRC Request (Item No. 21)

Forthe Foxboro Spec 200 platform, identify any changes in hardware from the precedent systems. Provide the design report and the equipment qualificationinformation.

TVA Response:

A vendor system description is not available for the Foxboro Spec 200 system. The hardware description and qualification documents are provided on a component level basis.

A TVA-generated system description is provided to assist the reviewer. The hardware differences from the Unit 1 systems are provided in the loop and card comparison documents. As agreed with the reviewer, the component level documents are not required to be submitted at this time, but may be required later based on the review of attached documents. The following TVA-generated documents are provided (Attachment 1):

1. Analog loop comparison.

2. Analog card comparison.

3. Analog system description.

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ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval

3. NRC Request (Item No. 41)

Please provide the following Westinghouse documents:

(1) WNA-DS-01617-WBT Rev. 1, "PAMS System Requirements Specification" (2) WNA-DS-01667-WBT Rev. 0, "PAMS System Design Specification" (3) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g" Please provide the following Westinghouse documents or pointers to where the material was reviewed and approved in the CQ TR or SPM:

(4) WNA-PT-00058-GEN Rev. 0, "Testing Processfor Common Q Safety systems" (5) WNA-TP-00357-GEN Rev. 4, "Element Software Test Procedure" TVA Response:

Items (1) and (2) were docketed by TVA letter dated April 8, 2010 (Reference 2).

Items (3), (4) and (5) WNA-CD-00018-GEN Rev. 3, "CGD for QNX version 4.5g," WNA-PT-00058-GEN Rev. 0, "Testing Process for Common Q Safety systems" and WNA-TP-00357-GEN Rev. 4, "Element Software Test Procedure" are available for audit at the Westinghouse Rockville office (Westinghouse letter WBT-D-1 526, Reference 6).

4. NRC Request (Item No. 42)

On December 16, 2009: EICB stated to DORL: "Iam having trouble reading the drawings in the binderthat was given to me. Is it possible to produce a set of full size drawing that are in the FSAR?"

On February23, 2010: EICB received a set of enlarged Chapter 7 FSAR pages (drawings) that are still unreadable.

... Please produce a large and legible set of drawing that are the ones in Chapter 7 of the FSAR.

TVA Response:

Attachment 2 provides a drawing cross reference list for Final Safety Analysis Report (FSAR) Chapter 7 and electronic copies of the legible current drawings previously submitted in full size hard copies.

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ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval

5. NRC Request (Item No. 43)

The PAMS ISG6 compliance matrix supplied as Enclosure 1 to TVA letter dated February5, 2010 is a first draft of the information needed. The shortcomings of the first three lines in the matrix are:

Line 1: Section 11 of the Common Q topical reportdid include a commercial grade dedication program, but this program was not approved in the associatedSE.

Westinghouse stated that this was the program and it could now be reviewed. The NRC stated that TVA should identified [identify] what they believe was previously reviewed and approved.

Line 2: TVA stated the D3 analysis was not applicable to PAMS, but provided no justification. The NRC asked for justification since SRP Chapter 7.5 identified SRM to SEC V-93-087 Item /1.Q as being SRP acceptance criteriafor PA MS.

Line 3: TVA identified that the Design report for computer integrity was completed as partof the common Q topical report. The NRC noted that this report is applicable for a system in a plant, and the CQ topical report did no[t] specifically address this PAMS system at Watts Bar Unit 2.

NRC then concluded that TVA should go through and provide a more complete and thorough compliance matrix.

TVA Response:

Attachment 3 contains the revised Common Q PAMS ISG-6 Compliance Matrix, dated June 11, 2010, that addresses these items (Reference 13). This revised matrix resulted from input that TVA provided Westinghouse.

6. NRC Request (Item No. 44)

The PAMS system describedin Section 7.5 of the FSAR is implemented in various manners. TVA should identify:

(1) Those variables that are implemented identical to what was reviewed and approved for Unit 1.

(2) Those variable that are implemented identicalto Unit 1, but that have been changed (e.g., under 50.59) and not reviewed by the NRC.

(3) Those variables that are implemented in a manner that is unique to Unit 2 (e.g., using Common Q).

TVA should supply supportinginformation appropriateto the manner of implementation.

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ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

The following variable list is contained in FSAR Table 7.5-2, "Regulatory Guide 1.97 Post Accident Monitoring Variable Lists." The first two columns are excerpted from the table to simplify the response to the questions. The notes referenced in the last column follow the table and provide details of the changes or unit differences.

Var. U2 Variable U1 = Ul Unique

1. Variable Name Source U2 50.59? to U2? Notes 1 Auxiliary Feedwater Flow Foxboro Spec N N Y 12,19 200 Containment Lower Foxboro Spec N N Y 1,19 2 Compartment Atmosphere 200 Temperature 3 Containment Pressure Eagle 21 N N Y 12,19 (Narrow Range) 4 Containment Radiation Rad Monitor N N Y 2 5 Containment Sump Level Eagle 21 Y Y N 15,19 (Wide Range) 6 Core Exit Temperature CommonQ N N Y 3 PAMS 7 Main Steam Line Radiation Rad Monitor Y N N 8 Nuclear Instrumentation Source Range N N Y 14 (Source Range) NI 9 RCS Pressurizer Level Eagle 21 N Y y 13, 19, 20 10 RCS Pressure Wide Range Eagle 21 N Y Y 12,19, 20 11 RCS Temperature T Cold Eagle 21 N Y Y 19, 20 12 RCS Temperature T Hot Eagle 21 N Y Y 19, 20 13 Refueling Water Storage Eagle 21 N N Y 12,19 Tank Level 14 Steam Generator Level Eagle 21 N Y y 12, 19, (Narrow Range) 20 15 Steam Generator Pressure Eagle 21 N Y Y 12, 19, 20 16 Subcooling Margin Monitor CommonQ N N Y 3 PAMS 4

ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval U2 Variable U1 = U1 Unique Variable Name Source U2 50.59? to U2? Notes Unit 1 Auxiliary Building Passive Racks Instrument N/A N N/A 4 Sump Level Racks Containment Isolation Valve Valve Limit 18 Position Indication Y N N Switches Containment 19 Containment ConcentrationMoirHydrogen Hydrogen N N Y 5 Monitor 20 Control Rod Position CERPI Y Y N 17 21 Nuclear Instrumentation Intermediate N N 14 (Intermediate Range) Range NI 22 Reactor Vessel Level CommonQ N N Y 3, 13 PAMS 23 Containment Pressure Foxboro Spec N N y 12, 19, (Wide Range) 200 20 24 Shield Building Vent (Noble Rad Monitor Y N N Gas Activity) 25 ABGTS High Pressure Unit 1 N/A N N/A 4 Alarm Per Fan Instruments Unit 1 26 ACAS Pressure Unt Instruments N/A N N/A 4 27 AFW Valve Status Valve Limit Y N N Switches Accumulator Flow Isolation Valve Limit Valve Status Switches 29 Accumulator Tank Level Foxboro IA N N Y 8,12,19 30 Accumulator Tank Pressure Foxboro IA N N Y 8,12, 19 31 Annulus Pressure Foxboro IA N N Y 8, 12,19 Aux. Feed Pump Turbine Valve Limit 32 Steam Supply Isolation Switches Y N N Valve Status 33 Battery Current (125 V DC Ammeter y N N 11 Vital) Shunt 34 Bus Voltage (125V DC Vital) Direct Y N N 11 35 Bus Voltage (480V Direct Y N N Shutdown) 5

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval Var. U2 Variable UI = U1 Unique

1. Variable Name Source U2 50.59? to U2? Notes 36 Bus Voltage (6.9KV PT Y N N Shutdown) 37 CCS Surge Tank Level Foxboro IA N N Y 8,12,19 38 Centrifugal Charging Pump Foxboro IA N N Y 8,12 Total Flow 39 Charging Header Flow Foxboro IA N N Y 8,12 40 Component Cooling Water Foxboro Spec N N Y 1,12 To ESF Flow 200 41 Component Cooling Water Foxboro Spec N N 1,12 Supply Temperature 200 42 Condensate Storage Tank Standalone y N N 11 Water Level loop 43Containment Air Return Fan Breaker limitNN Status switches 44 Containment Cooling Valve Valve Limit y N N Status Switches 45 containment Spray Flow Eagle 21 N N Y 12, 19 Containment Spray HX 46Outlet - Outlet Temperature FobrIA N NY 81 47Containment Sump Water FobrIA N NY 81 47Level (Narrow Range) FxooI ,1 48Containment Sump Water Eagle 21 N N Y 19 48Temperature 49 Diesel Generator Power EI-82-70A Y N N 11 50 Diesel Generator Volts EI-82-66A Y N N 11 51 ECCS Valve Status VleLmt Y N N Switches 52 ERCW Header Flow Foxboro Spec N N 1,1,9 200N NY 1,1,9 53 ERCW Supply Temperature ICS Y Y N 9, 11 54 Emergency Gas Treatment Damper Limit y N N Damper Position Switches 55 Emergency Ventilation Damper Limit y N N 11 Damper Status Switches 56 Hydrogen Recombiner NAN *NY1 Status - Not Used in Unit 2 NAN NY1 6

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval Var. U2 Variable U1 = Ul Unique

1. Variable Name Source U2 50.59? to U2? Notes 57 ~BreakerN N 57 Igniter Group Status Position Y N N 58 Inverter Current (120V ac Ammeter y y N 10 Vital) shunt 59 Inverter Voltage (120V ac Direct Y Y N 10 Vital) 60 Letdown Flow Foxboro IA N N Y 8,12 Common 61 MCR Pressure Pressure Inst. N/A N N/A 6, 11 62 MCR Radiation Level Commonirs N/A N N/A 6,R11 Monitors NA N NA 61 63 Main Feedwater Flow Eagle 21 Y Y N 12,19, 20 64 Normal Emergency Boration Foxboro IA N N Y 8,12 Flow 65 There is no Variable 65 N/A N/A N/A N/A Pressurizer Heater Status 66 (Electric Current) ICS Y Y N PORV &

CODE -

Acoustic Pressurizer Pressure Relief Monit 67 Valve Position (PORV, System Y N N Block, and Code) BLOCK-Valve Limit Switches 68 Pressurizer Relief Tank FoxboroIA N N Y 8,12,19 Level 69 Pressurizer Pressure Relief Tank Foxboro IA N N Y 8,12,19 70 Pressurizer Foxboro IA N N TemperatureRelief Tank Y 8,12,19 71 RCP Seal Injection Flow Foxboro IA N N Y 8, 12, 72 RCS Head Vent Valve Foxboro Spec N N Y 1, 19 Status 200 RHR Heat Exchanger Outlet Foxboro IA N Y Y 8, 12, 20 Temperature 7

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval Var. U2 Variable Ul = Ul Unique

1. Variable Name Source U2 50.59? to U2? Notes RHR Pump Flow (RHR Foxboro IA N N Y 8,12 System Flow) 75 ~Valve LimitN N 75 RHR Valve Status Switches Y N N 76 Reactor Coolant Pump CT Y N N Status (Motor Current) 77 Safety Injection Pump Flow Foxboro IA N N Y 8,12 78 Safety Status Injection System Valve Limit Y N N Valve Switches 79 Spent Fuel Pool Level Common N/A N N/A 6,11 Alarm 80 Spent Fuel Pool Common N/A N N/A 6,11 Temperature Alarm 81 Steam Generator Blowdown Valve Limit N N Isolation Valve Status Switches 82 Steam Generator Level Eagle 21 N 12,19, (Wide Range) 20 83 Main Steam Flow Eagle 21 N Y y 12,19, 20 84 Tritiated Drain Collector Common N/A N N/A 6 Tank Level 85 Volume Control Tank Level Foxboro IA N N Y 8,12 86 Waste Gas Decay Tank Common N/A N N/A 6 Pressure 87 Radiation Exposure Meters Not used N/A N/A N/A 88 Airborne Radio-halogens Portable y N/A N/A and Particulates Monitor 89 Plant and Environs Portable Y N/A N/A Radiation Monitor Plant and Environs Portable Radioactivity Monitor 91 Auxiliary Building Vent Common N/A N N/A 6 (Noble Gas) Rad Monitor 92 Auxiliary Building Vent Common /A N N/A 6 (Flow Rate) Rad Monitor 93 Auxiliary Building Vent Common N/A N N/A 6 (Particulates and Halogens) Rad Monitor 8

ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval Var. U2 Variable U1 = UI Unique

1. Variable Name Source U2 50.59? to U2? Notes Condenser Vacuum Pump Foxboro IA N N Y 8,12 Exhaust Vent (Flow Rate) 95 Condenser Vacuum Pump Rad Monitor N N Y 18 Exhaust Vent (Noble Gas) 96 ERCW Radiation Monitors Common N/A N N/A 6 Rad Monitor 97POST ACCIDENT N/A N/A N/A N/A SAMPLING Grab sample Reactor Coolant Chloride with sa te 97a Cnetainwith onsite Y N Y7 Concentration aayi analysis Grabsml Reactor Coolant Dissolved ab sample 97b Hydrogewith onsite Y N Y Hydrogen analysis Reactor Coolant Dissolved Grab sample 97c with onsite Y N Y 7 Oxygen analysis Reactor Coolant Total Grab sample 97d Dissolved Gas with onsite Y N Y 7 analysis Grab sample 97e Reactor Coolant Boron with onsite Y N Y 7 analysis Grab sample 97f Reactor Coolant pH with onsite Y N Y 7 analysis Reactor Coolant Sample Grab sample 97g Actor with onsite Y N Y 7 analysis Reactor Coolant Gamma Grab sample 97h Spectrumwith onsite Y N Y 7 Spectrum analysis 98 CONTAINMENT AIR N/A N/A N/A N/A Not used 98a Containment Air Hydrogen Deviation 22 N/A N/A N/A 98b Oxygen Content Not Used for N/A N/A N/A WBN 1 or 2 9

ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval Var. U2 Variable UI = U1 Unique

1. Variable Name Source U2 50.59? to U2? Notes 98c Gamma Spectrum Sample Grab Sample Y N N 99 Shield Building Vent Flow Rad Monitor Y N N 100 Shield Building Vent Monitor Rad Monitor Y N N (Particulate and Iodine)

Steam Generator Discharge Acoustic 101 Vent (Flow Rate and Noble Monitor Y N Y 21 Gas) System 102 METEOROLOGY N/A N/A N/A N/A 102a Vertical Temperature Common N/A N N/A 6 Difference 102b Wind Direction Common N/A N N/A 6 102c Wind Speed Common N/A N N/A 6 103 Radiation Exposure Rate Portable N/A N/A N/A Monitor NOTES:

1. In Unit 2, this variable is provided by the Foxboro Spec 200 hardware upgrade.

2. In Unit 2, this variable is provided by the RM1000 digital Containment High Range Radiation monitors.

3. In Unit 2, this variable is provided by the Common Q Post Accident Monitoring System (PAMS).

4. These variables are common for both units and are provided by the Unit 1 systems.

5. In Unit 2, this variable is provided by the single non-safety-related hydrogen monitor.

6. These variables are common for both units and are provided by common systems.

7. These variables are obtained via portable sampling equipment and laboratory analysis.

8. In Unit 2, this variable is provided by the non-safety-related Foxboro Intelligent Automation (IA) Distributed Control System (DCS).

9. In Unit 1, this variable was within the scope of the 10 CFR 50.59 for the Integrated Computer System (ICS) modification which replaced the plant P2500 and Emergency Response Facility Data System (ERFDS) mainframe computers.

10. In Unit 1, this variable was within the scope of the 50.59 for the vital inverter replacement modification.

11. In service for Unit 1 Operation.

12. In Unit 2, the transmitters for this variable have been changed to Rosemount, and the transmitter range has changed to 4-20ma.

13. In Unit 2, the transmitter range for this variable has changed to 4-20ma.

14. The source/intermediate range replacement in Unit 2 uses the same digital component (shutdown monitor), but the analog electronics and detectors have been upgraded.

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ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval NOTES: (Continued)

15. In Unit 1, the transmitter and transmitter configuration were changed to improve reliability due to problems with the fill fluid in the original capillary type transmitters (DCN 39608). This included changing the transmitters, recorder and indicators to 4-20ma technology. Unit 2 copied the Unit 1 change (EDOCR 52419 excerpts submitted March 12, 2010).

16. For Unit 2, the hydrogen recombiners are abandoned in place.

17. Unit 1 replaced the rod position indication with the Combustion Engineering Rod Position Indication system (CERPI) in 2003 (DCN 51072) under 10 CFR 50.59. The Unit 1 system has been upgraded several times, most recently in 2009. Unit 2 copied the Unit 1 system including all upgrades through 2009.

18. In Unit 2, the separate medium and high range monitors are replaced with a single extended range monitor.

19. In Unit 2, the indicators and recorders have been replaced with 4-20ma devices.

20. In Unit 1, the recorders have been replaced due to obsolescence.

21. In Unit 2, the accelerometers and pre-amplifiers have been replaced due to obsolescence. Other components were replaced due to end of qualified life with newer models of the same components.

7. NRC Request (Item No. 481 Reference 16 of the PAMS System Requirements Specification (SysRS) is the Unit 1 PrecautionsLimitationsand Setpoints document [PLS]. When and how will the transition to the Unit 2 document be made.

TVA Response:

To ensure technical fidelity with the Unit 1 ICCM-86 system, the Unit 1 PLS was used as an input to the Common Q PAMS System Requirements Specification. This was done to ensure the Unit 2 PAMS had at a minimum the same capabilities and accuracy as the Unit 1 system.

The Unit 2 Common Q PAMS PLS section was developed based on the actual Common Q PAMS system design as reflected in the System Requirements Specification. As such, the Common Q PAMS PLS section is an output of the Common Q PAMS System Requirements Specification. Therefore, no "transition" from the Unit I to the Unit 2 PLS is required.

The Unit 2 PLS is scheduled to be issued December 13, 2010.

8. NRC Request (Item No. 49)

Pleaseprovide 00000-ICE-30156 Rev. 6. The PAMS SysRS incorporatessections of this document by reference.

TVA Response:

Per Westinghouse letter WBT-D-2024 (Reference 7), this document is available for audit at the Westinghouse Rockville office.

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ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval

9. NRC Request (Item No. 50)

How should the "shall"statements [in the Common Q PAMS System Requirements Specification] outside of the bracketed requirementsbe interpreted?

TVA Response:

These sections are descriptive text and not requirements. The next revision of the Watts Bar Unit 2 PAMS System Requirements Specification will remove 'shall" from the wording in those sections. The next revision of the Unit 2 Common Q PAMS System Requirements Specification will be provided to NRC no later than August 31, 2010.

10. NRC Request (Item No. 54)

Please describe all the different environments in which the RM-1000 will be requiredto operate. Please group these environments into two categories (a) Harsh environment, per 10 CFR 50.49, and (b) Mild Environment.

TVA Response:

The only safety-related application for the RM-1 000 is the Containment High Range radiation monitors. The Containment High Range monitors will be installed in the main control room, a mild environment. The detectors will be installed remotely in the containment.

For WBN Unit 2, a mild environment is defined as:

A defined room or building zone where (1) the temperature, pressure, or relative humidity resulting from the direct effects of a design basis event (DBE) (e.g, temperature rise due to steam release) are no more severe than those which would occur during an abnormal plant operational condition, (2) the temperature will not exceed 130°F due to the indirect effects of a DBE (e.g., increased heat loads from electrical equipment), (3) the event radiation dose is less than or equal to 1 x 104 rads, and (4) the total event plus the 40 year TID (total integrated dose) is less than or equal to 5 x 104 rads. (Reference 3).

11. NRC Request (Item No. 55)

The "QualificationTest Report Supplement, RM-1000 Upgrades,"Document No. 04508905-1SP Rev. A states that the qualificationwas done in accordance with IEEE 323-1974 and -

1983. Please describe andjustify all differences in this qualificationmethodology and that endorsed by Regulatory Guide 1.209. Specifically address EMI and RFI.

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ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

Regulatory Guide (RG) 1.209 endorses IEEE 323-2003 for seismic and environmental qualification. It also endorses EPRI TR 102323 (Sept. 94) for Radio Frequency Interference (EMI-RFI) testing. The major difference between IEEE 323-2003 and IEEE 323-1974 and 1983 is that 2003 contains an allowance that harsh environment qualification testing is not required for Safety-Related Computer-Based Instrumentation and Control Systems located in mild environments. RG 1.209 accepts this allowance.

The RM-1 000 was qualified to the previous versions of IEEE 323 which does not contain an allowance for harsh environment qualification. As a result, the qualification testing of the RM-1000 was done for service in a harsh environment. Therefore, the qualification testing of the RM-1000 exceeds the IEEE 323-2003 requirements of RG 1.209.

The RM-1 000 was tested for Electro-Magnetic Interference and Radio Frequency Interference (EMI-RFI) in accordance with EPRI TR 102323 (Sept. 94) as documented in the Equipment Qualification Test Report submitted under TVA letter dated March 12, 2010, (Reference 4). Therefore, RM-1 000 meets the requirements of RG 1.209 for EMI/RFI testing.

For WBN Unit 2, a harsh environment is defined as:

A defined room or building zone where either (1) the temperature, pressure, and relative humidity resulting from the direct effects of a DBE (e.g., temperature rise due to steam release) are more severe than those which would occur during an abnormal plant operational condition, (2) the temperature will exceed 130°F due to the indirect effects of DBE (e.g., increased heat loads from electrical equipment), (3) the event radiation dose is greater than 1 x 104 rads, or (4) the total event plus the 40-year TID is greater than 5 x 104 rads. (Reference 3)

12. NRC Request (Item No. 56)

The "RM-1000 Version 1.2 Software Verification and Validation Report," Document No.

04508006 Rev. A, is an incrementalreport. That is to say it addresses the verification an[d]

validationfor changes that resulted in Version 1.2; therefore, the NRC has not received a software verification and validationreport for all other aspects of the software. Please provide the last complete verification and validation report, and all incremental reports after the complete report.

TVA Response:

The initial draft Software Verification and Validation (V&V) report document, version 1.0, was never issued.

Attachment 4 contains the latest complete proprietary version 1.1 Software V&V report (04508005). The non-proprietary version and withholding affidavit will be submitted by July 14, 2010. Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 119.

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ENCLOSURE1 Responses To Licensee Open Items To Be Resolved For SER Approval The latest proprietary version is 1.2 (an incremental report that addresses the differences from the version 1.1 report), and was submitted by TVA letter dated March 12, 2010 (Reference 4). Submittal of the non-proprietary version and withholding affidavit is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 101, due June 30, 2010.

13. NRC Request (Item No. 57)

Please describe the ability to change the software of the RM-1000 at site, including all requiredequipment and administrative controls (e.g., temporary digitalconnections).

TVA Response:

Firmware/software changes are done by connecting a laptop to a port on the front of the RM-1000 and placing the Operate/Calibrate switch in the Calibrate position. The first physical barrier to access is the location of the RM-1 000 in the main control room which has limited access. The RM-1000 Operate/Calibrate switch is located behind the hinged front panel. The front panel must be opened (held closed by two thumbscrews) to access the switch. This provides a physical barrier to inadvertent switch operation. The system malfunction alarm is visible locally and will annunciate on the control board when the switch is in the Calibrate position.

Administrative control of software/firmware updates is in accordance with TVA Standard Specification SS-El 8.15.01, Software Requirements for Real-Time Data Acquisition and Control Computer Systems, and TVA procedures SPP-9.3, Plant Modifications and Engineering Change Control, and SPP-2.6, Computer Software Control. Approved changes to software/firmware are implemented utilizing the TVA work order process.

14. NRC Request (Item No. 58)

Please describe all digital communications used in the [RM-1000] installed configuration.

TVA Response:

There are no digital communications between the RM-1 000 and any other plant system or component.

15. NRC Request (Item No. 59)

Previously TVA provided the "RM-1000 DigitalRadiation ProcessorTechnical Manual,"

Document No. 04508100-1TM Revision C dated October 2003. The "RM-1000 Version 1.2 Software Verification and Validation Report,"Document No. 04508006 Rev. A is dated April 2008.

(a) What software version does the technical manual address?

(b) When was Version 1.2 implemented?

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ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

(a) The technical manual is applicable to versions 1.1 and 1.2 of the software.

(b) Version 1.2 was implemented April 1, 2008.

16. NRC Request (Item No. 66)

By letter dated March 12, 2010 TVA stated that the target submittal date for the "Watts Bar 2 PAMS Software Design Description (two documents, one for flat panel display and one for AC160)" was March 31, 2010.

TVA Response:

Per Westinghouse letter WBT-D-1961 (Reference 8), these items are available for audit at the Westinghouse Rockville office.

17. NRC Request (Item No. 67)

By letter dated March 12, 2010 TVA statedthat the targetsubmittal date for the "CommercialGrade Dedication Instructions for A1687, A1688, UpgradedPC node box and flat panels." was September 28, 2010.

TVA Response:

The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix submitted in response to Item 43:

a. A1687, A1688 - Scheduled for September 28, 2010

b. Upgraded PC node box and flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), these items are available for audit at the Westinghouse Rockville office.

c. Power supplies - Per Westinghouse letter WBT-D-2035 (Reference 12), these items are available for audit at the Westinghouse Rockville office.

18. NRC Request (Item No. 68)

By letter dated March 12, 2010 TVA stated that the targetsubmittal date for the "Summary Report on acceptance of A1687, A1688, UpgradedPC node box, flat panels, and power supplies." was September 28, 2010.

TVA Response:

The following status is from the revised WB2 Common Q PAMS ISG-6 Compliance Matrix submitted in response to Item 43:

a. A1687, A1688 - Scheduled for September 28, 2010 15

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval

b. Upgraded PC node box - Per Westinghouse letter WBT-D-2024 (Reference 7), this item is available for audit at the Westinghouse Rockville office.

c. Flat panel displays - Per Westinghouse letter WBT-D-2024 (Reference 7), this item is available for audit at the Westinghouse Rockville office.

d. Power supplies - Per Westinghouse letter WBT-D-2035 (Reference 12), these items are available for audit at the Westinghouse Rockville office.

19. NRC Request (Item No. 70)

By letter dated March 12, 2010 TVA statedthat the targetsubmittal date for the "Concept and Definition Phase V&V Report" was March 31, 2010.

TVA Response:

Per Westinghouse letter WBT-D-1 961, (Reference 8) this document is available for audit at the Westinghouse Rockville office.

20. NRC Request (Item No. 77)

By letter dated March 12, 2010 TVA stated that the target submittal date for seven other documents was "TDB" [TBD]. Please provide a schedule for the docketing of the remaining documents.

TVA Response:

The availability dates for these documents are included in the revised WBN Unit 2 Common Q ISG-6 Compliance Matrix submitted in response to item 43. As stated in the March 12, 2010 letter (Reference 4), the dates in the matrix are the dates the documents will be available to TVA to prepare for submittal or being "Available for Audit". They do not reflect the dates the documents will be submitted to the NRC. Expected submittal date is two weeks after TVA receives the document.

Note: There is a typo in the matrix in line item 33. The power supply entry date says TBD.

Per Westinghouse letter WBT-D-2035 (Reference 12) this item is complete and the documents are available for audit at the Westinghouse Rockville office.

21. NRC Request (item No. 81)

The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in Section 7, lists codes and standardsapplicable to the Common Q PAMS. This list contains references to old revisions of several regulatory documents, for example:

1. RG 1.29 - September 1978 vs. March 2007

2. RG 1.53- June 1973 vs. November 2003

a. IEEE 379-1994 vs. -2000

3. RG 1.75 - September 1975 vs. February2005

a. IEEE 384-1992 vs. -1992 16

ENCLOSURE I Responses To Licensee Open Items To Be Resolved For SER Approval

4. RG 1.100- June 1988 vs. September 2009

a. IEEE 344-1987 vs. -2004

5. RG 1.152 - January 1996 vs. January2006

a. IEEE 7-4.33.2-1993 vs. -2003

6. RG 1.168 - September 1997 vs. February2004

a. IEEE 1012-1986 vs. -1998

b. IEEE 1028-1988 vs. -1997

7. IEEE 279-1991 vs. 603-1991

8. IEEE 323-1983 vs. -1974 (RG 1.89 Rev. 1 June 1984 endorses 323-1974)

However, LIC-110, "Watts Bar Unit 2 License Application Review," states: "Designfeatures and administrativeprograms that are unique to Unit 2 should then be reviewed in accordance with the currentstaff positions." Please identify all differences between the versions referenced and the current staff positions. Please provide a justification for the acceptabilityPAMS with respect to these differences.

TVA Response:

The codes and standards documents listed in Section 7 of the Common Q PAMS Licensing Technical Report are the documents that the Common Q platform was licensed to when the NRC approved the original topical report and issued the approved SER. The WBN Unit 2 Common Q PAMS is designed in accordance with the approved Common Q topical report and approved SER and the codes and standards on which the SER was based. Since the current versions referenced are not applicable to WBN Unit 2, there is no basis for a comparison review.

22. NRC Request (Item No. 84)

Please provide: TVA Design CriteriaWB-DC-30-7 Rev. 22, Post Accident Monitoring Instrumentation.

TVA Response:

Attachment 5 contains Design Criteria WB-DC-30-7 Rev. 22, Post Accident Monitoring Instrumentation.

23. NRC Request (Item No. 86)

The PAMS Licensing Technical Report (WNA-LI-00058-WBT Rev. 0, Dated April 2010), in Section 6, lists references applicable to the Common Q PAMS. This list contains references to old revisions of several regulatory documents, for example:

(1) DI&C-ISGO4 - Rev. 0 (ML072540138) vs. Rev. I (ML083310185)

However, LIC-1 10, "Watts Bar Unit 2 License Application Review, "states: "Designfeatures and administrativeprogramsthat are unique to Unit 2 should then be reviewed in accordance with the current staff positions." Please identify all differences between the versions referenced and the current staff positions. Pleaseprovide a justificationfor the acceptabilityPAMS with respect to these differences.

17

ENCLOSUREI

• Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

The regulatory documents listed in the Common Q PAMS Licensing Technical Report are the documents that the Common Q platform was licensed to when the NRC approved the original topical report and issued the approved SER. The WBN Unit 2 Common Q PAMS is designed in accordance with the approved Common Q topical report and approved SER and the regulatory documents on which the SER was based. Since the current versions referenced are not applicable to WBN Unit 2, there is no basis for a comparison review.

24. NRC Request (Item No. 87)

Regarding the Sorrento RM-1000 Digital Radiation Processor:Please identify the model and version to be installed. Please include explicit identification of software version.

TVA Response:

The rate meter is model RM-1 000. The software is version 1.2

25. NRC Request (Item No. 88)

Regarding the Sorrento RM- 1000 Digital Radiation Processor:Please provide prior software V&V reports. The latest report only addresses Version 1.2.

TVA Response:

See response to Item 12.

26. NRC Request (Item No. 91)

TVA to submit excerpts of EDCRs 52421, 52987, 52321, 52351 and 52601 TVA Response:

1. Attachment 6 contains the EDCR 52421 excerpt.

2. Attachment 7 contains the EDCR 52987 excerpt.

3. EDCR 52321 is scheduled to be issued Oct 13, 2010. Submittal of EDCR 52321 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 103 due October 31, 2010.

4. EDCR 52351 is scheduled to be issued November 30, 2010. Submittal of EDCR 52351 excerpts is tracked by Responses to Licensee Open Items to be Resolved for SER Approval item 104 due December 15, 2010.

5. Attachment 8 contains the EDCR 52601 (RVLIS) excerpt. The RVLIS EDCR has been split into two EDCRs. The second EDCR is 55385. Submittal of EDCR 55385 excerpts is tracked by "Responses to Licensee Open Items to be Resolved for SER Approval" item 118, due November 15, 2010.

18

ENCLOSURE I Responses To Licensee Open Items To Be Resolved For SER Approval

27. NRC Request (Item No. 102)

Provide a schedule for resolution of items 80, 82 and 83 TVA Response:

Item 80 - no later than July 23, 2010.

Item 82 - no later than July 23, 2010.

Item 83- no later than July 23, 2010.

28. NRC Request (Item No. 106)

Confirm that the Unit I and Unit 2 CERPI systems utilize the same processor(ACI 10 or AC160).

TVA Response:

Westinghouse Unit 2 Drawing 6D31420 (Reference 9), Watts Bar 2- CERPI AC160 Chassis Configuration, Rev. 2, shows the processors are Model AC160, which are the same that are utilized for Unit 1, as shown on Westinghouse drawing 2D82995 Rev. 0 (Reference 10),

Watts Bar CERPI AC 160 Chassis Configuration.

29. NRC Request (Item No. 107)

Describe any control functions associatedwith the RM-1000 radiationmonitors.

TVA Response:

The RM-1 000 radiation monitors do not provide any control functions.

30. NRC Request (Item No. 111)

The reviewer was unable to locate information (SER) on the plant computer or annunciator systems and asked us to provide the location within the FSAR where these systems are described.

TVA Response:

The annunciator system is not described in the WBN Unit 1 Updated FSAR (UFSAR). As such it is not included in the WBN Unit 2 FSAR.

With the exception of the ERFDS functions in Section 7.5, the plant computer is not described in the WBN Unit 1 UFSAR. As such it is not included in the WBN Unit 2 FSAR.

31, NRC Request (Item No. 113)

Are the new model Eagle 21 power supplies installedin Unit 1 ?

19

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

Yes. Attachment 9 provides a work order excerpt and unit difference form.

32. NRC Request (Item No. 114)

Provide the resolution of the Eagle 21 Rack 5 lockup on update issue.

TVA Response:

The following non-proprietary response was developed from proprietary Westinghouse letter WBT-D-2027 (Reference 11), which provided the resolution of this issue. Westinghouse approved this non-proprietary response via e-mail from A. Drake to M. Clark on June 15, 2010.

As documented in WBT-D-1917, "Eagle-21 Rack 5 LCP Diagnostic Failures",

(Reference 14), Westinghouse noted an occasional diagnostic failure while performing the parameter update function on Rack 5 during the factory acceptance testing for the Unit 2 Eagle-21 System.

Subsequently, TVA provided to Westinghouse for testing and examination, a Loop Control Processor (LCP) board removed by TVA from Unit 1 Rack 5 for life cycle-based preventive maintenance. TVA personnel familiar with Unit 1 had indicated they had not experienced problems when performing parameter updates on Unit 1 Rack 5.

Based on Westinghouse examination and testing, a difference in hardware was identified between the Unit 1 LCP shipped to Westinghouse, the new Unit 2 Rack 5 LCP, and an older LCP (older than the Unit 1 LCP) from the Westinghouse Eagle 21 test bed. A different version of an 80287 math coprocessor chip (80287 XL) was installed on the Unit 1 LCP.

This version of the 80287 had an improved specification for calculation speed. Use of this chip on both the Unit 2 LCP and the test bed LCP allowed proper performance of the LCP when making parameter updates using the Unit 1/Unit 2 Rack 5 software. Also, use of the slower 80287 on any of the three LCP boards caused failure in parameter update with the Unit 1/Unit 2 Rack 5 software.

Through investigation of historical records, Westinghouse found that the 80287 XL chip had been evaluated and used by its former Process Control Division (now Emerson) for this application, but the current Westinghouse documentation had not been updated. This part has now been evaluated, and the Westinghouse documentation and drawing have been revised to allow use of the 80287 XL coprocessor. The 80287 XL coprocessor has been installed on the Unit 2 Rack 5 LCP, and the appropriate factory acceptance testing has been successfully conducted using this updated board. Additionally, the LCP boards in the balance of the Unit 2 racks have been updated with the 80287 XL coprocessor.

33. NRC Request (Item No. 115)

Provide a list of digital 1E systems that have a digital communications path to non safety related systems and if it has:

a. Been reviewed before for unit 1

b. Or been installed in unit I under 50.59, or

c. is unique to unit 2 20

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval TVA Response:

Safety Non Unit I Review Unit 2 Interface Review Related Safety System Related Interface Eagle 21 Plant While Eagle was installed The digital Eagle to ICS interface Computer prior to Unit 1 Licensing, in Unit 1 is via node boxes on a (ICS) the interfaces to the ring network. The interface for ERFDS/P2500 main frame Unit 2 is direct from the Eagle computers were analog, cabinets to a network switch on a With the replacement of star network. While the Unit 2 the ERFDS/P2500 ICS computer hardware interface mainframes by the is different than Unit 1, the Eagle Integrated Computer interface is the same in both units; System (ICS), the interface via a mono-directional became digital. Since ICS communication path described in was installed under 50.59, Reference 1. Due to the the Unit 1 digital difference in the ICS connection, communications interface the Unit 2 interface is unique.

has not been reviewed.

Common Q Plant Common Q is not installed The Common Q to Plant Computer Computer in Unit 1 interface is via the safety-related (ICS) Maintenance and Test Panel (MTP) fiber optic interface which blocks all except the minimum low level TCP/IP commands necessary to support communications. A detailed description of the MTP communications is contained in WNA-LI-00058-WBT, Revision 0, Watts Bar Unit 2 (WBN2) Post Accident Monitoring System (PAMS) Licensing Technical Report submitted under Reference 2. Additional communication isolation is provided by non-safety-related data diodes (one for each train).

The Common Q to ICS interface is unique to Unit 2.

21

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval

34. TVA Identified (Item No. 127)

Provide the status of the Eagle 21 Rack 2 RTD accuracy issue.

TVA Response:

The following non-proprietary response was developed from proprietary Westinghouse letter WBT-D-2034 (Reference 15), which provided the details of this issue. Westinghouse approved this non-proprietary response via e-mail from A. Drake to M. Clark on June 16, 2010.

During the Watts Bar Unit 2 Eagle 21 Factory Acceptance Test (FAT) of Rack 2, it was discovered that the narrow range Resistance Temperature Detector (RTD) temperature inputs were consistently reading about 0.20 F higher than expected. Investigation revealed that these inputs are configured in the Loop Calculation Processor software as a shared RTD. This is incorrect. Rack 2 RTDs are not shared. Racks 6, 10 and 13 RTDs are shared. Configuration as a shared RTD input alters the equation used for the temperature calculation. Watts Bar Unit 1 uses identical software to Unit 2.

Further investigation by Westinghouse showed this configuration error causes the Narrow Range Temperatures for only Division I to read 0.2 to 0.270 F higher over the Narrow Range span of 510-6500 F. The 0.20 F shift affects Thot and Tcold equally and thus will not affect the indication-of Delta T. Tavg will indicate high by 0.20 F, which will decrease the Over temperature and Overpower set points; which is in the conservative direction. The indicated high 0.2' F Tavg, if selected for control (via auctioneered high), would cause the controlling temperature to result in an actual temperature 0.20 F low; which is in the conservative direction for consideration of DNB. The Tavg - Low-Low function (P-12) would be non-conservative by 0.20 F, which would cause the permissive/interlock for block of steam dump post reactor trip to be delayed slightly via that channel. This delay would not be considered significant. Westinghouse will discuss this issue with Watts Bar Unit 1 personnel in accordance with their Part 21/Potential Issue process.

Westinghouse initiated a corrective action item (CAP # 10-140-M021) and performed an Evaluation of Potential Nuclear Safety Issue. Based upon the above investigations, Westinghouse determined that this issue does not represent a substantial safety hazard at Watts Bar Unit 1, even if left uncorrected.

A report on the final resolution of the Eagle 21 RTD input issue will be provided no later than December 3, 2010.

References:

1. TVA letter to NRC dated August 25, 2008, "Watts Bar Nuclear Plant (WBN) - Unit 2 -

Westinghouse Eagle 21 Process Protection System, Response to NRC I&C Branch Request for Additional Information (TAC No. MD631 1)" (ML082410088) (T02 080826 001) 22

ENCLOSUREI Responses To Licensee Open Items To Be Resolved For SER Approval

References:

(Continued)

2. TVA letter to NRC dated April 8, 2010, "Watts Bar Nuclear Plant (WBN) Unit 2 -Additional Information Regarding Final Safety Analysis Report (FSAR), Chapter 7, "Instrumentation And Controls" Review - Requested Common Q Proprietary Documents (T02 100408 001)

3. Watts Bar Design Criteria Document WB-DC-40-54, Environmental Qualification To 10CFR50.49, Rev. 4.

4. TVA letter to NRC dated March 12, 2010, "Watts Bar Nuclear Plant (WBN) Unit 2 -

Additional Information Regarding Final Safety Analysis Report (FSAR), Chapter 7,

'Instrumentation And Controls' Review - Requested Common Q Proprietary Documents" (T02 100312 001)

5. TVA letter to NRC dated April 27, 2010, "Watts Bar Nuclear Plant (WBN) Unit 2 - Staff Information Requests Resulting From NRC December 15, 2009, Meeting With Tennessee Valley Authority (TVA) Regarding Digital Instrumentation And Controls Review And NRC Clarifications To The Requests Provided During February 18, 2010, Telephone Conference Call (TAC No. ME0853)" (T02 100427 002)

6. Westinghouse letter WBT-D-1 526, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, NRC Access to Common Q Documents at the Westinghouse Rockville Office

7. Westinghouse letter WBT-D-2024, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, NRC Access to Common Q Documents at the Westinghouse Rockville Office

8. Westinghouse letter WBT-D-1 961, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, NRC Access to Common Q Documents at the Westinghouse Rockville Office

9. Westinghouse Unit 2 Drawing 6D31420 Revision 2, Watts Bar 2- CERPI AC160 Chassis Configuration

10. Westinghouse drawing 2D82995 Rev. 0, Watts Bar CERPI AC 160 Chassis Configuration

11. Westinghouse letter WBT-D-2027, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, Unit 2 Eagle-21 Rack 5 Testing and Hardware Release

12. Westinghouse letter WBT-D-2035, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, NRC Access to Common Q Documents at the Westinghouse Rockville Office

13. Westinghouse letter WBT-D-2044, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, Updated Common Q PAMS ISG-6 Compliance Matrix

14. Westinghouse letter WBT-D-1917, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, Eagle -21 Rack 5 LCP Diagnostic Failures

15. Westinghouse letter WBT-D-2034, Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2, Eagle-21 Rack 2 Deviation and Release 23

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT I (This Attachment contained on the OSM)

1. Analog Loop Comparison

2. Analog Card Comparison

3. Analog System Description

Foxboro Analog Spec 200 Unit I to Unit 2 Loop Comparison 5/27/2010 Page 1 of 3 Same as< Change System~ Unit 1 Package Number Loop Number Loop Function Y/N~ Comments No.

46 2-F-46-57 Turbine Driven AFW Y Flow control Loop 52343 Pump Control 3 2-P-3-122A Auxiliary Feedwater N Pressure Loop 52427 Pump 2A-A Differental Pressure 3 2-P-3-1 220 Auxiliary Feedwater Y Pressure Loop 52343 Pump 2A-A Differental Pressure Aux Control 3 2-P-3-132A Auxiliary Feedwater N Pressure Loop 52427 Pump 2B3-B3 Differential Pressure 3 2-P-3-1 320 Auxiliary Feedwater Y Pressure Loop 52343 Pump 2B3-B Differental Pressure Aux Control 3 2-F-3-147A Steam Generator 3 N Flow control Loop 52427 Auxiliary Feedwater Flow 3 2-F-3-147B Steam Generator 3 N Flow control Loop 52343 Auxiliary Feedwater Flow 3 2-F-3-1 55A Steam Generator 2 N Flow control Loop 52343 Auxiliary Feedwater Flow 3 2-F-3-1 55B Steam Generator 2 N Flow control Loop 52427 Auxiliary Feedwater Flow 3 2-F-3-163A Steam Generator 1 N Flow control Loop 52427 Auxiliary Feedwater Flow 3 2-F-3-1 63B3 Steam Generator I N Flow control Loop 52343 Auxiliary Feedwater Flow 3 2-F-3-1 70A Steam Generator 4 N Flow control Loop 52343 Auxiliary Feedwater Flow 3 2-F-3-1 70B Steam Generator 4 N Flow control Loop 52427

_______Auxiliary Feedwater Flow 30 2-P-30-310 Containment Pressure N Pressure Loop 52427

_______(Train A) 30 2-P-30-311I Containment Pressure N Pressure Loop 52427

______________ (Train B) 30 2-T-30-1 032 Lower Containment N Temperature Loop 52427 Ambient Temperature (Train A)

Foxboro Analog Spec 200 Unit I to Unit 2 Loop Comparison 5/27/2010 Page 2 of 3 Same as Chiange~

System Unit I KPackage Number Loop Number Loop Function YIN Comments No.

30 2-T-30-1 033 Lower Containment N Temperature Loop 52427 Ambient Temperature (Train B) 30 2-T-30-1 034 Lower Containment N Temperature Loop 52427 Ambient Temperature (Train A) 30 2-T-30-1 035 Lower Containment N Temperature Loop 52427 Ambient Temperature (Train B) 70 2ý-F-70-165A RHR Heat Exchanger N Flow Loop 52427 213-13 Supply Header Flow 70 2-F-70-215A & - Sample Heat Exchanger N Flow Loop - Each loop 52427 215B Header Differential Flow - shares a common Summer with one output 3 2-L-3-148 Steam Generator 3 Motor YIN Flow loop - (YES) Like U-1 52343 Driven AFW Level - for Main Control System Pump B (ACR & MCR) and (NO) for signals to Indicators (ACR &

MCR) and Annunciator 3 2-L-3-156 Steam Generator 2 Motor Y/N Flow loop - (YES) Like UI 52343 Driven AFW Level - for Main Control System Pump A (ACR & MCR) and (NO) for signals to Indicators (ACR &

MCR) and Annunciator 3 2-L-3-164 Steam Generator 1 Motor Y/N Flow loop -(YES) Like U1 52343 Driven AFW Level - for Main Control System Pump A (ACR & MCR) and (NO) for signals to Indicators (ACR &

MCR) and Annunciator 3 2-L-3-171 Steam Generator 4 Motor Y/N Flow loop - (YES) Like U-1 52343 Driven AFW Level - for Main Control System Pump B (ACR & MCR) and (NO) for signals to Indicators (ACR &

MCR) and Annunciator 3 2-L-3-172 Steam Generator 3 Y/N Flow loop - (Y'ES) Like U1 52343 Turbine Driven AFW for Main Control System level (Train A) (PNL 2-L-381A (Local) &

MCR) and (NO) for signals to Indicators (ACR & MCR) and Annunciator

Foxboro Analog Spec 200 Unit I to Unit 2 Loop Comparison 5/27/2010 Page 3 of 3 Same asChange

~System Uniit 1, Package Number Loop Number Loop Function YiNj Comments No.

3 2-L-3-173 Steam Generator 2 Y/N Flow loop - (YES) Like U1 52343 Turbine Driven AFW for Main Control System level (Train B) (PNL 2-L-381A (Local) &

MCR) and (NO) for signals to Indicators (ACR & MCR) and Annunciator 3 2-L-3-174 Steam Generator 1 Y/N Flow loop - (YES) Like U1 52343 Turbine Driven AFW for Main Control System level (Train B) (PNL 2-L-381A (Local) &

MCR) and (NO) for signals to Indicators (ACR & MCR) and Annunciator 3 2-L-3-175 Steam Generator 4 Y/N Flow loop - (YES) Like U1 52343 Turbine Driven AFW for Main Control System level (Train A) (PNL 2-L-381A (Local) &

MCR) and (NO) for signals to Indicators (ACR & MCR) and Annunciator 68 2-F-68-397-A Reactor Vessel Head N Flow Loop 53765 Vent Throttle Manual Loading Station (Train A) 68 2-F-68-396-B Reactor Vessel Head N Flow Loop 53765 Vent Throttle Manual Loading Station (Train B)

same as Lhunge System Unit 1 Package Number Loop Number Loop Function Y/N Comments No. Unit 1 Component U1 Manufacturer/Model # Unit 2 Component U2 Manufacturer/Model #

2-F-46-57/ 2 46 F-3-142 Turbine Driven AFW Pump Control Y Flow control loop 52343 I-FC-46-57A Foxboro/f-Z2AUKAM Z-FC-46-57A foxboro/N-ZAl+AM 1-FC-46-57B Foxboro/N-2AX÷A4 2-FC-46-57B Foxboro/N-2AX-M3+A4 F-FpC-46em7AF Foxboro/N-2AX+M2NH 2-FIC-46-57A Foxboro/N-2AXiM2NH 1-FIC-46-57B Foxboro/N-25cHM-M2NH-F 2iFIC-46-onB Foxboro/N-25oH-M-M2NH-F 1-FM-46-57A Foxboro/N-2AI-H2V 2-FM-46-57A Foxboro/N-2A0-12V 1-FM-46-578 Foxboro/N-2AO-V2H This loop controls the Turbine driven Auxiliary Feedwater Pump outlet flow (fro. 2-FT-3-142) by varying the speed of the Turbine driven Auxiliary 1-FM-46-57D Robertshaw/572-C2 2-FM-46-57D Foxboro/N-2AO-VAI IF-65 PSP112202F-65 obr/-A Feedwater pump. Flow indicating controller 2-FIC-46-57A (on panel 2-M-4) can be used in either manual or automatic mode, this Main Control Room controller is used when transfer switch 2-XS-46-57 (in junction box JB-8017) is in the normal position. When transfer switch 2-XS-46-S7 (in junction box IP-65AFxooN2XP9 APCS/SE160-2t3310 2-FM-3-142A Foxboro/N-2AP+SQE JB-8017) or transfer switch 2-XS-46-S7A (in junction box JB-2235) is in the auxiliary position the loop is transferred into automatic mode. While the loop 1-FM-3-142A

-FM-3-142A APCS/SE139-217610 2-FM-3-142A Foxboro/N-2AO-VAI is in the auxiliary mode local flow indicating controller 2-FIC-46-57B (on panel 2-L-381) is used, this controller can transfer the loop back into manual I1-F-M-3-14213 APCS/S1139-2176100 2-FM-3-142B Foohoro/N-2A0-VAI control for local operator control or it can be left in manual mode. When the turbine driven auxiliary feedwater pump outlet flow reaches its high 1-FM-3-142C APCS/51139-2176100 2-FM-3-142C Foxboro/N-2AO-VAI 2-Fr-42A setpoint a warning annunciation light is illuminated on panel 2-L-381 and the loop is transferred to automatic mode to prevent turbine over speed. Main as a "reset" to transfer this loop out of automatic mode after plant conditions have initiated a transfer it 2-FS-46-57A Foxboro/N-2AO-L2C-R Control Room hand switch 2-HS-46-57 is used 2-FS-46-57B Foxboro/N-2AO-L2C-R into automatic mode. This loop also provides input into the ICS. Flow indicator 2-FI-3-142A (on panel 2-M-4) provides main control room indication of 2-FS-46-S7C Foxboro/N-2AO-L2C-R the turbine driven auxiliary feedwater pump outlet flow. Flow indicator 2-FI-3-142C (on panel 2-L-10) provides auxiliary control room indication turbine 2-FS-46-57D Foxboro/N-2A0-L2C-R driven auxiliary feedwater pump outlet flow.

2-FS-46-57E Foxboro/N-2AP+ALM-AR 2-FS-46-57FA Foxboro/N-2A1-C2L 2-FS-46-S7FB Foxboro/N-2A1-C2L 2-FX-46-S7A Foxboro/N-2AX+DSl (N-ECEP-8629) 2-FX-46-57R Foxboro/N-2AX+DS1 (N-ECEP-8629) 2-FX-46-57C Fouhoro/N-2AXcDSS (N-ECRP-R625(

This loop Is functionally equivalent to Unit 1. 2-XM-46-57 Foxboro/N-2AO-VAI AuxiliaryFeedwater Pump2A-ADifferental 3 12-P-3-122A iPressure N IPressure Loop 152427 1-PDIC-3-122A GE/549 2-PDIC-3-122A Foxboro/N-2SOHM-M2NH-F 1-PDM-3-122A Ct/SSt 2-PDM-3-122A Fouboro/N-2A0-VAI Indicating 1-PM-3-122 Fisher/546 This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varying valve 2-PCV-3-122. Differential Pressure Controller 2-PdIC-3-122A (on panel 2-M-4) can be used either in manual mode or in automatic mode. This loop controls this valve from the Main Control 2-PDM-3-122AE Foxboro/N-2Al-12V Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the normal position. 2-PDC-3-122A Foxboro/N-2AC+A4 This loop is functionally equivalent to Unit 1. 2-PDM-3-122AA Foxboro/N-2AO-VAI Auxiliary Feedwater Pump 2A-A Differental 3 2-P-3-122C PressureAux Control N Pressre Loop 152343 1-PDIC-3-122C GE/549 2-PDIC-3-122C Foxboro/N-250HM-M2NH-F This loop controls the differential pressure of the Auxiliary Feedwater Pump 2A-A by varping valve 2-PCV-3-122. Differential Pressure Indicating I-PM-3-122 Fisher/546 Controller 2-PdIC-3-122C (on panel 2-L-10) can be used either in manual mode or in automatic mode. This loop controls this valve from the Auxiliary 2-PDM-3-122CE Foxboro/N-2Ai-12V Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11A) is in the auxiliary position. 2-PDC-3-122C Foxboro/N-2AC+A4 This loop Is functionally equivalent to Unit 1. 2-PDM-3-122CA :oxboro/N-2AO-VAI 2Auxiliary Feedwater Pump 2B-13 Differential 3 2-P-3-132A Pressure N Pressure loop 52427 1-PDC-3-132A GE/549 2-PDMC-3-132A Foxboro/N-2AOHM-M2NI-F 1-PM-3-132 ie/246 This loop controls the differential pressure of the Auxiliary Feedwater Pump 2B-B by varying valve 2-PCV-3-132. Differential Pressure Indicating PM-3-132 -- bishel/546 Controller 2-PdIC-3-132A (on panel 2-M-4) can be used either in manual mode or in automatic mode. This loop controls this valve from the Main Control 2-PDM-3-132A Foxboro/N-2AC+A4 Room when transfer switch 2-XS-3-132 (on panel 2-L-11B) is in the normal position.

This loop Is functionally equivalent to Unit 1. 2-PDM-3-132AA Foxboro/N-2AO-VAI 1Auxiliary Feedwater Pump 2R-RSifferental 3 2-P-3-132C Pressure Aux Control I N Pressure Loop 152343 -PDIC-3-132C- G1549 2-PDIC-3-132C Fooboro/N-250HM-M2N--F This loop controls the differential pressure of the Auxiliary Feedwater Pump 2BoB by varying valve 2-PCV-3-132. Differential Pressure Indicating I-PM-3-132 Fisher/546 Controller 2-PdlC-3-132C (on panel 2-L-10) can be used either in manual mode or in automatic mode. This loop controls this valve from the Auxiliary 2-PDM-3-132CE Foxboro/N-2Al-12V Control Room when transfer switch 2-XS-3-122 (on panel 2-L-11B) is in the auxiliary position. 2-PDC-3-132C Foxboro/N-2AC+A4 This loop is functionally equivalent to Unit 1. __ -PDM-3-532CA Foxboro/N-2AO-VAI

,-. . ,-.. ... .M..r,/, .. . ... . . . . . . .... . ... t-- .. - .- ....A ..... ..

3 12-F-3-147A ISteam Generator 3 Auxiliary Feedwater Flow I N IFlow control Loop 152427 1-FM-3-147AA Moore/SRT 2-FM-3-147AA noXboro/N-2AP+5AE

!-xhoro/N-?An-VAl 5 1-FM-3-147AB Robertshaw/572-C2 Z-FM-3-147AB P-9206)

This loop provides Main Control Room indication of Steam Generator 3 Auxiliary Feedwater Flow. Flow indicator 2-FI-3-147A (on panel 2-M-3) is used as 1-FM-3-147AD IMoore/SCT 12-FM-3-147AD

a PAM category I device. This loop also provides input into the ICS. 1-PX-3-147A Robertshaw/513-Al LOGPT Y0703A m This loop is functionally equivalent to Unit 1.

3 12-F-S-147B (team Generator 3 Auxiliary Feedwater Flow I N lFlow control Loop 152343 1-FM-3-147BA GE/S50 2-FM-3-147BA Foxhoro/N-2AO-VAI This loop provides Main Control Room indication of Steam Generator 3 Auxiliary Feedwater Flow, flow indicator 2-FI-3-147B (on panel 2-M-3) is used as 1-FM-3-1470B GE/565 2-FM-3-147BB Foxboro/N-2AP+SQE a PAM category 2 device. Flow indicator, 2-FI-3-147C (on panel 2-L-10), provides Auxiliary Control Room indication of Steam Generator 3 Auxiliary 1-FM-3-147D E-Max lnst/175D 127-S 2-FM-3-147D Foxboro/N-2AO-VAI Feedwater Flow. This loop provides local flow indication, 2-FI-3-147D (on panel 2-L-381), outside of the Turbine Driven Auxiliary Feedwater Pump Room.

1-PX-3-147B GE/57O-SO___________________

This loop is functionally equivalent to Unit 1. 2-FM-3-147BE Foxboro/N-2AI-12V 3 2-F-3-SSA ]Steam Generator 2 Auxiliary Feedwater Flow N Flow control Loop 152343 1-FM-3-155AA GE/550 2-FM-3-155AA Foxboro/N-2AO-VAI This loop provides Main Control Room indication of Steam Generator 2 Auxiliary Feedwater Flow, flow indicator 2-FI-3-155A (on panel 2-M-3) is used as 1-FM-3-1SSAB GE/565 2-FM-3-1SSAB Foxboro/N-2AP+SQE a PAM category 1 device. Flow indicator, 2-FI-3-155C (on panel 2-L-10), provides Auxiliary Control Room indication of Steam Generator 2 Auxiliary 1-FM-3-15SD E-Max lnst/175D 127-5 2-FM-3-ISSD Foxboro/N-2AO-VAI Feedwater Flow. This loop provides local flow indication, 2-FI-3-155D (on panel 2-L-381), outside of the Turbine Driven Auxiliary Feedwater Pump Room.

1-PX-3-155A GE/570-06 This loop is functionally equivalent to Unit 1. 2-FM-3-155AE Foxboro/N-2AI-12V 3 2-F-3-SSSR Steam Generator 2 Auxiliary Feedwater Flow N Flow control Loop 12427 1-FM-3-155BA Moore/SRT 2-FM-3-ISSBA Foxboro/N-2AP+SQE 1-FM-3-155BB Robertshaw/572-C2 2-FM-3-155BB Foxboro/N-2AO-VAI (N-ECEP-9206)

This loop provides Main Control Room indication of Steam Generator 2 Auxiliary Feedwater Flow. Flow indicator 2-FI-3-155R (on panel 2-M-3) is used as S-FM-3-155RD Moore/SCT 2-FM-3-155BD Foxboro/N-2AO-VAI a PAM category 2 device. This loop also provides input into the ICS. 1-PX-3-1558 Robertshaw/513-A1 LOGPT Y0704A N/A LOGPT Y0704A N/A This loop is functionally equivalent to Unit 1. 2-FM-3-155BE Foxboro/N-2Al-12V 3 2-F-3-563A Steam Generator 1 Auxiliary Feedwater Flow N lFow control Loop 52427 1-FM-3-163AA Moore/SRT 2-FM-3-163AA Foxboro/N-2AP+SQE 1-FM-3-163AS Robertshaw/572-C2 2-FM-3-163AB Foxboro/N-2AO-VAI (N-ECEP-9206)

This loop provides Main Control Room indication of Steam Generator 1 Auxiliary Feedwater Flow. Flow indicator 2-FI-3-163A (on panel 2-M-3) is used as 1-FM-3-163AD Moore/SCT 2-FM-3-163AD foxboro/N-2AO-VAI a PAM category 1 device. This loop also provides input into the ICS. I-PX-3-163A Robertshaw//13-A1l LOGPT Y0708A N/A LOG PT Y0708A N/A This loop is functionally equivalent to Unit 1. 2-FM-3-163AE foxboro/N-2A1-12V 3 2-F-3-563B Steam Generator 1 Auxiliary Feedwater Flow N Flow control Loop 152343 -FM-3-163BA GE/550 2-FM-3-163BA Foxboro/N-2AO-VAI This loop provides Main Control Room indication of Steam GeneratorS Auxiliary Feedwater Flow, flow indicator 2-FI-3-163B (on panel 2-M-3) is used as 1-FM-3-163BB GE/565 2-FM-3-163BB Foxboro/N-2AP+SQE a PAM category 2 device. Flow indicator, 2-FI-3-163C (on panel 2-L-10) provides Auxiliary Control Room indication of Steam Generator 1 Auxiliary 1-FM-3-163D E-Max lnst/175D 127-5 2-FM-3-163D Foxboro/N-2AO-VAI Feedwater Flow. This loop provides local indication, 2-FI-3-163D (on panel 2-L-381), outside of the Turbine Driven Auxiliary Feedwater Pump Room. S-PS-3-S63R GE/570-6 This loop is functionally equivalent to Unit 1. 2-FM-3-163BE Foxboro/N-2AI-12V 3 2-F-3-70A ISteam Generator 4 Auoiliary Feedwater Flow N Flow control Loop 52343 1-FM-3-170AA GE/SSG 2-FM-3-170AA Foxboro/N-2AO-VAI This loop provides Main Control Room indication of Steam Generator 4 Auxiliary Feedwater Flow, flow indicator 2-FI-3-170A (on panel 2-M-3) is used as 1-FM-3-170AB GE/565 2-FM-3-170AB Foxboro/N-2AP+SQE a PAM category 1 device. Flow indicator, 2-FI-3-170C (on panel 2-L-10) provides Auxiliary Control Room indication of Steam Generator 4 Auxiliary 1-FM-3-17GD E-Max Inst/175D 127-5 2-FM-3-170D Foxboro/N-2AO-VAI Feedwater Flow. This loop provides local indication, 2-FI-3-170D (on panel 2-L-381), outside of the Turbine Driven Auxiliary Feedwater Pump Room. 1-PX-3-170A GE/570-06 This loop is functionally equivalent to Unit 1. 2-FM-3-170AE Foxboro/N-2Al-12V 3 2-F-3-575 ISteam Generator 4 Auxiliary Feedwater Flow I N IrFlowcontrol Loop 52427 1-FM-3-170BA Moore/SRT 2-FM-3-170BA Foxboro/N-2AP+SQE S-FM-3-17OBB Robertshaw/572-C2 2-FM-3-170BB Foxboro/N-2AO-VAI (N-ECEP-9206)

This loop provides Main Control Room indication of Steam Generator 4 Auxiliary Feedwater Flow, flow indicator 2-FI-3-170B (on panel 2-M-3) is used as 1-FM-3-170BD Moore/SCT 2-FM-3-1700D Foxboro/N-2AO-VAI a PAM category 2 device. This loop also provides input into the ICS. S-PX-3-17OB Robertshaw/513-A1 LOGPT Y0709A N/A LOG PT Y0709A N/A This loop is functionally equivalent to Unit 1. 2-FM-3-170BE Foxboro/N-2AI-12V 30 2-P-30-310 Containment Pressure (Train A) I N IPressure Loop 52427 1-PM-30-310 APCS/S1139-2166100 2-PM-30-310 Foxboro/N-2AO-VAI (N-ECEP-9206) 1-PO-30-310 APCS/PS108-2020500__________________

N/A 1GPTP12A /

S I-PT Pl10 This loop provides Main Control Room indication of Containment Pressure, pressure indicator 2-PI-3-310 (on panel 2-M-9) is used as a PAM category LOG-PTP1121A N/A LOG PTP1121A N/A device. This loop also provides input into the ICS.

2-PM-30-310A Foohoro/N-2A0-VAI This loop is functionally equivalent to Unit 1. 2-PM-30-310E Foxboro/N-2A1-12V 30 2-P-30-311 Containment Pressure (Train 8) 1-N IPressure Loop 52427 1-PM-30-311 APCS/SI139-2166100 2-PM-30-311 Foxboro/N-2AO-VAI (N-ECEP-9206) 1-PX-30-351 APCS/PS108-252000___________

0 OGPTP02A as a PAM category 2 1' X01T N/A This loop provides Main Control Room indication of Containment Pressure, pressure indicator 2-PI-3-311 (on panel 2-M-9) is used device. This loop also provides input into the ICS. 2-PM-30-31S2A Foxboro/N-2AO-VAN This loop is functionally equivalent to Unit 1. 2-PM-30-311E Foxboro/N-2A1-12V jLo.er Containment Ambient Temperature (Train 30 2-T-30-1032 A) N Temperature Loop 12427 1-TM-30-1032 Moore/RBT 2-TM-30-1032 Foxboro/N-2AI-P2V (N-ECEP-9808O This loop provides two Main Control Room indications of Containment Ambient temperature, temperature indicator 2-TI-3-1032A (on panel 2-M-6) is used as a PAM category I device, and temperature indicator 2-TI-3-1034A (on panel 2-M-9) is used as a PAM category Sdevice. 2-TM-30-1032E ýoxboro/N-2AO-VAI

T1k loop is funcatl- ehalent to Unit 1. 2-TM-3D-ID32D Foxb-1N-2AD-VA)

T----- L-ower Containment Ambient Temperature (Train 30 2-T-30-1033 IIn B) 1 ' Temperature Loop 52427 1-TM-30-1033 Moore/RBT 2-TM-30-1033 Foxboro/N-2AI-P2V (N-ECEP-9808)

This loop provides two Main Control Room indications of Containment Ambient temperature, temperature indicator 2-TI-3-1033A (on panel 2-M-6) is used as a PAM category 2 device, and temperature indicator 2-TI-3-1035A (on panel 2-M-9) is used as a PAM category 2 denice. 2-TM-30-1033E Foxboro/N-2AO-VAI This loop is functionally equalalent to Unit 1. 2-TM-30-1033D Foxboro/N-2AO-VAI Lower Containment Ambient Temperature (Train 30 2-T-30-1034 A) N Temperature Loop 152427 -TM-30-1034A Moore/RBT 2-TM-30-1034A Foxboro/N-2AI-P2V (N-ECEP-980R)

This loop provides two Main Control Room indications of Containment Ambient temperature, temperature indicator 2-TI-3-10328 (on panel 2-M-6) is 1-TM-30-1034B Moore/SCX 2-TM-30-10348 Foxboro/N-2AO-VAI (N-ECEP-9206) used as a PAM category I device, and temperature indicator 2-TI-3-10348 (on panel 2-M-9) is used as a PAM category S device. This loop also provides LOG PT T4009A N/A LOGPT T4009A N/A input into the ICS. 2-TM-30-1034E Foxboro/N-2AO-VAI This loop is functionally equivalent to Unit 1. 2-TM-30-1034D Foxboro/N-2AO-VAI Lower.Containment Ambient Temperature (Train 30 2-T-30-1035 () N Temperature Loop 52427 1-TM-30-1035A Moore/ROT 2-TM-30-1035A Foxboro/N-2AI-P2V (N-ECEP-980R)

This loop provides two Main Control Room indications of Containment Ambient temperature, temperature indicator 2-TI-3-1033B (on panel 2-M-6) is 1-TM-30-1035B Moore/SCX 2-TM-30-1035B Foxboro/N-2AO-VAI (N-ECEP-9206) used as a PAM category 2 device, and temperature indicator 2-TI-3-1035B (on panel 2-M-9) is used as a PAM category 2 device. This loop also provides LOGPTT4010A N/A LOG PT T4010A N/A input into the ICS. 2-TM-30-1035E Foxboro/N-2AO-VAI This loop is functionally equlvalent to Unit 1. 2-TM-30-1035D Foxboro/N-2AO-VAI 70 12-F-70-SOSA IRHOHeatExchanger 2B-3SupplyHeaderFlow I N IFlowLoop 512427 1-FM-70-16SA GE/SOS 2-FM-70-165A Fooboro/N-2AP+SQE 1-FM-70-16SB Fobertshaw/572-C2 2-FM-70-165B Foxboro/N-2AO-VAI This loop provides Main Control Room indication of RHR Heat Exchanger 2B-B Supply Header Flow on flow indicator 2-FI-70-165A (on panel 0-M-27B). 1-FS-70-165A GE/560 1-PX-70-165A GE/570-06 This loop Is functionally equivalent to Unit 1. 2-FM-70-16SAE Foxboro/N-2Al-12V

-F7-5A&-Flow Loop- Each ioop sbae a..

common.

70 25 Sample Heat Exchanger r Dithoneoutput. IH 5227 1-FDS-70-215 Oobertshaw/553-C2-B2-RS 2-FDS-70-215 Foxboro/N-2AO-L2C-R 1-FM-70-215A Robertshaw/570-C2 2-FM-70-215A Foxboro/N-2AP+SQE 1-FM-70-215B Oobertshaw/570-C2 2-FM-70-215B Foxboro/N-2AP+SQE This loop controls the flow through the Sample Heat Exchanger by varying valve 2-FCV-70-183. Moore/ASM/2X15-[-MA/7N0-S-FM-70-215D S0MA/SS7VAC/-KO(AR( 2-FM-70-215D Fouboro/N-2AP+SUM 2-FM-70-215AE Foxboro/N-2AI-12V 2-FM-70-215BE Foxboro/N-2Al-12V This loop is functionally equivalent to Unit 1. 2-FDS-70-215A Foxboro/N-2AP+ALM-AR

ýFlowloop- (YES) LikeUSfor MainControl Steam Generator3 Motor Drinen AFWLenel- System (ACR& MCR) and (NO) for signals to 3 Pump B Y/N Indicators (ACR& MCR) and Annunciator 52343 1-LC-3-148A Foxboro/N-2AX+AM 2-LC-3-148A Foxboro/N-2AX+AM S-LC-3-140B Foxboro/N-2AX+A4 2-LC-3-148B Foxboro/N-2AC-M3+A4 1-UC-3-148A Foxboro/N-2AX+M2NH 2-LIC-3-48A Foxboro/N-2AX+M2NH 1-UC-3-140B Foxboro/N-25OHM-M2NH-F 2-LIC-3-148B Foxboro/N-2SOHM-M2NH-F 1-LM-3-4 E/ 2LM-3-4 Foxboro/N-2A0-VAI This loop controls Steam Generator 3 level by varying valves 2-LCV-3-148 and 2-LCV-3-148A which control the amount of water input from Auxiliary S-LM-3-148A Masoneilaw/7OOSN _.-M-3148 Fboo/N2AOVA Feedwater Pump 20-P. This loop is controlled from the main control room by level indicating controller 2-LIC-3-148A (on panel 2-M-4) when transfer 1-LM-3-1400 OoberosNaw/O72-C2 2-LM-3-148C Foxboro/N-2AO-VAI switch 2-XS-3-148A (on panel 2-L-11B) is in the normal position. This controller can beused in either automatic or manual mode. Level indicator 2-U 148 (on panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-148A is transferred to the auxiliary position the loop is put 1-LM-3-148C :oxboro/No2AI-H 2-LM-3-148C Foxboro/N-2Al-V 1-LM-3-148D Fooboro/N-2A5-H2V 2-LM-3-148D Foxboro/N-2AO-12V into automatic mode and control is transferred to the auxiliary control room level indicating controller 2-LIC-3-148B (on panel 2-L-SIB). This controller 1-LS-3-148B/D GE/S6O 2-LS-3-148B/D Fooboro/N-2A0-L2C-O can be put into manual mode or left in automatic. Level indicator 2-LI-3-148C (on panel 2-L-10) provides auxiliary control room indication. Transfer 1-LX-3-1480/B (SPARE) GE/50 switch 2-XS-3-148 (on panel 2-L-11B) transfers this loop from manual to automatic control. This loop provides main control room annunciation when I-PX-3148g GE/570 steam generator 3 level is high (window box 3C, window 62B), and when transfer switch 2-XS-3-148Ais in the auxiliary position (widow box 6F, window 148C). 2-LM-3-148E Foxboro/N-2Al-12V 2-LS-3-148A Foxboro/N-2AP+ALM-AR 2-LS-3-148EB Foxboro/N-2AI-C2L 2-LS-3-14SEA Foxboro/N-2AI-C2L 2-LS-3-148F Foxboro/N-2AO-L2C-R This loop is functionally eqaivalent to UnitS.

2-LX-3-148ABC Foxboro/N-2AX+DS1 (N-ECEP-8629)

Flowloop- (YES) LikeUSfor MainControl Steam Generator 2 Motor Driven AFW Level - System (ACR& MCR) and (NO) for signals to 3 2-L-3-156 Pump A I /N Indicators (ACR& MCR) and Annunciator 52343 1-LC-3-156A Foxboro/N-2AX+AM 2-LC-3-S56A Foxboro/N-2AX+AM S-LC-3-S16B Foxboro/N-2AX+A4 2-LC-3-156B Foxboro/N-2AC-M3+A4 1-LIC-3-S16A JFoxboro/N-2AX+M2NH 12-LIC-3-156A tFoxboro/N-2AX+M2NH

This loop controls Steam Generator 2 lenl by varying valves 2-LCV-3-156 and 2-LCV-3-156A which control the amount of water input from Auxiliary Feedwater Pump 2A-A. This loop is controlled from the main control mom by level indicating controller 2-LIC-3-156A(on panel 2-M-4) when transfer 11-LM-3-156A Masoneilan/gO05A switch 2-XS-3-156A (on panel 2-L-11A) is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-UI 1-LM-3-156B Robertshaw/572-C2 2-LM-3-156B Foxboro/N-2AO-VAI 156 (on panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-156A is transferred to the auxiliary position the loop is put 1-LM-3-156C Foxboro/N-2AO-V2H 2-LM-3-156C Foxboro/N-2AO-VAI into automatic mode and control is transferred to the auxiliary control room level indicating controller 2-LIC-3-156B (on panel 2-L-11A). This controller 1-LM-3-156D Foxboro/N-2AI-H2V 2-LM-3-156D Foxboro/N-2Al-12V can be put into manual mode or left in automatic. Level indicator 2-LI-3-156C (on panel 2-L-10) provides auxiliary control room indication. Transfer 1-LS-3-156B/D tE/560 2-LS-3-156B/D Foxboro/N-2AO-L2C-R switch 2-XS-3-156 (on panel 2-L-11A)transfers this loop from manual to automatic control. This loop provides main control room annunciation when 1-LS-3-156D/B (SPARE) GE/360 steam generator 2 level is high (window box 3C, window 61B), when transfer switch 2-XS-3-156A is in the auxiliary position (widow box 6F, window 1-PX-3-156 GE/S70 148B), and when there is a power failure in panel 2-L-11A (window box 6F, window 146D). 2-LM-3-156E Foxboro/N-2Al-12V S2-LS-315lS6A IFoxboro/N-2AP+ALM-AR 2-LS-3-156EB Foxboro/N-2AI-C2L This loop Is functionally equivalent to Unit 1.

boro/N-2AX+DS1 (N-ECEP-g629)

-L31 Pump A Flow loop - (YES)Like Ut for Main signals Control to System (ACR& MCR) and (No) for Steam Generator/ Motor Drinen AFW Lenel -

23 -/N Indicators (ACR& MCR) and Annunciator 52343 oxorj-2 il-LC-34ruuuFoxboo, -2AXc+AM j1-C-uenM 4

I-LC-3-164B Foxboro/N-2AX+A4 2-LC-3-164B Foxboro/N-2AC-M3+A4 I-LIC-3-164A Foxboro/N-2AX+M2NH 2-LIC-3-164A Foxboro/N-2AX+M2NH S-LIC-3-164B Foxboro/N-25OHM-M2NH-F 2-LIC-3-164B Foxboro/N-25OHM-M2NH-F O-LM-3-164 GE/5S0 2-LM-3-164 Foxboro/N-2AO-VAI This loop controls Steam Generator I level by varying valves 2-LCV-3-164 and 2-LCV-3-164Awhich control the amount of water input from Auxiliary 1-LM-3-164A Masoneilan/800SA Feedwater Pump 2A-A. This loop is controlled from the main control room by level indicating controller 2-LIC-3-164A (on panel 2-M-4) when transfer 1-LM-3-164B Robertshaw/572-C2 2-LM-3-164B Foxboro/N-2AO-VAI switch 2-XS-3-164A (on panel 2-L-11A)is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI O-LM-3-164C Foxboro/N-2AO-V2H 2-LM-3-164C Foxboro/N-2AO-VAI 164 (on panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-164A is transferred to the auxiliary position the loop is put O-LM-3-164D Foxboro/N-2AI-H2V 2-LM-3-164D Foxboro/N-2AI-12V into automatic mode and control is transferred to the auxiliary control room level indicating controller 2-LIC-3-164B(on panel 2-L-11A). This controller 1-LS-3-164B/D GE/560 2-LS-3-164B/D Foxboro/N-2AO-L2C-R can be put into manual mode or left in automatic. Level indicator 2-LI-3-164C (on panel 2-L-10) provides auxiliary control room indication. Transfer O-LS-3-164D/R(SPARE) GE/S60 switch 2-XS-3-164 (on panel 2-L-11A) transfers this loop from manual to automatic control. This loop provides main control room annunciation when 1-PX-3-164 GE/570 steam generator 1 level is high (window box 3C, window 60B), and when transfer switch 2-XS-3-164A is in the auxiliary position (widow box 6F, window 1-PX-3-164A Foxboro/N-2AX-PS9A 148B).

2-LM-3-164E Foxboro/N-2Al-12V 2-LS-3-164A Foxboro/N-2AP+ALM-AR 2-LS-3-164EB Foxboro/N-2AI-C2L 2-LS-3-164EA Foxboro/N-2AI-C2L F

This loop Is functionally equivalent to Unit 1.

ABC Flow loop - (YES)Like U 1 for Main Control Steam Generator 4 Motor Driven AFW Level - System (ACR& MCR) and (NO) for signals to 3 2-1-3-171 Pump8 Y/N Indicators (ACR& MCR) and Annunciator 12545 0-LC-3-171A 'oxboro/N-2AX+AM 2-LC-3-171A Foxboro/N-2AX+AM 2-LC-3-171B Foxboro/N-2AC-M3+A4 2-IIC-3-171A X+M2NH 1-LIC-3-171B :oxboro/N-25OHM-M2NH-F 2-LIC-3-171B Foxboro/N-25OHM-M2NH-F This loop controls Steam Generator 4 level by varying valves 2-LCV-3-171 and 2-LCV-3-171A which control the amount of water input from Auxiliary 1-LM-3-171 GE/550 2-LM-3-171 Foxboro/N-2AO-VAI Feedwater Pump 2BB. This loop is controlled from the main control room by level indicating controller 2-LIC-3-171A(on panel 2-M-4) when transfer 1-LM-3171A Masoneilan/g0OSA switch 2-XS-3-171A (on panel 2-L-11B)is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI -ILM-3-171B Robertshaw/572-C2 2-LM-3-171B Foxboro/N-2AO-VAI 171 (on panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-171A is transferred to the auxiliary position the loop is put 1-LM-3-171C Foxboro/N-2AO-V2H 2-LM-3-171C Foxboro/N-2AO-VAI into automatic mode and control is transferred to the auxiliary control room level indicating controller 2-IIC-3-171B (on panel 2-L-11B). This controller 1-LM-3-171D Fooboro/N-2AI-H2V 2-LM-3-171D Foxboro/N-2Al-12V can be put into manual mode or left in automatic. Level indicator 2-LI-3-171C (on panel 2-L-10) provides auxiliary control room indication. Transfer 1-LS-3-171B/D GE/560 2-LS-3-171B/D Foxboro/N-2AO-L2C-R switch 2-XS-3-171 (on panel 2-L-11B) transfers this loop from manual to automatic control. This loop provides main control room annunciation when O-LS-3-71D/B (SPARE) GE/560 steam generator 4 level is high (window box 3C, window 63B), when transfer switch 2-XS-3-171A is in the auxiliary position (widow box 6F, window 1-PX-3-171 GE/570 148C(, and when there is a power failure in panel 2-L-118 (window box 6F, window 146D). j2-LM3-171E lFoxboro/N-2AJ-12V 2-L-S-3-71A Foxboro/N-2AP+ALM-AR 2-LS-3-171EB 2-LS-3-171EA 2-LS-3-O71F This loop Is functionally equivalent to Unit 1.

2-LX-3-171ABC Foxboro/N-2AX+DS1 (N-ECEP-8629)

Flaw naop- (YES)Like 31 tar Main Contral System (PNL 2-L-381A (Local) & MC.) and (NO)

(ACR& MCR) and Steam Generator 3 Turbine Driven AFWlevel for signals to Indicators 3 2-L-3-172 (Train A) Y/N Annunciator 52343 1-LC-3-172A Foxboro/N-2AX+AM t-LC-3-172A :obohro/N-2AX+AM Foxboro/N-2AX+A4

+

I ooboroIN-2AC-M3+A4 A Foxboro/N-2AX+M2NH A  :: FoxborolN-2AXvM2NH I-LIC-3-172B Foxboro/N-250HM-M2N H-F --LIC-3-172B :oxboro/N-25DHM-M2NH-F 1-LM-3-172 a-L This loop controls Steam Generator 3 level by varying valve 2-LCV-3-172 which controls the amount of water input from the Turbine Driven Auxiliary I-LM-3-172A Feedwater Pump. This loop is controlled from the main control room by level indicating controller 2-LIC-3-172A (on panel 2-M-4) when transfer switch 2 1-LM-3-172C oxboro/N-2AO-VAI XS-3-172A (on panel 2-L-11A) is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI-3-172 (on 1-LM-3-172D AI-H2V I-LM-3-172D -0oboro/N-2AI-12V panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-172A is transferred to the auxiliary position the loop is put into 1-LS-3-172B/D GE/SR6 .-LS-3-172B/D -oxboro/N-2AO-L automatic mode and control is transferred to level indicating controller 2-LIC-3-172B (on panel 2-L-381) located on a local panel outside of the turbine

.- L.-.-.75/. -- SPARFi GE/SRi driven auxiliary feedwater pump room. This controller can be put into manual mode or left in automatic. Transfer switch 2-XS-3-172 (on panel 2-L-11A) '+ +

Moore/DCA/10-SMA/SL2/

transfers this loop from manual to automatic control. This loop provides input into the AMSAC system. This loop provides main control room :oxboro/N-2Al-12V 1-LS-3-172E 117VAC/-AD,-RE,-RF,-[AB] Z-LM-3-172E annunciation when steam generator 3 level is high (window box 3C, window 62B), when transfer switch 2-XS-3-172A is in the auxiliary position (widow 1-PX-3-172 GE/570 box 6F, window 148B), and when there is a power failure in panel 2-L-3BSAcompartment A (window box 6F, window 147D).

1-PX-3-172A Foxboro/N-2AX-PS9A t-S-3-172EB :oxboro/N-2Al-C2L t-LS-3-172EA :oxboro/N-2A[-C2L This loop is functionally equivalent to Unit 1.

+ I Flow loop - (YES)Like U for Main Control System (PNL2-L-381A (Local) & MCR) and (NO)

Steam Generator 2 Turbine Driven AFW level for signals to Indicators (ACR& MCR) and l-LC-3-173A -oxboro/N-2AX+AM 3 2-L-3-173 (Train B) Y/N Annunciator 52343 1-LC-3-173A 3i NIB li-LC-3-173B IFoxboro/N-2AC-M3+A4 C-LM-C22 1-LIC-3-173A 2-LIC-3-173A :oxboro/N-2AX+M2NH-1-LIC-3-173B Foxboro/N-25OHM-M2NH-F --LIC-3-173B :oxboro/N-2 This loop controls Steam Generator 2 level by varying valve 2-LCV-3-173 which controls the amount of water input from the Turbine Driven Auxiliary 1-LM-3-173 Feedwater Pump. This loop is controlled from the main control room by level indicating controller 2-LIC-3-173A (on panel 2-M-4) when transfer switch 2 1-LM-3-173A XS-3-173A (on panel 2-L-11B) is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI-3-173 (on 1-LM-3-173C :oxboro/N-2AO-VAI panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-173A is transferred to the auxiliary position the loop is put into 1-LM-3-173D A--H2V 2-LM-3-173D -oxboro/N-2AI-12V automatic mode and control is transferred to level indicating controller 2-LIC-3-173B (on panel 2-L-381) located on a local panel outside of the turbine 1-LS-3-1738/D GE/S6D 2-LS-3-173B/D :oxboro/N-2AO-L2C-R driven auxiliary feedwater pump room. This controller can be put into manual mode or left in automatic. Transfer switch 2-XS-3-173 (on panel 2-L-11B) 5-15-3-173D/B (SPARE) FF1/560 transfers this loop from manual to automatic control. This loop provides input into the AMSAC system. This loop provides main control room Moore/DCA/10-SOMA/SL2/

annunciation when steam generator 2 level is high (window box 3C, window 61B), when transfer switch 2-XS-3-173A is in the auxiliary position (widow 1-LS-3-173E 117VAC/-AD,-RE,-RF,-[AB] Z-LM-3-173E :oxboro/N-2Al-12V box 6F, window 14BC). 1-PX-3-173 GE/570 2-LS-3-173A Foxboro/N-2AP+ALM-AR 2-LS-3-173EB :Foxboro/N-2A[-C2L 2-LS-3-173EA Foxboro/N-2A[-C2L 2-LS-3-173F iFoxboro/N-2AO-L2C-R This loop Is functionally equivalent to Unit 1. t-LSX-1-73ABC Foxboro/N-2AX+DS11N-ECEP-86291 4-B-LX 13B -oxbro/-2AXDSI(N-EEP-62 Flow loop - (YES)Like US for Main Control System (PNL2-L-381A (Local) & MCR) and (NO)

Steam Generator 1 Turbine Driven AFW level for signals to Indicators (ACR& MCR( and 3 2-L-3-174 (Train B) Y/N Annunciator 52343 I-LC-3-174A Foxhoro/N-2AX.AM l-LC-3-174A :oxboro/N-2AX+AM l-LC-3-174B :oxboro/N-2AC-M3+A4 1-LC-3-174B Fooboro/s-2AIXcA4 I-LIC-3-174A Fooboro/N-2811.Mltd Z-LIC-3-174A :oxboro/N-2AX+M2NH 1-LIC-3-174B Foxboro/N-250HlM-Mý t-LIC-3-174B -oxboro/N-2SOHM-M2NH-F 1-LM-3-174 APCS/S1139-2176100 a-LM-3-174 :oxboro/N-2AO-VAI This loop controls Steam Generator I level by varying valve 2-LCV-3-174 which controls the amount ofwater input from the Turbine Driven Auxiliary Masoneilan/8005N Feedwater Pump. This loop is controlled from the main control room by level indicating controller 2-LIC-3-174A (on panel 2-M-4) when transfer switch 2 .L-LM-3-174A 1-LM-3-174C XS-3-174A (on panel 2-L-11B)is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI-3-174 (on 1-LM-3-174D panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-174A is transferred to the auxiliary position the loop isput into 1-LS-3-174B/D GE/560 Z-LS-3-174B/D Foxboro/N-2AO-L2C-R automatic mode and control is transferred to level indicating controller 2-LIC-3-174B (on panel 2-L-381) located on a local panel outside of the turbine 1-LS-3-174D/B(SPARE) GE/560 driven auxiliary feedwater pump room. This controller can be put into manual mode or left in automatic. Transfer switch 2-XS-3-174 (on panel 2-L-11B) Moore/DCA/10-SOMA/SL2/

transfers this oop from manual to automatic control. This loop provides input into the AMSAC system. This loop provides main control room 1-1S-3-174E 1i7VAC/-AD.-RE.-RF.-rABl 2-LM-3-174E :oxboro/N-2Al-12V annunciation when steam generator I level is high (window box 3C, window GOB),when transfer switch 2-XS-3-174A is in the auxiliary position (widow 1-PX-3-174 jGE/57G........I____________I__________________

I-PX-3-174A Foxboro/N-2AX-PS9A 2-LS-3-174A Foxboro/N-2AP+ALM-AR 2-LS-3-174EB Foxboro/N-2AI-C2L 2-LS-3-174EA Foxboro/N-2AI-C2L 2-LS-3-174F Foxboro/N-2AO-L2C-R This loop Is functionally equivalent to Unit 1.

2-LX-3-174ABC Foxboro/N-2AX+DS1 (N-ECEP-g629)

Flow loop - (YES) Like U1 for Main Control System (PNL 2-L-381A (Local) & MCR( and (No)

Steam Generator 4 Turbine Driven AFW level for signals to Indicators (ACR& MCR) and 3 2-L-3-175 (Train A) Y/N Annunciator 52343 1-LC-3-175A Foxboro/N-2AX+AM 2-LC-3-175A Foxboro/N-2AX+AM 1-LC-3-175B Foxboro/N-2AX+A4 2-LC-3-175B Foxboro/N-2AC-M3+A4 1-LIC-3-175A Foxboro/N-2AX+M2NH 2-LIC-3-175A Foxboro/N-2AX+M2NH I-LIC-3-175B Foxboro/N-250HM-M2NH-F 2-LIC-3-175B Foxboro/N-250HM-M2NH-F This loop controls Steam Generator 4 level by varying wive 2-LCV-3-175 which controls the amount of water input from the Turbine Driven Auxiliary 1-LM-3-175 APCS/SI139-2176100 2-LM-3-175 Foxboro/N-2AO-VAI Feedwater Pump. This loop is controlled from the main control room by level indicating controller 2-LIC-3-175A (on panel 2-M-4) when transfer switch 2- 1-LM-3-175A Masoneilan/8RGSN XS-3-17SA (on panel 2-L-11A) is in the normal position. This controller can be used in either automatic or manual mode. Level indicator 2-LI-3-175 (on 1-LM-3-175C Foxboro/N-2AO-V2H 2-LM-3-175C Foxboro/N-2AO-VAI panel 2-M-3) provides main control room indication. When transfer switch 2-XS-3-175A is transferred to the auxiliary position the loop is put into 1-LM-3-175D Foxboro/N-2Al-H2V 2-LM-3-175D Foxboro/N-2AI-12V automatic mode and control is transferred to level indicating controller 2-LIC-3-175B(on panel 2-L-381) located on a local panel outside of the turbine 1-LS-3-175B/D GE/S560 2-LS-3-175B/D Foxboro/N-2AO-L2C-R driven auxiliary feedwater pump room. This controller can be put into manual mode or left in automatic. Transfer switch 2-XS-3-175 (on panel 2-L-11A) S-LS-3-175D/B(SPARE) GE/Sh6 transfers this loop from manual to automatic control. This loop provides input into the AMSAC system. This loop provides main control room Moore/DCA/10-50MA/SL2/

annunciation when steam generator 4 level is high (window box 3C, window 63B), when transfer switch 2-XS-3-175A is in the auxiliary position (widow 1-LS-3-175E 117VAC/-AD,-RE,-RF,-[ABR 2-LM-3-175E Foxboro/N-2Al-12V box 6F, window 148B). 1-PX-3-175 GE/570 2-LS-3-175A Foxboro/N-2AP+ALM-AR 2-LS-3-175EB Foxboro/N-2AI-C2L 2-LS-3-17SEA Foxboro/N-2AI-C2L 2-LS-3-57SF Fooboro/N-2A0-L2C-R ECE 2 2-LS-3-175F Foxboro/No2A+-

This loop is functionally equivalent to Unit 1.

2-LX-3-175ABC Fooboro/N-2AXcDSS (N-ECEP-8E2R(

IReactor VesselHead Vent Throttle Manual Loading Westinghousel7SHC3000 208-68 2-F-6O-397-A Station (Train A) N Flow Loop 53756 1-HIC-68-397 101 2212 2-HIC-68-397 Foxboro/N-255HM-V Target Roco2/3IT592-This loop controls reactor vessel head vent throttle valve 2-FSV-68-397. This nvoie is controlled in the Main Control Room by hand indicating controller 2 1-FM-68-397 2-FM-68-397A Foxboro/N-2A0-VAI HIC-68-397 (on panel 2-M-4.

This loop is functionally equivalent to Unit 1. 2-HC-68-397 Foxboro/N-2AX+DIO IReactor(Vesse Head Vent Throttle Manual Loading Westinghouse/75HC3000 208-68 2-F-68-396-B Station Train B) N Flow Loop 53756 1-HIC-68-396 101 2212 2-HIC-68-396 Foxboro/N-255HM-V 1-FM-6g-3R6 Targot Rock/300592-1 2-FM-68-396A Foxboro/N-2AI-T2V+VE This loop controls reactor vessel head vent throttle valve 2-FSV-68-396. This valve is controlled in the Main Control Room by hand indicating controller 2 2-FM-68-396A Foxboro/N-2A0-VAI HIC-68-396 (on panel 2-M-4).

This loop is functionally equivalent to Unit 1. 12-HC-68-396 Foxboro/N-2AX+DIO

Review of Invensys Process Systems (Foxboro) SPEC 200 Safety-Related Analog Control System

Subject:

Review of Invensys Process Systems (IPS) Foxboro SPEC 200 Safety-Related Analog Control System for use at Watts Bar Nuclear Plant Unit 2 Supporting documentation for the use of the Foxboro SPEC 200 control system in Safety-Related applications at Watts Bar Nuclear Plant Unit 2 has be reviewed and approved by Bechtel Engineering. The review included the Foxboro Certificate of Conformance (COC) submitted for each component supplied. The COC for each component is included in IPS document number 800063-106. The document contains the calibration data sheets, Record of test results, certificate of conformance, and commercial grade dedication, if applicable, for each component supplied for the Auxiliary Feedwater and Emergency Gas Treatment Systems, TVA contract number 69016. The COC documents the qualifications of components in accordance with the requirements of the TVA approved Design Specification issued for the procurement of the safety-related control system.

Additionally, documents that support the qualification of the SPEC 200 system for safety-related applications are panel seismic qualification reports and EMI/RFI qualification report. The seismic qualification reports for panel 0-L-430 (EGTS) and 2-L-381A (AFW) were reviewed and approved by Bechtel Equipment Seismic Qualification (ESQ) group while the EMI/FRI qualification report was reviewed and approved by TVA Corporate EMI Specialist.

A listing of all the qualification documentation associated with the Foxboro SPEC 200 control system is listed below.

The documentation is assembled per cabinets with internal components, controllers, and housing for controls. Each section has Certificate of Conformance for each component with reference to the qualification reports.

Emergency Gas Treatment System (EGTS):

• Nuclear Qualification Service (NQS) seismic report 1703A Revl for Panel 0-L-430

• United Controls International, Seismic Analysis Report for Emergency Gas Treatment System Test Panel Train A & B, Report No. SA-3264-2 Auxiliary Feedwater System (AFW):

• United Controls International, Seismic Analysis Report for Invensys system, Inc.,

Auxiliary Feedwater System, Panel 2-L-381A, Report No. SA-3264-1 Common Reports for EGTS and AFW systems:

" IPS Electromagnetic Compatibility Test Reports, Document No. 800063-1930 0 TVA Corporate EMI/RFI test review work sheet for Foxboro SPEC 200 System R1 (B43 090731 001)

• Evaluation of Foxboro report number 800063-1820 (AFW & EGTS Seismic, Environmental Qualification Report)

May 27, 2010 Page 1 of 3

Review of Invensys Process Systems (Foxboro) SPEC 200 Safety-Related Analog Control System Common External Requirement Specifications:

" 10CFR50 Appendix B

• IEEE-313-1974

• IEEE-344-1975 Common Internal Requirement Specifications:

" ASME NQA-1 Part-1 as defined in Invensys Systems, Inc. Corporate Quality Assurance Program Requirement, QMS-2, Revision S

" Foxboro (IPS) Component Qualification Reports

" Electroswitch - Qualification Reports 2970-2A; 3151-1; ESC-Std-1 000 Technical Publication; NQS-Report 1702A All Reports referenced in this document are availed upon request. Each component listed has at least the cover sheet of the referenced report as an aid. See "References" Section for reports referenced.

Table of Contents:

SECTION 1:

(EMERGENCY GAS TREATMENT SYSTEM)

Cabinet 0-L-430 a) Nest - Model No. N-2ANU-P b) Current to Voltage Converter - Model No. N-2AI-12V c) Controller with Removable Manual - Model No. N-2AC d) Control Module - Model No. N-2AX+A4 e) Voltage to Current Converter - Model No. N-2AO-V21 f) Contact Output Isolator - Model No. N-2AO-L2C-R g) Power Supply - Model No. N-2AX+PS9A SECTION 2:

(AUXILIARY FEEDWATER SYSTEM)

Cabinet 2-L-381A a) Nest - Model No. N-2ANU-P b) Current to Voltage Converter - Model No. N-2AI-12V c) Auto/Manual Balance and Bias Card - Model No. N-2AC-M3 d) Auto/Manual Balance and Bias Card - Model No. N-2AX+AM e) Alarm, Relay Output - Model No. N-2AP f) Alarm, Relay Output - Model No. N-2AX+ALM-AR g) Square Root Converter - Model No. N-2AX+SQE h) Distribution Module - Model No. N-2AX+DSI, N-ECP-8269B i) Power Supply - Model No. N2AX+PS9A, N-ECEP-90029 j) Contact Output Isolator - Model No. N-2AO-L2C-R k) Voltage to Current Converter - Model No. N-2AO-VAI I) Contact Input Isolator - Model no. N-2AI-C2L m) Control Module - Model No. N-2AX+A4 May 27, 2010 Page 2 of 3

Review of Invensys Process Systems (Foxboro) SPEC 200 Safety-Related Analog Control System SECTION 3:

(Control Stations and Supporting Hardware) a) 250 Series, Style E, Display Station - Model No. N-2AX+M2NH b) 250 Series, Style E, Display Station - Model No. N-250HM-M2NH-F c) Display Housing - Model No. N-2AX+H144 d) Display Housing - Model No. N-2AX+H048 e) Retaining Bar - Model No. N-2AX+RB01 f) Transfer Switches - ELECTROSWITCH - Model No. 72426M-2 g) Internal Wiring - COC dated 07/22/2009 h) External Communication Cables

1. 20' Cable - Model No. N-2AK-FF020 - S/N 5683071 to 5683074

2. 20' Cable - Model No. N-2AK-FF020 - S/N 5683075

3. 125' Cable - Model No. N-2AK-FF125 - S/N 5683084

4. 150' Cable - Model No. N-2AK-FF150 - S/N 5683085 to 5683089

5. 150' Cable - Model No. N-2AK-FF150 - S/N 5683090

6. 200' Cable - Model No. N-2AK-FF200 - S/N 5683062 to 5683063

7. 270' Cable - Model No. N-2AK-FF270 - S/N 5683064 to 5683067

8. 310' Cable - Model No. N-2AK-FF310 - S/N 5683068

9. 525' Cable - Model No. N-2AK-FF525 - S/N 5683069 to 5683070 SECTION 4:

(References)

1) Nuclear Qualification Service (NQS) seismic report 1703A Revi for Panel 0-L-430

2) United Controls International, Seismic Analysis Report for Emergency Gas Treatment System Test Panel Train A & B, Report No. SA-3264-2

3) United Controls International, Seismic Analysis Report for Invensys system, Inc.,

Auxiliary Feedwater System, Panel 2-L-381A, Report No. SA-3264-1

4) IPS Electromagnetic Compatibility Test Reports, Document No. 800063-1930

5) TVA Corporate EMI/RFI test review work sheet for Foxboro SPEC 200 System R1 (B43 090731 001)

6) Evaluation of Foxboro report number 800063-1820 (AFW & EGTS Seismic, Environmental Qualification Report)

7) Foxboro (IPS) Component Qualification Reports

8) Electroswitch - Qualification Reports 2970-2A; 3151-1; ESC-Std-1 000 Technical Publication; NQS-Report 1702A May 27, 2010 Page 3 of 3

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 2 (This Attachment contained on the OSM)

1. Drawing Cross Reference List for FSAR Chapter 7

2. Electronic Copies of Legible Current Drawings

FSAR Chapter 7 Drawing Cross Reference List May 27, 2010 Page 1 of 2 Figure # Title Drawing No.

Figure 7.1-1 Protection System Block Diagram NA Figure 7.1-2 Powerhouse-Units 1 and 2 Wiring Diagrams 45W1 640 Control Boards Critical Wiring Braid Installation Providing 2-45W2640 and 2-45W2640-1 which provide U2 separation details.

Figure 7.1-3-SH-1 Train A and Train B Process Interlocks NA Figure 7.1-3-SH-2 Train A and Train B Process Interlocks NA Figure 7.1-3-SH-3 Train A and Train B Process Interlocks NA Figure 7.1-3-SH-4 Train A and Train B Process Interlocks NA Figure 7.2-1-SH-1 Powerhouse Unit I Electrical Logic Diagrams - 47W611-99-1 Reactor Protection System Figure 7.2-1-SH-2 Powerhouse Unit 1 Electrical Logic Diagrams - 47W611-99-2 Reactor Protection System Figure 7.2-1-SH-3 Powerhouse Unit 1 Electrical Logic Diagrams - 47W611-99-6 Reactor Protection System Figure 7.2-1-SH-4 powerhouse Unit 1 Electrical Logic Diagrams - 47W611-3-8 Reactor Protection System Figure 7.2-2 Setpoint Reduction Function for Overpower and NA Overtemperature AT Trips Figure 7.3-1 ESF Test Circuits (Typical) NA Figure 7.3-2 Deleted by Amendment 81 NA Figure 7.3-3-SH-1 Powerhouse Units 1 & 2 Electrical Logic Diagram 47W611-3-2 Feedwater System Figure 7.3-3-SH-2 Powerhouse Units 1 & 2 Auxiliary Feedwater 47W611-3-4 System Logic Diagram Figure 7.3-3-SH-3 Powerhouse Units 1 & 2 Electrical Logic Diagram 47W611-63-1 for Safety Injection System Figure 7.3-3-SH-4 Powerhouse Units 1 & 2 Logic Electrical Diagram 47W611-88-1 for Containment Isolation Not Sent Figure 7.6-1 Deleted by Amendment 65 NA Figure 7.6-2 Deleted by Amendment 65 NA Figure 7.6-3 Powerhouse Unit 1 Electrical Logic Diagram for 47W611-63-7 Safety Injection System Figure 7.6-4 Powerhouse Auxiliary Building Units 1& 2 Wiring 45W760-63-2 Diagrams for Safety Injection System Figure 7.6-5 Reactor Building Unit 1 Variable Processing for 47W611-68-3 Low Temperature Interlocks for RCS Pressure Control Figure 7.6-6-SH-1 Powerhouse Unit 1 Electrical Logic Diagram for 47W611-63-2 Safety Injection System Figure 7.6-6-SH-2 Powerhouse Unit I Electrical Logic Diagram for 47W611-63-5 Safety Injection System Figure 7.6-6-SH-3 Powerhouse Electrical Logic Diagram Residual 47W611-74-1 Heat Removal System Figure 7.6-7-SH-1 RHR Suction Isolation Valve Interlocks NA

(,A

FSAR Chapter 7 Drawing Cross Reference List May 27, 2010 Page 2 of 2 Figure # Title Drawing No.

Figure 7.6-7-SH-2 RHR Bypass Valve Logic FCV-74-8 T (FCV-7 4-9) NA Figure 7.7-1 Simplified Block Diagram of Reactor Control NA System Figure 7.7-10 Typical Location of Control Board Systems NA Figure 7.7-11 Simplified Block Diagram Rod Control System NA Figure 7.7-12 Control Bank D Partial Simplified Schematic NA Diagram Power Cabinets 1 BD and 2BD Figure 7.7-2 Control Bank Rod Insertion Monitor NA Figure 7.7-3 Rod Deviation Comparator NA Figure 7.7-4 Block Diagram of Pressurizer Pressure Control NA System Figure 7.7-5 Block Diagram of Pressurizer Level Control NA System Figure 7.7-6 Block Diagram of Steam Generator Water Level NA Control System Figure 7.7-7 Block Diagram of Main Feedwater Pump Speed NA Control System Figure 7.7-8 Block Diagram of Steam Dump Control System NA Figure 7.7-9 Incore Instrument Sysem NA Figure 7A-1 Instrumentation Symbols and Tabulation from NA TVA DS E18.3.3 Figure 7A-2 Mechanical System Identification Numbers 85M430B617-2D Figure 7A-3 Mechanical Flow and Control Diagram Symbols NA Figure 7A-4 Mechanical Basic Instrumentation and Radiation NA Symbols Figure 7A-5 Mechanical Application of Basic Instrumentation NA Symbols Figure 7A-6 Mechanical Digital Logic Symbols (and/or) NA

l-i9-09m*-t IIýIs lii 11 1 I I 4 4 II I I . I I1,8 I 9 1 1,0 111 1 I 12 1 02990O..00No `ofAl 4003 I-IS-63-3 800NEETCR 0220200 400....o 4 20..... 4 0...232. NOTS:

I- ALL EQU P"N' Is LOCATED ' THE 'A"O'ROM .1-,ITS A - TIC)E LOAD is KIEREO 1NLESS OTFER.ISE OZSCHATED.

.4j NOR. 22 20 S33.4S 0IS POS2200O4 4 SlIEC4 OUN00 ONT4E2`OF 2 HE -O AND IS

'2 ~II 40

-PREFIX.

0 092UN.1 FB 2020 4O 20422.UO*EDCNIC L

20[SlGNAII 00 COTROL 0ERS9 0R2AIDE R0T NUM4ERS.

UNITAU PREFIX A

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DELETED NOTE 1.TABLE 11 REFERENCE AN LINT2 REFERENCE PER ADiIN (T25981201846). DRAWING S 30H617-R"0 REV ICWACE REF1 PREPARERI CECK(ER IAPPROVED I DATE(T I

_IRS

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 3 (This Attachment contained on the OSM)

Revised Common Q PAMS ISG-6 Compliance Matrix

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix Application Non-Prop TVA Non-Prop Target Submittal Proprietary for.

ISG-6 Document Submittal (S) Issued, WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Issued Date / Letter

.for Audit (A) (Y/N) (WEC to TVA) Date / Letter Date / Letter or Forecast (F)

Common Q Topical Report (Section 11)

Approved in SER ML003740165 (P. 4, "The staff made several visits to the CENP sites in Windsor, Connecticut and Rockville, Maryland During the site visits, the staff inspected CENP procedures that are referencedin the topical reportand auditedreportsof commercial-gradededication Approved Approved Approved Commercial Grade Dedication Plan activities." P. 36, "However, during a visit to a CENP site, the staff did ML050350234 N/A N/A DONE Topical Topical Topical Report audit a sampling of CENP's manualsfor CGD activities. On the basis of Report Report the audit, the stafffinds that the procedures andprocesses in the manuals correspondto the requirements of IEEE 7-4.3.2 and the guidance ofEPRI TR-106439 and, therefore, provide an acceptableprogramfor the dedicationof commercial-gradeitems. ")

WB2 PAMS D3 Analysis Technical Report: WNA-LI-00058-WBT, WBT-D-1800 WBT-D-1800 June 30, 2010 2 D3 Analysis This will addressedin Plant Specific Action Item PSA176.11 'in the Rev 0 S Y TVA Action April 6,2010 April 6,2010 (F)

TechnicalReport Common Q Topical Report (Sections 6.4 and 9)

This citation in the Common Q Topical Report applies to the platform.

For system test and calibrationandfault detection thefollowing Design Report on Computer documents apply: Approved Approved 3 Integrity, Test and Calibration, and ML050350234 N/A N/A DONE Topical Topical Approved Fault Detection 1. WNA-DS-01667-WBT, Watts Bar 2 PAMS System Design Report Report. TopicalReport Specification

2. WNA-DS-01617-WBT, Watts Bar 2 PAMS specific System RequirementsSpecification Common Q Topical Report (Sections 6.2 and 6.3)

This citation in the Common Q Topical Report applies to the platform.

For system theory of operation descriptionthe following documents apply- Approved Approved Approved 4 Theory of Operation Description 1. WNA-DS-O1667-WBT, Watts Bar 2 PAMS System Design ML050350234 N/A N/A DONE Topical Topical TopicalReport Spciiato A W W B PReport Report Specification"-

2. WNA-DS-01617-WBT, Watts Bar 2 PAMS specific System Requirements Specification Common Q Topical Report (Section 8)

The Common Q equipment was qualified accordingto the plan specified Approved Approved Approved 5 EQ Testing Plans in the Common Q Topical Report. All EQ activities were ultimately ML050350234 N/A N/A DONE Topical Topical Topical Report approved by the NRC. Any open items on equipment qualificationwere Report Report identifiedas Plant Specific Action Items.

Common Q Software Program Manual (Section 4)

SER: "On the basis ofthe foregoing review of CENP's software development processfor applicationsoftware, the staff concludes that the Approved Approved Approved 6 SQA Plans and Procedures SPMspecifiesplans that willprovide a quality software life cycle process, ML050350234 N/A N/A DONE Topical - Topical Topical Report Report Report and that these plans commit to documentation of life cycle activities that will perm it the staff or others to evaluate the quality of the design features upon which the safety determination will be based."

WB2 Common Q ISG-6 Conipliance Matrix (Jun 11 2010).doc Page I of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix Application Non-Prop TVA Non-Prop Target Submittal Proprietary for ISG-6 Document Submittal (S) Issued, WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Issued Date / Letter for Audit (A) (Y/N) (WEC to TVA) Date / Letter Date / Letter or Forecast (F)

WBT-D-1680 B-160 WBT-D-1680 W TD68 DiagramDescription System Level to Block Watts Bar 2 PAMS System Design Specification WNA-DS-01 667-WBT, Rev. 1I S TVA Action March 3, March 3, 2010 June 25, 2010 2010 WBT-D- WBT-D-1680 June 25, 2010 WNA-DS-01667-WBT, Rev. I S Y TVA Action 1680, March HW and SW Architecture Watts Bar 2 PAMS System Design Specification and Software Requirements 3,_2010_Marh_3,_2010_(F)

Descriptions Specification WBT-D- WBT-D-1786 June 25, 2010 WNA-SD-00239-WBT, Rev. I S Y TVA Action 1686, March 5,2010 April6,2010 (F) 9 FMEA Watts Bar 2 PAMS specific FMEA WNA-AR-00180-WBT S TVA-TBD 8/31/10 N/A

. SPM Safety Planstates, "It applies to all Common Q safety critical software whose failure could result in severe consequences to public health and safety. For Common Q systems, safety criticalsoftware is defined as software belonging to the "Protection" class as defined in Section 1."

1 SPMExhibit 4-1 ASSIGNMENT OF COMMON Q SOFTWARE TO Approved Approved Approved I0 Safety Analysis CLASSES, classifies PAMS as Important To Safety. N/A N/A N/A DONE Topical Topical Topical Report

. SER states, ""On the basis ofthe foregoingreview ofCENP'ssoftware Report Report development processfor applicationsoftware, the staff concludes that the SPM specifies plans that will provide a quality software life cycle process, and that these plans commit to documentation of life cycle activities that will permit the staff or others to evaluate the quality of the designfeatures upon which the safety determinationwill be based.

WBT-D-1680 WBT-D-1680 I System Requirements Specification Watts Bar 2 PAMS specific System Requirements Specification WNA-DS-01617-WBT, Rev. 1 5 Y TVA Action March 3 March 3,2010 June 25, 2010 2010 WBT-D-1526, January 28, 12 System Test Plan Testing Process for Common Q Safety Systems WNA-PT-00058-GEN, Rev. 0 A N DONE N/A N/A 2010 Document at W Rockville Office WBT-D-1961, 13 Software Design Spec Watts Bar 2 PAMS Software Design Description (two documents, one for flat WNA-SD-00248-WBT, Rev. 0 (FPDS) A N May 5, 1010 N/A N/A May 21,, 2010 panel display and one for AC 160) WNA-SD-00250-WBT, Rev. 0 (AC 160) May 12, 2010 Document at W Rockville Office WBT-D-1526, 14 Software Development Plan Watts Bar 2 PAMS Software Project Plan WNA-PD-00073-WBT, Rev. 0 A N DONE N/A N/A January 28, 2010 Document at W Rockville Office WB2 Common Q ISG-6 Compliance Matrix (Jun 11 201 0).doc Page 2 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix r I '. 1* p Application - Non-Prop TVA Non-Prop Target Submittal Proprietary for ISG-6 Document Submittal (S) Issued, WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Issued Date/ Letter for Audit (A) (Y/N) (WEC to TVA) Date / Letter Date / Letter or Forecast (F)

Common Q Software Program Manual (Section 7)

SER: "On the basis of theforegoing review of CENP's software 15 Software Maintenance Plan development processfor applicationsoftware, the staff concludes that the Approved. Approved . Approved SPMspecifies plans that willprovide a quality software life cycle process, ML050350234 N/A N/A DONE Topical Topical Topical Report and that theseplans commit to documentation oflife cycle activities that Report Report will permit the staff or others to evaluate the quality of the designfeatures upon which the safety determination will be based."

4-6 Seft:'ae Operation Plan

• W.VattBAr 2 PA41S Tznhieail MIan',ual (Not required per Feb 12, 2010 ISG-6 N/A N/A N/A DELETED DELETED DELETED DELETED draft)

WBT-D- WBT-D-1786 17 Application SRS Watts Bar 2 PAMS Software Requirements Specification WNA-SD-00239-WBT, Rev. I S Y TVA Action 1686, March June 25, 2010 5,2010 April 6, 2010 Common Q Software Program Manual (Section 3)

• SPM Safety Plan states, "It applies to all Common Q safety critical software whose failure could result in severe consequences to public health and safety. For Common Q systems, safety critical software is defined as software belonging to the "Protection" class as defined in Section 1."

• SPM Exhibit 4-1 ASSIGNMENT OF COMMON Q SOFTWARE TO Approved Approved Approved 18 Software Safety Plan CLASSES, classifies PAMS as Important To Safety. N/A N/A N/A DONE Topical Topical Ap pr t

• SER states, ""On the basis of theforegoing review of CENP's software Report Report Topical Report development processfor applicationsoftware, the staff concludes that the SPM specifies plans that will provide a quality software life cycle process, and that these plans commit to documentation oflife cycle activities that will permit the staff or others to evaluate the quality of the design features upon which the safety determination will be based."

WBT-D-1526, January 28, 19 Software Test Plan Testing Process for Common Q Safety Systems WNA-PT-00058-GEN, Rev. 0 A N DONE N/A N/A 2010 Document at W Rockville Office WB2 Common Q ISG-6 Compliance Matrix (Jun 11 2010).doc Page 3 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix I' ¶

• 9 9 V Application Non-Prop TVA Target Submittal Proprietary ISG-6 Document Non-Prop for Issued, Submittal (S) Rqr'd Date Issued Withholding WEC Equivalent Document WEC Document Number (Draft dated Feb/12/2010) or Available Date / Letter (YIN) (WEC to TVA) Date / Letter Issued for Audit (A) or Forecast (F)

Date / Letter 1~ 4 4 4 4 4

1) 00000-ICE-37722, Rev 00, dated November 11, 1999, "Commercial Grade Dedication Report for the QNX Operating System for Common Q Applications";

2) WNA-CD-00018-GEN, Rev 03, dated October 8, 2008, "Commercial Dedication Report for QNX 4.25G For Common Q Applications";

3) GWK F 700 778, Rev. 01, dated February 18, 2000, "Generic Operating History Eyaluation Report on Previously-Developed Software in ABB AC 160, 1/0 Modules and Tool Software";

4) GWK F 700 777, Rev. 02, dated February 22, 2000, "Design and Life Cycle Evaluation Report on Previously-Developed Software in ABB AC 160, I/O Modules and Tool Software" Common Q SER ML003740165 P.2 "As regardsto the commercial dedication of the Common Qplatform, includingthe previously developed software and tools, CENP conducted a quality evaluation of the A C6O programmablelogic controller(PLC) system planned to be used in implementing the safety functions of the reactorprotection system for the OskarshamnModernization Project in Sweden. "

P.4 "CENPsubmitted the six proprietaryreports:

" 2008677-IC-TR560-10, Rev. 00, dated September 24, 1999, 00000-ICE-37722, Rev. 00 WBT-D-1526, "Seismic Qualification Test Reportfor Common Q Applications" WNA-CD-0001 8-GEN, Rev. 03 January 28, 20 Software Tool Verification Program " 2008677-IC-TR560-11, Rev. 00, dated September 24, 1999, A N DONE N/A N/A 2010 "EnvironmentalTest Reportfor Module Equipment Qualification GWK F 700 778, Rev. 02 Document at W for Common Q Applications" GWK F 700 777, Rev. 02 Rockville Office

" 2008677-IC-TR560-12, Rev. 00, dated October8, 1999, "EMI Qualification Test Report for Module Equipment Qualificationfor Common Q Applications"

" 00000-ICE-37722, Rev 00, datedNovember 11, 1999, "Commercial Grade DedicationReportfor the QNX Operating System for Common Q Applications"

" GWK F 700 778, Rev. 01, dated February 18, 2000, "Generic OperatingHistory EvaluationReport on Previously-Developed Software in ABB AC] 60, I/0 Modules and Tool Software"

" GWK F 700 777, Rev. 02, datedFebruary22, 2000, "Designand Life Cycle EvaluationReport on Previously-DevelopedSoftware in ABB ACI60, I/0 Modules and Tool Software" P. 28 "CENPdid not dedicate the software development tools. IEEE Std 7-4.3.2 does not require that the software tools be dedicatedif the V&V process will detect errorsthat the tools may introduce. The CENP V& V procedures are specified in the SPM and have been evaluatedin this safety evaluation.IEEE Std 7-4.3.2 requires that the tools be identified and placed undersoftware configurationmanagement control. CENP configurationmanagement is evaluatedandfound acceptable in Section 4.3. l.k. On the basis of the above, the staff concludes that it is acceptable that the PDSdevelopment tools from QSSL not be dedicated."

Page 4 of 8 Common Q Compliance Matrix (Jun II 2010).doc WB2 Common W132 Q ISG-6 ISG-6 Compliance Matrix (Jun 11 201 0).doc Page 4 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix I. Y 7 1 7 Application TVA Non-Prop ISG-6 Document Non-Prop Target Submittal Proprietary for Submittal (S) Issued, WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Date / Letter (Y/N) (WEC to TVA) Date / Letter Issued for Audit (A) or Forecast (F)

Date / Letter 24I- Seftmu'ar TrFaining PlanAW A'atcBr 21Sefrvare Training Plan (Utility Respensilty (Not required per N/A N/A DELETED DELETED DELETED DE LETED Feb 12, 2010 ISG-6 draft)

Common Q Software Program Manual (Section 5)

SER states, ""On the basis ofthe foregoing review of CENP's software development processfor applicationsoftware, the staff concludes.that the Approved Approved Approved 22 Software V&V Plan and Procedures SPMspecifiesplans that will provide a quality software life cycle process, ML050350234 N/A N/A DONE Topical Topical Topical Report and that these plans commit to documentation oflife cycle activitiesthat Report Report will permit the staff or others to evaluate the quality ofthe designfeatures upon which the safety determinationwill be based."

WBT-D-1961, Concept & Definition Phase: WNA-VR- A N DONE N/A N/A May 21,, 2010

• 00279-WBT, Rev 0 Document at W Rockville Office 23 Rqirment TacabiltyWatts Bar 2 PAMS specific RTM 23 Requirements Traceability Matrix (Lifecycle Document, same ID, different revision depending on phase) Design Phase A N July 9, 2010 N/A N/A Implementation Phase A N Sept 10, 2010 N/A N/A Integration Phase A N Oct 8, 2010 N/A N/A Final A N Nov 12,2010 N/A N/A A1867/AI688 A N Sept 28, 2010 N/A N/A WBT-D-2024, PC Node Box & Flat Panel Display A N DONE N/A N/A June 9, 2010 (CDI372, 8Document Re 7 CD-380, Rv at W 24 Commercial Grade Dedication Commercial Grade Dedication Instructions for A1687, A1688, Upgraded PC (CDI-3722, Rev 7 & CDI-3803, Rev 8R) ockville Office Report node box and flat panels, power supply _ockvileOffice WBT-D-2035, Power Supply (CDI-4057, Rev 4) A N DONE N/A N/A June 11,2010 Document at W Rockville Office

• WEC Level II QA Procedures WEC WBT-D-1526, Commercial Grade Dedication WEC Level II QA Procedures WEC 7.2, 7.3; RRAS Level II Procedures NA 7.2 (Rev 1), WEC 7.3 (Rev. 0) January 28, Procedures 7.4,

• RRAS Level III Procedures NA 7.4 (Rev. 0) Document at W Rockville Office 26 Final Design Description (As Final Watts Bar 2 PAMS specific SysRS and SRS. .WNA-DS-01617-WBT, Rev. >1 S Y Nov. 30, 2010 Built/End of FAT) (Lifecycle Document(s), final revision identification unknown.) WNA-SD-00239-WBT, Rev. >1 S Y Nov. 30, 2010 27 Final Logic Diagrams Watts Bar 2 PAMS specific logic diagrams CD with print out of final delivered function A N Nov. 30, 2010 chart code 28 Final Reliability Analysis Watts Bar 2 PAMS specific reliability analysis TBD A N August 31, 2010 N/A N/A 29 Final Report on Acceptance of Summary report on acceptance of A1687, A1688, Upgraded PC node box, flat A1867/AI688 A N Sept 28, 2010 N/A N/A WB2 Common Q ISG-6 Compliance Matrix (Jun 11 2010).doc Page 5 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix V r I Application Non-Prop TVA Non-Prop Target Submittal Proprietary for Issued, ISG-6 Document Submittal (S)

WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Issued Date / Letter for Audit (A) (Y/N) (WEC to TVA) Date / Letter Date / Letter or Forecast (F)

Commercial Grade Dedication panels and power supply WBT-D-2024, PC Node Box - LTR-EQ-10-50 A N DONE N/A N/A June 9, 2010 Document at W Rockville Office WBT-D-2024, Flat Panel Display- LTR-EQ-10-50 A N DONE N/A N/A June 9, 2010 Document at W Rockville Office WBT-D-2035, Power Supply - EQ-TP-105-GEN, EQ-TP- A N DONE N/A N/A June 11, 2010 1i7-GEN, EQ-TP- I14-GEN Document at W Rockville Office 30 Final System Configuration Watts Bar 2 PAMS specific configuration drawings TBD A N Nov. 30, 2010 N/A N/A Documentation 31 Final Factory Acceptance Test Watts Bar 2 PAMS specific FAT report TBD A N October 20 10 N/A N/A Reports

-n-stallatien Tpt Planq and Watts Bar 2 P.44S speeifie SAT test plan and prazadure (Not required per Feb N/A N/A N/A DELETED DELETED DELETED DELETED PFeeedFeS 12, 2010 ISG-6 draft)

A1867/A1688 A N July 2, 2010 N/A N/A PC Node Box & Flat Panel Display WBT-D-1961, 33 Qualification Test Procedures EQ test procedures for A1687, A1688, Upgraded PC node box and flat panels, (EQTP33GEN, EQ-TP-35-GEN, A N DONE N/A N/A May 21,, 2010 power supply EQ-Document at W EQ-TP-60-GEN) Rockville Office Power Supply A N TBD N/A N/A A1867/A1688 A N Sept 28, 2010 N/A N/A 34 Summary of Final EQ Test Results 34oumareofFialEQTespRsutsPC EQ Summary report for A1687, A1688, Upgraded PC node box and flat panels, Node Box & Flat Panel Display A N Sept 17, 2010 N/A N/A power supply Power Supply A N Sept 17, 2010 N/A N/A WBT-D-1961, Concept & Definition Phase: WNA-VR- A N DONE N/A N/A May 21,, 2010 00283-WBT, Rev 0 Document at W Rockville Office 3 Summary of Test Results (including Watts Bar 2 PAMS specific IV&V Phase Summary Reports FAT)

Design Phase A N July 30, 2010 N/A N/A Implementation Phase A N Sept 30, 2010 N/A N/A Integration Phase A N October 29, 2010 N/A N/A Final Report S Y Nov 30, 2010 36 System Test Procedures Watts Bar 2 PAMS specific FAT Procedure TBD A N Sept 30 2010 WB2 Common Q ISG-6 Compliance Matrix (Jun 11201 0).doc Page 6 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix T I I Y I 7 7 Application Non-Prop TVA Non-Prop Target Submittal Proprietary ISG-6 Document for Issued, Submittal (S) Rqr'd Date Issued WEC Equivalent Document WEC Document Number Withholding (Draft dated Feb/12/2010) or Available Issued Date / Letter for Audit (A) (Y/N) (WEC to TVA) Date / Letter Date / Letter or Forecast (F)

WBT-D-1526, 37 leftware Management Watts Bar 2 PAMS specific Project Plan and Software Project Plan WNA-PD-00073-WBT, Rev. 0 A N DONE N/A January 28, N/A 2010 Implementation Procedures Document at W Rockville Office WBT-D-1526, January 28, 38 Software Project Risk Management Watts Bar 2 PAMS specific Project Plan and Software Project Plan WNA-PD-00073-WBT, Rev. 0 A N DONE N/A N/A 2010 Report Document at W Rockville Office WBT-D-1526, January 28,

1) Element Software Test Procedure, WNA-TP-00357-GEN WNA-TP-00357-GEN, Rev. 4 A N DONE N/A N/A 2010 Document at W 39 Software Test Procedures Rockville Office

2) Watts Bar 2 PAMS specific Processor Module Software Test TBD A N August 31, 20 10 N/A N/A WBT-D-1526, January 28, 40 Software Tool Analysis Report See Software Tool Verification Program See Software Tool Verification Program A N/A DONE N/A N/A 2010 (Item # 20)

Document at W Rockville Office N See item #35 for for See Sedule item #35 Sedule See item #35 forSedule 41 V&V Reports Watts Bar 2 PAMS specific IV&V Phase Summary reports See item #35 for list A schedule for schedule for schedule 42 System Build Documents Software Release Records TBD A N Nov. 30, 2010 N/A N/A Common Q Software Program Manual (Section 5)

SER states, ""On the basis of theforegoing review of CENP'ssoftware development processfor applicationsoftware, the staff concludes that the Approved Approved 43 Software Configuration SPMspecifiesplans that will provide a quality software life cycle process, " Appical Apical Approved Management Plan and that these plans commit to documentation of life cycle activities that will ML050350234 N/A N/A DONE Topical Topical Topical Report permit the staff or others to evaluate the quality of the designfeatures upon Report Report which the safety determinationwill be based."

WBT-D-2024, 44 TVA/NRC Open Items List 5 N/A 00000-ICE-30156 Rev. 6 A N DONE N/A N/A June 9, 2010 2010 Document at W Rockville Office WB2 Common Q ISG-6 Compliance Matrix (Jun 11 2010).doc Page 7 of 8

Watts Bar 2 - Common Q PAMS ISG-6 Compliance Matrix Application Non-Prop TVA Non-Prop Target Submittal Proprietary for ISG-6 Document Submittal (S) Issued, WEC Equivalent Document WEC Document Number Rqr'd Date Issued Withholding (Draft dated Feb/12/2010) or Available Issued Date / Letter (Y/N) (WEC to TVA) Date / Letter for Audit (A) or Forecast (F)

Date / Letter I) C1527 AFI00 Peripheral Component Interconnect (PCI) interface card

2) Common Q TC514 AF100 Fiber Optic Modems (Evolutionary Product These components can be found in the Maintenance/Improvements) Summary Qualification Report Of WBT-D-2024, 45 New or modified items listed in the 3) PM646A Processor Module Hardware Testing For Common Q A N DONE N/A N/A June 9, 2010 technical report Applications, 00000-ICE-37764, Rev 3 and Document at W

4) C1631 AF100 Communication Interface Module TWICE Qualification Status Report, WNA- Rockville Office

5) D0620 Digital Output Card QR-000I I-SSP W1B2 Common Q ISG-6 Compliance Matrix (Jun 11 2010).doc Page 8 of 8

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 5 (This Attachment contained on the OSM)

Design Criteria WB-DC-30-7 Revision 22, "Post Accident Monitoring Instrumentation"

TENNESSEE VALLEY AUTHORITY Division of Nuclear Engineering ii RIMS QA RECORD N/A DESIGN CRITERIA DOCUMENT No. WB-DC-30-7 WATTS BAR NUCLEAR PLANT UNIT 1 / UNIT 2 TITLE: POST ACCIDENT MONITORING INSTRUMENTATION

• Signatures on original REVISION RO R21 R22 DATE:

• 1-29-2007 8-27-2008 PREPARED

• H.Henderson R.Pachigolla CHECKED D.C.Mather VERIFIED J.L.Seeley D.C.Mather APPROVED

• R.M.Johnson V.L.Lotspeich TVA MGMT S.A.Hilmes

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED Revisions were required to remove the "holds" originally placed on the unresolved portions of this criteria. Other 12/18/84 minor changes were also incorporated.

The "hold" shown on paragraph 3.4.1.6 will be resolved when information requested from NEB is received per memorandums from F. W. Chandler to J. A. Raulston dated August 31, 1984 (EEB 840904 980), and November 15, 1984 (EEB 841115 918).

This is a general revision of the Design Criteria which 2 complies with the requirements of Supplement 1 to NUREG-0737 09/22/88 and the guidance of Regulatory Guide 1.97 Rev 2.

The revision introduces Type and Category definitions which are consistent with R.G. 1.97 Rev. 2. The category "Support Instrumentation" is no longer included or defined :

references to Support Instrumentation have been deleted.

Included in the revision are changes which were introduced through revision of the set of design input calculations listed in the References (Section 9).

The substantial number of changes in this revision has made it impractical to indicate the changes with lines in the margin.

This revision incorporated Commitments and Requirements in the C/R Data Base as of May 16, 1986.

Type D variables will be identified at a later date.

This is a general revision of the design criteria which 3 complies with the requirements of supplement 1 to NUREG - 06/15/90 0737 and the guidance of Regulatory Guide 1.97 revision 2.

The following Design Input Memorandums have been incorporated with editorial changes where required.

DIM-WB-DC-30-7-2 (B26 890405 014)

DIM-WB-DC-30-7-3 (B26 891025 077)

DIM-WB-DC-30-7-4 (B26 890814 076)

DIM-WB-DC-30-7-5 (B26 891215 076)

DIM-WB-DC-30-7-6 (B26 900419 077)

DIM-WB-DC-30-7-7 (B26 900426 076)

DIM-WB-DC-30-7-1 does not exist and is an invalid number.

Other editorial changes were made throughout the document to clarify the requirements for post accident monitoring instrumentation and its circuitry.

Also included in this revision are changes which were introduced through revision of the design input calculations listed in the reference section. (Section 9.0)

The revision levels have been deleted from the calculations referenced in the reference section. (Section 9.0) ii

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED Appendix B "Required Accuracies" has been deleted. The 3 Category 1 required accuracies are given in calculation WBN-(cont'd) OSG4-111. (Reference 9.1.14). [PL-08-0485 thru -0489]

The substantial changes in this revision have made it impractical to indicate the changes with revision bars in the margin.

DCN DCN RIMS No. B26 900928 801 S-12931-A 09/28/90 Revised Sections 3.4.1.4, 3.5.1.1, 3.5.1.4, 3.5.1.5, and 4.3.1.1 to correct discrepancies and clarify the language regarding separation and isolation. Paragraph3.4.1.4 was changed to delete an improper reference and clarify that isolation devices shall be 1E qualified for that application.

Paragraphs 3.5.1.1, 3.5.1,4, 3.5.1,5, and 4.3.1.1 were revised to clarify the requirements for separation of PAM channels 1, 2, and 3 (PAM 1, PAM 2, and PAM 3).

Revised Appendix A, Table A-1 to specify a third SG NR level loop instead of using the SG WR level as the SG level PAM 3 channel and changed the diverse parameter for auxiliary feedwater flow from SG NR level to SG WR level.

Revised pages: 12, 16, 21, Appendix A, Table A-1 (see revision bars).

This is a general revision of the design criteria. Minor 4 changes, corrections, and editorial comments were 05/28/91 incorporated.

References 9.1.5, 9.1.16, 9.1.17, and 9.3.4 were deleted.

In Table A-1, "Steam Generator Power Operated Relief and Safety Valves Status" was revised to read "Main Steam Flow",

as allowed by R.G. 1.97.

Revised 3.4.1.5, 3.4.1.6, and 3.4.2.6 to clarify recording requirements.

Added recording requirements for Category 3 variables.

Added requirements for instrument accuracy calculation.

Revised Section 6.0 "Quality Assurance" and added the requirement to identify Category 2 non-Class 1E cables in CCRS as required by CAQR WBP 90021P.

Added Appendix B - Table B-1.

Incorporated OIDB-288 7-RO0.

No pages were deleted in this revision.

The following pages were revised: 2-4, 7, 10-15, 18-24, 26-28, A-I, A-2, Table A-1, page numbers 1, 2, 3, 6, 8, 9, 10, i1, 12, and 14.

iii

TVA

~REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED DCN DCN RIMS NO T56920410957 M-18087-A Revised Appendix A Table A-I Page 5 VAR NUM 36 to have an 04-10-92 Analog Scale Range from 6400 to 7400 and a digital display from 0 to 9999 and a Non-lE Power Supply.

Page added: Revision Log - V DCN DCN RIMS NO. T56920918899 S-20605-A Revised Appendix A Table A-i Page 5 VAR NUM 36 to have a 09-18-92 digital display from 6400 to 7400.

DCN DCN RIMS NO. T56921116957 M-21497-A Revise variable number 70 pressurizer relief tank temperature 11-16-92 to show vertical line "range to" to read 400.

PP revised: Rev Log P. V, P. 8 of Appendix A, Table A-I DCN DCN RIMS NO. T56921116962 M-18200-A Revised Appendix A, Table A-I, Pages 1 & 14, to rescale 11-16-92 Auxiliary Feedwater Flow Transmitters to 0-700 GPM.

Pages revised: V, Page 1 & 14 of Appendix A, Table A-I DCN DCN RIMS NO T56 921124 882 S-21610-A 11-24-92 Revised Section 3.4.1.7 to clarify accuracy calculation requirements for PAM Category 2 instruments. Revised Page 12 and Page V.

Total pages affected equals 2.

DCN DCN RIMS No. T56 930222 930 S-23452-A 02-21-93 Revised Post Accident Monitoring Variables List, Appendix A Table A-i, VAR NUM 17.

DCN DCN RIMS No. T56 930529 805 S-25193-A 05-08-93 Appendix A, Table A-I revised to correct range units for variables 92, 94 and 99. (Pages 10, 11 & 12).

Appendix B, Table B-I revised to add variable 92, Auxiliary Building Vent Flow Rate (Page B-I).

DCN DCN RIMS No. T56 930618 892 M-09964-A 06/18/93 Revised Post Accident Monitoring Instrumentation Component Qualification Matrix, Appendix A, Page A-I and Section 3.5.2.2 to indicate PAM Category 2 control power requirements as "highly reliable (diesel or battery backed) non-divisional power sources." Revised Appendix A, Table A-i to revise Type/Category requirements for Main Steam Line Radiation, Variable Number 7, from Al, CI, E2" to "C2, E2".

DCN DCN RIMS No. T56 931124 971 W-25945-A 11/23/93 Revised Table B-I to correct the variable names, primary elements, and computer addresses to agree with the ERFDS I/O List (45B901) [PL-08-0490] and the PAM Category 2 Variable calculation (WBPEVAR9202003). [PL-08-0491 thru -0500]

Added page vii and revised Page B-I of Appendix B.

iv

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED Revised to add Source Notes 1 and 2.

5 Made minor administrative changes throughout the document. 11/30/93 Pages Revised: i, Coordination Log, vi, 4, 5, 8, 12, 13, 14, 20, 22, 27, 28, 30, 32, through 46.

Pages Added: 48 Pages Deleted: None Revised to delete the MCR Particulate Monitor and to delete 6 deviation 14 by meeting the R.G. 1.97 required range. 01/27/94 Revised Sections 3.4.1.6 and 3.4.2.4 to clarify category 2 isolation.

Pages Revised: 12, 14, 39, 42, 46 No Pages added or deleted.

DCN DCN RIMS No. T56 940519 812 S-30679-A 05/18/94 Revised name, primary element, and computer address for Variable 94.

Added Page: via Revised Page: 47 DCN DCN RIMS No. T56 940926 882 S-31881-A 09/23/94 Revised to add Source Note 3.

CATD 22911-WBN-01 Revised Pages: via, 48 Added Pages: None Deleted Pages: None DCN DCN RIMS No. T56 950408 838 S-35446-A 04/08/95 Revised Sheet 12, Section 3.4.1.7 to add additional detail found in the FSAR.

Revised Pages: via, 12 Added Pages: None Deleted Pages: None Revised to add deviations to Reg Guide 1.97 R2, add 7 additional references, added variable 95 to the ERFDS PAM 05/08/95 display, and to make revisions to the ranges for variables 95

& 96 are a result of revision to WBNAPS3-048 R8. [PL-08-0501]

Pages Revised: i, vii, Coordination Log, (viii), 4, 28, 32, 43, 47 Pages Added: 49 thru 67 Pages Deleted: None DCN DCN RIMS No. T56 950526 960 S-36511-A 05/26/95 Revised Table B-1 to correct instrument I. D. number and Table A-1 to correct range.

Revised Pages: via, 44, 47 V

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED DCN DCN RIMS No. T56 950617 869 S-36997-A 06/17/95 Revised sheet 43, to revise the range of the condenser vacuum pump exhaust vent (noble gas) to agree with Revision 10 of WBNAPS3-048. [PL-08-0501]

Pages Revised: vii, 43 Pages Added: None Pages Deleted: None Revised to add deviation 14 per Revision 11 of WBNAPS3-048 8 [PL-08-0501] and correct typographical error on page 33. 09/11/95 Pages Revised: vii, viii, 28, 32, 33, 42, 46, 55 Pages Added: ix Pages Deleted: None Revised to clarify Appendix A, Component Qualification 9 Matrix, added note 12 to Appendix A, Table A-1, and correct 10/13/95 typographical errors in Table A-1. Revised instrument number in Table B-1.

Pages Revised: viii, 28, 30, 33, 34, 39, 46, 47, 55 Pages Added: 46a Pages Deleted: None DCN DCN RIMS No. T56 951107 810 S-38398-A 11/07/95 Revised to clarify Appendix A, Component Qualification Matrix and Appendix A, Table A-1, Post Accident Monitoring Variables List per DCN S-38398-A.

Pages Revised: 30, 44, 45, viii Pages Added: None Pages Deleted: None Revised to change Appendix A, table A-1, Variable Number 29 10 (Accumulator Tank Level), Range From to 7450 Gallons and 04/03/96 Range To to 8080 Gallons. This change was incorporated in the field based on DCN W-26189-A. Corrected typographical errors and pages numbers. Correctly identified Appendix C.

Deviation 15 (in Table C) justified a large deviation from the Range recommended in RG 1.97 for this Variable. The new range is slightly different from that discussed in the justification, but the basis for the acceptability of the deviation from the RG 1.97 Recommended Range does not change.

Therefore, no revision to Deviation 15 is necessary.

Pages Revised: viii, ix, 4, 36, 45, 50 through 68, 46a to end of the document renumbered to delete page number 46a.

Pages Added: None Pages Deleted: None vi

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED

• DCN E-50024-A (T56 981023 800) changed DS-E18.1.20, 11 "Instrumentation and Control, Labeling of Components" to 12/11/98 DS-E18.1.24, "Human Factors Engineering" in Section 3.4.1.3, 3.4.2.3, 4.3.2.5, and 9.3.11, added Deviation 37 and other minor corrections.

• Renumbered entire document, which changed page numbers on Table of Contents (pages xi through xiv).

Pages Revised: All Total Pages: 79 (includes i through xiv and 1-65)

In accordance with PER 99-010239, administrative change to 11A add effective date of Revision 11 on Coversheet and Revision 7/27/99 Admin Log page ix, and to add names on Coversheet of Preparer, Change Verifier, and Approver. Deleted RIMS No. on Coversheet Total Pages: 79 (includes i-xiv and 1-65)

Incorporates DCNs as follows:

12

• DCN M-39608-A (T56 980407 801) revised design criteria to 8/24/99 change Appendix-C, Table C, Deviation 32, transmitter range from 20 ft. to 200 inches. This change will be reflected upon field completion of DCN M-39608-A. Regulatory Guide 1.97, Post Accident Monitoring Variable List, Appendix A, Table A-1, variable number 5, Containment Sump Level (Wide Range) range to 20 ft. has been changed to 200 inches.

Added Reference 9.1.29.

• DCN M-39911-A (T56 981215 803): Modification M-39911-A replaces the obsolete Unit 1 Westinghouse P2500 Plant Process Computer with a new Plant Integrated Computer System. This Plant Computer System provides an operator friendly, state of the art, real time process computer system for the WBN plant operators. After this modification, the new Plant Computer will be operational and performing all the functions of the existing Plant Computer (WB-DC-30-29) and Emergency Response Facilities Data System (ERFDS) (WB-DC-30-8). Therefore, Design Criteria's WB-DC-30-8 and WB-DC-30-29 have been combined into one Design Criteria WB-DC-30-29, "Plant Integrated Computer System." Design Criteria WB-DC-30-7 has been revised to incorporate this change by removing references to the Emergency Response Facilities Data System (ERFDS),

Technical Support Center Computer or P2500 and replacing them with Plant Computer references. Revised Section 3.4.2.4, Appendix A, and Appendix B - Table B-1.

• Deleted Coordination Log, which is not required per NEDP-10.

" Renumbered entire document, which changed page numbers on the Table of Contents (pages x-xii).

Total Pages: 74 (includes i-xii and 1-62)

Incorporates DCN as follows:

13

• DCN 50885-A revised Section 3.4.1.4 to clarify that the 10/25/2001 requirement for isolation from components which perform automatic safety control functions applies to non-Class 1E components.

• Reformatted and renumbered pages i-x.

Total Pages: 72 (includes i-x and 1-62) vii

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED Incorporates DCN as follows:

14 9 DCN 50917-A revised TABLE B-I for PAM variable 46. Variable 3-29-2002 46 was changed from recorder points to Plant Computer System for MCR indication.

• Renumbered pages i-xi due to adding page to the Revision Log.

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates EDC as follows:

15

• EDC 51161-A revised design criteria to include a requirement 9-6-2002 to identify Category 3 components in MEL and to define high quality for Category 3 components. Added Note 14 and made minor corrections to Appendix A, Table A-I. Revised Sections 3.4.3.1, 4.3.1.4, 4.3.3, added Section 4.3.3.1, revised Section 6.3 and Appendix A Table A-I.

• Renumbered pages 1-62 due to adding Section 4.3.3.1, which changed page numbers on the Table of Contents (pages ix-xi).

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates DCN as follows:

16

• DCN 50189-A revised design criteria to delete reference to 10-30-2003 Note 8 for Variable Number 23 (Containment Pressure - Wide Range) in Appendix A, Table A-I, Page No. 4.

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates DCNs as follows:

17

• DCN 50933-A revised Appendix A, Component Qualification 4-22-2004 Matrix, to clarify recording requirements for Category 1 variables. Revised Appendix A, Table A-i, for variable number 4 to delete trending on non-divisional trend recorder. Revised Appendix B, Table B-I, to add variable number 4 and 96.

• DCN 51075-A revised Appendix A, Table A-I, and Appendix C, Table C, for Variable Number 41 and Deviation 7 to change the WBN recommended range from 50 to 30 Deg F.

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates DCN as follows:

18

• DCN 51239-A revised Appendix A, Component Qualification 8-31-2004 Matrix, and Appendix A, Table A-i, Post Accident Monitoring Variables List.

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates EDC as follows:

19

• EDC 51787-A revised Appendix A Table A-I and Appendix C 5-26-2005 Deviation 14 to change the lower range for particulates in accordance with calculation WBNAPS3-048 Revision 15.

[PL-08-0501]

Total Pages: 73 (includes pages i-xi and 1-62)

Incorporates EDC as follows:

20

• EDC 51723-A revised Appendix A to add footnote 15 for 11-29-2006 variable Number 18. Added References 9.1.30 and 9.1.31.

Total Pages: 73 (includes pages i-xi and 1-62) viii

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED Incorporates DCN as follows:

21

• DCN 51856 replaces the mineral insulated cable inside 1-29-2007 containment from the reactor vessel head to the containment penetrations. The reference junction boxes are also removed including the cold reference RTDs in the boxes.

The cold reference RTDs are replaced by RTDs which are integral with the cable at the transition from chromel and alumel to copper in the Incore Instrument Room (IIR). The replacement cable is routed in the same raceways, conduit, and reactor vessel refueling cavity wall penetration as the existing cable, no change in routing of the cable is occurring and mineral insulated cable is routed to the IIR.

Appendix C Table C, Deviation 30: Revised to delete reference junction boxes.

• Renumbered pages i-xii, due to adding a page to the Revision Log.

Total Pages: 74 (includes pages i-xii and 1-62)

I This DCD has been reviewed and determined to be fully 22 applicable to both Unit 1 and Unit 2. 8-27-2008 Outstanding WITEL Punchlist items are listed below:

PL-08-0482, see Section 9.2.10 PL-08-0483, see Appendix A, Table A-1, Note 15 PL-08-0484, see Appendix B, Table B-1 PL-08-0485, see Rev. 3 and Section 9.1.14 PL-08-0486, see Rev. 3 and Section 9.1.14 PL-08-0487, see Rev. 3 and Section 9.1.14 PL-08-0488, see Rev. 3 and Section 9.1.14 PL-08-0489, see Rev. 3 and Section 9.1.14 PL-08-0490, see Rev. DCN W-25945-A PL-08-0491, see Rev. DCN W-25945-A PL-08-0492, see Rev. DCN W-25945-A PL-08-0493, see Rev. DCN W-25945-A PL-08-0494, see Rev. DCN W-25945-A PL-08-0495, see Rev. DCN W-25945-A PL-08-0496, see Rev. DCN W-25945-A PL-08-0497, see Rev. DCN W-25945-A PL-08-0498, see Rev. DCN W-25945-A PL-08-0499, see Rev. DCN W-25945-A PL-08-0500, see Rev. DCN W-25945-A PL-08-0501, see Rev. 7; Rev. DCN S-36997-A; Rev. 8; Rev.

19; Section 9.1.15; Appendix A, Table A-1, Note 7 and Appendix C, Table C PL-08-0502, see Section 4.1, and Section 9.1.11 PL-08-0503, see Section 4.3.1.3; and Section 4.3.2.2 PL-08-0504, see Section 4.3.1.4; and Section 4.3.2.3 ix

TVA REVISION LOG TITLE: POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 REVISION DATE NO. DESCRIPTION OF REVISION APPROVED

• PL-08-0505, see Section 9.1.7 22 " PL-08-0506, see Section 9.1.8 (cont'd)

• PL-08-0507, see Section 9.1.9

• PL-08-0508, see Section 9.1.9

• PL-08-0509, see Section 9.1.9

• PL-08-0510, see Section 9.1.9

• PL-08-0511, see Section 9.1.9

• PL-08-0512, see Section 9.1.9

• PL-08-0513, see Section 9.1.9

• PL-08-0514, see Section 9.1.9

• PL-08-0515, see Section 9.1.9

• PL-08-0516, see Section 9.1.9

• PL-08-0517, see Section 9.1.12

" PL-08-0518, see Section 9.1.13

" PL-08-0519, see Section 9.1.13

• PL-08-0520, see Section 9.1.18 and Section 9.1.30

• PL-08-0521, see Section 9.1.18 and Section 9.1.30

" PL-08-0522, see Section 9.1.18 and Section 9.1.30

• PL-08-0523, see Section 9.1.18 and Section 9.1.30

• PL-08-0524, see Section 9.1.18 and Section 9.1.30

• PL-08-0525, see Section 9.1.18 and Section 9.1.30

• PL-08-0526, see Section 9.1.18 and Section 9.1.30

• PL-08-0527, see Section 9.1.18 and Section 9.1.30

• PL-08-0528, see Section 9.1.18 and Section 9.1.30

• PL-08-0529, see Section 9.1.18 and Section 9.1.30

" PL-08-0530, see Section 9.1.23

" PL-08-0531, see Section 9.1.23

• PL-08-0532, see Section 9.1.23

" PL-08-0533, see Section 9.1.23

• PL-08-0534, see Section 9.1.23

• PL-08-0535, see Section 9.1.23

• PL-08-0536, see Section 9.1.23

• PL-08-0537, see Section 9.1.23

• PL-08-0538, see Section 9.1.23

" PL-08-0539, see Section 9.1.23

• PL-08-0540, see Section 9.1.31 and Appendix A, Table A-I, Note 15

• PL-08-0541, see Section 9.2.1 Pages Revised: Coversheet, iii, iv, v, vi, viii, ix, x, 14, 16, 17, 20, 21, 22, 39, 40, 41, 60 Total Pages: 75 (includes pages i-xiii and 1-62)

X

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 TABLE OF CONTENTS Section Title Page 1 .0 SCOPE ............................................................ 1 1 .1 Purpose .................................................... 1 1.2 Scope of Coverage .......................................... 1 2.0 DEFINITIONS ...................................................... 1 2.1 Type A Variables............................................ 1 2.2 Type B Variables ........................................... 2 2.3 Type C Variables ........................................... 2 2.4 Type D Variables ........................................... 2 2.5 Type E Variables ........................................... 2 2.6 Immediately Accessible Information .......................... 2 2.7 Primary Information ........................................ 2 2.8 Key Variable ............................................... 2 2.9 Backup Variable ............................................ 2 2.10 Categories 1, 2, and 3 ..................................... 2 2.11 Diverse Variable ........................................... 3 2.12 Critical Safety Functions .................................. 3 3.0 DESIGN BASES ...................................................... 3 3.1 Functional Requirements .................................... 3 3.1.1 Variable Type Determination ....................... 4 3.1.2 Selection of Variable Category ...................... 4 3.1.2.1 Selection Criteria for Category 1 ..... 4 3.1.2.2 Selection Criteria for Category 2 ..... 5 3.1.2.3 Selection Criteria for Category 3 ..... 5 3.2 Design Basis Events ......................................... 5 3.3 Plant Environmental Conditions ............................... 5 3.4 Specific Instrumentation Requirements ........................ 5 3.4.1 Category 1 Instrumentation ........................ 5 3.4.1.1 General Qualification Requirements .... 5 3.4.1.2 Single Failure Criteria ................ 6 3.4.1.3 Unique Identification In The MCR ...... 6 3.4.1.4 Interface to Non-Class 1E Components .. 6 3.4.1.5 Display Means ........................... 7 3.4.1.6 Recording Requirements ................. 7 3.4.1.7 Instrument Accuracy Calculations ...... 7 3.4.2 Category 2 Instrumentation ........................ 8 3.4.2.1 General Qualification Requirements .... 8 3.4.2.2 Single failure Criteria ................ 8 3.4.2.3 Unique Identification In The MCR ...... 8 3.4.2.4 Interface to Non-Class 1E Components .. 8 3.4.2.5 Display Means ......................... 9 3.4.2.6 Recording Requirements ................. 9 xi

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 TABLE OF CONTENTS (continued)

Section Title Page 3.4.3 Category 3 Instrumentation ........................ 9 3.4.3.1 General Qualification Requirements .... 9 3.4.3.2 Display Means .......................... 9 3.4.3.3 Recording Requirements ................ 9 3.4.4 Common Requirements ............................... 9 3.4.4.1 Human Factors ......................... 9 3.4.4.2 Direct Measurement .................... 9 3.4.4.3 Routine Use ........................... 10 3.5 Electrical Requirements .................................... 10 3.5.1 Category 1 ........................................ 10 3.5.1.1 Redundancy ............................ 10 3.5.1.2 Signal Isolation ...................... 10 3.5.1.3 Control Power ......................... 10 3.5.1.4 Separation and Isolation .............. 11 3.5.1.5 Third Channels ........................ 11 3.5.2 Category 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.5.2.1 Redundancy ............................ 12 3.5.2.2 Control Power ......................... 13 3.5.2.3 Separation ............................ 13 3.5.2.4 Additional Requirements ............... 13 3.5.3 Category 3 . . . . . .. . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . 13 3.5.3.1 Separation and Redundancy ............. 13 3.5.3.2 Control Power ......................... 13 3.5.3.3 Additional Requirements ............... 13 3.6 Mechanical Requirements .................................... 13 3.6.1 Category 1 ........................................ 14 3.6.1.1 Category I Structures ................. 14 3.6.2 Category 2 ........................................ 14 3.6.2.1 Seismic Operability Required .......... 14 3.6.2.2 Seismic Operability Not Required ...... 14 3.6.3 Category 3 ........................................ 14 4.0 LAYOUT AND ARRANGEMENT ........................................... 14 4.1 General Description .................. 14 4.2 Location .............................. 15 4.2.1 Category 1 .................. 15 4.2.2 Category 2 and 3 ............ 15 4.2.3 Control-Display Integration. 15 4.3 Identification ...... 15 4.3.1 Category 1. 15 4.3.1.1 Derived Indication ... 15 4.3.1.2 Unique Identification In The MCR 16 4.3.1.3 Control Diagrams ..... 16 4.3.1.4 Components ........... 16 4.3.1.5 Cables ............... 17 4.3.1.6 Color Coded Nameplate 17 xii

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 TABLE OF CONTENTS (continued)

Section Title Page 4.3.2 Category 2 . . . . . . . . . . . . . . . .. . .. . .. . . . . . . . . . . . . . . . . . 17 4.3.2.1 Unique Identification In The MCR ......... 17 4.3.2.2 Control Diagrams.......................... 17 4.3.2.3 Components ............................... 17 4.3.2.4 Cables ................................... 18 4.3.2.5 Color Coded Nameplate .................... 18 4.3.3 Category 3 ........................................ 18 4.3.3.1 Components ............................... 18 5.0 TESTING AND SURVEILLANCE REQUIREMENTS ............................ 18 5.1 General Servicing, Testing, and Surveillance Requirements.. 18 5.1.1 Programs .......................................... 18 5.1.2 Channel Removal from Service ...................... 18 5.1.3 Administrative Control ............................ 19 5.1.4 Minimize Anomalous Indications .................... 19 5.1.5 Repair ............................................ 19 5.1.6 Capability for Verifying Operability ............. 19 5.2 Surveillance Requirements Category 1 and 2 Instrumentation. 19 6.0 QUALITY ASSURANCE ................................................ 19 6.1 Category 1 Variables ....................................... 19 6.2 Category 2 Variables ....................................... 19 6.3 Category 3 Variables ....................................... 20 7.0 EXCEPTIONS ....................................................... 20 8.0 ADDITIONAL REQUIREMENTS .......................................... 20

9.0 REFERENCES

........................................................ 20 9.1 Design Input ................................................ 20 9.2 Background ................................................. 22 9.3 Design Criteria and Standards .............................. 22 Appendix A - Post Accident Monitoring Instrumentation Component Qualification .................................. 23

- Post Accident Monitoring Instrumentation Requirements ..... 24

- Post Accident Monitoring Instrument Variables List ........ 26 Appendix B - Post Accident Monitoring Variables Utilizing The Plant Computer System for MCR Indication ... 41 Source Notes ........................................................... 42 Appendix C - Reg Guide 1.97 R2 Deviation and Justifications for Deviations ............................................ 43 xiii

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 1.0 SCOPE This document establishes the requirements for instrumentation used to assess plant and environs conditions during and following an accident at Watts Bar Nuclear Plant.

1.1 Purpose This document establishes the method of meeting several requirements derived from General Design Criteria 13, 19, and 64 of Appendix A to Title 10 Code of Federal Regulations Part 50 (10CFR50), and of Supplement 1 to NUREG-0737 "Requirements for Emergency Response Capability." In particular, it specifies WBN's approach to satisfying the intent of Regulatory Guide 1.97 (R2)1,2 as required by Supplement 1.

This document is not a governing document for all plant monitoring instrumentation. Some instrumentation may have more stringent requirements placed upon it to perform a function outside the scope of this criteria. Instrumentation with specifications less stringent than those placed on it by the requirements of this criteria must be upgraded as appropriate or have an approved exception entered in either Section 7.0 or Appendix A of this criteria. Per NEP 3.2, approval will require independent review of the exception request by both Electrical Engineering and Nuclear Engineering.

1.2 Scope of Coverage Instrumentation used by plant operators to assess plant and environs conditions during and following an accident includes a subset of instrumentation used for normal plant operation plus instrumentation for specific accident monitoring functions. The plant parameters included in this Design Criteria are listed in Appendix A.

The Category 1 instrumentation provides essential information required by the operator to diagnose and monitor significant accident conditions.

Category 2 and Category 3 instrumentation provide additional nonessential information to the operator to diagnose and monitor significant accident conditions as well as information required to determine the magnitude of radioactive material releases and continually assess such releases.

2.0 DEFINITIONS 2.1 Type A Variables Those variables to be monitored that provide the primary information required to permit the control room operator to identify events and take specific manually-controlled actions required by the emergency instructions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis events.

1

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 2.2 Type B Variables Those variables that provide information to monitor the process of accomplishing critical safety functions.

2.3 Type C Variables Those variables that indicate the potential for breaching or the actual breach of barriers to fission product release (including high level radioactive release through identifiable release points; i.e., plant vents).

2.4 Type D Variables Those variables that provide information to indicate the operation of individual safety systems and other plant systems. These variables are to help the operator make appropriate decisions in using the individual systems in mitigating the consequences of an accident.

2.5 Type E Variables Those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases.

2.6 Immediately Accessible Information Information that is available to an operator within human response time once the decision that the information is needed has been made.

2.7 Primary Information Primary information is information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures.

2.8 Key Variable A key variable is that single variable (or minimum number of variables) that provides primary information and most directly indicates the accomplishment of a safety function (in the case of Types B and C) or the operation of a safety system (in the case of Type D) or radioactive material release (in the case of Type E.)

2.9 Backup Variable Additional variables beyond those classified as key, that provide diagnostic or confirmatory information.

2.10 Categories 1, 2, and 3 Regulatory Guide 1.97 classifies the qualification criteria for instrumentation into three categories: Category 1 for the most stringent requirements, Category 2 for less stringent requirements, and Category 3 for the remainder of instrumentation. The discussion of specific instrumentation requirements is contained in Section 3.4.

2

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 2.11 Diverse Variable Where failure of a Category 1 channel results in information ambiguity that can lead the operator to defeat or fail to accomplish a required safety function, a second variable shall be identified to allow the operators to deduce the actual condition in the plant. The second variable, qualified identically to the first, is called a diverse variable. It is an independent channel to monitor the different variable that bears a known relationship to the multiple channels.

A diverse variable may be an additional channel of the same variable or of a different variable of a known relationship.

Diverse variables are identified in Table A-1. Additional, redundant instrumentation is discussed in Sections 3.5.1.1 and 3.5.1.5.

2.12 Critical Safety Functions Those safety functions that are essential to prevent a direct and immediate threat to the health and safety of the public. These are the accomplishing or maintaining of:

1. Reactivity Control

2. Reactor core cooling and heat removal from primary system

3. Reactor coolant system integrity

4. Radioactivity control

5. Containment 3.0 DESIGN BASES 3.1 Functional Requirements The function of post accident monitoring instrumentation is to provide data to assist control room operators in mitigating the consequences of design basis events.

Among the data to be provided are those plant parameters necessary to the operator to execute WBN Emergency Instructions. Specifically, the instrumentation provides information needed to:

a. Enable the operator to monitor plant conditions or take the correct manual action during the course of a Condition II, III, or IV event or during recovery from a Condition II, III, or IV event.

b. Maintain safe shutdown Type B and C variables will also provide monitoring capability beyond Condition II, III, or IV events as addressed by the emergency instructions.

3

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.1.1 Variable Type Determination Variable types are defined in Section 2. Calculations have been performed in which the definitions are used to identify the type to be assigned to specific plant parameters. The following calculations and R.G. 1.97 provide input to the Type and Category column of Table A-1.

Type Reference A 9.1.7 B and C 9.1.8 D 9.1.9 E 9.1.15 A variable included as a type A does not preclude it from being included as a Type B, C, D, or E or vice versa.

3.1.2 Selection of Variable Category Description of the type determination method is given in Section 3.1.1. The definitions for key and backup variables are given in Section 2. The sections below provide selection criteria for Category 1, 2, and 3 variables and are based on guidance provided in Reference 9.1.1.

3.1.2.1 Selection Criteria for Category 1 The selection criteria for Category 1 variables are subdivided according to the variable type. Type A variables are all key variables and are used for accident diagnosis and providing information necessary for manual operator action and shall be designated as Category 1.

For Type B, those key variables which are used for monitoring the process of accomplishing or maintaining critical safety functions shall normally be designated as Category 1. For Type C, those key variables which are used for monitoring the potential for breach or actual breach of a fission product barrier shall normally be designated as Category 1. For Type D, these variables are not designated Category 1 unless required by R.G. 1.97 R2. Exceptions to the Category 1 designation of Type B and C variables shall be allowed for those Type B and C variables identified in RG 1.97 R2 as having either a Category 2 or 3 classification. The variables category assignments will be identified in Table A-1. Category 1 accident monitoring instrumentation is designed with redundant or diverse channels so that a single failure does not prevent the operator from determining the need for operator action and the response of the plant to the safety measures in operation.

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.1.2.2 Selection Criteria for Category 2 The selection criteria for Category 2 variables are subdivided according to the variable type. No Type A variables shall be identified as Category 2. For Types B and C, those variables which provide backup information for safety related functions shall be designated as Category 2. For Type D, those key variables used for monitoring the performance of safety systems shall be designated as Category 2. For Type E, those key parameters to be monitored for use in determining the magnitude of the release of radioactive materials and for continuously assessing such releases shall be designated Category 2.

.3.1.2.3 Selection Criteria for Category 3 The selection criteria for Category 3 variables are subdivided according to the variable type. No Type A variables shall be identified as Category 3. For Types B, C, D and E, those variables which provide backup information shall be designated Category 3.

3.2 Design Basis Events 3.2.1 Indication of Type A variables is required for mitigation of design basis events (Condition II, III, and IV events as analyzed in Chapter 15 of the Watts Bar Nuclear Plant Final Safety Analysis Report, Reference 9.2.2) where manual action is required.

Indication of Type B and C variables provides support to control room operators in the mitigation of design basis events and events beyond the design basis. The ranges of some of the instruments monitoring Type C variables shall be selected to extend beyond the range of the parameter's expected value during design basis events.

3.3 Plant Environmental Conditions 3.3.1 The environmental conditions for normal operation and design basis event conditions are defined in Reference 9.2.1.

3.4 Specific Instrumentation Requirements 3.4.1 Category 1 Instrumentation 3.4.1.1 General Qualification Requirements Category 1 instrumentation located in a harsh environment and required to function for the 10 CFR 50.49 events shall satisfy the requirements in WB-DC-40-54 (Ref. 9.3.5).

Category 1 instrumentation located in a mild environment shall be suitable for operation within the environmental conditions for which it is located. Refer to WB-DC-40-54 for the definition of harsh and mild environments.

5

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Category 1 instrumentation shall be qualified in accordance with the Watts Bar Nuclear Plant Design Criteria (Reference 9.3.3 (WB-DC-40-31.2) "Seismic Qualification of Category I Fluid System Components and Electrical or Mechanical Equipment.").

Qualification applies to the complete instrumentation channel from the sensor to the display where the display is a direct reading meter or recording device.

Refer to "Component Qualification Matrix," Appendix A 3.4.1.2 Single Failure Criteria No single failure within the Category 1 instrumentation, its auxiliary support equipment, or its power sources, shall result in the loss of the information provided by the instrumentation.

Refer to WB-DC-40-64 (Ref. 9.3.6).

Any single failure within the Category 1 instrumentation shall not result in the loss of the monitoring function. To provide for a single failure proof design, additional redundant channels may be provided, one or several diverse channels (see Section 2.11) may be provided, or it shall be demonstrated by analysis that the operator will take conservative action to resolve ambiguity (see Reference 9.1.11). 'Single failure' includes such events as the shorting or open circuiting of interconnecting signal or power cables. It also includes single credible malfunctions or events that cause a number of consequential component, module, or channel failures. For example, the overheating of an amplifier module is a 'single failure' even though several transistor failures result.

Mechanical damage to a mode switch would be a 'single failure' although several channels might become involved.

3.4.1.3 Unique Identification in the MCR Category 1 variable main control room (MCR) display devices shall be specifically identified on the control panels so that the operator can easily discern that they are displaying information from a Category 1 channel. The symbol Cl shall be engraved on the nameplate per design standard DS-E18.1.24.

(Reference 9.3.11) 3.4.1.4 Interface to Non-Class 1E Components Transmission of Class 1E Category 1 signals to or from components that are non-lE shall only be through an isolation device which is classified as part of a Class 1E instrumentation system. This isolation device shall be accessible to operations and maintenance personnel during the worst-case post-accident environment of the area where the isolation device is located. The function performed by these isolators is to prevent electrical faults in nonqualified circuits, which derive their signals from qualified portions of Class 1E circuits, from propagating to the Class 1E circuit.

In addition, transmission of Category 1 signals to Non-Class 1E components from components which perform automatic safety control functions (i.e., Reactor Protection System) shall only be through isolation devices which are qualified as Class 1E instruments.

6

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.4.1.5 Display Means Category 1 instrumentation signals shall be displayed on an individual continuous display and immediately accessible in the main control room. Category 1 parameters which are displayed on displays that are continuously available (reactor vessel level and core exit temperature) are considered continuously displayed and therefore meets the requirements of this section.

3.4.1.6 Recording Requirements Parameters which have safety related trends are identified in Reference 9.1.12, "Determination of R.G. 1.97 Variables Requiring Trend Indication." Reference 9.1.13 "Determination of Devices Required for Indicating Safety Related Trends for WBNP PAM" determines the hardware required to display the trends. At least one of the channels used to monitor each Category 1 analog parameter shall be recorded in an immediately accessible manner to provide a historical record. Non-iE recorders or a computer-based data acquisition and display system may be used where primary indication is provided by a qualified meter or other qualified display. Non-Class 1E recorders provided for the latter function shall be isolated from the instrument circuit as described in SectionS2 3.4.1.4 above and qualified to Category 2 isolation requirements in accordance with Section 3.4.2.

3.4.1.7 Instrument Accuracy Calculations Where two or more instruments are needed to cover a particular range, overlapping of instrument spans and accuracies will be provided to ensure one of the two instruments will be on scale at all times.

All Category 1 or 2 instruments located in a I0CFR50.49 harsh environment shall have a demonstrated instrument accuracy calculation performed.

Category 2 instruments which receive their input signal from a Category 1 loop do not require an accuracy calculation.

Range and accuracy requirements are determined through the analysis of Condition II, III, or IV events as described in FSAR Chapter 15. The display system meets the following requirements:

a. The range of the readouts extends over the maximum expected range of the variables being measured.

b. The combined indicated accuracies are within the errors used in the safety analysis.

7

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.4.2 Category 2 Instrumentation 3.4.2.1 General Qualification Requirements Category 2 instrumentation located in harsh environments and required to function for I0CFR50.49 events shall be qualified in accordance with WB-DC-40-54 (Reference 9.3.5) 2. Seismic qualification is required per seismic Category I requirements, (see Section 3.6.2), if the instrument is part of a safety-related system. Where the channel signal is to be processed or displayed on demand, qualification applies to the complete instrumentation channel from the sensor through the isolator/input buffer. The location of the isolation device or input buffer should be such that it shall be accessible for maintenance during accident conditions. Category 2 instrumentation which does not experience harsh environmental conditions may be designed and installed according to Category 3 requirements (See Section 3.4.3).

A variable designated as Category 2 shall be designed and installed to the higher of the qualification requirements determined in this design criteria or in the respective system description.

Refer to "Qualification Matrix," Appendix A 3.4.2.2 Single Failure Criteria The single failure criteria do not apply to Category 2 instruments.

3.4.2.3 Unique Identification in the MCR Category 2 MCR instruments shall be specifically identified on the control panels so that the operator can easily discern that they are displaying information from a Category 2 channel. The designation C2 shall be engraved on the nameplate per design standard DS-E18.1.24 (Reference 9.3.11). Section 4.3.2.1 contains identification requirements for computer or annunciator based Category 2 displays.

3.4.2.4 Interface to Non-Class 1E Components Category 2 instrumentation that is Class 1E for its normal system function shall be isolated from non-Class 1E circuits in accordance with Section 3.4.1.4.

Category 2 instrumentation that is non-lE shall have isolation from other non-lE circuits by means of typical industry methods (optional isolation, transformer or resistor networks, etc.).

This isolation is to ensure that other non-IE circuits will not affect Category 2 instrumentation loops. An example of adequate isolation is provided by the annunciator system that uses optical isolation of all inputs coming into the system. This prevents any input failure or fault from affecting the annunciator system and other loops. Another example is the plant computer system which uses transformer and optical isolation.

8

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.4.2.5 Display Means The instrumentation signal may be displayed on an individual instrument or it may be processed for display on demand by a computer based data acquisition and display system or by other appropriate means.

The display device need not be Class 1E. If a non-class 1E display device is used on a Class 1E channel, the interface requirements of Section 3.4.2.4 above shall be met.

3.4.2.6 Recording Requirements Category 2 effluent radioactivity monitors and area radiation monitors shall be recorded. No other safety-related recording is required for Category 2.

3.4.3 Category 3 Instrumentation 3.4.3.1 General Qualification Requirements The instrumentation shall be of high-quality commercial grade. A high quality device demonstrates superiority and excellence in attributes that are determined to be critical characteristics such as reliability, durability, long life, safety, physical construction, and design. Refer to "Qualification Matrix,"

Appendix A 3.4.3.2 Display Means The instrumentation signal may be displayed on an individual instrument or it may be processed for display on demand by a computer based data acquisition and display system or by other appropriate means.

3.4.3.3 Recording Requirements Category 3 meteorology data shall be recorded either on a recorder or on the computer. No other recording is required for Category 3.

3.4.4 Common Requirements 3.4.4.1 Human Factors Human factors principles shall be used in determining type and location of displays. (See Reference 9.3.7, WB-DC-30-23 "Human Factors")

3.4.4.2 Direct Measurement To the extent practical, monitoring instrumentation inputs shall be from sensors that directly measure the desired variables. An indirect measurement shall be made only when it can be shown by analysis to provide unambiguous information.

9

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.4.4.3 Routine Use To the extent practical, the same instruments shall be used for accident monitoring as are used for the normal operations of the plant to enable the operators to use, during accident situations, instruments with which they are most familiar. However, where the required range of monitoring instrumentation results in a loss of instrumentation sensitivity in the normal operating range, separate instruments shall be used.

Means shall be provided for checking, with a high degree of confidence, the operational availability of each system input sensor during reactor operation.

This may be accomplished in various ways, for example:

(1) By perturbing the monitored variable; or (2) By introducing and varying, as appropriate, a substitute input to the sensor of the same nature as the measured variable; or (3) By cross checking between channels that bear a known relationship to each other and that have readouts available.

3.5 Electrical Requirements 3.5.1 Category 1 3.5.1.1 Redundancy Normally, Category 1 circuits shall be required to have two redundant channels, post-accident monitoring channel 1 (PAM 1) and post-accident monitoring channel 2 (PAM 2). The single failure analysis (Reference 9.1.11) may require a third redundant post-accident monitoring channel 3 (PAM 3) to be used.

3.5.1.2 Signal Isolation Transmission of Class 1E category 1 signals to components that are non-lE shall only be through isolation devices which are classified as part of the Class 1E instrumentation and meet all the requirements of the system. No credible failure at the output of an isolation device shall prevent the associated monitoring system channel from meeting the minimum performance requirements considered in the design bases. Examples of credible failure include short circuits, open circuits, grounds, and the application of the maximum credible AC or DC potential (140 V DC or 118 V AC).

3.5.1.3 Control Power Control power for Category 1 variables shall be supplied from the station standby power sources, meaning Class 1E battery backed power. Circuits requiring 125 VDC power shall be supplied by the 125 VDC vital battery boards. Circuits requiring 120 VAC power shall be supplied by the 120 VAC vital instrument power boards.

Control power for PAM 1 circuits shall be supplied from either an A-train source, 125 VDC battery boards I or III, or 120 VAC vital instrument power boards I or III.

10

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Control power for PAM 2 circuits shall be supplied from either a B-train source, 125 VDC battery boards II or IV, or the 120 VAC vital instrument power boards II or IV.

Control power for PAM 3 circuits shall be supplied from any of the 125 VDC battery boards I, II, III, or IV, or the 120 VAC vital instrument power boards I, II, III, or IV but shall not be from the same power supply as the PAM 1 or PAM 2 channels for that same variable.

See Table 1 "Category 1 Power Requirements."

3.5.1.4 Separation and Isolation Redundant channels shall be electrically independent and physically separated from each other and shall meet the requirements set forth in WB-DC-30-4, "Separation/Isolation" (Reference 9.3.1). The same requirements apply to separation of PAM 3 cables from PAM 1 and PAM 2 cables.

3.5.1.5 Third Channels Specific variables which require three channels (identified in the single failure analysis Reference 9.1.11 and designated in Table A-1) of information to be displayed in the MCR shall have the third channel cables routed and separated as described in Section 3.5.1.4. The control power supply for these channels shall be derived as described in Section 3.5.1.3 above.

11

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.5.2 Category 2 3.5.2.1 Redundancy Redundant circuitry is not required.

IChannell 125V DC Control Power 1 120 V AC Control Power I I III I PAM 1 1 TRAIN I BATTERY1 - BATTERYI I 120V I I 120V I I A I IBD-I I IBD-III I AC I I AC I I IVITALI VITAL I FINSTRI IINSTR I POWERI POWER I I I I I I I JBD-I I F BD-III I I I PAM 2 1 1 TRAIN I IBATTERY1 IBATTERY1 1120V I 1120V ACI I I F B I IBD-Ill I BD-IVI AC I VITAL I F IVITALI FINSTR I I FINSTRI POWER I I I I IPOWERI FBD-IV I I F F F F F BD-II I I PAM 3 1 1 IBATTERYFBATTERYIBATTERYFBATTERYF120V 1120V 1120V AC 1120V ACI I F I I BD-I* I BD-II*IBD-III*F BD-IV*F AC I AC VITAL VITAL I I FVITAL VITAL IINSTR FINSTR I I FINSTR IINSTR POWER POWER I F

I FPOWER I I POWER FBD-III* FBD-IV* I I F BD-I* FBD-II* I

• Must not be the same power supply as PAM 1 or PAM 2 for that same variable.

TABLE 1 CATEGORY 1 INSTRUMENT POWER REQUIREMENTS 12

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.5.2.2 Control Power If Class 1E power is required due to system functional requirements as specified in the respective system description, then the channel shall be installed in the Class 1E division selected by the designer and shall satisfy the requirements appropriate to that division.

(See Reference 9.3.2) Where non-Class 1E power is used, then control power shall be derived from highly reliable (diesel or battery backed) non-divisional power sources.

3.5.2.3 Separation Separation is not required by Regulatory Guide 1.97 for Category 2 instrumentation. However, separation may be required because of other regulatory, functional, power, or system requirements. In those cases, the most stringent requirements shall be met and separation shall be implemented according to WB-DC-30-4, "Separation/Isolation" (See Reference 9.3.1).

3.5.2.4 Additional Requirements Some circuits have more stringent requirements placed upon them due to other design or regulatory requirements. The most stringent requirements shall apply (i.e., PAM may allow non-lE power and no QA but the normal system function requires 1E power and full QA.).

3.5.3 Category 3 3.5.3.1 Separation and Redundancy Separation and redundant circuitry are not required for PAM. The cable routing shall be in accordance with the requirements for non-divisional circuits from Reference 9.3.1. However, separation may be required because of other regulatory, functional, power, or system requirements.

3.5.3.2 Control Power The control power supply for these circuits may be derived from non-divisional power sources.

3.5.3.3 Additional Requirements Some circuits may have more stringent requirements placed upon them due to other design or regulatory requirements. The most stringent requirements shall apply.

3.6 Mechanical Requirements References 9.3.3 and 9.3.8 describe the requirements outlined in the following sections.

13

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 3.6.1 Category 1 3.6.1.1 Category I Structures Components located in seismic Category I structures shall continue to perform the required function following a design basis seismic event.

3.6.2 Category 2 No specific requirements exist for seismic operability due to the guidance of Reference 9.1.1. However, specific system requirements may exist for seismic operability; if so, the instrumentation shall be qualified as described below or as specified in the instrument's respective system description.

3.6.2.1 Seismic Operability Required Components required to be operable after a seismic event due to normal system requirements shall be qualified to Seismic Category I requirements (Reference 9.3.3).

3.6.2.2 Seismic Operability Not Required Components not required to be operable after a seismic event shall be designed and mounted such that they do not have an adverse effect on safety systems during or following a design basis seismic event.

This shall be accomplished through qualification to Seismic Category I (L) requirements for components located in Category I structures (Reference 9.3.8).

3.6.3 Category 3 3.6.3.1 Components shall be designed and mounted such that they do not have an adverse effect on safety systems during or following a design basis seismic event. This shall be accomplished through qualification to Seismic Category I (L) requirements for components located in a Category I structure (Reference 9.3.8).

4.0 LAYOUT AND ARRANGEMENT 4.1 General Description Category 1 parameters shall be monitored by at least two redundant channels PAM 1 and PAM 2. The single failure analysis calculation (WBN-OSG4-051 Reference 9.1.11) defines the variables that require a third redundant channel. [PL-08-0502] The third redundant channel will be designated as PAM 3. Instrumentation for Category 2 and 3 variables shall consist of at least one channel, but the instrumentation may have redundant channels if they have been provided to satisfy other regulatory or design requirements.

14

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 4.2 Location 4.2.1 Category 1 All Category 1 variables shall be displayed on individual instruments located in the MCR.

4.2.2 Category 2 and 3 Category 2 and 3 variables may be displayed on individual instruments or the variables may be displayed on one of the computer-based displays.

Some Category 2 and 3 variables will not be required to be in the MCR. The types of instrumentation not required to be displayed in the MCR can be categorized as portable or post-accident sampling instrumentation. Additional instrumentation not requiring a display in the MCR is identified in Table A-1 with the entry "local indication" and meet the following guidelines:

1. The information displayed is of a non-critical or diagnostic nature.

2. The local panel display is accessible under accident conditions.

3. The information can be retrieved in a timeframe necessary to support the operator's action.

4. The parameter changes slowly such that only infrequent updates are needed.

4.2.3 Control - Display Integration Individual display instruments shall be located with related-system controls and displays. Human factors principles shall be used in the configuration of the control board layout (See Reference 9.3.7) 4.3 Identification 4.3.1 Category 1 4.3.1.1 Derived Indication In general, PAM Category 1 components and cables shall.be identified by the unique identifier and separation suffix as assigned for their normal safety function from the sensor to the indicator and shall conform to the requirements of WB-DC-30-4 "Separation/Isolation" (Reference 9.3.1).

Where a PAM indication is derived from the reactor protection system, the signal to the indicator shall be isolated from the protection instrumentation at the protection rack. The isolated cables and indicators shall be designated "J" for PAM 1 or "K" for PAM 2 .and shall follow the separation criteria in WB-DC-30-4. The isolated cables and indicators of the third PAM channel PAM 3, where required, shall be separated and identified with a suffix as specified in WB-DC-30-4. Indicators shall bear the same suffix as their cables.

15

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Where an instrument loop is designed and installed specifically for a PAM Category 1 variable and has no other safety function the components and cables shall use the separation suffix "J" for PAM 1 and "K" for PAM 2 from the sensor to the indicator and shall be purchased, designed, qualified, and installed as 1E equipment.

4.3.1.2 Unique Identification in the MCR Category 1 display devices shall be uniquely identified in the main control room. The symbol C1 shall be engraved on the nameplate.

(Reference Table 2) 4.3.1.3 Control Diagrams Category 1 PAM instrumentation loops shall be identified on the control diagrams (47W610-series) [PL-08-0503]. The symbol P1, P2, or P3 shall be placed on the drawing adjacent to the loop indicator symbol and the symbol shall be enclosed in a small box to accent its appearance. P1, P2, and P3 shall correspond with PAM 1, PAM 2, and PAM 3 respectively. (Reference Table 2) 4.3.1.4 Components Each Category 1 variable loop component shall be identified on the instrument tabulation drawings (47B601-series) [PL-08-0504]. The words PAM 1, PAM 2, or PAM 3 shall be placed in the remarks field for each component that is required to meet Category 1 qualification requirements. (Reference Table 2) Those components shall only include the ones required to provide indication for the post accident monitoring function including transmitters, modifiers, power supplies, isolators, and indicators. Those components not required for indication such as isolated outputs to other systems, isolated local indicators, isolated controllers, and other devices not in the indicating circuit shall not be identified as PAM. The isolator separating non-PAM devices from the PAM portion of the loop shall be identified as PAM.

Each Category 1 and 2 variable in the 50.49 program shall be identified as PAM on the "I0CFR 50.49 List" similar to the instrument tabulation except that only the word "PAM" is used. It is not required to identify cables as PAM on the "10CFR 50.49 List".

(Reference Table 2)

CATEGORY PAM DEVICE I TAB I CONTROL MCR I Q 1 50.49 1 DIAGRAM I TAG LIST I EQUIP*

11 CHANNEL 1 1 PAM 1 1 [P1] Cl ** PAM 1 1 CHANNEL 2 PAM 2 [P2] Cl ** PAM 1 CHANNEL 3 PAM 3 [P3] Cl ** PAM 2 ANY PAM C2 -- C2 *** PAM 3 ANY PAM C3 ........

• Not required for the cable "I0CFR 50.49 List".

• • Device shall be listed on the Q-list as 'IQ,,.

• • • Device shall be listed on the Q list as "Q" if it is required to be in the 10CFR 50.49 pro gram.

IDENTIFICATION SYMBOLS FOR PAM DEVICES TABLE 2 16

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 4.3.1.5 Cables PAM 1, PAM 2, and PAM 3 cables shall be identified and separated according to Section 4.4.5 of Reference 9.3.1 "Separation/Isolation."

4.3.1.6 Color Coded Nameplate Nameplates and tags on Category 1 components shall be consistent with the requirements of DS-El.2.2 "Electrical Equipment Nameplates, Sequoyah and subsequent Nuclear Plants," with the exception of the main control room tags which shall be consistent with DS-E18.1.20 "Instrumentation and Control, Labeling of Components." (Reference 9.3.10 and 9.3.11)

Cable tags and labeling shall be consistent with standard drawing SD-E15.3.4. (Reference 9.3.9) 4.3.2 Category 2 4.3.2.1 Unique Identification in the MCR Category 2 display devices shall be uniquely identified in the main control room with the symbol C2 engraved on the nameplate or annunciator window. Where Category 2 variables are displayed on a computer screen, they shall be uniquely identified on the screen as Category 2 parameters. A special screen may be used to display all post accident monitoring variables in one display and in such cases it is not required to additionally identify variables as PAM where they are used on other screens for normal system requirements.

(Reference Table 2) 4.3.2.2 Control Diagrams There is no requirement to identify Category 2 devices on the 47W610-series drawings. [PL-08-0503]

4.3.2.3 Components Each Category 2 variable component shall be identified on the instrument tabulation drawings (47B601-series) [PL-08-0504]. The words PAM C2 shall be placed in the remarks field for each component that is required to meet Category 2 qualification requirements (Reference table 2). Those components shall only include the ones required to provide indication for the post accident monitoring function including transmitters, modifiers, power supplies, isolators, and indicators. Those components not required for indication such as isolated local indicators or local controllers shall not be identified. Any isolators separating non-PAM devices from the PAM portion shall be identified as PAM. (Reference Table 2)

Each Category 2 variable that has been included in the I0CFR50.49 program shall be identified as PAM on the "10CFR 50.49 List" similar to the instrument tabulation except that only the word "PAM" is used.

It is not required to identify cables as "PAM" on the cable "I0CFR 50.49 List" (Reference Table 2) 17

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 4.3.2.4 Cables Cables for Category 2 PAM circuits shall follow the requirements imposed by their normal system functions. Additionally, Category 2 non-Class 1E cables that are not in the 10CFR 50.49 program shall be identified as PAM in the computerized cable routing system (CCRS) data base in accordance with Reference 9.2.10.

4.3.2.5 Color Coded Nameplate Nameplates and tags on Category 2 components shall be consistent with the requirements of DS-El.2.2 "Electrical Equipment Nameplates, Sequoyah and subsequent Nuclear Plants," with the exception of the main control room tags which shall be consistent with DS-E18.1.24 "Human Factors Engineering" (Reference 9.3.10 and 9.3.11).

4.3.3 Category 3 4.3.3.1 Components Each Category 3 variable component shall be identified in the Master Equipment List (MEL) on the instrument tab of the component specification template. The words "PAM C3" shall be placed in the remarks field for each component that is required to meet Category 3 qualification requirements (Reference Table 2). Those components shall only include the ones required to provide indication for the post accident monitoring function including transmitters, modifiers, power supplies, isolators, and indicators. Those components not required for indication such as isolated local indicators or local controllers shall not be identified. Any isolators separating non-PAM devices from the PAM portion shall be identified as PAM. Components required to meet Category 1 or Category 2 requirements should not be identified as Category 3 (PAM C3) in MEL.

5.0 TESTING AND SURVEILLANCE REQUIREMENTS 5.1 General Servicing, Testing, and Surveillance Requirements 5.1.1 Programs Servicing, testing, and calibration programs shall be specified to maintain the capability of the monitoring instrumentation. For those instruments where the required interval between testing will be less than the normal time interval between generating station shutdowns, a capability for testing during power operation shall be provided.

5.1.2 Channel Removal From Service Whenever a means for removing channels from service is included in the design, the design shall facilitate administrative control of the access to such removal means. The system shall be designed to permit any one channel to be maintained when required during power operation. During such operation, the active parts of the system need not themselves continue to meet the single failure criterion. As such, monitoring systems comprised of two redundant channels are permitted to violate the single failure criterion during channel bypass provided that acceptable reliability of operation can be otherwise demonstrated. The bypass time interval allowed for a maintenance operation is specified in the plant technical specifications. Bypass indication is applied either administratively or automatically.

18

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 5.1.3 Administrative Control The design shall facilitate administrative control of the access to all setpoint adjustments, module calibration adjustments, and test points.

Access to all setpoint adjustments, module calibration adjustments, and test points shall be administratively controlled.

5.1.4 Minimize Anomalous Indications The monitoring instrumentation design should minimize the development of conditions that would cause meters, annunciators, recorders, alarms, etc.,

to give anomalous indications potentially confusing to the operator.

5.1.5 Repair The instrumentation shall be designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

5.1.6 Capability for Verifying Operability Means shall be provided for verifying the operability of the monitoring system channels. Where channels exhibit a dynamic response during normal plant operation or are required frequently for normal plant operation, verification of operability is inherent in the normal functioning of the channels. For channels which monitor a normally static parameter, provisions shall be included to allow periodic testing thereby verifying channel operability. Identification of malfunctions are adequately identified by cross checking between duplicate redundant channels or cross checking between channels that bear a known relationship to each other during normal plant operation.

5.2 Surveillance Requirements Category 1 and 2 Instrumentation Category 1 channels shall have an out of service interval specified in the plant technical specifications. Category 2 and Category 3 channels do not have such a requirement unless required by the normal system requirements.

6.0 QUALITY ASSURANCE 6.1 Category 1 Variables A description of the Quality Assurance Program for Category 1 instrumentation is given in TVA Nuclear Quality Assurance Plan TVA-NQA-PLN89-A (Reference 9.2.5). Each Category 1 device identified as a PAM 1, PAM 2, or PAM 3 component shall be listed in the Watts Bar Q-list and be designated as "Q". (Reference Table 2) 6.2 Category 2 Variables For Category 2 instrumentation, the need for quality assurance requirements will be limited to components located in a harsh environment.

In general, quality assurance program requirements are not required to be imposed on nonsafety-related Category 2 instrumentation unless the instrumentation is part of the 10 CFR 50.49 Environmental Qualification Program (see Section 3.4.2 and Reference 9.3.5). Devices identified as PAM C2 shall be included in the Watts Bar Q-list if they have been included in the 10 CFR 50.49 program and shall be designated as "Q."

Other Category 2 devices shall follow normal system requirements.

(Reference Table 2) 19

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 6.3 Category 3 Variables The instrumentation should be of high-quality commercial grade and should be selected to withstand the specified environment. See Section 3.4.3.1 for a definition of "high quality." (Reference Table 2) 7.0 EXCEPTIONS None 8.0 ADDITIONAL REQUIREMENTS None

9.0 REFERENCES

9.1 Design Input 9.1.1 NRC Regulatory Guide 1.97 R2 and R3, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident."

9.1.2 Deleted 9.1.3 American Nuclear Society Report ANS-4.5-1980, "Functional Requirements for Post Accident Monitoring Capability for the Control Room Operator of a Nuclear Power Generating Station."

Paragraph 6.3.6.

9.1.4 NRC Regulatory Guide, 1.89 Rl, "Qualification of Class 1E Equipment for Nuclear Power Plants."

9.1.5 Deleted 9.1.6 USNRC, Supplement 1 to NUREG-0737, "Requirements for Emergency Response Capability" Generic Letter 82-33, December 1982.

9.1.7 WBN, "PAM Type A Variables Determination," (WBN-OSG4-047). [PL-08-0505]

9.1.8 WBN, "Basis for R.G. 1.97 R2 Type B and C Variables Determination,"

(WBN-OSG4-082). [PL-08-0506]

9.1.9 WBN, "R.G. 1.97 Type D Variable Selection." (WBN-OSG4-112)

[PL-08-0507 thru -0516]

9.1.10 Deleted.

9.1.11 WBN, "Single Failure Analysis for R.G. 1.97 Category 1 Variables,"

(WBN-OSG4-051). [PL-08-0502]

9.1.12 WBN, "Determination of R.G. 1.97 Variables Requiring Trend Recording," (WBN-OSG4-076). [PL-08-0517]

9.1.13 WBN, "Determination of Devices Required for Indicating Safety Related Trends." (WBEVAR8902002) [PL-08-0518 and -0519]

20

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 9.1.14 WBN, "R.G. 1.97 Cat 1 and Type A, B, C, D Required Range and Acc Determ" (WBN-OSG4-111) [PL-08-0485 thru -0489]

9.1.15 WBN, "Range and Accuracy Requirements and Demonstrated Range of Instrumentation Provided to Measure Regulatory Guide 1.97 Type E Variables" (WBN-APS3-048) [PL-08-0501]

9.1.16 Deleted 9.1.17 Deleted 9.1.18 WBN, "R.G. 1.97 Determination of Containment Isolation Valves Required Position Indication (WBN-OSG4-114) [PL-08-0520 thru -0529]

9.1.19 10 CFR50.49 "Environmental Qualification of Electric Equipment Important To Safety For Nuclear Power Plants" 9.1.20 10 CFR 50 Appendix A, "General Design Criteria for Nuclear Power Plants", Criteria 13, 19, and 64.

9.1.21 TVA letter to NRC dated August 31, 1990, Watts Bar Nuclear Plant (WBN)

Conformance to Regulatory Guide (RG) 1.97 Revision 2 (L44 900831 804).

9.1.22 TVA letter to NRC dated October 29, 1991, Watts Bar Nuclear Plant (WBN) - Emergency Response Capability, Regulatory Guide 1.97, Revision 2 - Request for addition information response (T04 911029 848).

9.1.23 WBN "PAM Instrumentation Evaluation and Verification Methodology, Standards, and Guidelines" (WBPEVAR8809048). [PL-08-0530 thru -0539]

9.1.24 WBN Unit 1 and 2 - Supplemental Safety Evaluation Report (SSER)-9 (RIMS Number T03 920722 912) 9.1.25 TVA letter to NRC dated May 9, 1994, "Watts Bar Nuclear Plant (WBN)

Units 1 and 2 - Regulatory Guide (RG) 1.97, Revision 2, Post-Accident Monitoring System (PAM) - Supplemental Response (RIMS T04940509901) 9.1.26 TVA letter to NRC dated April 21, 1995, "Watts Bar Nuclear Plant (WBN) Units 1 and 2 - Regulatory Guide (RG) 1.97, Revision 2, Post-Accident Monitoring System (PAM) - Supplemental Response (RIMS T04950421117) 9.1.27 WBN Units 1 & 2 - Supplemental Safety Evaluation Report NUREG-0847 Supplement No. 14 and 15.

9.1.28 Licensing Request, dated October 6, 1995, for Deviation 14. (RIMS No. T24 951006 479) 9.1.29 TVA Letter to NRC dated October 12, 1995, "Watts Bar Nuclear Plant (WBN)

Unit 1 & 2" - Regulatory Guide (RG) 1.97, Revision 2, Post-Accident Monitoring System (PAM) - Supplemental Response (T04 951012 228) 9.1.30 Regulatory Guide 1.97 - Determination of Containment Isolation valves Requiring Position Indication (WBNOSG4-114) [PL-08-0520 thru -0529]

9.1.31 Flooding Levels in the North and South Valve Vaults (WBNAPS2001)

[PL-08-0540]

21

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 9.2 Background 9.2.1 Watts Bar Nuclear Plant Environmental Drawings 47E235-Series.

[PL-08-0541]

9.2.2 Watts Bar Nuclear Plant Final Safety Analysis Report.

9.2.3 R.G. 1.97, Revision 2, "Type A Variables Determination" (NEB 820402 268).

9.2.4 Memorandum from J. A. Raulston to F. W. Chandler (NEB 820322 260).

9.2.5 TVA-NQA-PLN89-A, TVA Nuclear Quality Assurance Plan 9.2.6 "Single Failure Analysis for PAM Variables" (NEB 820319 251).

9.2.7 Letter from J. A. Domer to E. Adensam dated September 19, 1985 (L44 850919 806).

9.2.8 Memorandum from L. M. Mills to E. Adensam dated January 30, 1984 (27 840130 016).

9.2.9 L. M. Mills letter to E. Adensam of USNRC dated June 7, 1983.

9.2.10 EAI-3.15, "Cable and Conduit Record Development and Issue Procedure".

[PL-08-0482]

9.3 Design Criteria and Standards 9.3.1 WB-DC-30-4, "Separation/Isolation."

9.3.2 WB-DC-30-27, "AC and DC Control Power System."

9.3.3 WB-DC-40-31.2, "Seismic Qualification of Category I Fluid System Components and Electrical or Mechanical Equipment".

9.3.4 Deleted 9.3.5 WB-DC-40-54 "Environmental Qualification to IOCFR50.49".

9.3.6 WB-DC-40-64 "Design Basis Events Design Criteria" (Appendix B), "Single Failure" 9.3.7 WBN-DC-30-23 "Human Factors" 9.3.8 WB-DC-40-31.13 "Seismic Qualification of Category I(L) Fluid System Components and Electrical or Mechanical Equipment" 9.3.9 SD-E15.3.4 "Electrical Standard Drawing, Raceways, and CA&W Identification Tags (Sequoyah Nuclear Plant and all subsequent nuclear projects) 9.3.10 DS-El.2.2 "Electrical Equipment Nameplates, (Sequoyah and subsequent nuclear plants)."

9.3.11 DS-E18.1.24 "Human Factors Engineering" 22

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX A POST ACCIDENT MONITORING INSTRUMENTATION COMPONENT QUALIFICATION MATRIX (See Note)

Criteria Category 1 Category 2 Category 3 Redundancy At least 2 channels required Not Required Not Required EQ (10 CFR 50.49) Qualify Per WB-DC-40-54, Qualify per WB-DC-40-54, Not Required components placed in components placed in 10CFR50.49 Program I0CFR50.49 Program Seismic Must function after seismic Not Required Not Required event per WB-DC-40.31.2 QA Yes - See Section 6.1 Yes - See Section 6.2 Not required Power Supply Class-lE Non-Class 1E, diesel or Non-Class 1E Per WB-DC-30-27 battery-backed Physical Separation Required per WB-DC-30-4 Not required Not Required Electrical Non-lE circuit interfaces Not required Not Required Separation shall be through qualified isolation devices. (See WB-DC-30-4)

Indication Hardwired indicator (RVLIS Meter, indicator light, Meter, indicator and CET use plasma display computer display, or light, computer and recorder), light annunciator window display, or annunciator window Special Labeling on Cl engraved on MCR C2 engraved on MCR Not Required MCR Board label or window. label or window.

Testing and Required Required Required Maintenance Isolation Device Required Required for loops Not required Accessibility with isolation devices Recording At least 1 channel per analog Effluent and area Recorder or variable shall be recorded. radiation monitors shall computer for be recorded. meteorology.

Not required for others Where primary indication is Not required provided by qualified meter or for others.

display, non-divisional trend recorders or computer based data acquisition & display system may be used for at least 1 of the redundant loops of the variables indicated in Table A-1. Recording shall be qualified to Category 2 requirements.

Note: These are only post accident monitoring requirements. Normal system requirements may impose more stringent qualification requirements on components selected for PAM use and in those cases the most stringent requirements shall be met.

A-1 23

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX A POST ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS Table A-1 provides a listing of specific design requirements which are identified in Reference 9.1.6. The table represents minimum requirements.

Additional instrumentation or qualification may be provided as a result of other plant, system, or design requirements. The topics described are:

o Variable Name o Type and Category o Redundant Channels o Range, Range Units o Environmental qualification (EQ) o Seismic Qualification (SQ) o Quality Assurance (QA) o Power Supply Type and Category The variable's type(s) and associated category are identified. Entries in this column are derived from the Type selection calculations (References 9.1.7 through 9.1.10) and R.G. 1.97 (Reference 9.1.1).

Redundancy - The number of instrument channels required to monitor the variable. For Category 1 variables, the number of channels is determined from Section 3.4.1.2 and Reference 9.1.11. Diverse indication used to supplement or replace redundant information is also identified in Reference 9.1.11 and in Note 1.

Range - The required range and engineering units of the instrumentation are developed in the Type selection calculations, the required range and accuracy calculation, (Reference 9.1.14) or are identified in Reference 9.1.1.

Qualification (EQ) and Seismic (SQ)

Environmental and Seismic Qualification requirements are derived from the assignment of variable category. The qualification requirements for each category are listed in Section 3. The environmental operating times for Category 1 and Category 2 are specified in the Category and Operating Times Calculations.

Quality Assurance (QA) - A "Yes" entry indicates that the instrumentation must be included in the WBN QA program. A "No" entry indicates that the instrumentation is not required to be included in the QA program. The determination of "Yes" or "No" is made from the variable's assigned category.

A-2 24

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Category 2 equipment requiring environmental qualification to IOCFR50.49 shall be included in the QA program, while other Category 2 equipment need not be placed in the QA program to satisfy requirements of this Design Criteria.

Power Supply - The minimum required source of electrical power for post accident monitoring is identified as follows:

1E - Class 1E power Non-lE - Non-Class IE*

Batteries installed in portable instrumentation The requirement for electrical power source is derived from the variable's category and the design criteria of Section 3.

• Instrumentation shall be powered from lE sources if system function requires it.

Deviations The deviations are given in Appendix C. These deviations are found in References 9.1.21, 9.1.22, 9.1.25, 9.1.26 and 9.1.28. The deviation number is given in the "Notes" column of Table A-1.

A-3 25

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 1 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power, NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 1 Auxiliary Feedwater Flow Al D2 P1 P2 0 700 GPM YES YES YES 1E (See Note 1) 2 Channels Per Loop 2 Containment Lower Al D2 P1 P2 0 350 Deg F YES YES YES 1E Deviation #8 Compartment 2 Channels Atmosphere Temperature 3 Containment Pressure Al Bl Cl D2 4 Channels -2 15 PSIG YES YES YES 1E Deviation #24 (Narrow Range) (See Note 14) Note 8 4 Containment Radiation Al C3 El P1 P2 1 1.0E7 R/hr YES YES YES 1E Deviation #36 2 Upper 2 Lower 5 Containment Sump Level Al Bi Cl D2 P1 P2 0 200 Inches YES YES YES 1E Deviation #32 (Wide Range) 6 Core Exit Temperature Al Bl C1 D2 P1 P2 200 2300 Deg F YES YES YES 1E Minimum of 8 PAM 1 16 Operable 8 PAM 2 Thermocouples, 4 From Each Quadrant (See Note 1,8,&10)

Deviation #30

& #37 26

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 2 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 7 Main Steam Line Radiation C2 E2 1 Channel 1.0E-l 1.0E3 uCi/cc YES NO YES NON-lE (See Note 7)

Per Steam Generator 8 Nuclear Instrumentation Al Bl D2 P1 P2 1.0E-1 2.0E5 CPS YES YES YES 1E Note 8 (Source Range) 9 RCS Pressurizer Level Al Dl P1 P2 P3 0 100  % YES YES YES 1E Note 8 & 12 10 RCS Pressure Wide Range Al Bl Cl D2 P1 P2 P3 0 3000 PSIG YES YES YES 1E Note 8 & 12 11 RCS Temperature T Cold Al Bl Cl D2 4 Channels 50 700 Deg F YES YES YES 1E (See Note 1 1 Per Loop & 8)

Deviation #1 12 RCS Temperature T Hot Al D2 4 Channels 50 700 Deg F YES YES YES 1E (See Note 1 1 Per Loop & 8)

Deviation #1 13 Refueling Water Storage Al D2 P1 P2 0 100  % YES YES YES 1E Note 8 Tank Level 14 Steam Generator Level Al Bl P1 P2 P3 0 100  % YES YES YES 1E (See Note 1, 8

& 12 (Narrow Range) 3 Channels Per Steam Generator 27

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 3 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 15 Steam Generator Pressure Al B1 D2 PlP2 0 1300 PSIG YES YES YES 1E Deviation #3 2 Channels Notes 1 & 8 Per SG 16 Subcooling Margin Monitor Al B2 Cl D2 P1 P2 200 35 Deg F YES YES YES iE 200 Deg.

Subcooling to 35 Deg.

Superheat Notes 8 & 10 17 Auxiliary Building Passive Bl Cl P1 P2 12.5 72.5 Inches YES YES YES 1E Note 8 Sump Level 18 Containment Isolation B1 D2 1 Per Valve Closed Not N/A YES YES YES 1E Deviation #20 Valve Position Indication CLOSED Note 15 19 Containment Hydrogen Bl Cl D2 P1 P2 0 10  % YES YES YES IE Deviation #2 Concentration 20 Control Rod Position D3 1 Channel 0 235 Steps NO NO NO Non-lE Deviation #35 Per Bank 21 Nuclear Instrumentation Bl D2 P1 P2 1.OE-8 200  % Power YES YES YES 1E Note 8 (Intermediate Range) 22 REACTOR VESSEL LEVEL Bl C1 D2 P1 P2 See Note 5 YES YES YES 1E (See Note 5, 8, & 10) 22a Static Mode 0 100 9- 0% Represents (Pumps Not Running) Reactor Vessel Empty. 100%

represents reactor vessel full.

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 4 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 22b Dynamic Mode 20 100 100%

(Pumps Running) Represents Reactor Vessel Full 23 Containment Pressure Cl P1 P2 -5 60 PSIG YES YES YES 1E (Wide Range) 24 Shield Building Vent C2 E2 1 Channel 1.OE-6 1 .0E4 uCi/cc YES NO YES NON-1E (Noble Gas Activity) 25 ABGTS High Pressure D2 1 Channel NA -0.2 In.H20 YES NO YES NON-lE Alarm Per Fan 26 ACAS Pressure D2 1 Channel 0 150 PSIG YES NO YES NON-lE Per Train 27 AFW Valve Status Dl 1 Channel Open Closed NA YES YES YES 1E Per Valve 28 Accumulator Flow D3 1 Channel Open Closed NA NO NO NO NON-lE Deviation #16 Alarm Valve Status Per Valve 29 Accumulator Tank Level D3 1 Channel 7450 8080 GAL NO NO NO NON-lE Deviation #15 Per Tank 30 Accumulator Tank D3 1 Channel 0 700 PSIG NO NO NO NON-lE Deviation #6 Pressure Per Tank 31 Annulus Pressure D2 1 Channel -10 0 In. H20 YES NO YES NON-lE 32 Aux. Feed Pump Turbine D3 1 Channel Open Closed NA NO NO NO NON-lE Steam Supply Isolation Per Valve Valve Status 29

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 5 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-i WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 33 Battery Current D2 1 Channel -200 +600 AMPS YES NO YES N/A (125V dc Vital) Per Battery 34 Bus Voltage D2 1 Channel 75 150 VOLTS YES NO YES N/A (125V dc Vital) Per Battery 35 Bus Voltage (480V D2 1 Channel 0 600 VOLTS YES NO YES N/A Shutdown) Per Train 36 Bus Voltage D2 1 Channel 6400 7400 VOLTS YES NO YES NON-lE Analog (6.9KV Shutdown) Per Train Scale, Digital Display 37 CCS Surge Tank Level D3 1 Channel 0 100 NO NO NO NON-lE Per Train GPM 38 Centrifugal Charging D2 1 Channel 0 1000 YES NO YES NON-lE Pump Total Flow GPM 39 Charging Header Flow D3 1 Channel 0 110 NO NO NO NON-lE Deviation #17 GPM 40 Component Cooling D2 1 Channel 0 5561 YES NO YES NON-lE Water To ESF Flow Per Hx 41 Component Cooling Water D2 1 Channel 30 150 Deg F YES NO YES NON-lE Deviation #7 Supply Temperature Per Train 42 Condensate Storage Tank D3 1 Channel 0 385,000 GAL NO NO NO NON-lE Not Primary Water Level Per Tank Source of Aux.

Feedwater.

See Variable 27 30

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC--30-7 Page No. 6 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-l WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 43 Containment Air Return D2 1 Channel On Off NA YES NO YES NON-lE (Breaker Status Per Fan Status) 44 Containment Cooling Valve D3 1 Channel Open Closed NA NO NO NO NON-lE Status Per Valve 45 Containment Spray Flow D2 1 Channel 0 4400 GPM YES NO YES NON-lE Per Train 46 Containment Spray HX D2 1 Channel 0 200 Deg F YES NO YES NON-IE Outlet Temperature Per HX 47 Containment Sump Water D3 1 Channel 2 66 Inches NO NO NO NON-lE Deviation #12 Level (Narrow Range) 48 Containment Sump Water D2 1 Channel 50 400 Deg F YES NO YES NON-lE Used RHR Temperature Inlet Temperature Loop 49 Diesel Generator Power D2 1 Channel 0 4.84 MWATTS YES NO YES N/A Per DG 50 Diesel Generator Volts D2 1 Channel 0 6900 VOLTS YES NO YES N/A Per DG 51 ECCS Valve Status D2 1 Channel Open Closed NA YES NO YES NON-lE Per Valve 52 ERCW Header Flow D2 1 Channel 0 20,000 GPM YES NO YES NON-lE Per Header 31

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 7 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 53 ERCW Supply Temperature D2 1 Channel 32 200 Deg F YES NO YES NON-lE Per Header 54 Emergency Gas Treatment D2 1 Channel Open Closed NA YES NO YES NON-lE Damper Position Per Damper 55 Emergency Ventilation D2 1 Channel Open Closed NA YES NO YES NON-lE Damper Status Per Damper 56 Hydrogen Recombiner D3 1 Channel On Off NA NO NO NO NON-lE Status Per Recombiner 57 Igniter Group Status D3 1 Channel On Off NA NO NO NO NON-IE Per Group 58 Inverter Current D2 1 Channel 0 167 AMPS YES NO YES N/A Local (120V ac Vital) Per Inverter Indication Note 9 & 13 59 Inverter Voltage D2 1 Channel 115 125 VOLTS YES NO YES N/A Local (120V ac Vital) Indication Note 9 & 13 60 Letdown Flow D3 1 Channel 0 144 GPM NO NO NO NON-lE Deviation #18 61 MCR Pressure D3 1 Channel 0 0.50 In. H20 NO NO NO NON-IE 62 MCR Radiation Level D2 1 Channel 1.0E-I 1.0E4 MR/Hr YES NO YES NON-lE 32

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 8 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 63 Main Feedwater Flow D3 1 Channel 0 4,372,720 lb/hr No No No NON-lE Per Loop 64 Normal Emergency Boration D2 1 Channel 0 150 GPM YES NO YES NON-lEDeviation #4 Flow 65 THIS LINE INTENTIONALLY LEFT BLANK 66 Pressurizer Heater Status D2 1 Channel 0 50.5 AMPS YES NO YES NON-lE(See Note 3)

(Electric Current) Per Group 67 Pressurizer Pressure D2 1 Channel Closed Not N/A YES NO YES NON-lE Relief Valve Position Per Valve Closed (PORV, Block, and Code) 68 Pressurizer Relief Tank D3 1 Channel 0 100 NO NO NO NON-lE Level 69 Pressurizer Relief Tank D3 1 Channel 0 100 PSIG NO NO NO NON-lE Pressure 70 Pressurizer Relief Tank D3 1 Channel 502 4002 Deg F NO NO NO NON-iEDeviation #11 Temperature 71 RCP Seal Injection Flow D3 1 Channel 0 13.2 GPM NO NO NO NON-lE Per RCP 72 RCS Head Vent Valve Status D2 1 Channel Closed Not NA YES NO YES NON-IE Per Valve Closed 73 RHR Heat Exchanger Outlet D2 1 Channel 50 400 Deg F YES NO YES NON-iEDeviation #9 Temperature Per HX 33

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POST ACCIDENT MONITORING INSTRUMENTATION WB -DC 7 Page No. 9 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7 VAR Redundant R ange Power NUM Variable Name Type/Catego ry Channels Range From Range To Units EQ SQ QA Supply Notes 74 RHR Pump Flow (RHR D2 1 Channel 0 5500 GPM YES NO YES NON-IE System Flow) Per Pump 75 RHR Valve Status D3 1 Channel Open Closed NA NO NO NO NON-lE Per Valve 76 Reactor Coolant Pump D3 1 Channel 0 712 AMPS NO NO NO NON-IE Status (Motor Current) Per Pump 77 Safety Injection Pump D2 1 Channel 0 715 GPM YES NO YES NON-lE Flow Per Pump 78 Safety Injection System D3 1 Channel Open Closed N/A NO NO NO NON-lE Valve Status Per Valve 79 Spent Fuel Pool Level D2 1 Channel 74811-1/2 749'2-1/2 ft,in YES NO YES NON-iERange Alarm Reflects Low and High Alarm Setpoints 80 Spent Fuel Pool D2 1 Channel 127 Deg F YES NO YES NON-lEUpper range Temperature Alarm Is Alarm Setpoint 81 Steam Generator Blowdown D2 1 Channel Closed Not NA YES NO YES NON-lE Isolation Valve Status Per Valve Closed 82 Steam Generator Level D1 4 Channels 0 100  % YES YES YES NON-iEDeviation #10 (Wide Range) 1 Per SG Notes 1 & 8 83 Main Steam Flow D2 1 Channel 0 4,500,000 lb/Hr YES NO YES NON-IE Per SG 34

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC 7 Page No. 10 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-i WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 84 Tritiated Drain Collector D3 1 Channel 4 96 NO NO NO NON-iELocal Tank Level Per Train Indication Deviation #25 85 Volume Control Tank Level D3 1 Channel 0 100  % NO NO NO NON-lEDeviation #19 86 Waste Gas Decay Tank D3 1 Channel 0 150 PSIG NO NO NO NON-lELocal Pressure Per Tank Indication Deviation #23 87 Radiation Exposure Meters E3 NA NA NA NA NA NA NA NA Deviation #22 88 Airborne Radiohalogens E3 Portable 1.OE-9 1.OE-3 uCi/cc NO NO NO NA Airborne and Particulates 1-131 and particulates 2

89 Plant and Environs E3 Portable 1. 0E-3 1.0E42 R/hr NO NO NO NA Radiation 90 Plant and Environs E3 Portable NA NA NA YES NO YES NA Multi Channel Radioactivity Gamma Ray Spectrometer 91 Auxiliary Building Vent E2 1 Channel 1.0E-6 1.OE-2 uCi/cc YES NO YES NON-lEDeviation #13 (Noble Gas) 92 Auxiliary Building Vent E2 1 Channel 0 250,800 CFM YES NO YES NON-lE (Flow Rate) 93 Auxiliary Building Vent E3 1 Channel Note 11 Note 11 uCi/cc NO NO NO NON-lESampling with (Particulates and Onsite Halogens Analysis Capability Deviation #14 35

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 11 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-1 WB-DC-30-7

'AR Redundant Range Power N[UM Variable Name Type/Catego ry Channels Range From Range To Units EQ SQ QA Supply Notes 94 Condenser Vacuum Pump E2 1 Channel 0 45 SCFM YES NO YES NON-lE Exhaust Vent (Flow Rate) 95 Condenser Vacuum Pump C3 E2 1 Channel 4.OE-7 2.4E3 uCi/cc YES NO YES NON-iEDeviation #33 Exhaust Vent (Noble Gas) 96 ERCW Radiation Monitors E2 1 Channel 3.3E-4 1.65E-2 uCi/cc YES NO YES NON-lE Per Discharge Point 97 POST ACCIDENT SAMPLE E3 1 System See below NO NO NO NON-lESampling with SYSTEM Onsite Analysis Capability 97a Reactor Coolant E3 NA 20 ppm Deviation #29 Chloride Concentration 10 97b Reactor Coolant E3 NA 2000 cc/kg Deviation #21 Dissolved Hydrogen (STP) 10 97c Reactor Coolant E3 NA 20 ppm Deviation #34 Dissolved Oxygen 97d Reactor Coolant E3 NA 100 2000 cc/kg Deviation #34 Total Dissolved Gas (STP) 97e Reactor Coolant Boron E3 NA 50 6000 ppm Deviation #26 36

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POST ACCIDENT MONITORING INSTRUMENTATION WB -DC- 30-7 Page No. 12 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-I WB-DC VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 97f Reactor Coolant PH E3 NA 1 13 pH 97g Reactor Coolant C3 E3 NA lOuCi/ml loCi/ml Ci/ml Deviation #5 Sample Activity 97h Reactor Coolant Gamma E3 NA NA NA NA Isotopic Spectrum Analysis 98 CONTAINMENT AIR 98a Containment Air E3 NA 0 10  % by NO NO NO NON- Also Measured Hydrogen Volume 1E by Hydrogen Analyzer Deviation #2 98b Oxygen Content NA NA NA NA NA NA NA NA Deviation #27 98c Gamma Spectrum Sample E3 NA NA NA NA NO NO NO NA Isotopic Analysis 99 Shield Building Vent E2 1 Channel 0 28,000 CFM YES NO YES NON-IE Flow Per Unit 100 Shield Building Vent E3 1 Channel 1.OE-3 1.0E-2 uCi/cc NO NO NO NON-lESampling with Monitor (Particulate Per Unit Onsite And Iodine) Analysis Capability 101 Steam Generator E2 1 Channel Note 4 Note 4 Note 4 YES NO YES NON-IE Discharge Vent (Flow Per Release Rate and Noble Gas) Point 37

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 13 Regulatory Guide 1.97 Post Accident Monitoring Variables List Appendix A Table A-l WB-DC-30-7 VAR Redundant Range Power NUM Variable Name Type/Category Channels Range From Range To Units EQ SQ QA Supply Notes 102 METEROROLOGY 102a Vertical Temperature E3 1 Channel -9 +18 Deg F NO NO NO NON-IE Difference 102b Wind Direction E3 1 Channel 0 360 Deg NO NO NO NON-lE 102c Wind Speed E3 1 Channel 0 50 MPH NO NO NO NON-lE Deviation #28 103 Radiation Exposure E3 Portable 1. 0E-3 1. 0E4 R/Hr NO NO NO NA Deviation #31 Rate 38

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 14 APPENDIX A POST ACCIDENT MONITORING VARIABLES LIST TABLE A-i Notes:

1. The following parameters are identified as diverse in Reference 9.1.11.

Parameter Diverse Parameter T (Hot) Core Exit Temperature Core Exit Temperature T (Hot)

T (Cold) SG Pressure Auxiliary Feedwater Flow SG NR/WR Level

2. Deleted

3. Pressurizer Heater Status required only for safety-related heater banks (backup heater IA-A and lB-B). Range is given in amps per element.

4. Recorder shall be provided for duration of release from all discharge points.

Noble Gas Activity (See Main Steam Line Radiation, Var No. 7)

Steam Flow Rate 0 to 4945200 lb/hr PORV and Safety Valves 0 to 63375 lb/hr To Aux. Feedwater Pump Turbine

5. Vessel level on the plasma display is the compensated actual vessel level derived from a microprocessor algorithm using the upper range, lower range, dynamic range differential pressure, wide range temperature, and wide range pressure.

6. Deleted.

7. Also monitors steam generator discharge vent noble gas activity. Required range of sensitivity specified is met by indication displaying in units of dose rate. Conversion to required range is performed using conversion factor specified in Calc. WBNAPS3-048. [PL-08-0501]

8. At least one of the redundant loops is trended on a non-divisional trend recorder qualified to meet Category 2 requirements.

9. Justification for local indication is found in Reference 9.1.22.

10. The Core Exit T/C Temperature (hottest), reactor vessel level, and Saturation Margin are trended on redundant Class 1E plasma displays (the last 30 minutes trending only) in the Main Control Room.

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 Page No. 15 APPENDIX A POST ACCIDENT MONITORING VARIABLES LIST TABLE A-I Notes:

11. The ranges for particulates and halogens: 5x10-10 to 10-5uCi/cc for particulates, 10. 9 to 10- 4uCi/cc for halogens (iodine).

12. The requirements for Category I variables which require a third independent channel to resolve ambiguity resulting when redundant displays disagree are being implemented at WBN as follows:

The loop instrumentation for each channel is assigned to a redundant protection set (I, II, III, and IV) and electrical independence is maintained from sensor to display. Physical separation is maintained from the sensor to the isolator in the Auxiliary Instrument Room. From the isolator to the indicator in the Main Control Room, third channel (PAM 3) cables may be routed with either PAM 1 or PAM 2 cables (but not both) depending on its associated protection set.

13. The 120V AC Vital Inverter has a trouble alarm in the MCR which notifies of trouble on the bus.

14. Four channels are provided for this variable. Two channels are designated as PAM 1, and two channels are designated as PAM 2. Reference 9.1.11 evaluated three channels for this variable and determined that three channels are adequate for eliminating ambiguous readings.

15. In accordance with Technical Specification Bases B 3.3.3, PAM position indication is not required for containment isolation valves when the valves are closed and power removed. MSIV bypass valves (Main Steam warming valves, 1-FCV-147, -148, -149, and -150) are normally closed during power operation (modes 1 and 2) with power removed. Consequently, position indication is not required for the valves in this configuration.

The valves are powered and open during modes 3 and 4. Thus, position indication is required in this operational configuration. However, valves 1-FCV-147, -150, [PL-08-0483] and associated position indication instrumentation are subject to flooding subsequent to a feedwater line break. As evaluated in Reference 9.1.31 (WBNAPS2001, Rev. 4), the valves will close prior to flooding .[PL-08-0540]. Flooding will result in power being removed from the valves and instrumentation. Consequently, valve position indication is only required for these valves prior to loss of power due to flooding.

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX B TABLE B-I POST ACCIDENT MONITORING VARIABLES UTILIZING THE PLANT COMPUTER SYSTEM FOR MCR INDICATION TYPE /

IACATEGORY COMPUTER VAR VARIABLE NAME PRIMARY ELEMENT ADDRESS 46 CONTAINMENT SPRAY D2 1-TE-72-31 T0168A HX OUTLET 1-TE-72-6 T0169A TEMPERATURE 47 CONTAINMENT SUMP D3 I-LT-77-125 L0471A WATER LEVEL (NARROW RANGE) 53 ERCW SUPPLY D2 TE-67-455 T2612A TEMPERATURE 1-TE-67-456 T2613A 2-TE-67-455 T2614A 2-TE-67-456 T2615A 61 MCR PRESSURE D3 0-PDT-31-1D P4002A 66 PRESSURIZER HEATER D2 I-EM-68-341A E4003A STATUS l-EM-68-341D E4004A 92 AUXILIARY BUILDING E2 0-EM-90-300C F2704A VENT (FLOW RATE) 94 CONDENSER VACUUM E2 1-FT-2-256 F2700A PUMP EXHAUST VENT (FLOW RATE) 95 CONDENSER VACUUM C3 E2 1-RE-90-404A, R9061A PUMP EXHAUST VENT 1-RE-90-404B R9062A (NOBLE GAS) 101 STEAM GENERATOR E2 1-XE-1-300 A-F, 1-ZE-1-5 F9051A DISCHARGE VENT I-PT-1-5-G FLOW RATE 1-XE-1-301 A-F, 1-ZE-1-12 F9052A 1-PT-i-12-F 1-XE-1-302 A-F, 1-ZE-1-23 F9053A 1-PT-1-23-F 1-XE-1-303 A-F, I-ZE-1-30 F9054A I-PT-1-30-G 1-FT-1-17 F9050A 1-FCV-1-15 FD9300 4 Containment Al 1-RE-90-271 R9018A Radiation C3 1-RE-90-272 R9019A El I-RE-90-273 R9020A 1-RE-90-274 R9021A 96 ERCW RADIATION E2 O-RE-90-133A R1032A MONITORS 0-RE-90-134A R1033A 0-RE-90-140 R1035A 0-RE-90-141 R1036A

[PL-08-0484]

B-I 41

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 SOURCE NOTES SOURCE NOTE TRACKING SOURCE NOTE NUMBER NUMBER/DOCUMENT APPLICABLE SECTION 1 Letter to the NRC dated 1.1 August 31, 1990 (L44 900831 804) 2 Letter to the NRC dated 1.1, 3.4.1.6, October 29, 1991 3.4.2.1, and (T04 911029 848) App. A, Table A-I (Pages 40 & 42) 3 CATD 22911-WBN-01 Various, not specifically noted in text 42

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 1 VARIABLES (11 AND 12)

Reactor Coolant System (RCS) Cold- and Hot-Leg Water Temperatures DEVIATION FROM REGULATORY GUIDE (RG) 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 50 to 750 F; the recommendation for Watts Bar Nuclear Plant (WBN) is 50 to 700 F.

JUSTIFICATION The Reactor Coolant System Description N3-68-4001 states that the design temperature of the RCS is 650 F. The RG 1.97, Revision 2 recommended range is 50-750 F. However, NRC has revised its position on this range and RG 1.97, Revision 3, now recommends a range of 50-700 F will provide a 50 F margin over the design limit for both temperatures, which should provide the operator with adequate information for all transients. NRC concurs with WBN that an upper limit of 700 F is acceptable. (

Reference:

NRC letter from Youngblood to White dated July 24, 1986.)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the RCS hot-leg water temperature (Variable 12) parameter be a Bl variable. WBN recommends that this be an Al and D2 variable.

JUSTIFICATION Type B variables provide information to indicate whether plant safety functions are being accomplished. WBN's position is that RCS pressure (Type Al, Bl, Cl and D2), core exit temperature (Type Al, Bl, Cl, and D2), reactor vessel level (Type Bl, Cl, and D2), and subcooling margin (Al, B2, Cl, and D2) are sufficient to monitor for adequate core cooling and the approach to superheat conditions in order to determine the margin by which the core cooling safety function is being accomplished. Therefore, it is WBN's position the RCS hot-leg water temperature be required only as a Type Al and D2 variable.

DEVIATION 2 VARIABLE (19)

Containment Hydrogen Concentration C-1 43

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 0 to 30 percent, whereas WBN has provided instrumentation for this variable with a range of 0 to 10 percent.

JUSTIFICATION WBN has performed an analysis that shows the worst-case hydrogen concentration will be less than 4 percent post-loss-of-coolant (LOCA) with one of the hydrogen recombiners operating. Also, the hydrogen igniter system handles degraded core hydrogen releases as specified in 10 CFR 50.44 and will also keep the hydrogen concentration below 10 percent for these events. Therefore, the instrumentation will always be on scale. The hydrogen recombiner status is indicated by a PAM D3 variable.

DEVIATION 3 VARIABLE (15)

Steam Generator (SG) Pressure DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 0 psig to 20 percent above the lowest safety valve setting (corresponding to 1422 psig at WBN); the recommended range for WBN is 0-1300 psig.

JUSTIFICATION The design pressure for the main steam system at WBN is 1185 psig. The main steam safety valves are designed to maintain system pressure less than 110 percent of design pressure, which is 1303.5 psig. RG 1.97, Revision 2, recommends a range of 0 psig to 20 percent above the lowest safety valve set pressure, which corresponds to a range of 0 to 1422 psig. The highest main steam safety valve set pressure is 1224 psig and the accumulation pressure for each of the highest pressure safety valves is 1284 psig. Therefore, since the accumulation pressure is below 1300 psig and the 110 percent design pressure of approximately 1300 psig, the WBN recommended range of 0-1300 psig is adequate to cover the design range. The RG 1.97, Revision 2 range is well above the design requirements for the system and the ASME Code requirements for relief valves. Thus it is concluded that the WBN SG pressure range provides adequate feedback to the operator on SG pressure response to accidents or transients, and should be acceptable.

DEVIATION 4 VARIABLE (64)

Normal/Emergency Boration Flow (Boric Acid Charging Flow)

DEVIATION FROM RG 1.97 GUIDANCE WBN recommends that this variable not be environmentally qualified (as required for RG 1.97, Revision 2, Category 2 variables) since other variables perform the required emergency boration monitoring function.

C-2 44

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS JUSTIFICATION The flow path monitored by this variable is a normally isolated path that requires operator action to utilize. This path is used for manual boration of the RCS. This path is not required for mitigation of any event. Postaccident reactivity control is accomplished by the Emergency Core Cooling System (ECCS) injecting borated water from the refueling water storage tank (RWST) into the RCS. Manual boration is not utilized. The ECCS flow is monitored by the centrifugal charging pump total flow (high pressure injection flow), the safety injection (SI) pump flow (low pressure injection flow), and the residual heat removal (RHR) pump flow (RHR System flow)/

These three variables are in the environmental qualification program and meet the 110 percent design flow measurement requirement.

DEVIATION 5 VARIABLE 97g Radiation Level in Circulating Primary Coolant (Reactor Coolant Sample Activity).

DEVIATION FROM RG 1.97 GUIDANCE This variable has been identified in RG 1.97, Revision 2, as Type C, Category 1, whereas WBN has identified this variable as Type C, Category 3.

JUSTIFICATION For the fuel cladding integrity safety function, RG 1.97 recommends core exit temperature and RCS activity as key variables and gamma spectrum analysis of the reactor coolant as a Category 3 variable. Core-exit temperature provides primary indication of a significant breach or potential breach of fuel throughout the emergency instructions (EIs), functional restoration guidelines (FRGs), and Final Safety Analysis Report (FSAR). Therefore, this variable was included as the Category 1 or key indication. Radiation level in circulating primary coolant was

'considered; however, it indicates conditions following fuel damage and provides less timely information. Thus, this variable is considered to be less useful to the operators and was included as a backup variable. TVA meets the intent of the RG 1.97 recommended range by monitoring this variable using the gross activity analysis of primary coolant samples taken in the post accident sampling facility.

DEVIATION 6 VARIABLE (30)

Safety Injection (Cold-Leg) Accumulator Tank Pressure DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the pressure instruments meet the D2 criteria with a range of 0 to 750 psig. WBN recommends retaining this variable as D3, with a range of 0 to 700 psig.

C-3 45

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS JUSTIFICATION The primary function of these instruments is to monitor the preaccident status of the accumulators to ensure the passive safety function of the system. By design they do not perform any safety function postaccident. Other seismically and environmentally qualified instruments such as RCS pressure can be monitored to determine if a cold-leg accumulator injection has occurred.

The design pressure of the cold-leg accumulator tanks is 700 psig. The precautions, limitations, and setpoints (PLS) limit the nitrogen cover gas to a maximum pressure of 632 psig. Therefore, WBN's position is that monitoring of the tanks to pressures higher than the relief setpoints is not needed. WBN considers the existing range of 0 to 700 psig to the acceptable.

DEVIATION 7 VARIABLE (41)

Component Cooling Water (CCW) Temperature to Engineered Safety Features (ESF)

Equipment DEVIATION FROM RG 1.97 GUIDANCE The range recommended in Rg 1.97, Revision 2, is 32 to 200 F; the recommendation for WBN is 30 to 150 F.

JUSTIFICATION WBN analysis has determined that the highest expected CCW temperature (post-LOCA safety injection) is 120 F.

An upward trend of the CCW temperature above 120 F could be readily detected and would be expected to be slow moving. Thus, there would be sufficient time well within the 150 F upper range to alert the operator to the condition and the need to check other PAM-related variables for potential manual actions.

DEVIATION 8 VARIABLE (2)

Containment Atmosphere Temperature (Containment Lower Compartment Atmosphere Temperature)

DEVIATION FROM RG 1.97 GUIDANCE The range for this variable is recommended to be 40 to 400 F in accordance with RG 1.97, Revision 2. WBN recommends the range to be 0 to 350 F.

C-4 46

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS JUSTIFICATION WBN is an ice condenser plant and, therefore, has a lower containment temperature post-accident than dry containments. The maximum temperature expected post-LOCA at WBN is 250 F as compared to 275 to 290 F for dry containments. The maximum temperature expected at WBN after a steam line break is 327 F as compared to 380 to 450 F for dry containments. The minimum expected containment atmospheric temperature will be 60 F. This minimum temperature is due to the minimum allowable RWST water temperature which could be sprayed into containment by inadvertent operation of the containment spray. Therefore, it is WBN's position that a range of 0 to 350 F is adequate.

DEVIATION 9 VARIABLE (73)

Residual Heat Removal (RHR) Heat Exchanger Outlet Temperature DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 32 to 350 F; the recommendation for WBN is 50 to 400 F.

JUSTIFICATION NRC letter from Youngblood to White dated July 24, 1986, states that RG 1.97, Revision 3, increased the minimum required range of this variable to 40 F and that WBN's range of 50 to 400 F was acceptable due to the minor deviation.

DEVIATION 1Q VARIABLE (82)

SG Level Wide Range DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends this variable as a Type D, Category 1 variable, which requires redundancy in the instrumentation. WBN recommends this variable be Category 1, Type D, but utilizing only one wide range transmitter per SG.

JUSTIFICATION SG wide range level indication is utilized as a diverse variable to auxiliary feedwater (AFW) flow for gross indication of flow to the SGs. The WBN AFW monitors are Types Al and D2. WBN's position is that since SG wide range level is only used as a backup to redundant AFW flow monitors, it does not require redundancy.

C-5 47

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 11 VARIABLE (70)

Quench Tank (Pressurizer Reflief Tank [PRT]) Temperature DEVIATION FROM RG 1.97 GUIDANCE The range for this variable is recommended to be 50 to 750 F in accordance with RG 1.97, Revision 2. WBN recommends the range to be 50 to 400 F.

JUSTIFICATION The purpose of this variable is to monitor operation. The PRT rupture disk is designed to operate between 86-100 psig. Assuming that the rupture disk operates at 100 psig and the pressurizer is at 2500 psig at saturated conditions, the maximum temperature during discharge when all valves in the line are open could be approximately 350 F. High temperature due to discharges or leakage into the tank form the pressurizer or other sources would produce an early upward trend in PRT temperature above normal. Temperatures far below the RG 1.97 recommended temperature of 750 F or the 400 F WBN recommended temperature would be sufficient to alert the operator to an abnormal condition and the potential need to check related PAM variables. Therefore, the recommended range of 50 to 400 F is sufficient to permit the operator to monitor plant operation.

DEVIATION 12 VARIABLE (47)

Containment Sump Water Level (Narrow Range)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, revision 2, recommends this variable as Types B and C, Category 2. WBN recommends this variable as Type D, Category 3.

JUSTIFICATION The operator does not monitor this variable to perform any required safety function.

In addition Chapter 15 of the FSAR takes no credit for monitoring this variable for any design bases event. This variable is used primarily to monitor RCS leakage. This variable, along with the lower containment atmosphere particulate radioactivity monitoring systems are used to detect RCS leakage. These small leakages do not cause plant perturbations or detect RCS leakage. These small leakages do not cause plant perturbations or transients that would cause a reactor trip or SI signal to be generated. Therefore, the operator does not enter the emergency procedures to detect or mitigate these leakages and corrective actions based on the emergency procedures and the use of PAM equipment are inappropriate. However, for the purpose of monitoring gross leakage, this variable will be designated as a Type D3 variable.

The containment sump water level (wide range) is a Type Al, Bl, Cl, and D2 variable and is used at WBN to monitor the containment water level for the mitigation of accidents.

C-6 48

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 13 VARIABLE (91)

Auxiliary Building Exhaust Vent Radiation Level - Noble Gas Release DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 10-6 to 10 3 microcuries/cubic centimeter (cc); the recommendation for WBN is 10-6 to 10-2 microcuries/cc.

JUSTIFICATION The Auxiliary Building vent monitor is provided to continuously monitor the airborne radioactivity released through the Auxiliary Building exhaust vent. An accident causing Auxiliary Building radiation level to be high will cause all ventilation paths exhausting into the Auxiliary Building vent duct to automatically close and the Auxiliary Building gas treatment system to be activated. Because the isolation function occurs before accident-range activity is reached, a normal-range monitor only is employed to monitor activity in the 2Auxiliary Building exhaust vent.

Therefore, the recommended range of 10-6 to 10 microcuries/cc is adequate for detecting and measuring noble gas concentrations.

DEVIATION 14 VARIABLE (93)

Auxiliary Building Exhaust Vent Radiation Level - Particulates and Halogens DEVIATION FROM RG 1.97 GUIDANCE

. -32 The range recommended in RG 1.97, Revision 2, is 10 to 10 microcuries/cc; the recommendation for WBN is 5x10-1' to 10-5 for particulates and 10-9 to 10' microcuries/cc for halogens (iodine).

JUSTIFICATION The Auxiliary Building Exhaust Vent monitor is provided to continuously monitor the radioiodine and particulate radioactivity released through the Auxiliary Building vent. A Design Basis Fuel Handling Accident in the Auxiliary Building or a Design Basis LOCA in the Reactor Building will cause all ventilation paths exhausting into the Auxiliary Building vent duct to automatically close and the Auxiliary Building Gas Treatment system to be activated. Because the isolation function occurs before accident range activity is reached, a normal range monitor only is employed to monitor activity in the Auxiliary Building vent. Therefore, the recommended range of 5x10-10 to 10-5 microcuries/cc for particulates and 10-9 to 10-4 microcuries/cc for halogens is adequate for detecting and measuring normal operation particulate and radioiodine concentrations. Laboratory analysis of collected samples allows measurement over a wide range.

C-7 49

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 15 VARIABLE (29)

Safety Injection (Cold-Leg) Accumulator Tank Level DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is 10 to 90 percent volume using a D2 variable. WBN recommends a range of 75 to 82 percent volume, using a D3 variable.

JUSTIFICATION The present accumulator tank level indication range of 7632 to 8264 gallons corresponds to 75 to 82 percent of volume.

Postaccident level does not serve any safety function since the passive injection of the cold-leg accumulators (CLA) into the RCS would be observed through other qualified instrumentation such as RCS pressure. Hence, level instrumentation which meets the requirements of a D3 variable is appropriate.

DEVIATION 16 VARIABLE (28)

Cold-Leg Accumulator Isolation Valve Position Indication DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the position indication of the CLA isolation valve be qualified to D2 requirements. WBN recommends designating this variable as D3.

JUSTIFICATION The CLA isolation valves do not need to change from their normally open position in the event of an accident which requires CLA injection. These valves will already have been opened during startup soon after the RCS pressure sufficiently exceeds the CLA normal operating pressure. Then the associated motive power will be removed.

There is no accident event in which instantaneous emptying of all four CLAs could cause inadequate core cooling or cold overpressurization of the RCS. The steamline break is the only Condition IV event other than a LOCA that causes a rapid depressurization of the RCS. However, even for that accident the RCS depressurizes rapidly down to 900 psi where the pressure stabilizes or rises. Further depressurizations are at a much more controlled rate, giving the operator time to react.

For a Condition III event, such as a 4- or 6-inch break (small break LOCA), the depressurization of the RCS may cause emptying of the CLA. Even under such cases, emptying the CLAs will not cause inadequate core cooling or cold overpressurization of the RCS.

C-8 50

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS Furthermore, closing the CLA isolation valves is not a safety function for accident mitigation that necessitates environmentally qualified valve position indication.

Hence, there is no need to environmentally qualify these valves.

WBN recommends designating the position indication of the CLA isolation valve as a D3 variable.

DEVIATION 17 VARIABLE (39)

Chemical and Volume Control System (CVCS) Makeup Flow-In (Charging Header Flow)

DEVIATION FROM RG 1.97 GUIDANCE The RG 1.97, Revision 2, recommends that the design flow should be monitored using a D2 variable. WBN recommends designating this variable as D3.

JUSTIFICATION This variable is used to monitor operation. The charging flow is isolated on a SI signal. While certain events may produce a harsh environment'for the flow instruments, makeup flow is not required to mitigate these events. Thus, the installed instrumentation qualified to D3 requirements is appropriate for the intended monitoring function at WBN.

DEVIATION 18 VARIABLE (60)

CVCS Letdown Flow-Out (Let Down Flow)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends 0 to 110 percent design flow monitoring using D2 variables to monitor flow. TVA recommends this variable as D3.

JUSTIFICATION This variable is used to monitor normal operation. The letdown flow isolation valves close on a SI signal, low pressurizer level, or Phase A isolation signal. While certain events may produce a harsh environment for the flow instruments, letdown flow is not required to mitigate these events. Thus, the installed instrumentation qualified to D3 requirements is appropriate for the intended monitoring function at WBN.

DEVIATION 19 VARIABLE (85)

Volume Control Tank (VCT) Level DEVIATION FROM RG 1.97 GUIDANCE The RG 1.97, Revision 2, recommends that the VCT level be monitored from top to bottom with a D2 variable. TVA recommends using a D3 variable and a range slightly less than top to bottom.

C-9 51

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS JUSTIFICATION The VCT is isolated on a SI signal. While certain events may produce a harsh environment for the level instruments, the VCT itself is not required to mitigate the events. Hence the D3 type and category variable is appropriate for its performance requirements.

The present VCT indication reads from 0 to 100 percent over a range of 70 inches which is entirely within the approximately 80-inch cylindrical portion of the tank. Extending the range to include the top and bottom hemispherical portions of the tank would result in nonlinear readings at the extreme ends of the scale. Including the hemisphere and the remaining 10 inches of the vertical cylinder would not add significantly to monitoring capability.

DEVIATION 20 VARIABLE 18 Containment Isolation Valve (CIV) Position DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the CIV position indication should meet the requirements of a Bl variable (which encompasses position indication for the duration of the event). WBN's reactor coolant system (RCS) letdown CIVs flow control valves (FCV)-

62-72, -73, -74, and -76 will be submerged postaccident inside containment. These valves' limit switches are not qualified for operation during post submergence.

In addition, safety relief valves which are also designated as CIVs are not monitored for position.

JUSTIFICATION The RCS letdown CIVs close on an SI signal, Phase A signal, or a low pressurizer level signal. The valves and associated position indication limit switches are qualified to perform their intended safety functions prior to being submerged. The limit switch for the valve position indication is located on the valve and hence subject to submergence.

The limit switch is not qualifiable for submergence. The limit switch performs its intended safety function well before submergence. Valve positions are indicated both in the Main Control Room and the Technical Support Center.

Once the limit switches are flooded, it must be assumed that the control circuit fuses will be blown and position indication will be lost. This indication circuit, however, is isolated from the other CIV indication circuits.

The solenoids for these valves are included in WBN's environmental qualification (EQ) program and will vent to automatically close the FCVs as required under accident conditions. An analysis in WBN's EQ binder demonstrates that once closed, a submergence failure of the solenoid will not cause the FCV to change position. Hence the valves are considered closed and no further indication is required.

C-10 52

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS For safety relief valves, position indication is not necessary since these valves are constantly in their containment isolation position (i.e., closed). Verification that these valves have accomplished their containment isolation function is not necessary since they do not change position to provide this function.

DEVIATION 21 VARIABLE (97B)

Reactor Coolant Dissolved Hydrogen DEVIATION FROM RG 1.97 GUIDANCE The RG 1.97, Revision 2 (refer to Table 2, Type E variables), recommends that primary coolant grab sample capability exists for hydrogen analysis.

JUSTIFICATION The WBN postaccident sampling facility (PASF) will have two independent methods for measuring dissolved hydrogen in the RCS. It will have the capability to measure dissolved hydrogen in the range from 10-2000 cc/kg with an inline ion chromatograph.

In addition, it will have a total dissolved gas analyzer to measure the total dissolved gas in the pressurized coolant in the range from 100-2000 cc/kg. Dissolved oxygen will be separately measured with a dissolved oxygen analyzer. These latter two measurements provide another determination of the dissolved hydrogen. The two available methods provide sufficient backup monitoring capability for dissolved hydrogen and will eliminate the need for handling highly radioactive, undiluted, pressurized reactor coolant grab samples. Diluted, unpressurized reactor coolant grab samples may be obtained as necessary at the PASF for other analyses.

DEVIATION 22 VARIABLE (87)

Radiation Exposure Meters DEVIATION FROM RG 1.97 GUIDANCE Rg 1.97, Revision 2, recommends that Type E radiation exposure meters with continuous indication be available at fixed locations. No category is specified. WBN recommends not classifying these meters as a RG 1.97 variable.

JUSTIFICATION RG 1.97, Revision 2, was issued with an outstanding question regarding the practicality of deploying radiation monitors at fixed locations. A study (NUREG/CR-2644) concluded that it is unlikely that a few fixed-station area monitors could provide sufficiently reliable information to be of use in detecting releases from unmonitored containment release points.

C-11 53

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS NRC agreed with this conclusion and in Revision 3 of RG 1.97 deleted the environs radiation monitors from the pressure water reactor (PWR) table of variables.

TVA thereby requests a deviation from RG 1.97, Revision 2 specification of this Type E variable.

DEVIATION 23 VARIABLE (86)

Waste (Radioactive) Gas Holdup Tank Pressure (Waste Gas Decay Tank Pressure)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that waste (radioactive) gas holdup tank pressure be monitored from 0 to 150 percent of design pressure. WBN recommends that the pressure be monitored from 0 to 100 percent of design pressure. (150 psig).

JUSTIFICATION The design pressure of the waste gas decay tanks is 150 psig. The waste gas decay tanks are equipped with pressure relief valves set at 150 psig. Therefore, WBN's position is that monitoring of the tanks to pressures higher than the relief setpoints is not necessary. WBN considers the existing range of 0 to 100 percent of design to be acceptable.

DEVIATION 24 VARIABLE (3)

Containment Pressure (Narrow Range)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends Type B and Type C variable which covers a range of -5 psig to the design pressure. WBN recommends a lower range of -2 psig using a Type Al, Bl, Cl, and D2 variable (with no deviation to the upper range).

JUSTIFICATION The WBN containment vessel design net external pressure is 2 psig. Inadvertent containment spray initiation will cause rapid depressurization inside containment.

However, for this event the pressure will drop below the minimum design pressure.

Another event that can cause a depressurization inside containment is continuous inadvertent air return fan operation. However, this will occur slowly enough to allow the operators sufficient time to observe trending of containment depressurization and afford ample opportunity to terminate the air fan operation and manually open the lower compartment pressure reflief line.

C-12 54

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS In addition, the containment pressure wide range instrumentation (-5 to 60 psig) overlaps the -2 psig lower range instrumentation. The -2 psig value is the lower design limit and is consistent with the use of upper range design limit of 15 psig.

Hence, a lower range value of -2 psig is appropriate for WBN.

DEVIATION 25 VARIABLE (84)

High Level Radioactive Liquid Tank Level (Tritiated Drain Collector Tank)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends a range for this variable from top to bottom. WBN recommends a range from 11 to 133 inches from the bottom of the tank.

JUSTIFICATION The capacity of the tank is approximately 24,700 gallons. The quantity of water that is excluded from the range of the indication is approximately 1000 gallons at the bottom and an equal amount at the top. Thus, the present range is capable of monitoring approximately 22,700 gallons which is about 92 percent of the total capacity of the tank. TVA thereby considers the proposed range for the existing level taps (11 to 133 inches from the bottom of the tank) to be sufficient for indicating postaccident storage volume for this tank.

DEVIATION 26 VARIABLE (97E)

Reactor Coolant Boron DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the analysis range for boron content in the primary coolant and sump be between 0 to 6,000 parts per million (ppm) and be monitored with a Type B3 and E3 variable. WBN recommends that the range be between 50 to 6,000 ppm and be monitored with a Type E3 variable.

JUSTIFICATION For boron concentrations below 500 ppm, the tolerance for WBN's instrumentation would be limited to plus or minus 50 ppm. This tolerance band is considered by WBN to be acceptable for ensuring that postaccident shutdown margin is maintained. WBN's position is that the current range capability for boron analysis (50 to 6,000 ppm) is sufficient.

C-13 55

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Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS RCS boron concentration used in conjunction with control rod position indication and RCS cold-leg temperature only provides indirect indication. These are backup variables for monitoring reactivity control. Neutron flux is a direct variable that allows the operator to determine if reactivity is under control (i.e., the reactor has tripped and the core is in a subcritical condition). Neutron flux is a Type B1 and D2 variable at WBN. Therefore, the boron concentration is not required for direct reactivity control determination. It is available as a Type E3 variable for backup verification of reactivity control.

DEVIATION 27 VARIABLE (98b)

Containment Air Oxygen Content DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2 recommends a measurement range of 0-30 percent volume for containment air oxygen content. WBN recommends that the measurement of this variable should not be required.

JUSTIFICATION The measurement of containment air oxygen content is not required by NUREG-0737.

Following a design basis LOCA at WBN, the combustible gas control system will operate as described in System Description N3-83-4001 R1 to maintain the hydrogen concentration in containment below the lower flammability limit of 4 percent volume.

Therefore, the oxygen concentration in containment is not important for combustion control. A measurement of the containment oxygen concentration is not needed for any other reason after an accident.

DEVIATION 28 VARIABLE (102c)

Meteorology (Wind Speed)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends that the wind speed measurement range be 0 to 67 mph.

WBN recommends that the range be 0 to 50 mph.

JUSTIFICATION RG 1.97, Revision 3, recommends that the wind speed measurement range be 0 to 50 mph.

Also, NRC letter from Youngblood to White dated July 24, 1986, states that since WBN meets the range recommended in RG 1.97, Revision 3, the 0 to 50 mph range is acceptable.

C-14 56

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Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 29 VARIABLE 97a Reactor Coolant Chloride Concentration DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, recommends a range of 0 to 20 ppm for reactor coolant chloride concentration. WBN recommends a range of 1 to 20 ppm.

JUSTIFICATION The WBN recommended range of 1 to 20 ppm accurately represents TVA's commitment to the NRC.

DEVIATION 30 VARIABLE 6 DEVIATION FROM RG 1.97 GUIDANCE The two channels/trains of the core thermocouple system at the bundling at the common reactor vessel refueling cavity wall penetration do not meet the separation requirement of RG 1.97.

JUSTIFICATION The design and the installation of the mineral insulated cables used for the core thermocouples within the reactor cavity was completed prior to upgrading the system to satisfy RG 1.97 requirements. The design within the refueling cavity is acceptable because:

1. Only a small self-generated signal exists in the cabling from the thermocouples to the Incore Instrument Room and, therefore, no chance exists for a postulated propagating fault.

2. Due to the interference provided by the rod control mechanisms and rod position indicator stack, no likelihood exists for rendering all thermocouples inoperable.

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POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 31 VARIABLE 103 DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, Revision 2, includes exposure rate monitors as Type E (Category 2) variables. These monitors are required to have a range of 1.0 E-1 Rem per hour (R/hr) to 1.0 E4 R/hr and are to be located inside buildings or areas where access is required to service equipment important to safety. The area monitors are intended for use in detection of significant releases, release assessment, and long-term surveillance.

RG 1.97, Revision 2, also included radiation exposure rate monitors, with ranges of 1.0 E-1 R/hr to 1.0 E4 R/hr as Type C variables (these monitors were to be installed inside buildings or areas in direct contact with primary containment where penetrations and hatches were located). This variable was removed from RG 1.97 in Revision 3 and will not be addressed further.

WBN RG 1.97 monitoring instrumentation does not include installed high-range exposure rate monitors as Type E variables. The intended objectives of such instrumentation will be achieved in a different manner than that described in RG 1.97. The following paragraphs describe how WBN's program is designed to monitor radiation exposure rates.

A large number of useful missions outside the MCR during accident conditions may be postulated. These missions would be for activities, such as equipment maintenance, grab sample acquisition, and laboratory analyses of grab samples, that might enhance accident mitigation. Exposure rates encountered on these missions would vary over a wide range. This variability arises from the fact that most high exposure outside the containment during accident conditions would be attributable to contained sources and, therefore, be strong functions of distance from the sources. Because of the wide exposure rate variability, the installation of even a large number of high-range exposure rate monitoring instruments at selected locations on projected mission routes might not contribute substantially, either to the planning of missions for accident mitigation purposes or to the minimization of dose equivalent to personnel performing the missions.

Based on the above considerations, the WBN radiation monitoring system design uses portable high-range exposure rate instruments in lieu of installed high-range exposure rate monitors. Crews attempting missions outside the MCR following an accident would include Radiological Control personnel provided with high-range exposure rate instrumentation. The range of the Type E portable instrumentation available for this purpose is 1.0 E-3 R/hr to 1.0 E4 R/hr, which is consistent with the range required for area exposure rate monitoring.

C-16 58

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS Additionally, the TVA radiation monitoring system presently includes normal-range area monitors, each with a range from 1.0 E-1 MR/hr to 1.0E4 MR/hr. These monitors are located throughout the plant in areas where personnel access is common. Although the area monitors are not required to be within the scope of the environmental qualification program and they are not included in the Postaccident Monitoring (PAM) program, monitors located outside the primary containment and other locations of high postaccident exposure rates can be expected to remain on scale and to continue to provide exposure rate indication with required accuracy during accident conditions.

The monitors that remain on scale will provide useful input to MCR personnel for assessment of plant exposure rate levels during accident conditions. Based upon this assessment and WBN Radiological Emergency Plan dose limitations, a decision will be made as to whether or not missions outside the MCR would be attempted.

In summary, the WBN position on high-range accident monitoring is that high-range exposure rate instrumentation will not be installed and that high-range monitoring will be provided by portable monitoring instrumentation that meets the RG 1.97 required range.

DEVIATION 32 VARIABLE (5)

Containment Sump Level (Wide Range)

DEVIATION FROM RG 1.97 GUIDANCE The range recommended in RG 1.97, Revision 2, is "Bottom of containment to 600,000 gallon level equivalent." Watts Bar recommends a range from 0-200 inches (with the "0" level starting at six inches above the reactor floor) (see Note).

JUSTIFICATION Watts Bar utilizes a containment sump level monitoring system that starts measuring at six inches above the containment floor (level tap located at elevation 703' 3-3/8"). The range of the instrument is 200 inches (719' 11-3/8"). The total volume of water available to flood containment post-LOCA is 844,000 gallons, which is approximately equivalent to 717' 2-2/5" steady state maximum flood level. Therefore, the recommended range is fully adequate to monitor the maximum equilibrium flood level that would be experienced.

Note: The containment sump level monitoring system is utilized only during an accident. During normal operation reactor coolant leakage is monitored by the reactor building floor and equipment drain pocket sump. For post accident monitoring, the operator is aware that the "0" level actually begins at 6" above the floor and will realize that there is extra water inside containment when the sump monitor begins to indicate.

C-17 59

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 33 VARIABLE 95 Condenser Vacuum Pump Exhaust Vent (Noble gas)

DEVIATION FROM RG 1.97 GUIDANCE The RG 1.97, Revision 2, required range for the condenser vacuum pump exhaust monitors is 1.0 E-6 to 1.0 E+5uCi/cc.

JUSTIFICATION TVA has determined the total gas required range of the condenser vacuum pump exhaust monitors to be less than the 1.0E-6 value in RG for the low end of the range and 2.4E+3uCi/cc at the upper end of the range.

The steam generator tube rupture (SGTR) is the only credible accident monitored by the condenser vacuum pump exhaust monitor. NUREG-0800, Revision 2 requires that the SGTR accident be analyzed using the highest isotope concentrations allowed by the Watts Bar Technical Specifications. The specific activity of the reactor coolant is limited to:

a) Less than or equal to 1 microcurie per gram dose equivalent Iodine-131, and b) Less than or equal to 100/EuCi/gm The dose equivalent 1-131 is more than 4 times more restrictive that the 100/E limit.

The 100/E is more conservative and is selected to demonstrate that the monitor will remain on scale during the most severe accident. The highest concentration of mixed noble gas isotopes that can be present under the 100/E limit is 1.45E+3 uCi/cc as determined in TVA calculation WBNAPS3-048 [PL-08-0501]. For the SGTR source spectrum, the maximum measurable concentration for the condenser vacuum pump exhaust monitors is 3.53E+4. Therefore, the Watts Bar required range for the condenser vacuum pump exhaust monitors meets the intent of RG 1.97, Revision 2 based on either the mixed gas or the SGTR specific source spectrum.

DEVIATION 34 VARIABLE 97c & 97d Primary Coolant Dissolved Total Gas (97d) and Dissolved Oxygen (97c)

DEVIATION FROM RG 1.97 GUIDANCE RG 1.97, R2 indicates the range for variable 97d is from 0 to 2000 cc/Kg and the range from variable 97c is 0 to 20 ppm. The TVA required range for variable 97d is 100 to 2000 cc/Kg, and 1 to 20 ppm for variable 97c.

JUSTIFICATION The TVA required ranges for variable 97c and 97d permit adequate assessment of the primary system for these dissolved gases, and therefore, meets the intent of RG 1.97.

C-18 60

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 35 VARIABLE (20)

Control Rod Position DEVIATION FROM RG 1.97 GUIDANCE RG 1.97 recommends that control rod position indication be a Type B. Category 3 variable (B3) to monitor for reactivity control. Watts Bar recommends that this variable be a Type D, Category 3 variable (D3).

JUSTIFICATION Control rod position indication is an indirect variable. It provides backup indication for monitoring reactivity control. Neutron flux (category 1) is a direct variable that allows the operator to determine if reactivity is under control (i.e.,

the reactor has tripped and the core is in a subcritical condition). Since this provides backup indication, utilizing it as a Type D variable is sufficient.

DEVIATION 36 VARIABLE 4 Containment Area Radiation, High Range DEVIATION FROM RG 1.97 GUIDANCE Note 7 of RG 1.97, R2 for the subject variable states, "detectors should respond to gamma photons within any energy range from 60 KeV to 3 MeV with an energy response accuracy of 20 percent at any specific photon energy from 0.1 MeV to 1 MeV. Overall system accuracy should be within a factor of 2 over the entire range. TVA meets the requirements of RG 1.97, R3 Note 7 for the subject variable, which states, "Detectors should respond to gamma radiation photons within any range from 60 KeV to 3 MeV with a dose rate response accuracy within a factor of 2 over the entire range."

JUSTIFICATION It is acceptable to meet the requirements of RG 1.97, R3.

C-19 61

TVA

Title:

POST ACCIDENT MONITORING INSTRUMENTATION WB-DC-30-7 APPENDIX C TABLE C REG GUIDE 1.97 R2 DEVIATION AND JUSTIFICATION FOR DEVIATIONS DEVIATION 37 VARIABLE 6 Core Exit Temperature DEVIATION FROM RG 1.97 R2 GUIDANCE This Type A, Category 1 variable has been provided with a minimum of two independent channels (PAM 1 and PAM 2) for monitoring core exit temperature. Where failure of a channel would present ambiguous or confusing information to the operator, preventing the operator from taking action or misleading the operator, RG 1.97 recommends that an additional redundant (PAM 3) channel be provided. One channel of the WBN core exit temperature indication is subject to direct failure as a result of a specific pipe break jet impingement and/or pipe whip impact on the cable/conduit routed near the safety injection (SI) accumulator cold leg injection line in Loop 1. The WBN design does not include a third redundant channel for this variable.

JUSTIFICATION The core exit thermocouples were added to the plant design to provide direct indication of degrading core cooling conditions following transient events similar to that experienced at Three Mile Island (TMI). These events typically develop gradually over time and involve a great deal of operator action and control. The core exit temperature indication was intended to prevent erroneous operator termination of emergency core cooling system (ECCS) flow to the reactor coolant system (RCS) after small breaks or transients that do not rapidly depressurize the RCS.

The challenge to the channel redundancy in this case is due to a specific primary loop pipe break at the cold leg injection check valve. The injection line is 10-inches diameter, schedule 140 pipe and the postulated break is a full guillotine rupture which results in a blowdown flow area from the primary loop side of the break of 60 in 2 or 0.4176 ft 2 . This break is included in the loss-of-coolant-accident (LOCA) break size spectrum and is considered an intermediate size break. FSAR Chapter 15 analyses show that breaks in this range rapidly depressurize the primary system, causing automatic ECCS response which refloods the core and terminates the core heatup transient. However, should such a break occur, the affected channel is expected to fail open and not give erroneous indication that could confuse the operators.

It is the WBN position that the RG 1.97 R2 indication provided by reactor vessel level, RCS pressure, RCS temperatures Thot and Tcold, and containment pressure and temperature will enable the operators to compensate for a loss of one channel of CET due to this specific pipe break plus a single failure of the redundant channel. The operators will be able to correctly assess the accident scenario and determine the effectiveness of postaccident core cooling system response during performance of the Emergency Operating Procedures.

C-20 62

ENCLOSURE I Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 6 (This Attachment contained on the OSM)

EDCR 52421 Excerpt

LEGIBILITY EVALUATED AND EDCR 52421-A ACCEPTED FOR ISSUE. Page__

9Dre~LVA4 / ~AT L.N t)¶?ýeJ V_

01. SIGNATURE IJEN A A_

EDCR COVER SHEET Aw*(,& DATE J/ 7. I /

(d GENERAL INFORMATION Page No. 1 EDCR TYPE F-1 EDCR # Rev.

(Check One Box Only) [ EDCR-2 # 52421 Rev. A EL Check here if this is a Streamlined EDCR.

[] Check here if this EDCR is for Documentation change only & No construction work is required.

[j SR Li QR Check appropriate box if field material procurement quality requirements included.

92,99,235,261 RXB, AUX, 702, 737, 729, 278,293,55 CTL, AEB 755, 759, 757 SR I&C N/A System Building Elevation Quality Lead Code/Class Class Discipline WORK SCOPE STATEMENT:

Replace unqualified Westinghouse Source / Intermediate range Neutron Monitoring system with a Reg Guide 1.97 qualified system from Thermo-Fisher Scientific, procured under contract 75148. Detailed Workscope is contained on the following pages.

PREPARE VERIFIED:

Aaron Trelease 865 632-75 Design Engineer/'-\hne Dt Engineer aDate' I APPROVALS:/ j I INTER DISCIPLINE REVIEWS:

Civil E nMc ,er Date

-- lCtivil EGI S Dt I&C Engineer- Date Electric/ Engineh V A CUOe35 Oate I N/A NIA 7 Mechanical EGS Date Mechanical Engineer Date N/A N/A Plant Design EGS Date Plant Design Engineer D t Project Engineering Manager Date Project QA Manager IDate ACCEPTANCE: OTHER ORGANIZATIONS:

N/A Responsible Superintendent Date Signature/Org'n.: Date N/A Fd En eer Date Signature/Org'n.: Date N/A

(-1 .A40 TA KEngi berinag Manager Date Signature/Org'n.: Date Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page I of 9

EDCR 52421-A Page la EDCR COVER SHEET GENERAL INFORMATION Page No. la EDCR TYPE EEDCR # Rev.

(Check One Box Only) [ EDCR-2 # 52421 Rev. A El Check here if this is a Streamlined EDCR.

E3 Check here if this EDCR is for Documentation change only & No construction work is required.

U SR [] QR Check appropriate box iffield material procurement quality requirements included.

92,99,235,261 RPB, AUX, 702, 737, 729, 278,293,55 CTL, AEB 755, 759, 757 SR I&C N/A System Building Elevation Quality Lead Code/Class Class Discipline WORK SCOPE STA TEMENT:

Replace unqualified Westinghouse Source / Intermediate range Neutron Monitoring system with a Reg Guide 1.97 qualified system from Thermo-Fisher Scientific, procured under contract 75148. Detailed Workscope is contained on the following pages.

1PREPARED: VERIFIED:

Aaron Trelease (865) 632-7519 Design Engineer Phone Date Engineer Date APPROVALS: INTER DISCIPLINE REVIEWS:

C eEngi PPnr, D Civil EGS Date Civil Engineer Date I&C EGS Date l&C Engineer Date Electrical EGS Date Electrical Engineer Date N/A N/A Mechanical EGS Date Mechanical Engineer Date N/A N/A Plant Design EGS Date Plant Design Engineer Date Project Engineering Manager Date Project QA Manager Date ACCEPTANCE: OTHER ORGANIZATIONS:

N/A Rsonsible Superintendent -'Dar'e Signature/Org'n.: Date N/A Field Erfglne-er Ali Hemmati Date Signature/Org'n.: Date N!A TVA Engineering Manager Date Signature/Org'n.: Date Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 1 of 9

EDCR 52421-A Page I-EDCR COVER SHEET (CONTINUED)

EDCR# 52421 Rev. A Page No. 2 WORK SCOPE STATEMENT (CONTINUED):

The currently installed Unit 2 Neutron Monitoring system is not qualified for post accident monitoring required by Reg. Guide 1.97. This EDCR replaces the unqualified Westinghouse system with Class 1E qualified Neutron Monitoring system and cable.

The following actions are required to upgrade the Neutron Monitoring System for Regulatory Guide 1.97 compliance (1) Remove the following existing unqualified Westinghouse source and intermediate range equipment supplied on TVA contract 54114 from the field if installed, and from MEL:

Remote:

2-NMD-92-NE31-D Westinghouse Channel 1 Detector Source Range 2-NMD-92-NE32-E Westinghouse Channel 2 Detector Source Range 2-NMD-92-NE35-D Westinghouse Channel 1 Detector Intermediate Range 2-NMD-92-NE36-E Westinghouse Channel 2 Detector Intermediate Range (2) Install qualified Thermo-Fisher Scientific equipment procured under contract 75148. (Reference MR#

25402-011-MRA-JA37-00001). Construction is to notify RADCON prior to installing or moving the detectors.

Remote 2-NMD-92-131-D Channel 1 Detector (Source and Intermediate range) 2-NMD-92-132-E Channel 2 Detector (Source and Intermediate range) 2-NM-92-131-D Channel 1 Wide range Amplifier 2-NM-92-132-E Channel 2 Wide range Amplifier 2-NM-92-138-D Optical Isolator 2-TB-92-1 -E Channel 2 Junction Box 2-TB-92-2-D Channel 1 Junction Box 2-L-10 2-NI-92-138 Appendix R Wide Range Signal Processor 2-M-13 2-NI-92-131-D Channel 1 Source Range Signal Processor 2-NI-92-132-E Channel 2 Source Range Signal Processor 2-NI-92-133-D Channel 1 Shutdown Monitor 2-NI-92-134-E Channel 2 Shutdown Monitor 2-NI-92-135-D Channel 1 Intermediate Range Signal Processor 2-NI-92-136-E Channel 2 Intermediate Range Signal Processor Note: contact the Special Nuclear Material Custodian (SNMC) prior to movement of 2-NMD-92-131 -D and 2-NMD-92-132-E Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 2. of 9

EDCR 52421-A Page (3) Delete the existing cables and internal wiring associated with the Westinghouse source and intermediate range equipment (4) Add the new cables and internal wiring required to implement the replacement of the existing Westinghouse source and intermediate range equipment with the new Thermo-Fisher Scientific equipment.

(5) Control Diagram 2-47W610-92-1 has been created to reflect the configuration of the Neutron Monitoring System (6) Schematic Diagrams 2-45W600-92-1 and 2-45W600-92-2 have been created to reflect the configuration of the source and intermediate ranges of the Neutron Monitoring System.

(7) New UNIDs have been assigned for the new Thermo-Fisher Scientific source and intermediate range neutron monitoring equipment.

(8) The remaining UNIDs for the current Westinghouse system have been deleted.

Construction shall provide U2 operation labeling group all required data (MEL, drawings, DRAs) requiring ID tags / labels needed for completion of this EDCR.

The cables that will be installed as a part of this EDCR will be pulled via bulk cable pull packages. The following list of cables identifies the new cables added to support this EDCR. Each cable number is listed by its Cable ID number, and the bulk cable pull package that will physically pull the cable.

Cable Pull Package Cable Pull Package 2NM2330E EDCR54637 2NM2344D EDCR54637 2NM2331 E EDCR54639 2NM2345 EDCR54637 2NM2332E EDCR54639 2NM2346 EDCR54637 2NM2333D EDCR54637 2NM2347 EDCR54637 2NM2334D EDCR54639 2NM2348 EDCR54632 2NM2335D EDCR54639 2NM2349 EDCR54632 2NM2336E EDCR54637 2NM2350 EDCR54632 2NM2337E EDCR54637 2NM2351 EDCR54632 2NM2339D EDCR54637 2PV326D EDCR54636 2NM2340D EDCR54637 2PV327 EDCR54636 2NM2341 D EDCR54637 2PV328D EDCR54636 2NM2342D EDCR54637 2PV329E EDCR54636 2NM2343D EDCR54637 2NM2338E EDCR54637 Special Precautions to the Unit I Interface:

EDCR-2 52421 is based on the 0-TI-2 (revision 0) and 25402-3DP-GO4G-00081 (revision 5) procedures. The package installs equipment in an area that contains Unit 1 operating equipment. The installation of this equipment should have no adverse affect on Unit 1 operating equipment or common systems and components.

This EDCR installs a wide range amplifier in Panel 2-L-10 In the auxiliary control room. The following items are Unit 1 associated devices. These items are energized and are required for Unit I operation. Do not touch them, and use caution when working in their vicinity.

2-FI-67-61 C 2-FI-70-159C 2-FI-67-62C 2-HS-70-63C 2-LI-70-63C 2-HS-70-66C 2-LI-70-99C 2-PI-70-17C 2-FI-70-164C Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 3 of 9

EDCR 52421-A Page 4 In addition, connections will be made to 120V AC Vital Instrument Power Boards 2-1 and 2-11. DCN 52602 moves interface points from the terminal blocks to the breakers in the 120 VAC Power Boards 2-1 and 2-11, as well as changing terminal blocks L3A & L3B designations from non-safety related to safety related. DCN 52602 is a prerequisite to EDCR 52421. The following breakers will be utilized on Vital Power board 2-1: 18, 30, 45 and

46. On Vital power board 2-11, Breakers 45, and 46 will be used. The Vital power Boards are considered Unit 0 boundaries, and extreme caution must be taken to avoid interfering with the operating plant equipment. The connections to these boards will require outage conditions.

New Thermo Fisher Equipment Channel 2 2-NMD-92-132-E 2-NM-92-132-E 2-NI-92-136-E 2-NI-92-132-E 2-NI-92-134-E 180 degrees Az FIlEL729 M-13 M-13M-13MCRM-13 M-13 Detector well Addtnl equipt bldg MCR MCR M or Amplifier IR Monitor SR Monitor 2-NI-92-138 L-D Channel 1 AC R App. R Monitor 2-NMD-92-131-D 2-NM-92-131 -D 2-NM-92-138-D 2-NI-92-135-D 2-NI-92-131-D 2-NI-92-133-D 0 degrees Az FI EL 737 FI EL 737 M-13 M-13 M-13 Detector well Aux bldg Aux bldg MCR MCR MCR Amplifier Optical Isolator IR Monitor SR Monitor SD Monitor This EDCR will install the Unit 2 Source and Intermediate Range Neutron Monitoring System for Unit 2, replacing the obsolete Westinghouse system with an upgraded system that is reg guide 1.97 compliant. Unit 1 work was performed under DCN 03206.

Due to the nature of the differences in core orientation between Unit 1 and Unit 2, the NIS channels will follow the placement of the core geometry (see figure below), rendering the placement of the detectors opposite to Unit 1 in terms of the containment. This change will propagate through the setup and routing of the installed system, and will create a unit difference (see the unit difference form.)

Unit 2 Channel 1 Wide Range Amplifier [2-NM-92-131-D] shall be mounted in a similar manner to the Unit 1 Channel 2 Wide Range Amplifier, at elevation 737' in the Aux Building on the Unit 2 side of spent fuel pit heat exchanger room. Mounting the wide range amplifier in this location will require the relocation of a fire extinguisher. Mounting details shall be in accordance with the vendor documents, civil DRAs and seismic calculations. The mounting of the amplifier and optical isolator are seismically qualified under WCG-ACQ-051 1.

Unit 2 Channel 2 Wide Range Amplifier [2-NM-92-132-E] shall be installed in a manner similar to the Unit 1 Channel I Wide Range Amplifier in the additional equipment building room A15 approximately 15 feet off the floor. Note that as of January 2 0 th 2010, the wall that contains door A214 (an access to additional equipment Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 4 of 9

EDCR 52421-A Page  !

building room Al 5) is part of the ABSCE boundary. The mounting elevation for the Wide Range Amplifier is due to the requirement that source range instrumentation equipment be above the design basis flood plain, and shall be accessible during the flood. In order to comply with Design Criteria WB-DC-40-29, when the reactor vessel head is on, the source range neutron flux level shall be available to verify that decay heat in the reactor core is being safely removed by natural circulation in the reactor coolant loops. The criteria states that the maximum flood level is 736.9 feet, and mounting the device lower would subject it to be lower than design basis flood levels. The amplifier is housed in a spray-tight NEMA-12 enclosure, which is not qualified to operate submerged. The equipment will therefore be mounted in a manner similar to Unit 1, above the design basis flood plain.

Optical Isolator [2-NM-92-138-D] shall be mounted along with the Unit 2 Channel 1 Wide Range Amplifier at elevation 737' in the Aux Building on the Unit 2 side of the spent fuel pit heat exchanger room. The Optical Isolator's function is to isolate the signal from the Wide Range Amplifier, and send the signal to the Wide Range Signal Processor in the Auxiliary Control Room to provide neutron indication in the case of an Appendix R event that causes evacuation of the MCR. The decision was made to keep the Optical Isolator associated with Channel 1 so that the Wide Range Signal Processor in the L-1 0 panel is associated with the same core location as in Unit 1.

In Unit 1, the Optical Isolator's classification is safety related and 1 E but not EQ. The Optical Isolator is qualified by the vendor to the same conditions as the Wide Range Amplifier, and is contained in a similar.

NEMA-12 enclosure as the amplifier. The Unit 2 Optical Isolator will be in a harsh environment. Calculation WBNOSG4027 will be updated to reflect the addition of the Optical Isolator to a harsh environment, and is listed as an open item in the package.

Wide Range Signal Processor [2-NI-92-138] shall be mounted in panel 2-L-1 0 in the Auxiliary Control Room.

The purpose of this device is to satisfy 10CFR50 Appendix R or Branch Technical Position CMEB 9.5-1 (fire in the control room) remote shutdown monitoring requirements. The cutout shall be revised under EDCR 53338, while EDCR-2 52421 shall address the mounting. The Wide Range Signal Processor shall be mounted in place of the Westinghouse backup source range drawer and utilize the existing Westinghouse slides. The mounting of the signal processor to panel 2-L-1 0 and the structural integrity of the panel areseismically qualified under calculation: WCG-ACQ-0427.

The Signal Processor is mounted in a different location in the panel as Unit 1. The reason for this is that in Unit 1, Gamma Metrics / Thermo- fisher Scientific equipment had not been used to start up the plant, so the existing backup Westinghouse Source Range Drawer was kept in the plant to monitor the plant in case of a failure of the Gamma Metrics equipment. The Unit 1 Gamma-Metrics equipment has demonstrated its reliability, and the system has been used in Unit 1 startup operations successfully in the past, so the Westinghouse Backup Source Range Drawer is no longer needed. This device has been removed from the plant, and will be replaced physically and functionally by the Wide Range Signal Processor.

Source I Intermediate Range Signal Processors, Channels 1&2 shall be mounted in panel 2-M-13. The existing unqualified Westinghouse drawers were physically removed from panel 2-M-13. The drawers will utilize the existing Westinghouse slides for mounting purposes. Unit 1 added seismic screws to the signal processors for additional security. This change will be implemented in this EDCR. Mounting hardware will be supplied by Westinghouse under WBS: 3.2. Currently, there are no shutdown monitors installed in 2-M-1 3, and this is new equipment that will be installed per this package. The shutdown monitors are provided on a standard 19-inch mounted plate to mount the monitors. The mounting of the source/ intermediate range drawers and shutdown monitors to panel 2-M-1 3 and the panel structural integrity are seismically qualified by Westinghouse report WBT-D-0524. The anchorage of the panel is seismically qualified under calculation WCG-ACQ-0516.

Addressed UNIDs:

2-NI-92-135-D Channel 1 intermediate range monitor drawer (2-M-1 3) 2-NI-92-136-E Channel 2 intermediate range monitor drawer (2-M-1 3) 2-NI-92-131-D Channel 1 source range monitor drawer (2-M-13 Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 5 of 9

EDCR 52421-A Page b 2-NI-92-132-E Channel 2 source range monitor drawer (2-M-1 3) 2-NI-92-133-D Channel 1 shutdown monitor (2-M-1 3) 2-NI-92-134-E Channel 2 shutdown monitor (2-M-13)

UNIT 1 UNIT 2 N

CHANNEL I CHANNEL II CONTAINMENT 1801. GEOMETRY 180-

.9Q' WY2 270O Z7 0' 270 90 90 0* 0*

\, CORE QEOMETRY.-/

CHANNEL II CHANNEL I Documentation Review:

Calculations WBN-OSG4-051 (single failure analysis for RG 1.97 category 1 variables), WBN-OSG4-076 (Determination of category 1 RG 1.97 variables requiring trend indication), WBN-OSG4-082 (Basis for RG 1.97 R2 type B and C Variables Determination), and WBN-OSG4-112 (RG 1.97-type D Variable selection) were reviewed for Unit 2 applicability, and no action was found necessary. Calculation WBN-OSG4-1 11 (Regulatory Guide 1.97 category 1 and type A, B, C, D variable required range and accuracy determination) was reviewed for changes needed, and will require revision for Unit 2 applicability.

Appendix R:

System 092 is a required Appendix R system. Replacement of the obsolete equipment with upgraded components is being implemented to ensure that redundant components are in accordance with Appendix R separation requirements and will be included in the new fire protection report. A single wide range signal processor is being added in the auxiliary control room to satisfy 10CFR Appendix R (fire in the control room).

Cables and conduit will not be pulled via this EDCR, and therefore, fire and hazard barriers will not be impacted.

The addition of combustible loading in each fire zone is 4 lbs or less and thus does not create an Appendix R concern.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 6 of 9

EDCR 52421-A Page.*

Post Accident Monitoring:

The currently installed Unit 2 Neu*-pn Monitoring System is not qualified for Post Accident Monitoring (PAM) required by Reg. Guide 1.97. Thtis EDCR replaces the unqualified Westinghouse system with Class 1E qualified Neutron Monitoring system and cable.

The new Thermo- Fisher Scientific equipment is PAM category 1. The system is evaluated under calculations WBNEEBIDQ29990901 and WBNEEBIDQ29990903.

General Construction Notes and Design Implementation The vendor assembly drawing for the system, 900231, shows the system interconnection and the mounting details for the detector assemblies. Each of the assemblies is first mounted in its permanent location and then the assemblies are interconnected. Construction should mount the assemblies and route the cables with the aid of the Vendor Manual and use Thermo-Fisher Scientific Field service for interconnection, powering and checkout of assemblies in each channel.

The detector assemblies are delivered ready to install and with the ends of the cables prepared for the connectors and covered with packing. The connectors are provided in separate plastic bags. Care should be taken to protect the cable ends from being bent or damaged.

Notes:

1. The cable must not be damaged and the detector assemblies must be handled carefully to prevent accidental damage, especially to the area where the cable exits the detector.

2. System isolation from plant ground must be maintained. Great care should be exercised when handling the detectors to avoid kinking the associated detector cables. Each detector assembly with integral cable and the junction boxes must be installed isolated from plant ground. They should all be verified as isolated from plant ground with insulation resistances of greater than 105 Ohms at 50 volts. For mounting details and part numbers, refer to the vendor assembly drawing list and outline drawings in the vendor manual.

3. Due to the very low level input signal, the Wide Range Amplifiers are highly sensitive. To avoid excessive source range noise, it is important to use care in routing the amplifier cable assemblies. The following precautions must be observed:

a. The cable assemblies must be physically separated from all power-handling cables by a minimum of 5 feet at all points where they are not enclosed by conduit.

b. The cable may be routed in instrumentation-only cable trays provided that no annunciator or relay signals are carried by other wiring in the trays. Such signals are proven noise generators.

c. The cable must remain physically separated, by a minimum of 5 feet, at all points from cables supplying control rod or control rod drive mechanisms.

d. The signal wires should be kept separate from power cables inside the electronic enclosures and should be run in separate conduits between enclosures.

e. When attaching conduits to the electronic enclosures, enter the enclosure as close as possible to the destination terminal block to eliminate excess wire lengths inside the enclosures.

f. The enclosures should be tied securely to the plant ground with a ground strap.

g. The ground termination on the power terminal block should be tied securely to the plant ground.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 7 of 9

EDCR 52421-A Page S Installation can be broken down to those actions normally preformed by Construction, and the actions normally preformed by Thermo-Fisher Scientific Field service.

OPERATIONS TO BE PERFORMED BY CONSTRUCTION:

- Installation of detector assemblies and junction boxes, routing of the detector cables, and ensuring that these components are isolated from ground.

- Installation (mounting) of the electronic boxes: Wide Range Amplifiers and Optical Isolator

- Installation (mounting) of the source range signal processors, the Intermediate Range Signal Processors, and the Wide Range Signal Processors, and the shutdown monitors

- Installation of AC power to equipment (do not power up until inspected by Thermo-Fisher Scientific field service.)

- Interconnection between the Wide Range Amplifiers, Optical Isolator, Signal Processors, and customer-connection to the equipment outputs.

OPERATIONS TO BE PERFORMED BY THERMO-FISHER SCIENTIFIC:

- Routing of cable ends into the junction boxes for the detector cables and in-containment cable assemblies and installation of the cable-end connectors to the junction boxes.

- Connection of triaxial connectors to the penetrations (in-containment and amplifier cable assemblies).

- Installation of the amplifier cable-assembly connectors for connection to the preamplifiers.

- Cable checkout using a megohmeter or time delay reflectometer (if required) and verification of cable isolation from ground.

- Application of power and inspection of equipment.

BACKGROUND:

Unit 1 upgraded the corresponding Neutron Monitoring System from Westinghouse to Gamma- Metrics equipment under DCN 03206. This change was implemented because the existing Westinghouse equipment was not qualified for post accident monitoring as identified in 10CFR50 Appendix A criteria 13 and 19, and identified in REG Guide 1.97. DCN 03206 completed all support work, including installing the system, revising panel cutouts, revising annunciator windows, routing cables, moving conflicting equipment, installing cables, etc. EDCR 52421 will focus on the physical installation, interconnection and mounting of equipment. The remaining work is covered by other EDCRs as follows. Cable routing will be covered by EDCRs 54637-A, 54639-A, 54632-A, and 54636-A. Panel 2-L-1 0 will be revised by EDCR 53338. Annunciator windows are revised under EDCR 52315.

Several DCNs subsequent to DCN03206 have modified the unit 1 system. EDCR 52421 evaluates and incorporates relevant information from these DCNs as follows.

DCN 51239-A re-ranged the Unit 1 source range instrumentation due to the increase in boron concentration in the reactor coolant system during startup and refueling conditions. The increase in boron concentration is required to support the tritium production program. It was determined that Unit 2 should also incorporate this change in order to maintain unit consistency, and to address core improvements (low core leakage).

DCN 36179-A provided local neutron flux indication by implementing the capability to temporarily move the Wide Range Signal Processor from panel 2-L-1 0 to connect it to the amplifiers. This change was required for Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 8 of 9

EDCR 52421-A Page Unit 1 because of the concern that the power supply to 1-NI-92-138 and the D-channel Optical Isolator, as well as the signal circuits to the E-channel Short Range/intermediate Range Amplifier, could be lost simultaneously during an Appendix R event. Previously mentioned cable-routing EDCRs are routing cables such that there is no Appendix R concern, therefore this DCN will not require incorporation into Unit 2.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-005 Page 9 of 9

EDCR 52421-A Page Ig.

9 EDCR UNIT DIFFERENCE FORM EDCR# 82421 Rev. A Page No. 2L4 Operations Difference Is Identified as follows:

WBN Unit 1 currently has the Gamma-Metrics source intermediate range system model RCS-300, This model is obsolete, so Watts Bar Unit 2 will receive the new 3001 NFMS (neutron flux monitoring system). The 3001 system has several upgrades to the RCS-300.

Sourge Range / Intermediate Range Sianal Processor Imorovements:

• The source and Intermediate signal processors come with upgraded bar graph liquid crystal displays, as the Unit 1 analog meters are obsolete.

• In Unit 1, the source and Intermediate range signal processors have "Counts per second "or "Percent power level" displays, respectively. Unit 2 source and intermediate range signal processors come with "Decades per minute" on the drawer fronts in addition to the other displays.

" The selector knobs for Unit 2 on the Intermediate range signal processor are set up differently than on Unit 1.

There are a total of 3 dials on Unit 1, including level trip, adjust, and operation selector. On Unit 2, there are a total of 5 knobs, including test selector and output selector in addition to those previously mentioned.

" The shutdown monitor on the Unit 2 side will not contain an alarm reset button, which was used to manually disable the alarm during the drawer latching process. The alarm reset function is now obsolete, as this feature can be handled at the annunciator.

" Training differences will be required due to this upgrade. Detailed Information on the new equipment can be found In the Thermo-FIsher Scientific vendor manual for the source/Intermediate range neutron monitoring system.

The wide range signal processor In panel 2-L-10 will be in a different location than in Unit 1. The backup source range drawer is being removed from 2-L-10 due to obsolescence, and the wide range signal processor will be mounted In Its place.

In Unit I .due to Improper cable routing, there was a potential for both channels to be functionally disabled due to a possible appendix R event. To address this, unit 1 provided the ability to remove the wide range signal processor from the auxiliary control room, and take the device down to get signal directly from the channel 1 optical Isolator, and get power from channel 2 amplifier. Unit 2 will rout cables for the device in such a way that appendix R will not be a concem.

Operations should be aware that it is no longer required to move the wide range signal processor for Unit 2. Quick disconnects in the optical isolator, channel I amplifier and wide range signal processors are not required in unit 2, and will not be In'alledJo %qisEDCR.

1.:

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IJhIt7TVA Operatlont Acceptance (Mgropr Designee): -" Date: ' /

Refer to the electronic documents In TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081-005 Page I of 3

EDCR 52421-A Page 2-5 Maintenance Difference Is Identified as follows:

The Upgrade to the Unit 2 neutron monitoring system creates several unit differences that maintenance must be made aware of, including modified locations for the channel 1 / channel 2 equipment, and upgrades In testing methodology and equipment.

Front panel output selector switches allow source and intermediate level signals and all bistable set points to be read from the front panel test jacks with a 0-10 VDC test meter without having to rack out the drawers..

• Unit 2 equipment will employ new 6-point testing methodology, which is an improvement to the existing 4-point testing methodology of Unit 1. The maintenance and calibration procedures will need to be modified utilizing the vendor manual to reflect this upgrade.

The new design for the source and Intermediate range neutron monitoring system allows for the technician to conduct normal surveillance activities on the drawer without having to rack out the drawer. This functionality is reflected In the setup of the controls. While the Unit 1 system featured fuses on the front panel for control and instrument power, the Unit 2 300i system will feature circuit breakers on the back for control and instrument power. For more Information concerning the maintenance and functional testing of the equipment, consult the vendor manual.

The indicator lights between Units 1 and 2 signal processors are the same, with the exception of the intermediate range non-operate indicator. On unit 1, there was a single non-operate light, whereas unit 2 will feature with Indication for amplifier non-operate, and for SR/IR non operate. This additional indication will simplify troubleshooting for the technician.

• Watts bar Unit 1 has wired card edge connectors on the Signal Processors, Whereas the Unit 2 system signal Processors will have printed circuit card backplanes. For more Information concerning calibration, testing and maintenance, consult the vendor manual.

-)

11 Refer to theelectronic documents In TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 -005 Page 2 of 3

EDCR 52421 -A Page

'Engi-neerding Difference is identified asfoJlow...%

T TT.hechanrel I wide range amplifier and optical Isolator will be mounteditin the auxiliary building, floor elevation 737'. In:.:,

Unit 1, thecdevices were mounted inth eadditiona equipment builing, room A4 Thisidifference in relative location is due to the re*versed core orentationh of Unit :2.Seethe :EDCR work scope statement for more information.

The.ch6lannel 2 wide range. ampifir is. moU nte in th e Unit:2. Additinail Equipmet. building, Room.MA5;. Th e Un it I

• channel 2 wide range amplifier was mounted inthe Auxiliary building, floor elevation 737'.. This dcifference is due to the

.reversed corýdeoientation o.6f Unit 2. Seew wrk scope statemenht for more-informa~tion.

As.'tientio~ned, WBN Unit 1 currently ýhas. the Gamm*a-Metrics aorc inttermediate range systemn model RCS300.ý This Model is obsolete, andnthe new i (Nutrn Fiu monitogbentaled ystFem I in Unit.2...The system will retain all. of the fu ncti.0na!ity of the Unit ...I syst The fo1lwing differences are listed as improv*ments-over the Unit system:

.. Bettercables: The-Unit 2 vendor cable assemblies (2.01712 and 201722) feture hiermetic seals for -fixed center pin:

.alignTent relative to thepoaxial shieldecastle'1 for better Amphenol Taxia penetration cnneions.

S Better juncti onb.oxes: the"Unit 2.junction boxes inthe new sys m er-test.fitting that. io:n -add.v f cimplete evacuation and backfill; improving Its initial installation.

• ,Better Amplifier High VoltiagePower Suippy (HVPS) UnittIhal,2~generation poweirdesigns (000288-001),that failed high to 000 Vdc: Unit 2 will be provided with the.latest 20ý0460rev H:models.

.Watts bar Unit I has wired card edge. connectors on'the signal processors, whereas thebUnit 2 systemp signal processors wilhav pited circuit card backplaes 0, Ciruit breakers:gthesigl pr(cessors onrWattsBar Unit.Ihave AC power fuses on the front panel, whereas the Unit 2

- system has rear panel1 AC circuit breakers.,

• Cable interconnection between wide range amplifier and source I intermediate range signal processors wil be slightly - .

dif far nt. Whereas Unit i Interconnected ables betweenboth amplifier and source and intermediate range drawers, Unit 2, cablesill M alifi ie to the intermediate range signal pr ssor.:From there the cables interconnect

t. tho source range.signai represets.no difference in. perationshor mainteance,.andrepresents an improvem.ent on theUnit I system..

S WB:.!, nitIsgna procesorse had Gamnma -t.P'ak.isolator2002*6-101 along with resistive bffered outputs,. ile Unit 2 will have the improved 101033 series.quad isolators with separately isolated *utputs.

' WSN Unit 1isignal piocessors originally had*1600022 series log amplifiers ilater upgraded to 100623-101 series. Unit 2

will .hav.e.Improved ,i00950 srelog ampl ifiers.

S" The unit 2 front panel trip and priSsive indicators on the SR IIRdrawers will. have low voltage DC LED indicators.

This is a significanit Improvement over the Unit 1 120VAC incandescent jindicators, as the LEbs' last longer. have lower, power requirements and have a different failure mechanism in that theymfadeaway instead of burning out. This is an improvement because tiheoperator can now tell whena light is goingbadinstead of having to react when the light. goes out.'

.* Signal procesorswillfeature improvedtesting methodology, allowing normal surveillance activities to be completed With a 0- OVDC test meter from the front of the"proceessor without the need to rack out.the drawer.

' Due to the pressure test fitting on the front of the vendor supplied junctionbox, the unit 2junction box that Will house the vendor supplied junction,box will need to bedeeper. An equivalent junctionboxwill beobtained for unit 2with a deper dimaensIon to tousethe pressure test fittinga..

Due to cable routingUnit . had-to.create the.abiity move the wide range signal procesr to the field for emergencyy..

neutron monitoring due to an appendixgR iSsue (see Operations differences). Unit 2 :cbles willbe routed properly, and that fu*nctionali will not ber*euired.. Theriefore,.equipment corresponding to this design. change (including quick

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disconn6t~t~ wid rang sgaprocessor and optical isoliator) ar o eddfrnu Unt 2.

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Uni-..v TVA nieering Accetance (Mgr orDesignee):: : :: ::  :: : Date:

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SE1SG1TO ROUTE A COPY OF THIS ICEN S iN G : *:.***:* *:*****:**:****:*:**i*::

• *::L COMPLETED FORM TO TVA TRAINING MANAGER AND TO UNIT 2**::

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R Approved byt  : TA Oversight Wn A

Refer to the electronic documenhts in TVA business Suppoirt Library .(BSL) for current revision.

25402-ZPýGCKGý00081-.006  ::Page 3..of 3.

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 7 (This Attachment contained on the OSM)

EDCR 52987 Excerpt

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Ur-EDCR COVER SHEET GENERAL INFORMATION Page No. I A EDCR TYPE 0 EDCR # 52987 Rev. A (Check One Box Only) E5 EDCR-2 # Rev.

0 Check here ifthis EDCR Is for Documentation change only &No construction work is required.

[ SR E0 QR Check appropriate box Iffield material procurement quality requirements included.

ASME Class1; 1E; 068 RB Various SR I&C seismic cot 1 System Building Elevation Quality Lead Code/Class Class Discipline WORK SCOPESTATEMENT:

Installs new thermowells and RTD's for the RCS hot and cold legs on unit two. Originally unit I and 2 were equipped with a bypass line around the steam generators and RCPs to measure temperature. This was modified in unit I Into the current configuration. Westinghouse is procuring thermowells and RTDs and performing thermowell welds under WBS 2.6.1.9 I PREPARED: Mat Merten VERIFIED: Charles Fisher Design Engineer Phone Date Engineer Date APPROVALS: FINTER DISCIPLINE REVEWS:

Civil EGS Date CiilEnneer Dat I&C EGS Date I&C Engineer Date Electrical EGS Date Electrical Engineer Date Mechanical EGS Date Mechanical Engineer Date Plant Design EGS Date Plant Design Engineer Date Project Engineering Manager Date Project QA Manager Date I ACCEPTANCE: OTHER ORGANIZAT7ONS:

-Responsible Srup§ntendent Date Signature/Org'n.: Date

/Field Engineer M e Dite Signature/Org'n.: Date TVA Engineering Manager Date SignaturelOrg'n.: Date Refer to the electronic documents in IVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-003 Page 1 of 1

EDCR COVER SHEET GENERAL INFORMATION Page No. I P EDCR TYPE [ EDCR # 52987 Rev. A (Check One Box Only) El EDCR-2 # Rev.

El Check here ifthis EDCR is for Documentation change only & No construction work is required.

Z SR fl QR Check appropriate box iffield material procurement quality requirements included.

ASME Class 1; IE; 068 RB Various SR I&C Seismic Cat 1 System Building Elevation Quality Lead Code/Class Class Discipline WORK SCOPE STATEMENT:

Installs new thermowells and RTD's for the RCS hot and cold legs on unit two. Originally unit I and 2 were equipped with a bypass line around the steam generators and RCPs to measure temperature. This was modified in unit 1 into the current configuration. Westinghouse is procuring thermowells and RTDs and performinq thermowell welds under WBS 2.6.1.9 I PREPARED: Mat Merten I I VERIFIED: Charles Fisher 632-6626 , I /o-fZ -9o7 Design Engineer - one ate I Engineer Date APPROVALS: I INTER DISCIPLINE REVIEWS: I __j to V3E1Z05 Civi-EGFDate *Civil Enoir *3*>. *- "z Date I&C EnierDate I& EGA&PJLL IJ8I' ~ a 0A~

~4ou~uLA 4AX~ 0 Chrll Ue 6u,i Mechanical Engineer I2j0/0 Date I 0

Plant De

• e Date Plant Design Enbine7r -' Date Priolct.Enginsering Mnae Dhte' Prject QA Manager ,V. 49,f~,* *,---; Dite /~*,P ACCEPTANCE: OTHER ORGANIZATIONS:

faeey- IiA Responsible Superintendent Date SignaturelOrg'n.: Date Field Engineer Date SignaturelOrg'n.: Date e TVA Engineering Manager Date Signature/Org'n.: Date 10ý1ývll Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081-003 Page 1 of 1

EDCR 52987-A Page: 2 Statement of Work EDCR 52987 - RTD Bypass Engineering - WBS 2.6.1.9 The Design Review Board and Final Design Review meetings have been waived by TVA.

The EDCR procedure 25402-3DP-GO4G-00081 rev 4 was reviewed and the sole correction made was to the Unit Difference Form. No other technical changes need to be made to this in-process EDCR.

Discussion: This EDCR completes the install of new thermowells and RTD's on unit two. This EDCR was initially part of EDCR 52326 - RTD bypass removal - but was split off into three EDCRs (the other is for FIS removal - 53188).

Originally unit one and two were equipped with a bypass line around the steam generators and reactor coolant pumps (RCP) to measure temperature. This was modified in unit I into the current configuration which utilizes thermowells installed in the hot/cold legs and RTDs placed inside the thermowells.

In unit 1, every loop has... In unit 2, each loop currently has...

- 3 Narrow range (NR) That 2 NR Th"at - being removed as part of EDCR 52326

- 2 NR Tcold 2 NR Tcold- being removed as part of EDCR 52326

- 2 wide range (WR) Thot 2 WR Thot

- 1 WR TCOId 1 WR Tcod Related EDCRs

- EDCR 52319 will install the Eagle-21 system

- EDCR 53301 will install all the external wiring for Eagle-21. This will pick up at the outboard side of the steel containment vessel penetrations.

- EDCR 52326 removes the bypass line (work is complete)

- EDCR 53756 installs thermocouples in pre-existing hot leg thermowells that feed the auxiliary control room.

- EDCR 54639 installs low voltage cabling in the reactor building. This is a co-requisite to this EDCR Applicable DCNsIECNs The package that did the bypass elimination effort for unit 1 was the ECN Modification package ECN El10012.

DCN S08146 - added that the WR Tcold RTDs are required for Regulatory Guide 1.97 Post Accident Monitoring. The following items were physically or administratively done and must be accounted for within this EDCR

- Revise "I-tabs" - this is being done with the MEL package.

- Revise Demonstrated Accuracy Calc 1-TE-68-001 - this is being done as an open item

- Revise the 1 QCFR50.49 list to add PAM designators to the conduit seal assemblies. This is being done by the Electrical group's MEL package.

EDCR 52987-A Page 3

- Revise system 68 category and operating times calculation WBN-OSG4-017 to incorporate the PAM category and operating times (WBN-OSG4-049). This is being done as an open item.

o This calculation has a UVA that all unit 1 design changes will be made to unit 2 via EDCRs and DCNs. This calculation is applicable and has been added as an open item.

DCN S018147 - added that the WR Thot RTDs are required for Regulatory Guide 1.97 Post Accident Monitoring. The following items were physically or administratively done and must be accounted for within this EDCR.

- Revise "I-tabs" - this is being done with the MEL package.

- Revise Demonstrated Accuracy Calc 1-TE-68-001 -this is being done as an open item

- Revise the 10CFR50.49 list to add PAM designators to the conduit seal assemblies. This is being done by the Electrical group's MEL package.

- Revise system 68 category and operating times calculation WBN-OSG4-017 to incorporate the PAM category and operating times (WBN-OSG4-049).

o This calculation has a UVA that all unit 1 design changes will be made to unit 2 via EDCRs and DCNs. This calculation is applicable and has been added as an open item.

Thermowells - The bypass line being removed by EDCR 52326 is connected to the loops in three places. The first was a set of three 2" connections between the vessel and S/G (hot leg).

The next was a single 3" line between the S/G and RCP (cold leg), and the last was a single 2" line between the RCP and vessel. See the as designed drawing 47W813-1.

- The 2 WR Thot and 1 WR Tcold thermowells in each loop currently exist and will be re-used.

These are not, and were never part of the bypass line.

- The 3 NR Thor thermowells per loop will be constructed from the three 2" connections where the bypass line connects between the vessel and S/G. These are 1200 apart with one connection at 00.

- I of the 2 NR Tcld thermowells per loop will be machined where the other 2" bypass line was - which was at the top of the pipe (or 0°). The other NR T,,d thermowell in each loop will be newly machined.

o In unit 1, loop 2, 3, and 4's NR T*,,dthermowells/RTDs are installed at the 12 o'clock and 10 o'clock positions while looking into the core. Loop l's are at the 12 o'clock and 2 o'clock positions.

o The Westinghouse FCN (WBT-D-318; FCN-WBTM-1 0764) will make loops 1 and 3 be at the 12 o'clock and 10 o'clock positions while loops 2 and 4 will be at the 12 o'clock and 2 o'clock positions. Bechtel Engineering believes this is acceptable because loops 1 and 3 flow clockwise while loops 2 and 4 flow counter-clockwise.

Note there is interference with the already existing loop 3 WR thermowell that forces this configuration.

A total of twenty thermowells will be machined in some capacity.

Thermowells and associated welds are ASME class 1.

Thermowells will be installed per Westinghouse's FCN (see index) and welding specification (see welding section).

EDCR 52987-A Page 4 3" Caps The predecessor EDCR 52326 left around 3 feet of the 3" pipe. This EDCR will cut this down before welding the caps. See plant design's DRA's and the associated FCN for details. The caps do not have UNIDs.

Installation of caps will be per Westinghouse's FCN (see index) and welding specification.

RTD's This EDCR will install 4 WR Thot and 4 WR TCod RTDs in the pre-existing thermowells. These will be RDF Corporation's model 21205. The other four remaining WR Thot (one per loop) sensors are thermocouples and are for the auxiliary control room. Installation of the auxiliary control room thermocouples are part of EDCR 53756.

This EDCR will install RTD's in each of the newly machined NR thermowells (three for hot and two for cold) for a total of five per loop. These will be RDF Corporation model 21465.

Therefore a total of 28 RTDs will be installed.

RTDs will be installed according respective sections of their associated technical manuals, already processed and approved in BSL. Construction notes have been added to DRA's 52987-001 through 004.

NR RTD model 21465 VR-WBC-0169 section 4.0 WR RTD model 21205 VR-WBC-0170 section 4.0 The pigtails will connect to their associated junction box. If there is excess cable, route and store excess cable in a coil box. All junction boxes exist, the coil boxes do not. The field will install the coil boxes per standard installation details 47A056-217 series. The coil boxes are safety related and mounted to seismic category I (note the boxes themselves were procured as quality related only, but mounted as safety related). These coil boxes were never assigned UNIDs for unit 1.

The exact location of the coil boxes will be determines by the field. There are multiple surfaces in these areas available for mounting. If the field determines that the boxes need to be mounted to high density concrete as defined in EDCR 52977 (mostly on the environmental shield wall in this vicinity), an FCR and Civil Engineering concurrence will have to be obtained prior to installation. There is open item 01-52987-11 for evaluation of mounting location by ESQ/civil.

The field will support the RTD pigtails in accordance to the instructions on Westinghouse drawings 3D20476 and 2650C31 along with Category I Support Conduit Typical drawing 47A056-200B. (Only deviation is to the Narrow Range RTD pigtails - 3D20476 is more restrictive in their support requirements at 24" between clamps vice 4 ft 6"). In order for the 15" requirement to the first support to be met, an additional support will need to be engineered.

This is a planned FCR. The Unistrut will be supported according to 47A051-46 series.

Conduit Seals The narrow range RTDs supplied by Westinghouse will have their own environmentally qualified conduit seals (Conax is the provider). This is like the arrangement for unit 1. These do not have associated UNIDs.

EDCR 52987-A Page 5 The wide range RTDs supplied by Westinghouse will not have conduit seals. These will be procured separately under MR 25402-011-MRA-EYM0-00002 from electrical. These seals have UNIDs, are part of the MEL package, and are separate EQ components. Construction is to install them according to detail F3 on AD drawing 45W883-3 (there is a DRA to change this drawing to make it like unit 1).

RTD Cabling There is no cabling in this EDCR.

Weldingq All welding will be done by PCI Energy Services, a subsidiary of Westinghouse Electric Company Welding & Machining, LLC. The welding will be in accordance with PCI's welding program and approved Westinghouse Equipment Specification 679170. (25402-011-ViA-MG00-01362-001).

Appendix R The WR RTDs are appendix R components.

Items to Procure Conduit seals (or Conax seals), coil boxes - electrical Open Items See open items form Acceptance Testing Acceptance testing will be handled by startup.

Applicable DC/DS/TS/ES

" WB-DC-40-36 The Classificationof Piping Pumps, Valves, and Vessels

• WBNP-DS-1935-2473 - ASME Section III, nuclearclass I piping system

• WB-DC-40-31.12 - Seismic/StructuralQualificationof Seismic Category I and I(L) In-line Valves and OtherIn-line Fluid System Components See section 2.3

• WB-DC-30-7 R22 - Post Accident Monitoring Instrumentation. Establishes that wide range Thot and Tcold are variables that fall under Regulation Guide 1.97. See table A-i, variable number 11, 12.

PERS in question

• 149850 - This PER started when a TVV downstream of the steam isolation valves began leaking nuclear steam in Browns Ferry. A huge analysis was done to find other TW in the plant that could cause similar problems. The concern is FIV - flow induced

EDCR 52987-A Page 6 vibrations - that is more of a concern for steam systems due to the higher velocity. All the other thermowells found to have potential for the same problem were all for the secondary system. Therefore this PER is not applicable to these thermowells since they are for the primary.

a 74383 o This began with a GE augmented task report T0316 "augmented main steam, feedwater, and recirculation TW Evaluation for Flow induced vibrations - FIV" o Looking at the list of TW that would need design change modifications, all were secondary TWs. This PER is not relevant to this EDCR.

• 145147 - Westinghouse RTD cables were not installed correctly according to the drawings. For example the drawings require no more than 24" separation, but this was routinely violated. This is applicable to the RVLIS RTD's o This appears to mostly be a construction issue, but there were not as good document control as exists currently so it was difficult to identify applicable vendor drawings.

0 172642 - Install RTD cables inflexible stainless steel conduits. This EDCR is resolving this PER Important Documents 47W813 RCS flow diagram - see both AD and AC drawings 2-47W610-68-1 to 4 Reactor coolant control diagrams - u2 2326D52 NR Tc thermowell for newly drilled 5365C47 NR T, boss for newly drilled 1836E26 NR T, install instructions for newly drilled 1847E84 NR Th thermowells 9558D95 NR Th scoops 1847E83 NR T, thermowell where bypass was 1871 E46 NR T, install instructions and nozzle where bypass was 5365C 17 Cap 2D33462 Nozzle and cap WBN2-PD-068-141-01 walkdown Flow diagram loop 1 WBN2-PD-068-141-02 walkdown Flow diagram loop 2 WBN2-PD-068-141-03 walkdown Flow diagram loop 3 WBN2-PD-068-141-04 walkdown Flow diagram loop 4 2-47w611-68-1,2,3 Logic diagram - inputs from the WR RTDs 45N2616-8 RTD wiring diagram U2 AD 45N1616-8 RTD wiring diagram U1 AC WBN2-E-275-485-00 R-2 walkdown WBN2-E-275-577-00 R-6 walkdown WBN2-E-275-589-00 R-10 walkdown WBN2-E-275-598-00 R-13 walkdown SSD-T-68-01 RCS Loop 1 wide range hot leg temperature (by Vý)

SSD-T-68-18 RCS Loop 1 wide range cold leg temperature (by )

SSD-T-68-24 RCS Loop 2 wide range hot leg temperature (by M SSD-T-68-41 RCS Loop 2 wide range cold leg temperature (by A SSD-T-68-43 RCS Loop 3 wide range hot leg temperature (by \

SSD-T-68-60 RCS Loop 3 wide range cold leg temperature (by M SSD-T-68-65 RCS Loop 4 wide range hot leg temperature (by W_0

EDCR 52987-A Page 7 SSD-T-68-83 RCS Loop 4 wide range cold leg temperature (by SSD-T-68-02 RCS Loop 1 delta T average (by VV)

SSD-T-68-25 RCS Loop 2 delta T average (by \

SSD-T-68-44 RCS Loop 3 delta T average (by )

SSD-T-68-67 RCS Loop 4 delta T average (by W)

AREAS OF RESPONSIBILITIES:

Control Systems - Lead on package Electrical

- Procurement of conduit seals, coil boxes

- MEL package conduit seals, coil boxes CivilIESQ

- Certification of safety related RTDs and their installation details. Approval of seismic reports from Westinghouse (open itemed).

- Approval of mounting of coil boxes.

Mechanical

- DRA for 47W813 RCS flow diagram Plant Design

- Piping removal related to this piping system is addressed in EDCR 52326 and documented in stress calculations as shown in the listed EDCR package. Loop modifications in addition to thermowells are addressed by Westinghouse's FCN.

WestinghouselPCI

- Procurement for thermowells, RTDs, bosses and caps

- Welding of thermowells and caps (Westinghouse has hired PCI Energy Services - contact is Barry Smith and Ileana Santiago)

- FSAR markups

rr-OCe -Sa`(84-A EDCR UNIT DIFFERENCE FORM EDCR# 52987 Rev. A Page No. 17

.Operations Difference is identified as follows:

In unit 1, loops 2, 3, and 4's narrow range.(NR) Ted thermowells1RTDs are installed at the 12*o'clock and 10 o'clock positions while looking into the corg. Loop I 's are at the 12 o'clock and 2 o'clock positions, In unit 2 Westinghouse's FCN (WBT-D-318, FCN-WBTM-1 0764) modifies this to make loop I and 3 the same (12 and 10 o'clock) and loops 2 and 4 the same (12 and 2 o'clock).

Due to the difference in orientation of the thermowells in unit I, loop I which is different than the rest has the lowest of all the loop temperatures for the ."B" RTD, or the RTD at 600 from the vertical. However, this difference is minimal. Using TVA's DataWare historical data program and examihing the temperatures and different times In life (Sep 2009, August 2005, and August 2002 were examined and plotted), loop l's "B" RTD is always the coldest, but sometimes by'0.1 0F, sometimes 0.5 0F, but never'greater than I OF from the next coldest.

In conclusion, the operational difference is that the "B" RTDs will have slightly different values than seen on unit

1. Bechtel Engineering believes this minimal difference shown by historical data to be no more that 10F is acceptable. "

f A Unlt2 TVA Operations A6¶%ptance (Mgr of Dresignee): *Oate" Maintenance Difference Is Identified as follows:

The same model number of RTDs will be used as in unit 1. There will'be no maintenance difference.

Dierencca UEngineeri (Mgr or Designee): /sflos Engineering Difference Is Identified as follows:

- The location of the NR TcoI thermowells compared to unit 1 (discussed in detail in the Operations section) is an engineering difference. The same components a~re being used so there will be no.weight differences. This difference is too specific to have any impacts to the System Descriptions (N3-68-4002 Reactor Coolant System and N3-99-4003 Reactor Protection System were reviewed) nor licensing basis documents.

- The thermowells and RTDs will have the same manufacturer and model numbers

- The coil boxes will have UNIDs, unlike the unit 1 -coil boxes.

'LIAK Qý-- Unit 2 TVA Engineering Acceptance (Mgr or Designee):

1u 0//("

Date:

Mat Merten 10115/09 Prepared By:-- Date:

SESG TO ROUTE A COPY OF THIS COMPLETED FORM TO TVA TRAINING MANAGER AND TO UNIT 2 LICENSING.

Streamlined EDCR approved by TVA Oversight 1 1 Refer to the electronic documents in TVA Business Support Library (BSL) for current revision."

25402-3DP-G04G-00081-004 Page v I of 1.

ENCLOSURE I Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 8 (This Attachment contained on the OSM)

EDCR 52601 (RVLIS) Excerpt

NRC RAI Letter 6/18/10 LEGIBILITY EVALUATED AND Attachment 8 ACCEPTED FOR ISSUE.

SIGNATURE DATE EDCR COVER SHEET ,

• 1 .. v A GENERAL INFORMATION Page No. 1 EDCR TYPE L] EDCR # Rev.

(Check One Box Only) 0 EDCR-2 # 52601 Rev. A 17 Check here if this is a Streamlined EDCR.

1- Check here if this EDCR is for Documentation change only & No construction work is required.

0 SR Z QR Check appropriate box if field material procurement quality requirements included.

068, 304, 663 RB/AB various SR I&C ASME class 2 System Building Elevation Quality Lead Code/Class Class Discipline WORK SCOPE STATEMENT:

Installs the unistrut, capillary, density compensating RTDs, and piping for the Reactor Vessel Level Indication System (RVLIS). The remainder of RVLIS, mostly consisting of local panel instruments, will be done on EDCR 55385. Reference Westinghouse contract WBS 2.6.2.7.

t VERIFIED:

-Mat &Mer~tenCPE 632-6626 Ni.tT-rcAEu_ A-miT.A-mo ,5/Z7//C)

Design Engineer Phone Date Engineer Date APPROVALS: INTER DISCIPLINE REVIEWS:

Civil , Date Civil Engineer ', 1.. ,*.,) Date FM4¶c)AaL# Ait~At rAo3 57Z.11 Date AN~t C, ?&A3CqAll-09 1I121l1 t P4/A Plantfresign EGS Date A/i1A Pant D'esign Engineer Date Project Engineering Ma~ager Ilatde DELETED

/v tA- Date ACCEPTANCE: I OTHER ORGANIZATIONS:

Rc*tsM-i M(Lvo.X5 *k Responsible f Ult~iendent Z, PO&t' Qe4UA.Q#eI4 tb (If Constructability Walkdown is Date Signature/Org'n.: Date waived, this is NIA)

S ee. poop Field Engineeti '.

t-c...

Date

/v1A Signature/Org'n.: Date (If C stru tability Walkdowr..s w/

T dAE*giisNeeIA)

TVA Engbineering ManagrDt Signattre/Org'n.: Date Refer to the electronic documents in TVA Business Support Library (BSL) for current revision. -~

25402-3DP-G04G-00081 EFFECTIVE 4-22-10 P lof-eLAACev1 oV A-1. 1.-

"/ttlia/h

• oJ( tev p{les o*f L')04- so

NRC RAI Letter 6/18/10 Attachment 8 EDCR COVER SHEET GENERAL INFORMATION Page No. I..

EDCR TYPE I] EDCR # _ _Rev.

(Check One Box Only) 0 EDCR-2 # 52601 Rev. A

[3 Check here ifthis is a Streamlined EDCR.

El Check here ifthis EDCR is for Documentation change only & No construction work is required.

0 SR 19 QR Check appropriate box iffield material procurement quality requirements included.

0680 304, 663 RB/AR various SR I&C ASME class 2 System Buiding Elevation Quality Lead Code/Class Class Discipline WORK SCOPE STATEMENT:

Installs the unistrut, capillary, density compensating RTDs, and piping for the Reactor Vessel Level Indication System (RVLIS). The remainder of RVLIS, mostly consisting of local panel instruments, will be done on EDCR 55385. Reference Westinghouse contract WBS 2.6.2.7.

PREPARED: VERIFIED:

Mat Merten, PE 632-6626 Design Engineer Phone Date Engineer Date APPROVALS: INTER DISCIPLINE REVIEWS:

Civil EGS Date Civil Engineer Date I&C EGS Date I&C Engineer Date Electrical EGS Date Electrical Engineer Date Mechanical EGS Date Mechanical Engineer Date Plant Design EGS Date Plant Design Engineer Date Project Engineering Manager Date DELETED Date ACCEPTANCE: EOTHER ORGANIZATIONS:

Y-i0"es C. C4 bai /O, Piponsible Superintendt-t (IfConstructabllty Walkdown Is Date Signature!Org'n.: Date waived, tjh1 N/e qs ' (2io Fiel n 9'er $ /2 //tY Date Signature/Org'n., Date (ifC nstructabllity Watkdown is waived, this Is N/A) iVA Engineering Manager teSgaulr'i.De D ate Signature/Org'n, Date Page -00fAV

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A Page 2 EDCR COVER SHEET (continued)

WORK SCOPE STATEMENT (CONTINUED):

The EDCR procedurewas reviewed and no correctionsneed to be made to the in-process EDCR to comply with the technicalrequirementslisted herein.

This EDCR is to install the first phase of the Reactor Vessel Level Indication System. The rest of the system will be installed in EDCR 55385 (this is being driven by the receipt of as-built hardware drawings).

Phase 1 (EDCR 52601) consists of

• Unistrut (reactor and auxiliary buildings)

• Capillary tubing

• Compensating RTDs

• Steel containment vessel penetration connection

" concrete shield wall sleeves(DCN 55050(ABSCE Reversal) is a predecessor for doing the work on the concrete shield wall sleeves)

• crane wall sleeves

• Piping (done by FCR)

Phase 2 (EDCR 55385)

" Local panel work

• Mounting rest of instruments

• Tee "above seal table"

• System Fill EDCR 55385 is a co-requisite to this EDCR.

Applicable WITEL codes are AP2 New EDCR XP9 ASME Related L19 FSAR CP1 1 Instrument Sensing Lines CP6 Equipment Seismic Qualification BACKGROUND:

Unit one and two RVLIS systems were designed with ECN 2329 in September 1980. ECN 5513 separated the two unit's RVLIS systems in 1985. From 1985 and 1987 unit 1 and 2 RVLIS systems were being designed separately. The last modification done to unit 2 was with ECN 6772. All subsequent modifications (ECNs and DCNs) were done on unit 1 only. RVLIS was partially installed in unit 2.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 3 of 10

NRC RAI Letter 6/18/10

• Attachment 8 EDCR 52601-A Page 3 EDCR COVER SHEET (continued)

This EDCR does not incorporate any electronic signal once it leaves any component and enters into Common Q (EDCR 52351) or Eagle 21. This EDCR begins at the tap upstream of each root valve for the hot legs and head, and at the seal table tee for the bottom connection.

The tee below the seal table for mid-loop monitoring will be installed with EDCR 53756; however Westinghouse is supplying it under the RVLIS WBS.

Changes made to unit one's RVLIS system

- DCN 51287 - Replaced RVLIS tee fitting at Seal Table with a Swagelok deep bore compression fitting. This tee is being installed under EDCR 55385.

- DCN 17371 - SCV (secondary containment vessel) penetrations have capillary tubes rigidly attached to them. DCN reworks tubes to provide sufficient flexibility at SCV attachment (Penetrations: X-084B, X-084C, X-084D, X-087B, X-087C, X-087D). This is to meet the requirements of N3E-934 3.21.2.3. Additionally this relieves the requirement of placing clips every 2ft 3in and allows 60 in while penetrating the concrete shield wall sleeves due to their depth.

" The requirement is to leave an extra 5" to the actual distance between the connections. No more than 18" can be used.

" Allows maximum span of 60" through the shield building sleeve since it is not possible to place clips within the sleeve.

I This is being accomplished with construction note #7 and #8 on DRA 52601-09 DCN 51459 - Replaced valve 1-RTV-068-0454A due to external borated water leakage. The change was for a same type valve. No modification necessary EDC 51844 - Provides alternate support design of the capillary tubing while it goes through the "refueling water canal". Has a two part clamp - see 47A052-43,43A,43B o DCN allows for an alternative connection on the top half of the mount via a separate bolt. It includes a sheet metal cover to the clamps and tubing.

o Change being incorporated

- DCN 16781 - Went through and made various repairs to the welding on the Unistrut. This correlates with the two calculations which qualified the capillary discussed later in this document. Change being incorporated with construction note on DRA 052601-09

- DCN 17380 -Adding new supports and welds to capillary trays. Change being incorporated with construction note on DRA 052601-09

- SCR WBNNEB8522RO (associated PER 143774) - SEE WRITE-UP IN "Affected PERS" SECTION OF THIS DOCUMENT

- DCN 30066 - In the vicinity of the Unistrut from train A's seal table connection there is the 10" cold leg injection pipe. During a pipe rupture, the Unistrut and capillary tube could undergo damage and thus extra supports were added. No action taken in this package. See routing capillary section for explanation and more details.

Affected PERS

- Significant condition report (SCR) WBNNEB8522 (tracked under PER 143774) stated that the RVLIS RTDs were not adequately qualified for chemical spray. The corrective action was to protect the pigtails from submergence and chemical spray by providing a qualified seal o Westinghouse is providing a Minco RTD with an ethylene propylene rubber insulation and hypalon jacket which is weather proof. See 2654C65.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 4 of 10

NRC RAI Letter 6/18/10

& Attachment 8 EDCR 52601-A Page 4 EDCR COVER SHEET (continued) o Still must be protected against flood since multiple RTDs are below the flood level of 720ft. See drawing 47E235-45 o The corrective action is to have the cable termination assembly above the flood line.

On Bechtel's request, Westinghouse will provide 3 additional RTDs with 75 ft pigtails for the keyway.

Related EDCRs

- 55385 - RVLIS phase 2

- 52319 - Eagle-21 system

- 53301 - external wiring for Eagle-21

- 52351 - Common Q system - signals from RTDs go to Common Q.

- 53756 - Installs the tee "below the seal table" as part of the MID Loop Monitoring installation.

(the tee will be provided with the RVLIS WBS 2.6.2.7)

- 55231 - bulk cabling package reactor building Items to procure (Fittingsand tubin-g to be procuredon this EDCR. Othermaterialto be procuredon later packa-ges.)

- Westinghouse provided components - specifically RTDs and capillary - see WBS 2.6.2.7 (this WBS procures other items for EDCR 55385)

- Fittings, tubing, pipe

- Isolation valves Unistrut and associated clamps for capillary routing as needed. Construction will procure as safety related. The needed parts for each clamp are below. See 47A051-46.

o P1000 Unistrut (or N1 000 for nuclear version) o Clamp- P1006-1420 (or N1006-1420) o 1/4" nut o 1/4" bolt, at least 1.5" long to clear the top of the Unistrut. This is construction's decision.

Sleeve materials to be procured as quality related This EDCR's material requirements were reviewed with the PQAM or designee.

ASME On the loops and head connections, there is a flow restrictor that changes the classification to TVA class B corresponding to ASME class 2. Downstream of the sensor bellows, the classification is "TVA Instrument Class" in accordance to N3E-934. This requires that the capillary system that penetrates primary containment shall be installed, fabricated, and inspected to TVA class B requirements (not procured).

Stress analysis will be done by plant design on the coded piping - see 01-52601-04.

There is an inconsistency between design criteria WB-DC-30-17 Diaphragmand Bellows Seals and CapillarySystems and Engineering Specification N3E-934 Instrument and Instrument Line Installation and Inspection.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 5 of 10

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A EDCR COVER SHEET (continued) Page 5 The former states for capillary systems penetrating containment the "diaphragms shall be designed in compliance with ASME Section III, Paragraph ... " However, the latter lower tier document gives "special instructions... to account for material that cannot be supplied as ASME material". It states "diaphragm seal assemblies ... are considered outside ASME Section III Code requirements..." Unit l's sensor bellows are not ASME code components.

WB-DC-30-17 will be revised or an exception made with EDCR 55385. There is no action required for this EDCR.

Steel ContainmentVessel Penetrations See drawing 47W331-2 for penetration details The penetration assemblies (X84 and x87) consist of a 6" diameter piece of bar stock, 3/8" thick with four 3/4" holes 90 degrees apart, which will hold four 3/4" pipes. Three of these pipes are used by RVLIS and the last is capped or used for something else.

Civil Engineering calculations WCG-1-1119 and WCG-1-1 122 are complete for stress loading on the penetrations (see EDCR index).

The penetration assembly in unit 1 uses a piece of machined bar stock as part of the pieces to get from %" pipe to 3/16" tubing. This is not desired in unit two so a %" to 1/2" coupling unit will be used.

This would then be connected to a 1/2/" to 1/4" tube adapter (Parker's Weld-Lok). These will both be socket welded for ease of install (vice butt welded). See detail on DRA 52601-09.

X87 - train A - MK 102 - 721' 6" - 3060 X84 - train B - MK 101 - 723' 0" - 307' 30' Sleeves throughout Reactor Building The two sleeves through the concrete shield wall are MK 102 and MK 101. The capillary will be stuck through a hole and filled with a sealant placed in the gap. See 47W600-109 note 9 - "fill sleeve with RTV foam, Dow-Corning silicone product..." The sleeves currently exist filled with a black substance, but there is no capillary going through.

According to DCN 17371, it allowed the capillary clips to be placed at 60" through the sleeve vice the required 25".

There are four other crane wall sleeves. The first two are MK484 and MK 485 that come from the seal table and goes inwards to meet with other tubing. The second of the two are MK411 and MK365 for all the capillaries leaving the inside of the crane wall to eventually exit the reactor building.

Bosses The weld bosses are in Westinghouse's scope in accordance with the original WBS. However it has been determined that the bosses are installed.

RTD's The RTDs exist for density compensation purposes for vertical sections of tubing. In unit 1 there are six RTD's on train A and five on train B. Less RTDs needed for unit 2 due to the difference in routing.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 6 of 10

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A Page 6 EDCR COVER SHEET (continued)

For example, there will be none used for the hot legs since this is horizontal. However this plan could change as the field begins their verification that the pre-existing Unistrut is mounted to seismic CAT I standards. If the field needs to make adjustments and these adjustments change the route, more or less RTDs could be used. See construction note #3 on DRA 009.

Since approximately 90% of the Unistrut is present, the location of the RTDs has been determined.

See LSWP 1334.

A RTD consist of a sensor that is banded to capillary held inside Unistrut, and the MI (mineral insulated) cable which is part of the pigtail. This pigtail can reach 75ft long, will connect to the field cable, and will eventually connect to Common Q PAMS. See more details in the following section.

- Common Q can accept a maximum of eight RTDs per train.

- The excess MI pigtail will coiled and spliced per EDCR 55231.

The field will support the RTD pigtails in accordance to the instructions on Westinghouse drawing 2654C65 along with Category I Support Conduit Typical drawing 47A056-200B. The Unistrut will be supported according to 47A051-46 series.

Junction Boxes, Coil Boxes, and Conduit Seals The RTD's excess pigtail will be coiled and spliced with a conduit seal. All conduit seals must be above the surge flood level of 720ft (reference 2-47E235-41). A coil box may or may not be used.

The conduit seals, coil/junction box, and termination to the pigtail are being done with EDCR 55231 (specifically with an FCR).

What follows is the approximate location of the coil boxes obtained via walkthrough to be used with EDCR 55231. The boxes will be installed by the field at their discretion. These are possible locations based on the limitations of the situation (flood level, pigtail length, box size, and available space).

TE-68-376 and 383 - train A and B - Guide Tube RTDs in Keyway Due to limited unit I documentation, how the pigtail exits the Keyway is not known.

TE-68-377 - Train A - Seal Table and Head Elevation 726.1 ft Azimuth 72 degrees Mounted on the lower azimuth side of pressurizer relief tank TE-68-378 - train A - Head RTD #1 Vicinity of 46 degrees Mounted on ceiling Elevation (Approx) 754ft Within 1Oft of blowout window TE-68-379 - train A - Head RTD #2 Elevation 740ft Azimuth 72 degrees Crane wall TE-68-384 - train B - Seal Table and Head Elevation 725.6ft Mounted on inboard side of pressurizer housing 9ft above grating - this avoids the permanent ladder.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 7 of 10

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A Page 7 EDCR COVER SHEET (continued)

Azimuth (approx) 110 degrees TE-68-385 - train B - Head RTD #1 Mounted on ceiling Vicinity of 90 degrees Elevation 754 ft Within 1Oft of blowout window TE-68-386 - train B - Head RTD #2 Elevation 739ft Azimuth 100 degrees Crane Wall TE-68-393 - train B - Seal table and Head Elevation >720ft Azimuth 2020 On inside of crane wall Installationand Routingc of CapillaryTubing and CapillaryRTDs The pre-existing unistrut will be utilized to route as much capillary as possible. There are however gaps of a few feet, see LSWP 1334.

Note that Westinghouse will provide 11 RTDs with 25ft pigtails (2 for 1" tubing and 9 for 3/16" tubing -

but both with 25ft pigtails), and three more with 75ft pigtails.

The use of Unistrut mounted in a circle to wind up excess capillary will not be used (these are referred to as "Christmas trees"). All capillary will be cut to fit.

There is a series of documents that provide guidance and establish requirements on how to route/mount capillary tubing within Unistrut.

47A051 series - see specifically 47A05t -46 series along with 47A051 -01 series

- Max distance between welds or braces is 65" (5ft and 5in)

- Max space between bolt w/ spring nut and holding plate is 2'-3"

- Maximum of 7 capillaries in each tray

- Torque requirements of bolt and lock nut.

- Maximum cantilevered free end length is 6" N3E-934 - engineering specifications

- Instrument lines shall not be field routed within NUREG-0612 interaction areas as shown on 44W411. See 3.7.2.1.1 o According to 44W411-7 the head sensor bellows are located within a NUREG interaction area. However this program has not come alive yet for unit 2, so no coordination can be done.

- Minimum bend radius is 3 inches. Bending will be performed by hand.

- Capillary systems which penetrate containment shall be installed, fabricated, and inspected to TVA class B (ASME class 2) requirements

- Brazing of SS cap tubing will be iaw G-29 Process Specification 1 .E.2.3

- Trains separated by minimum of 18"

- The pressure test will be to 1.5 times design pressure.

47W600-0-4 Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081 EFFECTIVE 4-22-10 Page 8 of 10

NRC RAI Letter 6/18/10

, Attachment 8 EDCR 52601-A Page 8 EDCR COVER SHEET (continued)

- Capillary tubing < 3/16" shall be routed in P-1000 Unistrut.

- Maximum interval between bolt/spring/plate assemblies is 48". Note this is greater than the 25" mentioned in 47A051.

- Continuous support at corners is not required

- Exposed capillary kept to less than 6" 47A052 series

- This has a separate setup than the Unistrut that is only used in the "refueling water canal".

See DCN 51844M for more information.

In unit 1, train A's seal table Unistrut had to be reinforced in two places with DCN 30066 (see DRA W30066-01). This was due to a 10" cold injection pipe that was deemed too close that during a rupture, damage to the capillary and Unistrut would be caused by jet impingement. Therefore two extra supports were added. This similar work will be captured with the jet impingement program and any corrective actions from this will be captured via FCR.

Applicable DCIDSITSIES and Proceduresand otherrequirements

- WB-DC-30 Instrument Sense Lines - slope and separations. This is not for closed capillary systems. This DC is mostly applicable to capillary before the sensor bellows, however there are a few applicable requirements.

o Minimum separation between trained capillary is 18" o Minimize line length due to increased potential of having sensing line configurations which can trap gas or air at high points in liquid filled lines.

o If it is necessary to route a liquid filled sense line with an upward slope, a vent valve shall be placed at the high point in the line and have a loop seal at the root.

- WB-DC-30 DiaphragmAnd Bellows Seals and CapillarySystems o Volumetric displacement of the pressure sensing device shall be less than full span volumetric displacement of the diaphragm/bellows seal.

o Section 3.7.1 states the diaphragms shall be designed in compliance with ASME section III paragraph NC-3649 -- this seems contradictory to N3E-934 and the ASME code. See a more detailed comment in the ASME section.

o Armored capillary shall be used when available to reduce potential for physical damage to the capillary tube.

o Minimum bend radius supplied by manufacturer. If no specification is provided, then assume the minimum bend radius shall be 3 times the outside diameter of the capillary tubing.

- N3E-934 - Instrument line installation inspection - Engineering Specifications o States that capillary tubing which penetrate primary containment shall be installed, fabricated, and inspected to TVA class B (ASME class two) requirements.

o See Appendix E for capillary lines exiting containment.

- WB-DC-40-36 The Classificationof PipingPumps, Valves, and Vessels

- WBNP-DS-1935-2618 - ASME Section ///, Nuclear Class 2 Piping System

- IMI-t22.004 backfilling, venting, flushing and/or draining of instrument sensing lines and instruments

- MAI-4.4A instrument line installation

- TI-208 Design of supports for category I piping and instrument lines

- 47W600-0 various mounting and routing requirements o Has requirement that 3/16" OD or less must be in UNISTRUT - see 47a051 Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4,22-10 Page 9 of 10

NRC RAI Letter 6/18/10

• Attachment 8 EDCR 52601-A Page 9 EDCR COVER SHEET (continued)

- WB-DC-40 Containment Isolation System - Section 7.6.1 states RVLIS should not use any containment isolation valves because it would jeopardize the performance of the system.

- WB-DC-30 Post Accident Monitoring Instrumentation- establishes that reactor vessel level is a post accident monitoring needed parameter, see table A-1 variable 22.

- WB-DC-40-31.9 - CriteriaForDesign of Piping Supports and Supplemental Steel in Category I Structures PlannedOpen Items See open items list.

Note that NUREG section 0612 (see N3E-934 3.7.2.1) interaction area interference evaluation will be done separately. Any changes to RVLIS from this would be with the FCN process unless this program comes alive before the final package.

Required Calculations

- Qualification of capillary clamps in refueling water canal (47W052043)

- SCV Penetration X-84 nozzle and shell evaluation (WCG-1-1119)

- SCV Penetration X-87 nozzle and shell evaluation (WCG-1-1122)

There were two calculations done for unit 1 that certified the routing of the capillary for each train.

These were performed due to limited guidance for the field routing of the capillary at the time of installation. See...

- Qualification of capillary tray instrument panel L-388 (TEACEBEMG43)

- Qualification of capillary tray instrument panel L-340 (TEACEBEMG44)

For the Unit 2 installation, the requirements in section 3.21 of N3E-934 are imposed upon this EDCR and thus the qualification of capillary tray verification calculations are not required.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 10 of 10

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A Page /I EDCR OPEN ITEM FORM EDCR# 52601 Rev. A Page No. /9 Open Item Type Check all Applicable Calculation X Vendor Information X ICRDS Reports Drawing/DRA X DELETED DELETED Environmental Qualification - EQCS X Issuance Appendix R DELETED Other:

Open Item Details:

Open Item Open Item

Description:

Number 01-52601-01 Setpoint and Scaling Document (SSD) supporting calculation(s). Name to be determined.

01-52601-02 EQ Change Supplements for the RVLIS RTDs.

01-52601-03 Approve RVLIS RTD Seismic Report (Westinghouse).

01-52601-04 Sense line interface configuration drawings (4) associated with root valves 2-RTV-68-453A (head), 2-RTV-68-454A (hot leg 1), 2-RTV-68-455A (hot leg 3), and 2-RTV-68-387A (seal table), along with physical DRAs.

01-52601-05 Revise Reactor Coolant system (68) NUREG-0588 Category and Operating Times calculation Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 Effective 5/19/10 Page 1 of 2

NRC RAI Letter 6/18/10 Attachment 8 EDCR 52601-A Page /

EDCR OPEN ITEM FORM Action Plan for Open Item:

Open Item Open Item Action Plan Number 01-52601-01 Receive, review, and approve SSD supporting calculations from (at time of this writing) Westinghouse.

Ensure that supporting calculations are received for all relevant SSDs as listed in the Electrical and I&C Calculation Checklist. Note that one supporting calculation may be relevant to multiple SSDs.

The resolution of this open item will not require a revision to this EDCR.

01-52601-02 Issue change supplement.

The resolution of this open item will not require a revision to this EDCR.

01-52601-03 Approve RTD seismic reports (Westinghouse).

The resolution of this open item will not require a revision to this EDCR.

01-52601-04 I&C prepare isometric drawings. Plant Design prepare stress analysis on root valve piping and generate physical DRAs. Remove "HOLD" on DRA 52601-009.

The resolution of this open item will require a revision to this EDCR.

01-52601-05 Revise Reactor Coolant system (68) NUREG-0588 Category and Operating Times calculation WBNOSG4017 to incorporate the design that two of the RTDs that are used in unit 1 will not be used in unit 2 (see scope statement for why this is occurring). These two RTDs are TE-68-373 and TE-68-380.

The resolution of this open item wiil not require a revision to this EDCR.

Action Taken:

Open Item Action Taken for Closure:

Number 01-52601-01 01-52601-02 01-52601-03 01-52601-04 01-52601-05 Completed By: Date:

Verified By: Date:

Refer to the electronic documents in IVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 Effective 5/19/10 Page 2 of 2

NRC RAI Letter 6/18/10 Attachment 8 Attachment 1 EDCR 52601-A Page Z Page 1 of 23 Technical Evaluation Considerations of 0-TI-2 This attachment provides topics to be considered when evaluating the technical and safety aspect of changes being implemented in WBN Unit 0 and/or Unit 1 by the EDCR-2 process; see Reference 5.OA. It is not intended to be an all inclusive list of items to be considered. It is to be used as an aid in determining attributes that should be addressed in a technical evaluation. Information is also provided to aid in determining coordination interfaces. These are minimum guidelines which are primarily excerpts from SPP-9.3. It should be recognized that many topics and changes involve multiple disciplines and organizations and technical considerations must be coordinated accordingly. All parts of Attachment 1 must be considered for applicability for the associated EDCR-2.

NRC RAI Letter 6/18/10 Attachment 8 ,coo. -,Pao--A EDCR UNIT DIFFERENCE FORM EDCR# 52601 Rev. A Page No. t Operations Difference Is Identified as follows:

RVLIS is being installed in the same fashion as unit I and there should be no operatina difference.

Note that RVLIS signals feed into ICCM-86 in unit I and Common Q, PAMS (EDCR 52351) for unit

2. This is a significant unit difference, but this change does not affect RVLIS or this EDCR. The analysislof these differences will be done with EDCR 52351.

-n f'l*A porat'ons Acceptance (Mgr or Designee:- Date. I Maintenance Difference Is Identified as follows:

The number and location of the RVLIS RTDs will be different This is based on the routing of the capillary being different. This will affect corrective maintenance if the RTD fails.

The unistrut which contains the capillary was mostly installed in unit 2. and to save cost will be used. The Unistrut was field routed in both units so they are not the same. This has caused the location and number of the Unit 2 RTDs to be different than Unit 1.

,S 2C_, Dif*fe-rec Unit S-I¢-rl' I-"intentnie Ac seoll (Mgrows: 1ese): W Design Difference is Identified as follows": -

The routing of the capillary will be different. Approximately 80% of the Unistrut is already installed and will be used. Since RVLIS is a filled system, the route (including slope) will have no affect on the functioning of the system. Therefore this difference is technically acceptable.

o The difference in route causes the location of the RTDs to be different. These different elevations are factored into Common Q with addressable constants in Its reactor vessel level calculation.

. The mounting of the capillary to the 3%" pipe as part of the steel containment penetration (SCV) sleeve assembly will be different. There will be no piece of machined barstock as in unit 1. All items will be welded and this connection will be just a good of a union as on unit 1. Therefore this difference is technically acceptable.

New Unistrut will be the nuclear grade version vice generic (the company Unistrut did not make nuclear grade version at the time of install into unit 1). The nuclear grade Unistrut (N1000) is essentially the same as the non nuclear grade (P1000) except it has better material traceability.

o There are some very small differences in beam loading and column loading between the P1000 and N1000 versions of Unistrut. For example with an un-braced height of Refer to the electrnlc documents In TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081 EFFECTIVE 4-22-10 Page 1 of 2 Jiv~tjk-Iewývs

NRC RAI Letter 6/18/10 FPcA. f%6& -A Attachment 8 P If 72 in (47A051-46 requires 65") and a "K"value of 0.65 (mathematically describes the column end conditions - this value is a typical), vendor details stipulate a maximum column load of 48401bs for P1000 and 48001bs for N1000. This difference is negligible.

Therefore this difference is technically acceptable.

One of the RTDs on each train will be in a Unistrut containing both a head and seal table capillary lines. Since no differential pressure is taken across these two taps, vertical sections must be temperature compensated. A single RTD will be used, vice two, and fed into Common Q which is sophisticated enough to use a single RTD for both compensation calculations.

Therefore this difference is technically acceptable. This decision was made to save cost.

The seal table isolation valve RTV-68-387A will be a changed to a 1/2" valve (unit 1 is a 3/4").

This valve has better isolation characteristics and is readably available.

.o This valve does contain a stellite disk (contains cobalt). This has been fully justified in the ALARA checklist of this package and has been agreed to by TVA radiation protection as being technically acceptable. The basic justification is this valve has no flow and is very far from the reactor (other end of the thimble tube).

o The size of the valve does not affect any flow characteristics because there is no flow in this line, besides the minimal amounts of flow as pressure rises or falls (this valve is part of a sense line).

o The size of the valve should not affect any response time because the orifice size is 0.25" (reference 47VD600-9-1) while the there is 3/8" tubing in this section of piping (in both unit 1 and unit 2). The 3/8" tubing is mark number 15A corresponding to 0.065" wall thickness (reference 47BM600-6) which corresponds with a 0.245" internal bore. Since the 3/8" tubing internal bore is smaller than the internal bore of the valve, this difference will not change any response time and is technically acceptable.

" Downstream of the sensor bellows into the filled portion of RVLIS, the main section of capillary is even smaller 3/16" tubing which makes this change even more insignificant.

" Note that regardless of the above argument, RVLIS has no response time requirement in the licensing basis.

" Note that there is some conflicting documentation in unit 1 that states this valve is a 1/2" valve (making unit 2 the same). It is believed this piece of information is in error (MEL related documents). This analysis has taken the approach that said unit 1 valve is 3/4".

There will be other unit differences with the remainder of the RVLIS system installed under EDCR 55385. This is installing the local panels, sensor bellows, and high volume vents.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 2 of 3

NRC RAI Letter 6/18/10 At hment 8

• 4601-A Unit 2 TVA Engineering Acceptance (Mgr or Designee): Date:

Mat MedenByr 5/812010 Prepared By: "' 6 Date:

Streamlined EDCR approved by TVA Oversight __1__4 SESG TO ROUTE A COPY OF THIS COMPLETED FORM TO TVA TRAINING MANAGER AND TO UNIT 2 LICENSING.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-GO4G-00081 EFFECTIVE 4-22-10 Page 3 of 3

NRC RAI Letter 6/18/10 Attachment 8 Ck 5-A f -A EDCR UNIT DIFFERENCE FORM EDCR# 52601 Rev. A Page No. _,

This second unit difference form is to encompass another difference as an action item from the Constructability Walkdown.

[

Operations Difference is identified as follows:

See previous unit difference form.

N/A Unit 2 TVA Operations Acceptance (Mgr or Designee): Date:

{

Maintenance Difference is identified as follows:

See previous unit difference form.

NIA Unit 2 TVA Maintenance Acceptance (Mgr or Designee): Date:

Design Difference is identified as follows:

A crane wall sleeve used for train A will change from MK-417 (a 20" sleeve) used in unit 1 to MK-365 (a 4" sleeve) to be used in unit 2. The Unistrut is already routed to this sleeve and appears to be the sleeve unit 2 construction was intending to use. This sleeve is within a few feet of the originally planned sleeve, but is far enough to meet train separation criteria. Since RVLIS is a filled capillary system, the route does not matter so the sleeve used does not matter to the functionality of the system. Therefore this difference is technically acceptable.

Ui -nit2 Engineering Acceptance (Mgr or Designee): Date:

Mat Merten, " 511312010 Prepared By: Date:

Streamlined EDCR approved by TVA Oversight SESG TO ROUTE A COPY OF THIS COMPLETED FORM TO TVA TRAINING MANAGER AND TO UNIT 2 LICENSING.

Refer to the electronic documents inTVA Business Support Library (BSL) for cuDrevisio.n- JIM^' p,*- j 25402-3DP-G04G-00081 EFFECTIVE 4-22-10 Page I of 1

ENCLOSURE 1 Responses To Licensee Open Items To Be Resolved For SER Approval ATTACHMENT 9 (This Attachment contained on the OSM)

New Eagle 21 Power Supplies In WBN Unit I Work Order Excerpt and Unit Difference Form

EDCR: 52319-A PAGE: 79 9

o EDCR UNIT DIFFERENCE FORM EDCR# 52319 Rev. A Page No.

Operations Difference Is Identified as follows:

No.Operations-Differences have been identified. Unit 2 Eagle.21 is functionally the same as Unit 1 Eagle 21. Any design differences will be transparent to Operations.

. aL/1A Unit2TVA K)piratlons Acceptance (lgr or'Designee):

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081 Page 1 of 4

EDCR: 52319-A PAGE: 80 Maintenance Difference Is Identified as follows:

1. Unit 2 current input loops will be 4-20 mA. Unit I uses a combination of 4-20 mA and 10-50 mA current input loops. Per WBS 3.1 Unit 2 will use 4-20 mA transmitters in Eagle 21. 4-20 mA transmitters are the industry standard, require less power than the 10-50 mA transmitters, and qualified 4-20 mA transmitters are more widely available than the 10-50 rnA transmitters. Some 10-50 transmitters used in Unit I are obsolete and no longer available for procurement. Unit I has already changed a number of Eagle 21 transmitters to the 4-20 mA standard.

2. Unit 2 Eagle 21 current output loops will be 4-20 mA. Unit I uses 10-50 mA output loops.

Per WBS 3.1 Unit 2 will use 4-20 mA current loops in Eagle 21. 4-20 mA current loops are the Industry standard. Indicators, recorders, etc. are more widely available for 4-20 mA than 10-50 mA loops.

3. Transmitter Auxiliary Power Supplies (TAPS) will not be required or provided for Unit 2.

This is due to Unit 2 using 4-20 mA transmitters. 4-20 mA transmitters do not require the TAPS power supplies.

4. Eagle Analog Output Board impedance switch settings will differ from Unit 1. This is due to the 4-20 mA output signal change, changes in Westinghouse Inadequate Core Cooling Monitor (ICCM) design, and Foxboro Digital Control System changes.

5. Unit 2 Eagle 21 Racks will have a Luxcom OMI01-AUI Fiber Optic Converter with SC type fiber connectors. Unit 1 uses a Fiber Corn 7498 Fiber Optic Converter with ST type connectors InRacks 2, 6, 10, and 13 only. The Unit I Luxcom Fiber Optic Converter is obsolete and Is no longer available for procurement.

6. Unit 2 Fiber Optic Converters will be powered from the associated Serial to Ethernet Controller through the AUI cable. Unit I Fiber Optic Converters are powered from the associated Rack 15V power supply bus. This is due to the different power requirements of the Unit 2 Luxcom Fiber Optic Converter. See Item 5 above for more Information.

7. Unit 2 Fiber network will be of the direct link type. Unit I uses a Dual Ring type fiber network. The Unit 2 Luxcom Fiber Optic Converters cannot be configured to operate In a ring fashion, the way the Unit I Fiber Corn Fiber Optic Converters operate. See item 5 above for more information.

8. Upper level configuration drawings and assembly drawings for Unit 2 will differ from Unit 1.

This is a change initiated by Westinghouse. See items 8, 9, and 10 inthe Design Difference section for more information.

9. Two Man Machine Interface (MMI) Carts will be included in the Unit 2 Eagle 21 installation.

These new MMI Carts are of a new generation and will have an updated touch screen and printer. The Fluke model touch screen and printer provided in the original Unit I MMI Carts are obsolete and are no longer available for procurement. MMI Carts provided with the Unit 2 installation are compatible with the Unit I Racks, and MMI Carts provided with the Unit 1 installation are compatible with the Unit 2 Racks.

10. The Eagle 21 Configuration Control Specification (411A66) will be revised by Westinghouse to reflect the Unit 2 Eagle 21 changes.

Brian Briody /i / 10 Unit 2 alnance Acc an (Mgr or Designee): Onte:

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

I25402-3DP-G04G-00081 Page 2 of 4

EDCR: 52319-A PAGE: 81 Design Difference is identified and justified as follows:

1. All Unit 2 current input loops will be 4-20 mA. Unit 1 uses a combination of 4-20 mA and 10-50 mA input loops. This difference in input current loops is achieved by using a 50 ohm dropping resistor in the input channel for a 4-20 mA input and a 20 ohm dropping resistor in the input channel for a 10-50 mA input. Unit 2 Eagle Analog Input Boards will remain the same as Unit 1.

2. All Unit 2 current output loops will be 4-20 mA. Unit 1 uses 10-50 mA output loops. This

,difference in output loops is achieved by using a type I Eagle Analog Output Board (EAO-

01) for 4-20 mA loops. Unit 1 uses a type 2 Eagle Analog Output Board for 10-50 mA loops (EAO-02). Unit 2 will use a 50 ohm dropping resistor in the current output loops to develop the output test signal. Unit 1 uses a 20 ohm dropping resistor in the current output loops to develop the output test signal.

3. Transmitter Auxiliary Power Supplies (TAPS) will not be required or provided for Unit 2.

Unit 1 uses the TAPS for the 10-50 mA transmitters that require a higher input voltage than the Eagle 21 Analog Input (EAI) Boards can provide. The voltage output of the EAI Boards is enough to drive the Unit 2 4-20 mA transmitters.

4. Eagle Analog Output (EAO) Board impedance switch settings will differ from Unit 1 in Racks 2, 6, 10, and 13. This is due to the 4-20 mA output signal change, changes in Westinghouse Inadequate Core Cooling Monitor (ICCM) design, and Foxboro Digital Control System changes.

5. All Unit 2 Eagle 21 Racks will have a Luxcom OM101-AUI Fiber Optic Converter with SC type fiber connectors. Unit I uses a Fiber Com 7498 Fiber Optic Converter with ST type connectors in Racks 2, 6, 10, and 13. This change was necessary due to the Fiber Com Fiber Optic Converters being no longer manufactured and not available for procurement.

6. Unit 2 Fiber Optic Converters will be powered from the associated Serial to Ethernet Controller through the AUI cable. Unit 1 Fiber Optic Converters are powered from the associated Rack 15V power supply bus.

7. Unit 2 Fiber network will be of the direct link type. A Fiber Optic Converter in each Eagle 21 Rack will transmit to a 16 port network switch located in Rack 177. Unit I uses a Dual Ring type fiber network. A Fiber Optic Converter in Racks 2, 6, 10, and 13 transmit in a ring fashion to another Fiber Optic Converter in Rack 155. The Unit 2 Luxcom Fiber Optic Converters cannot be configured to operate in a ring fashion, the way the Unit 1 Fiber Com Fiber Optic Converters operate.

8. Upper level configuration drawings for Unit 2 will differ from Unit 1. Unit 2 Cabinet Configuration Drawings will be 1C83609-Series. Unit I Cabinet Configuration Drawings are 8250C10-Series. This change is due to the fact that Racks 2, 6, 10, and 13 will be updated in the Unit 2 Eagle 21 installation. Racks 2, 6, 10, and 13 in Unit 1 are of an earlier Eagle 21 design that was upgraded after installation to be functionally equivalent to the latest Eagle 21 design used in the other Unit 1 Protection Set Racks.

9. Input J Output board location drawings for Unit 2 will differ from Unit 1. Unit 2 1/0 Board location drawings will be 6D31444-Series. Unit 1 I/O board location drawings are 2007E88-Series. This change is due to the 4-20 mA input/output loop change.

10. Assembly drawings for Unit 2 will differ from Unit 1. Racks 2, 6, 10, and 13 in Unit 1 are of an earlier Eagle 21 design. 2005E44-Series, 2005E40-Series, and 3D21739-Series are the general assembly drawings for the Cabinet, Card Cage, and Status Panel for all Unit 2 Eagle 21 Racks and Racks 1, 3-5, 7-9, 11, 12, and 28 in Unit 1. 1870E97-Series, 1870E94-Series, and 3D20240 are the general assembly drawings for the Cabinet, Card Cage, and Status Panel for Racks 2, 6, 10, and 13.in Unit 1. This change is due to the fact that Racks 2, 6, 10, and 13 will be updated in the Unit 2 Eagle 21 installation.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081 Page 3 of 4

EDCR: 52319-A PAGE: 82

11. Two Man Machine Interface (MMI) Carts will be included in the Unit 2 Eagle 21 installation.

These new MMI Carts are of a new generation and will have an updated touch screen and printer. The Fluke model touch screen and printer provided in the original Unit I MMI Carts are no longer being manufactured and are not available. The operation and functionality of the MMI Carts are not changed. MMI Carts provided with the Unit 2 installation are compatible with the Unit I Racks, and MMI Carts provided with the Unit 1 installation are compatible with the Unit 2 Racks.

12. In Unit 1, all 'analog' Log point data created by Eagle 21 is routed from Eagle 21's output boards to the Plant Computer, In Unit 2, modifications performed during the installation of the Foxboro IAsystem have redirected some of the Eagle Log point outputs so that the Log data jpesent to the Plant Computer (ICS) via Foxboro IA's network link.

A/// ""U, ffl-ýý 64-)

Unit 2 TVA'Eigigneering Acceptance (Mgr or Designee):

4 -rL-Date:

(*

Jeremy Paxton L.,7_. j4_z_L oY/IO71Zo o Prepared By: C/ - Date:

Streamlined EDCR approved by TVA Oversight NA SESG TO ROUTE A COPY OF THIS COMPLETED FORM TO TVA TRAINING MANAGER AND TO UNIT 2 LICENSING.

Refer to the electronic documents in TVA Business Support Library (BSL) for current revision.

25402-3DP-G04G-00081 Page 4 of 4

PM WORK ORDER UNID: WBN-I-PX -099-0500A -E WO NO: 08-813412-000 EQUIP DESCRIPTION: POWER SUPPLY FOR LCP BOARD IN RACK 1-R-5 PART A: SENSITIVE EQUIPMENT

1. Sensitive Equipment/High Risk 1. Yes No_ _

2". Risk review per SPP-7.1 and critical evolutions as required. 2. Yes 2 PART B: OPERATIONS WORK PRE APPROVAL

1. Work Scope is Fully Understood 1. Yes 1/

2. Technical Specifications and Impact Evaluation Complete 2. Yes N/A

3. LCO -Entry Required, IF Yes, LCO# 3. Yes NiA____

4. The PMT Specified is Adequate to Meet Plant, Tech Specs, /

and Surveillance Requirements 4. Yes N/A_ __

5. Does the Work Involved Invalidate a Previously Satisified Tech Spec Surveillance Requirement 5. Yes _ No

6. Clearance Required, If Yes, Tagout*Section# . , _ 6. Yes N/A

7. All Clearance Constraints Listed in the Work Package and/or Procedures are identified on the Clearance set 7.,Yes N/A

a. Operations Notificatio isR d to tarting Work NCR____ WCC- NIA

9. Operations Work Approval

< S ROPS isgnee Signature */

Cosments:

PART C: RESPONSIBLE SECTION PRE APPROVAL

1. Work Scope is Fully Understood 1. Yes _____

2. All Required Permits Identified NA 2. Yes ' N/A_ _

3. All Req Pre-testing Identified NONE 3. Yes- N/A

4. All Support Identified OPS , 4. Yes ,, N/A

5. Radcon/ALARA RadCon Location 0/1 ALARA N RWP Required N RWP#

(RadCon completes for activities in the RCA or hat require an RWP. otherwise Reap Supv N/As)

Review Complete or N/Aad_ _ /I &_ __ _ _ _ e

6. Pre-Approval to Begia Work Work Supervisor / Date PART D: RESPONSIBLE SECTIONS APPROVAL TO BEGI WORK 1

1. Clearance in accordance with SPP-l0.2, Tagout-Section# 1. Yes N/A

2. Clearance boundary adequate for work scope. 2. Yes_ _ /A

3. All Initial Permits Required are Obtained 3. Yes .- N/A

4. Material, M&TE, Support and Qualified Personnel Available 4ý Yes j,

5. All Required Pretesting Completed T.Yes > N/A

6. Pre Job/Test Overview/Safety Briefings Completed as Required - 6. Yes,,<'_N/A -

7. Procedures and Drawings Verified for Use 7. Yes B N/A- _

8. If Part A Sensitive Equipment/High Risk Checked Yes, Department Head or Designee Approval Required Department Head or Designee / Date'

9. If Part B.8 Operations Notification Checked MCR or WCC, Then OPS Approval Required Prior o Start "D SRO/OPS Designee I Date

10. Approval to Begin Work______

Work E

Supervisor \ --- _

/ Date

UNID: WBN-1-PX -099-0500A -E WO NO: 08-813412-000 EQUIP DESCRIPTION: POWER SUPPLY FOR LCP BOARD IN RACK I-R-S PART E-1: WORK FIELD COMPLETE RESPONSIBLE SECTION

1. Physical Field Work Complete 1. Yes t'/" N/A

2. Jobsite Cleaned 2. Yes / N/A _

3. All Field Documentation Complete 3. Yes . N /A

4. Ready for PMT/RT0 4. Yes N/A

5. If PMT affects in-service equipment, then OPS review is required. 5. Yes / N/A Operatio_ Date/

Work Supervisor Signature Date Section PART E-2: WORK CLOSURE RESPONSIBLE SECTION

1. All Tech Spec Acceptance Criteria Met for Return To Service (Note 1) 1. Yes / N/A_

2. Clearance Released When Ready for PMT/RTO. 2. Yes N/A 4t-

3. PMT Complete 4 3. Yes _ NA__-____

Signature Date

4. Post Job Review complete as required, (i.e. TVA Form 40899) 4. Yes N/A PART E-3: DCN DOCUMENTATION CLOSURE SECTION

1. Modification Turnover Package Form SPP-9.3-12 has been completed as required. 1. YesN/A

2. Operability Checklist (0-TI-GXX-000-000.0) has been completed as required. (SQN Only) 2. Yes N/A

3. Notify Operations that all Clearances can be released. 3. Yes N/A

4. Ready for Operations Acceptance Signature Date Section PART F: OPERATIONS ACCEPTANCE FOR WORK CLOSURE

1. All FMTs Completed or Transferred to Document# _ _ _' _ 1. Yes - N/A.

2. All Technical Specification Acceptance Criteria Met for Return 7

to Service(Note 1) 2. Yes N/A

3. Equipment Ready for Unrestricted Return to Service (Note 1) 3. Yes /_ N/A

4. Operations Acceptance o~kti'ws / Date PART G: WORK PACKAGE COMPLETE(REVIEW BY RESPONSIBLE SECTION):

Signature / Date

1. Was work performed on equipment within the scope of the 10CFR50.49(EQ) program ?

If yes, obtain the signature of the EQ Coordinator. 1. Yes N/A EQ Coordinator / Date NOTE i: List any equipment not ready for return to service and/or that does not satisfy tech spec acceptance c ritr:

UNID DESCRIPTION OF PROBLE,. ER ER WO NUMBER 4.-'

NW WO INSTRUCTION REVIEW/APPROVAL SHEET UNID: WBN-1-PX -099-0500A -E WO NO: 08-813412-000 EQUIP DESCRIPTION: POWER SUPPLY FOR LCP BOARD IN RACK l-R-5 SIGNATURE/DATE REASON Rev. 0 PLANNER: I - ___/ m- "*- 09 Initial Planning TECH REVIEWER: ISee original Appendix B for initial approvals.

IQR ISee original Appendix B for initial approvals.

OPS Review*: ISee Work Approval Form For Rev 0 Ii Rev. _

PLANNER: i /,

TECH REVIEWER: __/ -/

IQR __ /_ _ _ _

OPS Review*: I / I Rev. ./

PLANNER. _______________/_______,___ _______"____

TECH REVIEWER: /

IQR /_,,-

OPS Review*: / /

Rev. _ I PLANNER: I TECH REVIEWER: _

IQR /

OPS Review*: I Rev. _

PLANNER: I TECH REVIEWER: /

IQR /

OPS Review*:

Rev. _

PLANNER: I /

TECH REVIEWER: _ __ /.

IQR I "__ /

OPS Review*: _ _/_/.

Rev.

PLANNER :

TECH REVIEWER:

IQR OPS Review* :

• The OPS Review is required for scope and any PMT revision in Work Order package. N/A otherwise.

iINg11111111111liiiIII1111111111 1110lI IIIIMINI1llIIi11111 INIll PPPP N M P p MMHMM SPPPP M M M P M M REPETITIVE TASK FORM RESPONSIBLE SECTION: MIG WO NO: 08-813412-000 UNID: WBN-1-PX -099-0500A -E FILE #: 2 REV#: 10 EQUIP DESC: POWER SUPPLY FOR LCP BOARD IN RACK I-R-5 SAFETY CLASS:SR EQ:N 1E:Y SECTION XI:N SECT XI R/R:N COMPLIANCE:N MULTISKILL ACTIVITY:

QR CODES:Q10 RELIAJILITY CLASSIFICATION CRITICAL WORK DESCRIPTION: PROTECTION SET II EAGLE 21 POWER SUPPLY & LCP NVRAM &

CLOCK CHIP REPLACEMENT AND ICCM TRAIN B POWER SUPPLY REPLACEMENT. PM 0287W JOB LOCATION: 708' CLEARANCE RECOMENDED: (Y/N): N QC HOLDPOINTS: N SCAFFOLD: N INSULATION: N FME LEVEL :2 DRAWINGS NONE VENDOR MANUAL

REFERENCES:

VTM-W120-2991 VTM-W120-3004 PROCEDURES/

REFERENCES:

PMUG 0287W

• Drawings and procedures marked with an

• are required for work performance.

SCHEDULE EARLY START: 09/06/2009 DUE DATE: 09/06/2009 LATE DATE: 09/06/2009 REFERENCE NO: 600123128 PM INSTRUCTION: 0287W PM CLASSIFICATION: MANDATORY 'N REGULATORY: N CRITICAL: COMMITMENT: Y CONCURRENT TASK: NONE SOURCE DOCUMENT: VM, PER WBPER970111 PM FREQUENCY: 54M OUTAGE CODES: RO 3R 3C 3C TVAWOPRT.V8.5 PRINTED: 02/06/2009 11:39:49 0

ENCLOSURE2 Responses To Licensee Open Items To Be Resolved For SER Approval Regulatory Commitments

1. The non-proprietary version of Sorrento/GA Software V&V Report Version 1.1 04508005 and withholding affidavit will be submitted by July 14, 2010. This item has been added to the "Licensee Open Items to be Resolved for SER Approval List," as Item 119.

2. Submit EDCR 55385 excerpts by November 15, 2010. This item is tracked by "Licensee Open Items to be Resolved for SER Approval List," Item 118.

3. Submit EDCR 52321 excerpts by October 31, 2010. This item is tracked by "Licensee Open Items to be Resolved for SER Approval List," Item 103.

4. Submit EDCR 52351 excerpts by December 15, 2010. This item is tracked by "Licensee Open Items to be Resolved for SER Approval List," Item 104.

5. The next revision of the Unit 2 Common Q PAMS System Requirements Specification will be provided to NRC no later than August 31, 2010. This item has been added to the "Licensee Open Items to be Resolved for SER Approval List," as Item 122.

6. The report on the final resolution of the Eagle 21 Rack 2 RTD input issue will be provided no later than December 3, 2010. This item has been added to the "Licensee Open Items to be Resolved for SER Approval List," as Item 128.