TSTF-09-07, Industry Plan to Resolve TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions

Industry Plan to Resolve TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions

ML090540849
Person / Time
Site:	Technical Specifications Task Force
Issue date:	02/23/2009
From:	Gambrell R, Joseph Messina, Raidy T, Schrader K Babcock & Wilcox, BWR Owners Group, Combustion Engineering, PWR Owners Group, Westinghouse
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TSTF-09-07 TSTF-493, Rev 3
Download: ML090540849 (21)

Text

TECHNICAL SPECIFICATIONS TASK FORCE TSTF A JOINT OWNERS GROUP ACTIVITY February 23, 2009 TSTF-09-07 PROJ0753 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Industry Plan to Resolve TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions"

Dear Sir or Madam:

On January 18, 2008, the TSTF submitted Revision 3 of TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions." On November 4, 2008, the NRC responded to the TSTF's submittal of Revision 3 and described the changes to TSTF-493 that would be required for the NRC Staff to find the Traveler acceptable.

At a public meeting between the NRC and the industry held on January 8, 2009, the proposed course of industry action was discussed. The NRC management and industry representatives agreed to a course of action to resolve TSTF-493. The industry agreed to develop a description of the actions to be taken.

Enclosed with this letter is the paper, "Resolution of Setpoint Issues Addressed in TSTF-493,

'Clarify Application of Setpoint Methodology for LSSS Functions'." The TSTF has discussed this paper with the NRC technical staff involved in the review of TSTF-493 and we have incorporated their comments.

We are informing the NRC that the TSTF's development of a revision of TSTF-493 will be based on the concepts addressed in the enclosed paper. The TSTF is not requesting any action by the NRC in response to this letter.

11921 Rockville Pike, Suite 100, Rockville, MD 20852 Phone: 301-984-4400, Fax: 301-984-7600 Administered by EXCEL Services Corporation

TSTF 09-07 February 23, 2009 Page 2 Should you have any questions, please do not hesitate to contact us.

Kenneth J. Schrader (PWROG/W) John Messina (BWROG)

Thomas W. Raidy (PWROG/CE) Reene' Gambrell (PWROG/B&W)

Enclosure cc: Robert Elliott, Technical Specifications Branch, NRC Joseph Williams, Special Projects Branch, NRC

Resolution of Setpoint Issues Addressed in TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions" On January 18, 2008, the TSTF submitted Revision 3 of TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions," (Ref. 1). On November 4, 2008, the NRC responded to the TSTF's submittal of Revision 3 (Ref. 2) and described the changes to TSTF-493 that would be required for the NRC Staff to find the Traveler acceptable.

The TSTF evaluated the positions in Reference 2 to determine whether they (1) addressed all the concerns that had been expressed by the NRC, (2) provide appropriate operational flexibility, and (3) are sufficiently generic to maximize industry adoption. This evaluation resulted in a proposed course of industry action.

The proposed course of industry action was considered and accepted by the Boiling Water Reactor Owners' Group (BWROG) Technical Specification Issues Coordinating Committee (TSICC) on December 3, 2008 and by the Pressurized Water Reactor Owners Group (PWROG) Licensing Subcommittee on December 16, 2008. The Owners Group committees were willing to accept the NRC Staff recommendations in Reference 2 with certain clarifications and implementation considerations, as described below.

The proposed course of industry action, clarifications, and implementation considerations were discussed in detail with the NRC at a public meeting on January 8, 2009. The industry was represented by the PWROG Chairman (Dennis Buschbaum) and the BWROG Chairman (Douglas Coleman). Among the NRC participants were the Director of the Division of Inspection and Regional Support (Frederick Brown), the Chiefs of the Technical Specification Branch (Robert Elliott) and the Instrumentation and Control Branch (William Kemper), as well as the responsible reviewers of TSTF-493 within their branches. The NRC management and staff provided clarifications and agreed to the resolution of the implementation issues in a manner consistent with the Owners Group committee's desired resolution.

Therefore, the Owners Groups and the NRC have reached agreement on the actions necessary to resolve the setpoint issues addressed in TSTF-493.

The changes to be incorporated in TSTF-493, Revision 4, to implement this agreement are described below.

Scope of Functions to be Addressed In order to reach resolution with the NRC on TSTF-493, the industry agrees to add the TSTF-493 footnotes to all instrument functions in the LCOs for the Reactor Trip System (also called Reactor Protection System), the Engineered Safety Feature Actuation System (also called Emergency Core Cooling System) and some instrument functions in other LCOs identified by the BWROG in TSTF-493, Revision 3.

Attachment A, "Identification of Functions to be Annotated with the TSTF-493 Footnotes," includes the disposition of Functions to be included in TSTF-493. The indicated generic dispositions were discussed with the NRC in a teleconference held on February 11, 2009 and the NRC staff agreed that the Attachment indicates those functions applicable to all licensees for which no plant-specific analysis is required.

1 02/16/2009

Resolution of Setpoint Issues Addressed in TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions" Licensees may choose to submit analysis to support plant-specific deviations from the list when adopting TSTF-493.

Functions are exempted from the application of the TSTF-493 footnotes if the functions are:

1. Manual actuation circuits

2. Automatic actuation logic circuits, or

3. Instrument functions that derive input from contacts which have no associated sensor or adjustable device, e.g., limit switches, breaker position switches, etc.

Many permissives or interlocks are excluded under this criterion. Other permissives and interlocks rely on the input from a sensor or adjustable device (e.g., a pressure transmitter). If the permissive or interlock derives input from a sensor or adjustable device that is tested as part of another TS function, then the permissive or interlock is excluded from the footnotes. Otherwise, the footnotes are added to the permissive or interlock to ensure that it is functioning as expected.

The industry agreement to annotate these functions with the TSTF-493 footnotes does not represent industry acceptance of the NRC's definition of SL-LSSS in Reference 2 or agreement that the functions to be annotated are LSSS, that the functions protect a Safety Limit, or that the functions meet a 10 CFR 50.36(c)(2) criteria. For example, the industry is considering the applicability of the 10 CFR 50.36(c)(2) criteria under Risk Informed Technical Specifications Task Force (RITSTF) Initiative 8a, and this agreement to resolve TSTF-493 does not prejudice that effort . The TSTF will eliminate the discussion of Safety Limits and Safety Limit-LSSS from the TSTF-493 justification and Bases.

Bases Addition for Instrumentation Functions that are Not Annotated with the Footnotes In Reference 2, the NRC Staff requested that for each instrument trip or actuation function (with the same limitations as applicable for the footnotes) not annotated with the TSTF-493 footnotes, the TS Bases should address the agreement concepts for testing (similar to the application of the footnotes) to ensure instruments are functioning as required in accordance with analyses of record. This would eliminate the need for NRC Staff RAIs to request this information during individual plant-specific license amendment reviews.

At the January 8, 2009, meeting the NRC Staff and industry representatives agreed that Surveillance Requirement Bases of ISTS Section 3.3, "Instrumentation," that verify the setpoint for instruments which provide an automatic actuation function and that are not annotated with the TSTF-493 footnotes will be modified to include the following statement, "There is a plant specific program which verifies that this instrument channel functions as required by verifying the as-left and as-found settings are consistent with those established by the setpoint methodology."

2 02/16/2009

Resolution of Setpoint Issues Addressed in TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions" The details of how the plant-specific program performs the verification described in the Bases statement and the method for establishing the as-left and as-found settings which are under licensee control would be subject to NRC inspection and to verification of compliance with the Bases statement.

TSTF-493 Adoption In the NRC's July 25, 2007, RAI on TSTF-493, the NRC requested that TSTF-493 contain a second option (Option B) which would relocate the trip setpoints to a licensee-controlled program. The NRC suggested that the format and content of Option B should be modeled after the Section 3.3 "Instrumentation," TS in ESBWR Design Control Document, Tier 2, Chapter 16, Technical Specifications and Bases dated 12/15/2006. A Setpoint Control Program (SCP) is added to the programmatic requirements in Section 5.0, "Administrative Controls." The SCP contains the TSTF-493 footnotes, a reference to the NRC staff Safety Evaluation for the approved licensee setpoint methodology, and identifies the licensee-controlled document that contains the relocated values and the calculated limiting trip setpoint. After adoption of the Setpoint Control Program, the licensee can revise these values using the approved methodology without NRC involvement.

In Reference 1, the TSTF acknowledged that Option B had many merits, but declined to pursue this second Option. After further consideration, the Owners Groups have agreed to include the Setpoint Control Program option in TSTF-493, Revision 4. However, the operating plants will develop their own proposal for a Setpoint Control Program which may be different from that proposed for the ESBWR.

The industry plans to discuss three TSTF-493 adoption strategies in Revision 4. The NRC staff agreed that a licensee may pursue any of these strategies when adopting TSTF-493, Rev. 4.

1. Setpoint Control Program Under this adoption strategy, a licensee proposes to relocate the TS Section 3.3, "Instrumentation," Limiting Trip Setpoints, Nominal Trip Setpoints, and/or Allowable Values from the Technical Specifications to a licensee-controlled Setpoint Control Program. The requirements for the Setpoint Control Program will be described in Chapter 5, "Administrative Controls." The licensee will either provide regulatory approval citations for their setpoint methodologies or, as applicable, will submit their setpoint methodology or methodologies used to calculate the relocated parameters for NRC review and approval. Each instrument surveillance requirement will contain a requirement to perform the surveillance test in accordance with the SCP.

2. Adoption of TSTF-493 with Changes to Setpoint Values Under this adoption strategy, a licensee submits a license amendment that adopts TSTF-493 (e.g., the footnotes are added to all the functions identified in TSTF-493 and the Bases changes are incorporated). One or more setpoint values are also proposed to be revised. The licensee is not required to provide the setpoint 3 02/16/2009

Resolution of Setpoint Issues Addressed in TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions" methodology for review. However, the licensee will provide a summary calculation for the revised setpoints. If multiple similar setpoints are proposed to be revised, the licensee may provide a summary calculation for each type of setpoint being revised provided that the amendment request contains a reasoned quantitative or qualitative analysis, as appropriate, of how the summary calculation(s) represent the type of setpoint values proposed to be changed.

3. Adoption of TSTF-493 with No Changes to Setpoint Values Under this adoption strategy, a licensee submits a license amendment that adopts TSTF-493 (e.g., the footnotes are added to all the functions identified in TSTF-493 and the Bases changes are incorporated). No changes to any setpoint values are proposed. Since no setpoint values are being revised, the licensee is not required to provide the setpoint methodology for review or to provide any full or summary calculations.

Until the NRC approves TSTF-493, Rev. 4, the TSTF encourages licensees to delay submittal of licensing actions that are affected by this issue. However, if a licensee desires to pursue such a licensing action prior to the approval of TSTF-493, we encourage them to be consistent with the approach to be used for TSTF-493, Rev. 4, with the exception that the TSTF-493 footnotes would be applied only to the specific setpoints being changed.

Next Actions

1. The TSTF will create a document describing the agreements reached between the industry and the NRC, provide it for industry review and comment. The document will include the specific functions to be annotated with Notes 1 and 2 in TSTF-493, Rev. 4. This action is complete.

2. The TSTF and the NRC will meet to review the industry document and to resolve any differences and then will transmit the document to the NRC. This action is complete.

3. The TSTF will develop TSTF-493, Revision 4, in accordance with the industry document and obtain industry review and concurrence.

4. The TSTF will request a meeting with the NRC to review the draft Revision 4 to resolve any misunderstandings or discrepancies.

5. After addressing any changes resulting from the meeting with the NRC, the TSTF will submit TSTF-493, Rev. 4, in the Spring of 2009. The TSTF will request that the NRC expeditiously pursue approval of TSTF 493 to resolve this longstanding issue.

4 02/16/2009

Resolution of Setpoint Issues Addressed in TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions" References

1. Letter from the Technical Specification Task Force to the Nuclear Regulatory Commission, TSTF-08-01, "Response to NRC June 25, 2007 Request for Additional Information Regarding TSTF-493, Revision 2, 'Clarify Application of Setpoint Methodology for LSSS Functions,' dated January 18, 2008.

2. Letter from Robert Elliott (NRC) to the Technical Specifications Task Force, "Evaluation Of TSTF Responses To NRC Staff Request For Additional Information (RAI) Regarding Traveler TSTF-493, Revision 2, 'Clarify Application Of Setpoint Methodology For LSSS Functions,' dated November 4, 2008.

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Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes Unless otherwise noted, the listed instrument function will be annotated with the TSTF-493 footnotes NUREG-1430, Babcock and Wilcox Plants Specification 3.3.1, "Reactor Protection System Instrumentation"

1. Nuclear Overpower

a. High Setpoint

b. Low Setpoint

2. RCS High Outlet Temperature

3. RCS High Pressure

4. RCS Low Pressure

5. RCS Variable Low Pressure

6. Reactor Building High Pressure

7. Reactor Coolant Pump to Power

8. Nuclear Overpower RCS Flow and Measured AXIAL POWER IMBALANCE

9. Main Turbine Trip (Control Oil Pressure)

10. Loss of Main Feedwater Pumps (Control Oil Pressure)

11. Shutdown Bypass RCS High Pressure Specification 3.3.5, "Engineered Safety Feature Actuation System Instrumentation"

1. Reactor Coolant System Pressure - Low Setpoint (HPI Actuation, RB Isolation, RB Cooling, EDG Start)

2. Reactor Coolant System Pressure - Low Low Setpoint (HPI Actuation, LPI Actuation, RB Isolation, RB Cooling)

3. Reactor Building (RB) Pressure - High Setpoint (HPI Actuation, LPI Actuation, RB Isolation, RB Cooling)

4. Reactor Building Pressure - High High Setpoint (RB Spray Actuation)

A-1 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes NUREG-1431, Westinghouse Plants Specification 3.3.1, "Reactor Trip System Instrumentation"

1. Manual Reactor Trip - (Manual actuation excluded from footnotes)

2. Power Range Neutron Flux

a. High

b. Low

3. Power Range Neutron Flux Rate

a. High Positive Rate

b. High Negative Rate

4. Intermediate Range Neutron Flux

5. Source Range Neutron Flux

6. Overtemperature T

7. Overpower T

8. Pressurizer Pressure

a. Low

b. High

9. Pressurizer Water Level - High

10. Reactor Coolant Flow - Low

11. Reactor Coolant Pump (RCP) Breaker Position - (Mechanical component excluded from footnotes)

12. Undervoltage RCPs

13. Underfrequency RCPs

14. Steam Generator (SG) Water Level - Low Low

15. SG Water Level - Low Coincident with Steam Flow/Feedwater Flow Mismatch

16. Turbine Trip

a. Low Fluid Oil Pressure

b. Turbine Stop Valve Closure (Mechanical component excluded from footnotes)

17. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS) (Automatic actuation logic circuit excluded from footnotes)

18. Reactor Trip System Interlocks (Permissive or interlock excluded from footnotes)

19. Reactor Trip Breakers (RTBs) (Mechanical component excluded from footnotes)

A-2 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

20. Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms (Mechanical component excluded from footnotes)

21. Automatic Trip Logic (Automatic actuation logic circuit excluded from footnotes)

Specification 3.3.2, "Engineered Safety Feature Actuation System Instrumentation"

1. Safety Injection

a. Manual Initiation (Manual actuation excluded from footnotes)

b. Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

c. Containment Pressure - High 1

d. Pressurizer Pressure - Low

e. Steam Line Pressure (1) Low (2) High Differential Pressure Between Steam Lines

f. High Steam Flow in Two Steam Lines Coincident with Tavg - Low Low

g. High Steam Flow in Two Steam Lines Coincident with Steam Line Pressure - Low

2. Containment Spray

a. Manual Initiation - (Manual actuation excluded from footnotes)

b. Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

c. Containment Pressure High - 3 (High High)

d. Containment Pressure High - 3 (Two Loop Plants)

3. Containment Isolation

a. Phase A Isolation (1) Manual Initiation (Manual actuation excluded from footnotes)

(2) Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

(3) Safety Injection (Automatic actuation logic circuit excluded from footnotes)

b. Phase B Isolation (1) Manual Initiation (Manual actuation excluded from footnotes)

(2) Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

A-3 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes (3) Containment Pressure High - 3 (High High)

4. Steam Line Isolation

a. Manual Initiation (Manual actuation excluded from footnotes)

b. Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

c. Containment Pressure - High 2

d. Steam Line Pressure (1) Low (2) Negative Rate - High

e. High Steam Flow in Two Steam Lines Coincident with Tavg - Low Low

f. High Steam Flow in Two Steam Lines Coincident with Steam Line Pressure - Low

g. High Steam Flow Coincident with Safety Injection (Automatic actuation logic circuit excluded t from footnotes)

Coincident with Tavg - Low Low

h. High High Steam Flow Coincident with Safety Injection (Automatic actuation logic circuit excluded from footnotes)

5. Turbine Trip and Feedwater Isolation

a. Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

b. SG Water Level - High High (P-14)

c. Safety Injection (Automatic actuation logic circuit excluded from footnotes)

6. Auxiliary Feedwater

a. Automatic Actuation Logic and Actuation Relays (Solid State Protection System) (Automatic actuation logic circuit excluded from footnotes)

b. Automatic Actuation Logic and Actuation Relays (Balance of Plant ESFAS)

(Automatic actuation logic circuit excluded from footnotes)

c. SG Water Level - Low Low

d. Safety Injection (Automatic actuation logic circuit excluded from footnotes)

e. Loss of Offsite Power

f. Undervoltage Reactor Coolant Pump A-4 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

g. Trip of all Main Feedwater Pumps

h. Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low

7. Automatic Switchover to Containment Sump

a. Automatic Actuation Logic and Actuation Relays (Automatic actuation logic circuit excluded from footnotes)

b. Refueling Water Storage Tank (RWST) Level - Low Low Coincident with Safety Injection (Automatic actuation logic circuit excluded from footnotes)

c. RWST Level - Low Low Coincident with Safety Injection (Automatic actuation logic circuit excluded from footnotes) and Coincident with Containment Sump Level - High

8. ESFAS Interlocks (Permissive or interlock excluded from footnotes)

NUREG-1432, Combustion Engineering Plants Specification 3.3.1, "Reactor Protective System Instrumentation" (Analog)

1. Variable High Power Trip

2. Power Rate of Change - High

3. Reactor Coolant Flow - Low

4. Pressurizer Pressure - High

5. Containment Pressure - High

6. Steam Generator Pressure - Low 7a. Steam Generator A Level - Low 7b. Steam Generator B Level - Low

8. Axial Power Distribution - High 9a. Thermal Margin/Low Pressure (TM/LP) 9b. Steam Generator Pressure Difference

10. Loss of Load (turbine stop valve control oil pressure)

Specification 3.3.4, "Engineered Safety Features Actuation System Instrumentation" (Analog)

1. Safety Injection Actuation Signal (SIAS)

a. Containment Pressure - High

b. Pressurizer Pressure - Low A-5 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

2. Containment Spray Actuation Signal

a. Containment Pressure - High

3. Containment Isolation Actuation Signal

a. Containment Pressure - High

b. Containment Radiation - High

4. Main Steam Isolation Signal

a. Steam Generator Pressure - Low

5. Recirculation Actuation Signal

a. Refueling Water Tank Level - Low

6. Auxiliary Feedwater Actuation Signal (AFAS)

a. Steam Generator A Level - Low

b. Steam Generator B Level - Low

c. Steam Generator Pressure Difference - High (A > B) or (B > A)

Specification 3.3.1, "Reactor Protective System Instrumentation" (Digital)

1. Linear Power Level - High

2. Logarithmic Power Level - High

3. Pressurizer Pressure - High

4. Pressurizer Pressure - Low

5. Containment Pressure - High

6. Steam Generator #1 Pressure - Low

7. Steam Generator #2 Pressure - Low

8. Steam Generator #1 Level - Low

9. Steam Generator #2 Level - Low

10. Reactor Coolant Flow, Steam Generator #1 - Low

11. Reactor Coolant Flow, Steam Generator #2 - Low

12. Loss of Load (turbine stop valve control oil pressure)

13. Local Power Density - High

14. Departure From Nucleate Boiling Ratio (DNBR) - Low Specification 3.3.5, "Engineered Safety Features Actuation System Instrumentation" (Digital)

1. Safety Injection Actuation Signal

a. Containment Pressure - High

b. Pressurizer Pressure - Low A-6 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

2. Containment Spray Actuation Signal

a. Containment Pressure - High High

b. Automatic SIAS (Automatic actuation logic circuit excluded from footnotes)

3. Containment Isolation Actuation Signal

a. Containment Pressure - High

b. Pressurizer Pressure - Low

4. Main Steam Isolation Signal

a. Steam Generator Pressure - Low

b. Containment Pressure - High

5. Recirculation Actuation Signal

a. Refueling Water Storage Tank Level - Low

6. Emergency Feedwater Actuation Signal SG #1 (EFAS-1)

a. Steam Generator Level - Low

b. SG Pressure Difference - High

c. Steam Generator Pressure - Low

7. Emergency Feedwater Actuation Signal SG #2 (EFAS-2)

a. Steam Generator Level - Low

b. SG Pressure Difference - High

c. Steam Generator Pressure - Low NUREG-1433, Boiling Water Reactor/4 Plants Specification 3.3.1.1, "Reactor Protection System Instrumentation"

1. Intermediate Range Monitors

a. Neutron Flux - High

b. Inop (Interlock excluded from footnotes)

2. Average Power Range Monitors

a. Neutron Flux - High, Setdown

b. Flow Biased Simulated Thermal Power - High

c. Fixed Neutron Flux - High

d. Downscale

e. Inop (Interlock excluded from footnotes)

3. Reactor Vessel Steam Dome Pressure - High

4. Reactor Vessel Water Level - Low, Level 3 A-7 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

5. Main Steam Isolation Valve - Closure (Mechanical device excluded from footnotes)

6. Drywell Pressure - High

7. Scram Discharge Volume Water Level - High

a. Resistance Temperature Detector (Mechanical device excluded from footnotes)

b. Float Switch (Mechanical device excluded from footnotes)

8. Turbine Stop Valve - Closure (Mechanical device excluded from footnotes)

9. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low

10. Reactor Mode Switch - Shutdown Position (Manual actuation excluded from footnotes)

11. Manual Scram (Manual actuation excluded from footnotes)

Specification 3.3.2.1, "Control Rod Block Instrumentation"

1. Rod Block Monitor

a. Low Power Range - Upscale

b. Intermediate Power Range - Upscale

c. High Power Range - Upscale

d. Inop (Interlock excluded from footnotes)

e. Downscale (Not part of RPS or ECCS excluded from footnotes)

f. Bypass Time Delay (Permissive or interlock excluded from footnotes)

2. Rod Worth Minimizer (Not part of RPS or ECCS excluded from footnotes)

3. Reactor Mode Switch - Shutdown Position (Manual actuation excluded from footnotes)

Specification 3.3.4.1, "EOC-RPT Instrumentation"

1. Trip Units

2. Turbine Stop Valve - Closure (Mechanical component excluded from footnotes)

3. Turbine Control Valve - Fast Closure, Trip Oil Pressure - Low Specification 3.3.5.1, "Emergency Core Cooling System Instrumentation"

1. Core Spray System

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. Reactor Steam Dome Pressure - Low (Injection Permissive) (Actuation logic excluded from footnotes)

d. Core Spray Pump Discharge Flow - Low (Bypass) (Actuation logic excluded from footnotes)

A-8 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

e. Manual Initiation - Manual (Manual actuation excluded from footnotes)

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. Reactor Steam Dome Pressure - Low (Injection Permissive) (Actuation logic excluded from footnotes)

d. Reactor Steam Dome Pressure - Low (Recirculation Discharge Valve Permissive) (Actuation logic excluded from footnotes)

e. Reactor Vessel Shroud Level - Level 0 (Actuation logic excluded from footnotes)

f. Low Pressure Coolant Injection Pump Start - Time Delay Relay Pumps A,B,D (Permissive or interlock excluded from footnotes)

Pump C (Permissive or interlock excluded from footnotes)

g. Low Pressure Coolant Injection Pump Discharge Flow - Low Bypass (If valve locked open, Function can be removed from TS)

h. Manual Initiation (Manual actuation excluded from footnotes)

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel Water Level - Low Low, Level 2

b. Drywell Pressure - High

c. Reactor Vessel Water Level - High, Level 8 (Optional to include footnotes or not)

d. Condensate Storage Tank Level - Low (If mechanical device, excluded from footnotes)

e. Suppression Pool Water Level - High (If mechanical device, excluded from footnotes)

f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) (If valve locked open, Function can be removed from TS)(If mechanical device, excluded from footnotes)

g. Manual Initiation (Manual actuation excluded from footnotes)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. Automatic Depressurization System Initiation Timer (Actuation logic excluded from footnotes)

d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)

A-9 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

e. Core Spray Pump Discharge Pressure - High (Actuation logic excluded from footnotes)

f. Low Pressure Coolant Injection Pump Discharge Pressure - High (Actuation logic excluded from footnotes)

g. Automatic Depressurization System Low Water Level Actuation Timer (Actuation logic excluded from footnotes)

h. Manual Initiation (Manual actuation excluded from footnotes)

5. ADS Trip System B

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. Automatic Depressurization System Initiation Timer (Actuation logic excluded from footnotes)

d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)

e. Core Spray Pump Discharge Pressure - High (Actuation logic excluded from footnotes)

f. Low Pressure Coolant Injection Pump Discharge Pressure - High (Actuation logic excluded from footnotes)

g. Automatic Depressurization System Low Water Level Actuation Timer (Actuation logic excluded from footnotes)

h. Manual Initiation (Manual actuation excluded from footnotes)

Specification 3.3.5.2, "Reactor Core Isolation Cooling System Instrumentation"

1. Reactor Vessel Water Level - Low Low, Level 2

2. Reactor Vessel Water Level - High, Level 8 - (Optional to include footnotes or not)

3. Condensate Storage Tank Level - Low (If mechanical device, excluded from footnotes)

4. Suppression Pool Water Level - High (If mechanical device, excluded from footnotes)

5. Manual Initiation (Manual actuation excluded from footnotes)

NUREG-1434, Boiling Water Reactor/6 Plants Specification 3.3.1.1, "Reactor Protection System Instrumentation"

1. Intermediate Range Monitors

a. Neutron Flux - High

b. Inop (Interlock excluded from footnotes)

2. Average Power Range Monitors

a. Neutron Flux - High, Setdown A-10 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

b. Flow Biased Simulated Thermal Power - High

c. Fixed Neutron Flux - High

d. Inop (Interlock excluded from footnotes)

3. Reactor Vessel Steam Dome Pressure - High

4. Reactor Vessel Water Level - Low, Level 3

5. Reactor Vessel Water Level - High, Level 8

6. Main Steam Isolation Valve - Closure (Mechanical component excluded from footnotes)

7. Drywell Pressure - High

8. Scram Discharge Volume Water Level - High

a. Transmitter/Trip Unit

b. Float Switch (Mechanical component excluded from footnotes)

9. Turbine Stop Valve Closure, Trip Oil Pressure - Low

10. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low (if mechanical device is used then exempt from footnotes)

11. Reactor Mode Switch - Shutdown Position (Manual actuation excluded from footnotes)

12. Manual Scram (Manual actuation excluded from footnotes)

Specification 3.3.2.1, "Control Rod Block Instrumentation"

1. Rod Pattern Control System

a. Rod withdrawal limiter

b. Rod pattern controller (Not part of RPS or ECCS excluded from footnotes)

2. Reactor Mode Switch - Shutdown Position (Manual actuation excluded from footnotes)

Specification 3.3.4.1, "EOC-RPT Instrumentation "

1. Trip Units

2. Turbine Stop Valve Closure, Trip Oil Pressure - Low (if mechanical device is used then exempt from footnotes)

3. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Specification 3.3.5.1, "Emergency Core Cooling System Instrumentation"

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High A-11 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

c. LPCI Pump A Start - Time Delay Relay (Permissive or interlock excluded from footnotes)

d. Reactor Steam Dome Pressure - Low (Injection Permissive) (Actuation logic excluded from footnotes)

e. LPCS Pump Discharge Flow - Low (Bypass) (Actuation logic excluded from footnotes)

f. LPCI Pump A Discharge Flow - Low (Bypass) (Actuation logic excluded from footnotes)

g. Manual Initiation (Manual actuation excluded from footnotes)

2. LPCI B and LPCI C Subsystems

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. LPCI Pump B Start - Time Delay Relay (Permissive or interlock excluded from footnotes)

d. Reactor Steam Dome Pressure - Low (Injection Permissive) (Actuation logic excluded from footnotes)

e. LPCI Pump B and LPCI Pump C Discharge Flow - Low (Bypass) (Actuation logic excluded from footnotes)

f. Manual Initiation (Manual actuation excluded from footnotes)

3. High Pressure Core Spray (HPCS) System

a. Reactor Vessel Water Level - Low Low, Level 2

b. Drywell Pressure - High

c. Reactor Vessel Water Level - High, Level 8 (Optional to include footnotes or not)

d. Condensate Storage Tank Level - Low (If mechanical device, excluded from footnotes)

e. Suppression Pool Water Level - High (If mechanical device, excluded from footnotes)

f. HPCS Pump Discharge Pressure - High (Bypass) (If mechanical device, excluded from footnotes) (If valve locked open, Function can be removed from TS)(

g. HPCS System Flow Rate - Low (Bypass) (If mechanical device, excluded from footnotes) (If valve locked open, Function can be removed from TS)(

h. Manual Initiation (Manual actuation excluded from footnotes)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water Level - Low Low Low, Level 1 A-12 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

b. Drywell Pressure - High

c. ADS Initiation Timer (Actuation logic excluded from footnotes)

d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)

e. LPCS Pump Discharge Pressure - High (Actuation logic excluded from footnotes)

f. LPCI Pump A Discharge Pressure - High (Actuation logic excluded from footnotes)

g. ADS Bypass Timer (High Drywell Pressure) (Actuation logic excluded from footnotes)

h. Manual Initiation (Manual actuation excluded from footnotes)

5. ADS Trip System B

a. Reactor Vessel Water Level - Low Low Low, Level 1

b. Drywell Pressure - High

c. ADS Initiation Timer (Actuation logic excluded from footnotes)

d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)

e. LPCI Pumps B & C Discharge Pressure - High (Actuation logic excluded from footnotes)

f. ADS Bypass Timer (High Drywell Pressure) (Actuation logic excluded from footnotes)

g. Manual Initiation (Manual actuation excluded from footnotes)

Specification 3.3.5.2, "Reactor Core Isolation Cooling System Instrumentation"

1. Reactor Vessel Water Level - Low Low, Level 2

2. Reactor Vessel Water Level - High, Level 8 (Optional to include footnotes or not)

3. Condensate Storage Tank Level - Low (If mechanical device, excluded from footnotes)

4. Suppression Pool Water Level - High (If mechanical device, excluded from footnotes)

5. Manual Initiation (Manual actuation excluded from footnotes)

Specification 3.3.6.5, "Relief and Low-Low Set (LLS) Instrumentation"

1. Trip Unit

2. Relief Function

a. Low

b. Medium

c. High

3. LLS Function A-13 2/16/2009

Attachment A Identification of Functions to be Annotated with the TSTF-493 Footnotes

a. Low (open and close)

b. Medium (open and close)

c. High (open and close)

A-14 2/16/2009