NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8

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Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
ML15176A682
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Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/19/2015
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ML15176A678 List:
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SQN-TS-11-10, CNL-15-128
Download: ML15176A682 (499)


Text

' . Since this loop involves only the rack instrumentation, the error terms for the process error and sensor are not applicable.

The source range and intermediate range rack instrumentation use the same detector.

The instrumentation is located in an auxiliary and control building area and is not subjected to the harsh environmental parameters of radiation and temperature of a design basis accident.

Therefore, the unmeasurable uncertainties during the channel operational test are 1.3332 percent. This calculation provides assurance that the margin between AV and As-Left Value includes all the uncertainties not measured during the channel operational test (COT). On this basis, the staff finds that the revised AVis adequate to provide assurance that the permissive will be given before the source range trip occurs. Engineering design output Setpoint and Scaling Documents will specify the as-left calibration tolerance and the as-found tolerance for the trip setpoint setting as evaluated within TVA calculations.

Periodic plant calibration will incorporate the as-left calibration tolerance value ensuring compliance with design basis requirements during performance of calibration activities.

For setpoint values found outside the as-left value and inside the as-found value, the setpoint will be adjusted and left within the as-left tolerance per the surveillance requirement.

Also, the licensee committed to using its setpoint calibration procedures to maintain the trip setpoints within the established setting tolerance to ensure that the instrument remains capable of performing its specified safety function.

If the allowable value is exceeded or a potential channel inoperability exists, Plant Procedure SPP-6.7, "Instrument Setpoint, Scaling, and Calibration Program," gives direction for controlling out-of-calibration instrument conditions and contains the requirements for entering the issue into the TVA Corrective Action Program (CAP). SPP-6.7 ensures that the condition is handled in accordance with the CAP including immediate actions to return the instrument to meet TS required functions.

Trending, recurrence controls, and cause of the condition are also part of the CAP process. Based on review of the licensee's procedures, the staff finds that the setpoint calibration procedures maintain the trip setpoints within the established setting tolerance to ensure that the instruments will be capable of performing their specified safety functions and are, therefore; acceptable.

4.5 Revise Fuel Storage Pool Area Radiation Monitor Setpoint Two area type exposure rate radiation detectors are installed in the spent fuel pool area of the auxiliary building to monitor the gross radiation in the air space above the spent fuel pool. The function of the monitors is to initiate isolation of the ventilation paths in the auxiliary building upon detection of high radiation levels and to activate the auxiliary building gas treatment system. The limiting radiation event in the auxiliary building is the fuel handling accident over spent fuel pool. No credit is taken for any of the isolation or filtration functions initiated by the fuel storage pool area radiation monitors.

As such, the automatic functions initiated by these monitors are anticipatory only. They are not variables on which a safety limit has been placed. TS Table 3.3-6, "Radiation Monitoring Instrumentation," Item 1, provides the fuel storage pool area radiation monitor. The licensee has proposed to revise the alarm/trip setpoint from ;:o:200 mR/hr to ;:o: 151 mRihr. The setpoint revision is needed to address identified errors in the dose calculations for a fuel-handling event. The identified errors in the dose calculation have been addressed by the TVA CAP. The licensee evaluated the proposed setpoint in the calculation to ensure that sufficient margin exists to the analytical limit. According to the licensee's calculation, the analytical limit is 7.149 volts. The AVis derived as follows: AV = analytical limit-(uncertainties not measured during COT+ margin) = 7.149 -0.172 = 6.977 volts. Converting 6.977 volts to mR!hr gives 307 mR!hr of the AV. Setpoint = AV -uncertainties measured during COT = 6.977 -0.618 = 6.359 volts. Converting to mR/hr gives 151 mR/hr of the Setpoint.

The staff concludes that the fuel storage pool area radiation monitor will actuate within the required accident analysis assumptions to support accident mitigation.

Therefore, the staff finds the proposed setpoint acceptable.

4.6 Auxiliary Feedwater and Emergency Diesel Generator Loss-of-Power Timers TS Table 3.3-3, Functional Unit 6.e provides for the automatic actuation of the AFW system upon loss of off-site power. This Functional Unit includes both voltage sensors and load shed timers. TS Table 3.3-3, Functional Unit 7 provides for the automatic actuation of the EDGs upon either loss-of-voltage or degraded voltage at the 6.9 kV Shutdown Board. This Functional Unit includes voltage sensors, load shed timers, and logic enable timers. The SON TSs has redundant load shed and logic enable timers for each shutdown board in each train for both Functional Units 6.e and 7. These timers support automatic actuation of the loss-of-power start of the AFW pumps and EDGs. Thus, the Minimum Channels Operable column of TS Table 3.3-3 requires that 2 load shed and logic enable timers per shutdown board remain operable.

The licensee has proposed to reduce the Minimum Channels Operable from 2 per shutdown board to only 1 per shutdown board. Since there is no NRC requirement for the licensee to have redundant timers, the staff finds the proposed change acceptable.

Actions 34 and 35 toTS Table 3.3-3 currently require prompt licensee action if one of the two load shed or logic enable timers of Functional Units 6.e or 7 become inoperable.

Since the Minimum Channels Operable requirement has been changed from 2 to 1 per shutdown board, the licensee has proposed modifications to Actions 34 and 35 to permit continued plant operation with only a single load shed or logic enable timer. The proposed changes to Actions 34 and 35 support the previous change to the Minimum Channels Operable.

The staff considers these changes to be administrative in nature and, therefore, acceptable.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment.

The State official had no comments.

  • 8-6.0 ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 1 0 CFR Part 20 and changes surveillance requirements.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 60688). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

7.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:

Sang Rhow Hukam Garg Date: September 13, 2006 Licensee Response/NRC Response/NRC Question Closure Id270NRC Question Number KAB022Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 8/20/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 8/20/2014 10:45 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=270 ITS NRC Questions Id 46NRC Question Number KAB023Category TechnicalITS Section 3.3ITS Number 3.3.2DOC Number L-6JFD Number JFD Bases Number Page Number(s) 437NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 437 of Enclosure 2, Volume 8, L06 provides the discussion of CTS Table 3.3-3 footnote (a) which is applicable to function unit 6.f, "Auxiliary Feedwater Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump."Footnote (a) states, "One channel may be inoperable during Mode 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service."TVA has chosen to add this footnote into the ITS as a required actions note in Condition N, which is applicable to function 6.e, "Auxiliary Feedwater Trip of all Main Feedwater Pumps."However, the ITS required action note does not include the phrase, "during Mode 1."Without the phrase, "during Mode 1,"added to the Note it expands the use of the note to Mode 2. This note is not in ISTS and the proposed change to the note is not allowed by CTS, therefore this is a beyond scope change. Provide the technical evaluation for NRC review or revise the note to be consistent with the CTS requirements.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy Bucholtz Date Modified Modified By Date Added 5/9/2014 8:44 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 95NRC Question Number KAB023 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement SQN is requesting a relaxation to the MODE of APPLIC ABILITY for Main Feedwater (MFW) pump OPERABILITY, fr om "during MODE 1" to "during MODES 1 and 2". The proposed relaxation to CTS Table 3.3-3 Function 6.f, Trip of Main Feedwater Pumps Star t Motor-Driven Pumps and Turbine Driven Pump, Footnote (a), as discussed in ITS 3.3.2, discussion of change (DOC) L06 provides for an operational al lowance during Modes 1 and 2 for placing MFW pumps in service or securing MFW pumps. This change is justified because the AFW Start function is anticipatory for loss of normal heat sink and is not credited in the accident analysis. Also, this relaxation does not affect the function that act uates AFW due to a blackout signal, low-low steam generator (S G) level, or a safety injection (SI) signal. The technical justificat ion for the addition of MODE 2 relaxa tion is the same as the previously approved MODE 1 relaxation.

On August 26, 2008, Tennessee Valley Authority (TVA) submitted a request for a TS change (TS-08-05) to Li censes DPR-77 and DPR-79 for SQN. The requested TS change would revise Functional Unit 6.f of Table 3.3-3, "Engineered Safety Feature Actuation System Instrumentation,"modifying the mode of applicabilit

y. A footnote was added to indicate that the AFW auto-start function associated with the trip of MFW pumps in Mode 2 is only required when one or mo re MFW pumps are suppl ying feedwater to the steam generators. Functional Unit 6.f of TS Table 3.3-3 is an anticipatory trip function that provides early actuation of the AFW system. This specific change was requested based on an NRC issued Inspection Report 2008-003 dated August 7, 2008, to Watts Bar Nuclear (WBN) Plant. In this report, NRC informed TVA that plant operation is not conforming to TS 3.3.2 Item 6.e when a non-operating main feedwa ter (MFW) pump is reset. This TS function is equivalent to the SQN TS Functional Unit 6.f of Table 3.3-3. TVA had considered the associated AFW auto-start channel operable; however, NRC informed WBN that a non-operating MFW pump in the reset condition impacts operability of the AFW auto-start due to the false indication of the MFW pump status.

On August 28, 2008, durin g a teleconference with NRC it was noted that entry into a limiting c ondition of operation (LCO) Action for placing the second main feedwater (M FW) pump in service or re moving it from service would be inconsistent with TS appl ication without addi tional notation. APage 1of 3 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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supplement to LAR TS-08-05, was submitted on A ugust 28, 2008, to add a footnote to the Minimum Channels Operable column for Functional Unit 6.f of TS Table 3.3-3 to i ndicate one channel may be inoperable during Mode 1 for up to four hours wh en starting up or shut ting down a MFW pump.

On August 29, 2008, the Nuclear Regulator y Commission issued Amendment No. 312 to Facility Operating License No. DPR-77 and Amendment No. 319 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively (ML082401385). The amendment revised the requirements for the auxiliary feedwater system auto-start function associated with the trip of main feedwater pumps. The approved change added (1)

Footnote (b), to i ndicate that Mode 2 applicability is limited to operati on when one or more MFW pumps are supplying feedwater to th e steam generato rs (SGs), and (2) Footnote (a), delaying the entry into the action statement when starting or stopping MFW pumps in Mode 1.The NRC stated in Section 3, Techni cal Evaluation, the following, "The second proposed change addresses a conflict be tween the TS channel operability requirement a nd the design of the MFW pump control circuitry, which requires the pump to be reset before being placed into operation.

Starting and stopping MFW pumps durin g plant startup and shutdown is a normal evolution, which will normally be accomplished within a short time.

It was not intended to result in unnecessary entries into the action statement, which provides a timefr ame to correct unpl anned equipment failures. For the normal operating evolution of starting and stopping pumps, the proposed change would allow a de lay of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before entering the action statement. The evo lution should be completed in less time, but the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides a re asonable allowance for operating contingencies. If the evolution takes longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, it is probably indicative of an equipment problem and entering the action statement would be appropriate. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with similar allowances in other SQN TSs, such as the emergency core cooling system and low-temperature overpre ssure protection."Response Date/Time 6/5/2014 4:10 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/5/2014 3:08 PMPage 2of 3 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Date Modified Modified By Page 3of 3 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 159NRC Question Number KAB023Select Application NRC ResponseAttachment 1 Attachment 2 Response Statement Please explain if Sequoyah operates with one MFP pump or two MFP pumps during Mode 2 with a brief explanation of your preferred method of operation in Mode 2 and before or during switchover to Mode 1.Response Date/Time 6/27/2014 6:00 PM Closure Statement Question Closure Date Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/27/2014 12:39 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id357 NRC Question Number KAB023Select Application Licensee Response Attachment 1 KAB023 Attachment 1 second response STB.pdf (87KB)Attachment 2 Response Statement In response to KAB023, the ITS 3.3.2 Condition N, NO TE (ISTS markups, Insert 6) on pages 458 and 492 of Enclosure 2, Volu me 8, will be revised.Specifically, the Note will be revised to state, "One channel may be inoperable during MODE 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service."The CTS markups for CTS Ta ble 3.3-3, Function 6.f (Auxiliary Feedwater, Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump), Footnote (a) will be revised to retain the phrase, "during Mode 1."(Pages 346 and 386)Discussion of change (DOC) L06, that justified the removal of the phrase will be deleted, as well as, DOC L06 indicators. (Pages 346, 386, 438, and 439)The IT S 3.3.2 Bases, Actions Section for ITS Actions N.1 and N.2 (Insert 16) will be revised to state, "The Required Actions are modified by a note delaying the entry into the Required Action statement when st arting or stopping MFW pumps during MODE 1."(Pages 581 and 659)Additionally, during review for KAB023, it was identified that the ITS 3.3.2 Bases, Applicable Safety Analyses, LCO and Applic ability Section, for ITS Table 3.3.2-1, Function 6.e (Auxiliary F eedwater, Trip of all Main Feedwater Pumps) indicated that there are two Footnotes associat ed with Function 6.e.The ITS 3.3.2 Bases (Inser t 9) will be revised to indicate that there is only one footnote associat ed with ITS Table 3.3.

2-1 Function 6.e, and the discussion concerning the second footnote will be deleted.(Pages 560 and 638)See Attachment 1 for the draft revised CTS, ITS, and ITS Bases markups and the deletion of DOC L06.Response Date/Time 9/26/2014 10:05 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillPage 1of 2 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Andrew HonRay Schiele Added By Scott Bowman Date Added 9/26/2014 9:03 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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ITS A01 ITS 3.3.2 TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION e. Loss of Power Start

1. Voltage Sensors 3/shutdown board** 2/shutdown board** 3/shutdown board** 1, 2, 3 35
2. Load Shed Timer 2/shutdown 1/shutdown 1/shutdown 1, 2, 3 35 board** board** board** f. Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump 1/pump 1/pump 1/pump (a) 1, 2 (b) 20 g. Auxiliary Feedwater Suction Pressure-Low 3/pump 2/pump 3/pump 1, 2, 3 21
h. Auxiliary Feedwater Suction Transfer Time Delays 1. Motor-Driven Pump 1/pump 1/pump 1/pump 1, 2, 3 21
2. Turbine-Driven Pump 2/pump 1/pump 2/pump 1, 2, 3 21
    • Unit 1 shutdown boards only

(a) One channel may be inoperable during Mode 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service.

(b) When one or more Main Feedwater Pump(s) are supplying feedwater to steam generators.

August 29, 2008 SEQUOYAH - UNIT 1 3/4 3-20 Amendment No. 41, 129, 182, 188, 207, 301, 310, 319 Page 15 of 80REQUIRED LA01 A02 ITS ACTION Table 3.3.2-1 6.d.(1) 6.d. 6.d.(2) 6.e 6.f 6.g 6.g.(1) 6.g.(2) L,M M N O O O Footnote (j) Required Action N Note Footnote (k) L06 ITS ITS 3.3.2 A01TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION e. Loss of Power Start

1. Voltage Sensors 3/shutdown board** 2/shutdown board** 3/shutdown board** 1, 2, 3 35 2. Load Shed Timer 2/shutdown 1/shutdown 1/shutdown 1, 2, 3 35 board** board** board** f. Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump 1/pump 1/pump 1/pump (a) 1, 2 (b) 20 g. Auxiliary Feedwater Suction Pressure-Low 3/pump 2/pump 3/pump 1, 2, 3 21
h. Auxiliary Feedwater Suction Transfer Time Delays 1. Motor-Driven Pump 1/pump 1/pump 1/pump 1, 2, 3 21
2. Turbine-Driven Pump 2/pump 1/pump 2/pump 1, 2, 3 21
    • Unit 2 Shutdown Boards Only (a) One channel may be inoperable during Mode 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service.

(b) When one or more Main Feedwater Pump(s) are supplying feedwater to steam generators.

August 29, 2008 SEQUOYAH - UNIT 2 3/4 3-20 Amendment No. 29, 116, 174, 180, 197, 290, 299, 312 Page 55 of 80Table 3.3.2-1 ITS ACTION LA01REQUIRED A02L.M M N O O O 6.g.(2) 6.g.(1) 6.g 6.f 6.e 6.d.(2) 6.d.(1) 6.d. Footnote (j) Footnote (k)

Required Action N Note L06 DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 27 of 35 The purpose of the ITS Table 3.3.2-1 Function 4 Applicability is to provide an exception to clarify that the Steam Line Isolation instrumentation Functions are not required when the MSIVs are in a position that supports the safety analyses.

This change is acceptable because the requirements continue to ensure that the structures, systems, and components are maintained in the MODES and other specified conditions assumed in the safety analyses and licensing basis. When all the MSIVs are in the closed position, they are in their assumed accident position, thus the isolation instrumentation is not needed. In addition, the MSIVs are not required to be OPERABLE in MODES 2 and 3 when the valves are closed, thus there is no purpose in requiring the instrumentation that closes the valves to be OPERABLE. This change is designated as less restrictive because the LCO requirements are applicable in fewer operating conditions than in the CTS. L05 (Category 2 - Relaxation of Applicability) CTS Table 3.3-3 requires Functional Unit 5.a (Turbine Trip and Feedwater Isolation Steam Generator Water Level - High High) and 5.b (Turbine Trip and Feedwater Isolation - Automatic Actuation Logic) to be OPERABLE in MODES 1, 2, and 3. ITS Table 3.3.2-1 requires the same Functions (ITS Table 3.3.2-1 Functions 5.a and 5.b) to be OPERABLE in MODE 1, and in MODES 2 and 3 except when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve, Footnote (k). This changes the CTS by not requiring the instrumentation to be OPERABLE when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve.

The purpose of the ITS Table 3.3.2-1 Functions 5.a and 5.b Applicability is to provide an exception to clarify that the Turbine Trip and Feedwater Isolation Steam Generator Water Level - High High (P-14) instrumentation and the Turbine Trip and Feedwater Isolation Automatic Actuation Logic and Actuation Relays are not required when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve. In this condition, the Function will not need to function since the valves are in a position that supports the safety analyses. This change is acceptable because the requirements continue to ensure that the structures, systems, and components are maintained in the MODES and other specified conditions assumed in the safety analyses and licensing basis. When all MFIVs, MFRVs, and MFRV bypass valves are in the closed position, they are in their assumed accident position. This change is designated as less restrictive because the LCO requirements are applicable in fewer operating conditions than in the CTS.

L06 (Category 2 - Relaxation of Applicability) CTS Table 3.3.3 footnote (a) is applicable to Functional Unit 6.f (Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump) "Minimum Channels OPERABLE" requirement. CTS Table 3.3.3 footnote (a) states that one channel may be inoperable during Mode 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service. ITS 3.3.2 ACTION N is applicable Function 6.e (Auxiliary Feedwater, Trip of Main Feedwater Pumps) and is modified by a similar Required Action Note. ITS 3.3.2 ACTION N Required Action Note states that one channel may DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 28 of 35 be inoperable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service. This changes the CTS by increasing the MODES in which this footnote relaxation is Applicable.

The purpose of CTS Table 3.3.3 footnote (a) is to prevent unnecessary entries into the ACTION statement during the normal evolution of starting or stopping a main feedwater pump. Making this relaxation Applicable in MODE 2 addresses the possibility that a situation may exist requiring starting or stopping of a main feedwater pump, preventing an unnecessary entry into the associated ACTION.

This change is acceptable because the requirements continue to ensure that the structures, systems, and components are maintained in the MODES and other specified conditions assumed in the safety analyses and licensing basis as the AFW auto-start function provides an anticipatory trip to reduce the effect of a feedwater transient. In addition, as in MODE 1, the evolution should be completed in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> providing a reasonable allowance for operating contingencies. This change is designated as less restrictive because the Required Channel relaxation is applicable in more operating conditions than in

the CTS.

L07 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports)

CTS Table 3.3-3 ACTION 17, requires in part that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This action is applicable to CTS Table 3.3-3 Functional Units: 1.c (Containment Pressure - High); 1.d (Pressurizer Pressure - Low); 1.f (Steam Line Pressure - Low); 4.d (Steam Line Pressure - Low); 4.e (Negative Steam Line Pressure Rate - High); and 5.a (Steam Generator Water Level - High-High). ITS 3.3.2, Required Action D.1 require placing the associated channel in trip with a Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for ITS Table 3.3.2-1 Functions 1.c (Containment Pressure - High); 1.d (Pressurizer Pressure - Low); 1.e (Steam Line Pressure - Low); 4.d.(1) (Steam Line Pressure - Low); 4.d.(2) (Negative Steam Line Pressure Rate - High); and 5.b (SG Water Level - High-High (P-14)). This changes the CTS by increasing the Completion Time for placing an inoperable channel for these Functional Units from six (6) hours to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The purpose of CTS Table 3.3-3 ACTION 17 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable or prior to being placed in a tripped state. This change is acceptable because the Completion Time is consistent with safe operation under the specified Condition, considering the OPERABLE status of the redundant systems or features. This includes the capacity and capability of remaining systems or features, a reasonable time for repairs or replacement, and the low probability of a DBA occurring during the allowed Completion Time. Additionally, this change is acceptable based on TVA's confirmation of applicability and incorporation of insights as described in Enclosure 4 of this submittal, required by the NRC in their letter and enclosed Safety Evaluation Report (SER) dated July 15, 1998, "Review of Westinghouse Owners Group Topical Reports WCAP-14333-P and WCAP-14334-NP, dated May 1995, 'Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times' (TAC NO. M92782)." This change is 3.3.2 Insert Page 3.3.2-5a CTS INSERT 6 ----------------NOTE--------------

One channel may be inoperable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service. ---------------------------------------

Table 3.3-3, Footnote (a) 2 3.3.2 Insert Page 3.3.2-5a CTS INSERT 6 ----------------NOTE--------------

One channel may be inoperable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service. ---------------------------------------

Table 3.3-3, Footnote (a) 2 B 3.3.2 Insert Page B 3.3.2-33a INSERT 9 This Function includes two footnotes. The first footnote indicates that MODE 2 applicability is limited to operation when one or more MFW pumps are supplying feedwater to the steam generators (SGs), and the second footnote provides for delaying the entry into the action statement when starting or stopping MFW pumps in MODE 1.

The first footnote limits the Applicability to require the auto-start logic to be operable in MODE 2 only when at least one MFW pump is in service supplying feedwater to the SGs. Because plant conditions at the time of entry into Mode 2 do not allow the MFW pumps to operate, without this footnote the channels would need to be tripped resulting in an AFW start signal, starting the turbine-driven pump in addition to the motor-driven AFW pumps, which is an undesirable situation. This resolves a conflict between the MODE applicability and plant design, which does not support MFW pump operation at the time of entry into MODE 2. Also, modifying the requirement for auto-start of the AFW pumps to be only required when the MFW pumps are in service limits the potential for inadvertent AFW actuations during normal plant startups and shutdowns that could lead to reactivity control issues due to over cooling transients.

The second footnote delays entry into the Required Action for less than minimum channels operable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. During the time of starting and stopping a second MFW pump, when the pump is in reset, the auto-start function is inoperable. Starting and stopping MFW pumps during plant startup and shutdown is a normal evolution, which will normally be accomplished within a short time. This note is intended to prevent unnecessary entries into the Required Actions, which provides a timeframe to correct unplanned equipment failures. For the normal operating evolution of starting and stopping pumps, the footnote allows a delay of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before entering the Required Action.

The evolution should be completed in less time, but the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides a reasonable allowance for operating contingencies. If the evolution takes longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, it is probably indicative of an equipment problem and entering the Required Action is appropriate.

5 B 3.3.2 Insert Page B 3.3.2-47e INSERT 16 The Required Actions are modified by a not e delaying the entry into the Required Action statement when starting or stopping MFW pumps. Starting and stopping MFW pumps during plant startup and shutdown is a normal evolution, which will normally be accomplished within a short time. It was not intended to result in unnecessary entries into the Required Actions, which provides a timeframe to correct unplanned equipment failures. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with similar allowances in other SQN TSs.

O.1 Condition O applies to the following ESFAS Functions:

These functions are provided by three pressure sensors located on the suction of

each AFW pump arranged in a two-out-of-three logic scheme. The motor driven AFW pumps have one time delay, while the TDAFW pump has two. The motor driven and the first TDAFW pump time delays prevent spurious transfer. The TDAFW Pump second time delay ensures ERCW Train A valves stroke open sufficiently.

If a pressure sensor channel or a time delay channel is inoperable, the associated AFW pump must be declared inoperable immediately.

7 2 B 3.3.2 Insert Page B 3.3.2-33a INSERT 9 This Function includes two footnotes. The first footnote indicates that MODE 2 applicability is limited to operation when one or more MFW pumps are supplying feedwater to the steam generators (SGs), and the second footnote provides for delaying the entry into the action statement when starting or stopping MFW pumps in MODE 1.

The first footnote limits the Applicability to require the auto-start logic to be operable in MODE 2 only when at least one MFW pump is in service supplying feedwater to the SGs. Because plant conditions at the time of entry into Mode 2 do not allow the MFW pumps to operate, without this footnote the channels would need to be tripped resulting in an AFW start signal, starting the turbine-driven pump in addition to the motor-driven AFW pumps, which is an undesirable situation. This resolves a conflict between the MODE applicability and plant design, which does not support MFW pump operation at the time of entry into MODE 2. Also, modifying the requirement for auto-start of the AFW pumps to be only required when the MFW pumps are in service limits the potential for inadvertent AFW actuations during normal plant startups and shutdowns that could lead to reactivity control issues due to over cooling transients.

The second footnote delays entry into the Required Action for less than minimum channels operable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. During the time of starting and stopping a second MFW pump, when the pump is in reset, the auto-start function is inoperable. Starting and stopping MFW pumps during plant startup and shutdown is a normal evolution, which will normally be accomplished within a short time. This note is intended to prevent unnecessary entries into the Required Actions, which provides a timeframe to correct unplanned equipment failures. For the normal operating evolution of starting and stopping pumps, the footnote allows a delay of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before entering the Required Action.

The evolution should be completed in less time, but the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides a reasonable allowance for operating contingencies. If the evolution takes longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, it is probably indicative of an equipment problem and entering the Required Action is appropriate.

5 B 3.3.2 Insert Page B 3.3.2-47e INSERT 16 The Required Actions are modified by a not e delaying the entry into the Required Action statement when starting or stopping MFW pumps. Starting and stopping MFW pumps during plant startup and shutdown is a normal evolution, which will normally be accomplished within a short time. It was not intended to result in unnecessary entries into the Required Actions, which provides a timeframe to correct unplanned equipment failures. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with similar allowances in other SQN TSs.

O.1 Condition O applies to the following ESFAS Functions:

These functions are provided by three pressure sensors located on the suction of

each AFW pump arranged in a two-out-of-three logic scheme. The motor driven AFW pumps have one time delay, while the TDAFW pump has two. The motor driven and the first TDAFW pump time delays prevent spurious transfer. The TDAFW Pump second time delay ensures ERCW Train A valves stroke open sufficiently.

If a pressure sensor channel or a time delay channel is inoperable, the associated AFW pump must be declared inoperable immediately.

7 2 Licensee Response/NRC Response/NRC Question Closure Id363NRC Question Number KAB023Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 9/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 9/30/2014 10:48 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 47NRC Question Number KAB024 Category Technical ITS Section 3.3 ITS Number 3.3.2 DOC Number A-14JFD Number JFD Bases Number Page Number(s) 419, 420NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 419 of Enclosure 2, Volume 8, A14 provides the discussion of CTS Table 3.3-3 functional unit 4.d, "Ste am Line Isolation Steam Line Pressure -Low,"and footnote #.CT S permit functional unit 4.d (ITS function 4.d.(1)) to be bypassed in Mode 3 below P-11 (Pressurizer Pressure Bl ock of Safety Injection) setpoint.

On page 420 of Enclosure 2, Volume 8, A15 provides the discussion of CTS Table 3.3-3 func tional unit 4.e , "Steam Line Isolation Negative Steam Line Pressure Rate-High,"and footnote ##.CTS permit functional unit 4.e (ITS function 4.d.(2)) to be bypassed in Mode 3 below P-11 when Safety Injection on Steam Line Pressure Low is not blocked and it states that this function is automatically blocked above P-11.

ITS footnote (a) states, "Above the P-11 (Pressurizer Pressure) interlock."ITS footnote (a) is the equivalent of CTS footnote #, the only difference between the two footnotes is that the ITS footnote discusses when it is re quired to be operable and the CTS footnote discusses when it is permitted to be bypassed.However, TVA is not proposing to add ITS footnote (a) to ITS function 4.d.

(1).TVA is proposing to add ne w footnote (f), which states, "When Steam Line Isolation on Steam Line Pressure, Negative Rate-High is blocked."ITS footnote (f) would not require function 4.d.(1) to be operable in Mode 3 unless the Steam Line Isolation Steam Line Pressu re, Negative Rate-High is Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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blocked/bypassed.

Furthermore, a similar footnote (g) is proposed for ITS function 4.d.(2), "Steam Line Isolation St eam Line Pressure Negative Rate-High,"and states that this function would not be required to be operable in Mode 3 unless the Stea m Line Isolation on Steam Line Pressure, Low is blocked."Therefore, in Mode 3 if neither function is blocked/bypassed then neither function is required to be operable.CTS operability of functional unit 4.d is not depend ent on functional unit 4.e, nor should the operability of ITS f unction 4.d.(1) be dependent on function 4.d.(2).In addition, if ITS function 4.d.(1) becomes inoperable and is placed in bl ock/bypass while above P-11 then ITS requires function 4.d.(2) to be operable, however this is not possible due to the design auto matically blocking above P-11.These footnotes are not in ISTS and the re sults of the proposed footnotes are not allowed by CTS, therefore this is a beyond scope change. Provide

the technical evaluation for NRC re view or revise the footnotes to be consistent with the CTS requirements.

Attach File 1 Attach File 2 Issue Date 5/9/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:48 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 96 NRC Question Number KAB024 Select Application Licensee Response Attachment 1 Attachment 1 revised submittal pages for 3.3.2 Footnotes.pdf (1MB)Attachment 2 Response Statement In response to KAB-024, SQ N will revise the ISTS Table 3.3.2-1 Footnotes (a), (f), and (g) associated with ITS Table 3.3.2-1 Func tions 1.d, 1.e, 4.d.(1), and 4.d.(2), to be consistent wi th CTS Table 3.3-3 Notes # and ##

requirements.

(1) CTS TABLE 3.3-3 Note #

as it applies to ITS Table 3.3.2-1 Footnote (a), will be revised to read, "Safety Injection, Pressurizer Pressure - Low and Safety Injection, Steam Line Pressure - Low may be bypassed below the P-11 (Pressurizer Pressure) interlock."Associated changes for ITS Table 3.3.2-1 Footnote (a) will be made to the CTS markups for Units 1 and 2 (pages 350 and 390 of Enclosure 2, Volume 8), discussion of change (DOC) A13 (page 419), and ISTS markups for Units 1 and 2 (pages 466 and 500).

(2) CTS TABLE 3.3-3 Note

  1. as it applies to ITS Table 3.3.2-1 Footnote (f) will be revised to read, "Steam Line Isolation, Steam Line Pressure - Low may be bypassed below the P-11 (Pressurizer Pressure) interlock."Associated changes for ITS Table 3.3.2-1 Footnote (f) will be made to the CTS markups for Units 1 and 2 (pages 350 and 390 of Encl osure 2, Volume 8), DOC A14 (page 419), and ISTS markups for Units 1 and 2 (pages 470 and 504).(3) CTS TABLE 3.3-3 Note ## as it applies to ITS Table 3.3.2-1 footnote (g) will be revised to read , "Steam Line Isolation, Steam Line Pressure Negative Rate-High is automatically blocked above P-11 and may be blocked below P-11 when Safety Inject ion, Steam Line Pr essure - Low is not blocked."Associated changes for ITS Table 3.3.2-1 Foot note (g) will be made to the CTS markups for Units 1 and 2 (pages 350 and 390 of Enclosure 2, Volume 8), DOC A15 (page 420), and ISTS markups for Units 1 and 2 (pages 470 and 504).

See Attachment 1 for the draft revised CTS markups/I nserts for Units 1 and 2; DOCs A13, A14, a nd A15; and ISTS Markups for Units 1 and 2.Response Date/Time 6/5/2014 4:15 PMClosure Statement Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 6/5/2014 3:13 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS A01 ITS 3.3.2TABLE 3.3-3 (Continued)

TABLE NOTATION

  1. Trip function may be bypassed in this MODE below P

-11 (Pressurizer Pressure Block of Safety Injection) setpoint. ## Trip function automatically blocked above P

-11 and may be blocked below P11 when Safety Injection on Steam Line Pressure

-Low is not blocked. ACTION STATEMENTS

ACTION 15 - With the number of OPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.

ACTION 16 - Deleted.

ACTION 17 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1.

ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 19 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

ACTION 20 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

September 14, 2006 SEQUOYAH - UNIT 1 3/4 3-22 Amendment No. 63, 141, 168, 182, 188, 202, 207, 213, 301, 311 Page 18 of 80Table 3.3.2-1 Footnote (a) and Footnote (f) (e) Except when all MSIV's are closed.

L04Table 3.3.2-1 Footnote (g)

ACTION S ACTION D ACTION B ACTION N 72 12Add proposed Required Action D.2.1 and D.2.2 Add proposed Required Action E.2.1 and E.2.2 ACTION E ACTION P 72 for ACTION E, otherwise 612 for ACTION E, otherwise 4 See ITS 3.3.6 Add proposed Required Action P.2.1 and P.2.2 (i) Except when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve.

L05 L07 L08 M07 M08 L10 L09 M09 A16 ACTION S Note INSERT 3 A13 INSERT 5 A15 INSERT 4 A14 Insert Page 3/4 3-22 ITS ITS 3.3.2Table 3.3.2-1 INSERT 3 Above the P-11 (Pressurizer Pressure) interlock.

INSERT 4 When Steam Line Isolation, Steam Line Pressure, Negative Rate-High is blocked.

INSERT 5 When Steam Line Isolation on Steam Line Pressure, Low is blocked.

A13 A14 A15 Footnote (a) Footnote (f) Footnote (g)

Page 19 of 80 ITS ITS 3.3.2 A01TABLE 3.3-3 (Continued)

TABLE NOTATION

  1. Trip function may be bypassed in this MODE below P

-11 (Pressurizer Pressure Block of Safety Injection) setpoint.

    1. Trip function automatically blocked above P

-11 and may be blocked below P-11 when Safety Injection on Steam Line Pressure

-Low is not blocked.

ACTION STATEMENTS

ACTION 15 - With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.

ACTION 16 - Deleted.

ACTION 17 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1.

ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 19 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

ACTION 20 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

September 14, 2006 SEQUOYAH - UNIT 2 3/4 3-22 Amendment Nos. 55, 132, 158, 174, 180, 192, 197, 203, 290, 300 Page 58 of 80Table 3.3.2-1 Footnote (a) and Footnote (f) Table 3.3.2-1 Footnote (g) (j) Except when all MSIV's are closed.

L04(k) Except when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve.

L05 ACTION S ACTION D 72 12Add proposed Required Action D.2.1 and D.2.2 L07 L08 M07 ACTION E ACTION P Add proposed Required Action E.2.1 and E.2.2 M08 L10 L09 See ITS 3.3.6 ACTION B ACTION N Add proposed Required Action P.2.1 and P.2.2 M09 ACTION S Note A16 72 for ACTION E, otherwise 6 12 for ACTION E, otherwise 4 INSERT 3 A13INSERT 4 A14 INSERT 5 A15 Insert Page 3/4 3-22 ITS ITS 3.3.2Table 3.3.2-1 INSERT 3 Above the P-11 (Pressurizer Pressure) interlock.

INSERT 4 When Steam Line Isolation, Steam Line Pressure, Negative Rate-High is blocked.

INSERT 5 When Steam Line Isolation on Steam Line Pressure, Low is blocked.

Page 59 of 80 A13 A14 A15 Footnote (a) Footnote (f) Footnote (g)

DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 8 of 35 A13 CTS Table 3.3-3 Note #, in part, is associated with Functional Units 1.d (Safety Injection, Pressurizer Pressure-Low) and 1.f (Safety Injection, Steam Line Pressure-Low). CTS Table 3.3-3 Note # modifies the Functional Unit's MODE of Applicability by stating that the trip function may be bypassed in MODE 3 below P-11 (Pressurizer Pressure Block of Safety Injection) setpoint. ITS Table 3.3.2-1 footnote (a) is associated with Functions 1.d (Safety Injection, Pressurizer Pressure-Low), and 1.e (Safety Injection, Steam Line Pressure-Low). ITS Table 3.3.2-1 footnote (a) modifies the Function's Applicability by stating "Above the P-11 (Pressurizer Pressure) interlock." This changes the CTS by replacing the description of how the P-11 interlock operates and when the Functions are allowed to be bypassed, with a statement of when the Functions are required to be OPERABLE.

The purpose of CTS Table 3.3-3 Note # is to modify the Applicability for the associated Functional Units stating when it is permissible for these Functional Units to be bypassed. Note # does this by providing information on the Functional Units interaction with interlock P-11. One purpose of P-11 is to prevent an inadvertent ECCS actuation during plant heatup and cooldown by blocking portions of the safety injection and steam line isolation signal actuation logic. The pressurizer low pressure and steamline low pressure safety injection actuation signals can be manually blocked when RCS pressure is below the P-11 permissive setpoint. CTS Table 3.3-3 Note # states that these Functional Units may be bypassed when below P-11. ITS Table 3.3.2-1 footnote (a) modifies the applicability of the pressurizer low pressure and steamline low pressure safety injection Functions, stating that they are required to be OPERABLE above the P-11 (Pressurizer Pressure) interlock. Thus replacing the statements in CTS for when they may be bypassed with statements in ITS for when these Functions are required to be OPERABLE. Therefore, ITS requires these Functions to provide a signal that will actuate safety injection under the same Conditions as CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A14 CTS Table 3.3-3 Note #, in part, is associated with Functional Unit 4.d (Steam Line Isolation, Steam Line Pressure-Low). CTS Table 3.3-3 Note # modifies the Functional Unit's MODE of Applicability by stating that the trip function may be bypassed in MODE 3 below P-11 (Pressurizer Pressure Block of Safety Injection) setpoint. ITS Table 3.3.2-1 footnote (f) is associated with Function 4.d.(1) (Steam Line Isolation, Steam Line Pressure, Low). ITS Table 3.3.2-1 footnote (f) modifies the Function's applicability by stating when Steam Line Isolation on Steam Line Pressure Negative Rate-High is blocked." This changes the CTS by replacing the description of how the P-11 interlock operates and when the Function is allowed to be bypassed, with a statement of when the Function is required to be OPERABLE.

The purpose of CTS Table 3.3-3 Note # is to modify the Applicability for the associated Functional Units stating when it is permissible for this Functional Unit to be bypassed. Note # does this by providing information on the Functional Units interaction with interlock P-11. One purpose of P-11 is to prevent an inadvertent ECCS actuation during plant heatup and cooldown by blocking DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 9 of 35 portions of the steam line isolation signal actuation logic. The steam line isolation steam pressure low actuation signal can be manually blocked when RCS pressure is below the P-11 permissive setpoint. CTS Table 3.3-3 Note #

states that this Functional Unit may be bypassed when below P-11. ITS Table 3.3.2-1 footnote (a) modifies the Applicability of the Steamline Isolation, Steam Line Pressure, Low Function by stating that this Function is required to be OPERABLE when Steam Line Isolation on Steam Line Pressure Negative Rate-High is blocked. Therefore, ITS requires this Function to provide a signal that will actuate steam line isolation under the same Conditions as CTS. This change is designated as administrative because it does not result in technical changes to the CTS. A15 CTS Table 3.3-3 Note ## is associated with Functional Unit 4.e (Steam Line Isolation, Negative Steam Line Pressure Rate-High). CTS Table 3.3-3 Note ##

modifies the Functional Unit's MODE of Applicability by stating that that the trip function is automatically blocked above P-11 and that it may be blocked below P11 when Safety Injection on Steam Line Pressure-Low is not blocked. ITS Table 3.3.2-1 footnote (g) is associated with Function 4.d.(2) (Steam Line Isolation, Steam Line Pressure, Negative Rate-High). ITS Table 3.3.2-1 footnote (g) modifies the applicability of the Steam Line Isolation, Steam Line Pressure, Negative Rate-High Function by stating that this Function is required to be OPERABLE when the Steam Line Isolation on Steam Line Pressure-Low Function is blocked." This changes the CTS by replacing the description of how the P-11 interlock operates and when the Function is allowed to be blocked, with a statement of when the Function is required to be OPERABLE.

The purpose of CTS Table 3.3-3 Note ## is to modify the Applicability for the associated Functional Unit stating when it is permissible for this Functional Unit to be blocked. Note ## does this by providing information on the Functional Unit's interaction with interlock P-11. One purpose of P-11 is to prevent an inadvertent ECCS or steam line isolation actuation during plant heatup and cooldown by blocking portions of the safety injection and steam line isolation signal actuation logic. The steam line isolation Negative Steam Line Pressure Rate-High actuation signal is automatically blocked when RCS pressure is above the P-11 permissive setpoint and can be manually enabled below P-11. CTS Table 3.3-3 Note ## states that this Functional Unit's trip function is automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on Steam Line Pressure-Low is not blocked. ITS Table 3.3.2-1 footnote (g) modifies the Applicability of the Steam Line Isolation, Steam Pressure, Negative Rate-High Function by stating that this Function is required to be OPERABLE when Steam Line Isolation on Steam Line Pressure-Low is blocked. Therefore, ITS requires this Function to provide a signal that will actuate steam line isolation under the same Conditions as CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A16 CTS Table 3.3-3 ACTION 20 requires that with the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. CTS Table 3.3-3 ACTION 20 is applicable to CTS Table 3.3-3 Functional Units ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-11 Rev. 4.0 SEQUOYAH UNIT 1 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 1 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

REQUIRED CHANNELS CONDITIONS

SURVEILLANCE REQUIREMENTS

ALLOWABLE VALUE

[NOMINAL (l) TRIP SETPOINT] 1. Safety Injection

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.

8 NA NA

b. Automatic Actuation Logic and Actuation Relays 1,2,3,4 2 trains C SR 3.3.2.2 SR 3.3.2.

4 SR 3.3.2.

6 NA NA c. Containment Pressure -

High 1 1,2,3 3 D SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [3.86] psig [3.6] psig d. Pressurizer Pressure - Low 1,2,3 (a) [3] D SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [1839] psig [1850] psig e. Steam Line Pressure (1) Low 1,2,3 [(a)] 3 per steam line D

SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [635](d) psig [6 75](d) psig (2) High Differential Pressure Between Steam Lines 1,2,3 3 per steam line D

[SR 3.3.2.1] SR 3.3.2.5 (b)(c) SR 3.3.2.9 (b)(c) SR 3.3.2.10 [106] psig

[97] psig (a) Above the P-11 (Pressurizer Pressure) interlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in

[insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

- 1.6 1.54 1864.8 1870592.2 600 3.3.2.1, and ACTION 3.3.2.1, and ACTION 1.a 1.b 1.c 1.d 1.f Note # Table 3.3-3 Table 3.3-4 Note 1 7 3 5 9 9 9 4 4 8 8 4 8 4 3 3 3 3 3 2 2 2 2 3 2UFSAR Section 7.1.2 2 ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-15 Rev. 4.0 SEQUOYAH UNIT 1 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 5 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS

CONDITIONS

SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 4. Steam Line Isolation

d. Steam Line Pressure (1) Low 1,2 (j),3 (j) (a) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR3.3.2.10 [635](d) psig [675](d) psig (2) Negative Rate - High 3 (h) (j) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR 3.3.2.

10 [121.6](i) psi [110](i) psi (a) Above the P

-11 (Pressurizer Pressure) in terlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.

(h) Below the P

-11 (Pressurizer Pr essure) interlock.

(i) Time constant utilized in the rate/lag controller is [50] seconds.

(j) Except when all MSIVs are closed and [de-activated].


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used b y the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

592.2 600 107.8 100.0Table 3.3-3 4.d 4.e 3.3.2.1, and ACTION 3.3.2.1, and ACTION Table 3.3-4 Note 1 Table 3.3-4 Note 2 DOC L04 Table 3.3-3 Note ## 9 9 4 8 4 8 4 3 2 3 3 3 3 3 3 2UFSAR Section 7.1.2 2 2Note # When Steam Line Isolationon Steam Line Pressure, Low is blocked When Steam Line Isolation on Steam Line Pressure, Negative Rate-High is blocked f f e e e g h g h ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-11 Rev. 4.0 SEQUOYAH UNIT 2 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 1 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

REQUIRED CHANNELS CONDITIONS

SURVEILLANCE REQUIREMENTS

ALLOWABLE VALUE

[NOMINAL (l) TRIP SETPOINT] 1. Safety Injection

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.

8 NA NA

b. Automatic Actuation Logic and Actuation Relays 1,2,3,4 2 trains C SR 3.3.2.2 SR 3.3.2.

4 SR 3.3.2.

6 NA NA c. Containment Pressure -

High 1 1,2,3 3 D SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [3.86] psig [3.6] psig d. Pressurizer Pressure - Low 1,2,3 (a) [3] D SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [1839] psig [1850] psig e. Steam Line Pressure (1) Low 1,2,3 [(a)] 3 per steam line D

SR 3.3.2.1 SR 3.3.2.

5 (b)(c) SR 3.3.2.

9 (b)(c) SR 3.3.2.

10 [635](d) psig [6 75](d) psig (2) High Differential Pressure Between Steam Lines 1,2,3 3 per steam line D

[SR 3.3.2.1] SR 3.3.2.5 (b)(c) SR 3.3.2.9 (b)(c) SR 3.3.2.10 [106] psig

[97] psig (a) Above the P-11 (Pressurizer Pressure) interlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in

[insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

- 1.6 1.54 1864.8 1870592.2 600 3.3.2.1, and ACTION 3.3.2.1, and ACTION 1.a 1.b 1.c 1.d 1.f Note # Table 3.3-3 Table 3.3-4 Note 1 7 3 5 9 9 9 4 4 8 8 4 8 4 3 3 3 3 3 2 2 2 2 3 2UFSAR Section 7.1.2 2 ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-15 Rev. 4.0 SEQUOYAH UNIT 2 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 5 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS

CONDITIONS

SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 4. Steam Line Isolation

d. Steam Line Pressure (1) Low 1,2 (j),3 (j) (a) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR3.3.2.10 [635](d) psig [675](d) psig (2) Negative Rate - High 3 (h) (j) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR 3.3.2.

10 [121.6](i) psi [110](i) psi (a) Above the P

-11 (Pressurizer Pressure) in terlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.

(h) Below the P

-11 (Pressurizer Pr essure) interlock.

(i) Time constant utilized in the rate/lag controller is [50] seconds.

(j) Except when all MSIVs are closed and [de-activated].


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used b y the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

592.2 600 107.8 100.0Table 3.3-3 4.d 4.e 3.3.2.1, and ACTION 3.3.2.1, and ACTION Table 3.3-4 Note 1 Table 3.3-4 Note 2 DOC L04 Table 3.3-3 Note ## 9 9 4 8 4 8 4 3 2 3 3 3 3 3 3 2UFSAR Section 7.1.2 2 2Note # When Steam Line Isolationon Steam Line Pressure, Low is blocked When Steam Line Isolation on Steam Line Pressure, Negative Rate-High is blocked f f e e e g h g h Licensee Response/NRC Response/NRC Question Closure Id106NRC Question Number KAB024Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/6/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/6/2014 10:05 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 48NRC Question Number KAB025Category Editorial ITS Section 3.3ITS Number 3.3.2DOC Number L-8JFD Number JFD Bases Number Page Number(s) 440NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 440 of Enclosure 2, Volume 8, L08 provides the discussion of the requirements for bypassing inoperable channels during surveillance testing as stated in CTS Table 3.3-3 ACTION 17. In the discussion, some of the numerical references are intermixed in such a way that they should reference the CTS numerical functional units and instead they reference the ITS numerical functions, and vice versa. For example, L08 states, "This allowance is applicable to CT S Table 3.3-3 Functional Units -:1.e (Steam Line Pressure -

Low); 4.d.(1) (Steam Line Pressure-Low); 4.d.(2) (Negative Steam Line Pressure Rate-High)-,"this sentence should list the CTS numbers for the functional units but instead lists the numbers for the same functions in ITS. Please review L08 and submit the needed corrections, or explain why intermixing the numerical identifiers is correct.Attach File 1 Attach File 2 Issue Date 5/9/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:50 AMNotification Scott BowmanMichelle Conner Andrew HonLynn MynattRay Schiele Roger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=48 Licensee Response/NRC Response/NRC Question Closure Id 65NRC Question Number KAB025 Select Application Licensee Response Attachment 1 Attachment 1 revised 3.3.2 DOC L08.pdf (16KB)Attachment 2 Response Statement In response to KAB025, discussion of change (DOC) L08, on page 440 of Enclosure 2, Volume 8, will be revised.Specifically, CTS Table 3.3-3 references to Functional Units 1.e, 4.d.(1), and 4.d.(2) will be revised to 1.f, 4.d, and 4.e, respectively.ITS Table 3.3.2-1 references to Functional Units 1.f, 4.d, 4.e, and 5.a will be revised to 1.e, 4.d.(1), 4.d.(2), and 5.b, respectively.

See Attachment 1 for the draft revised DOC L08.Response Date/Time 5/29/2014 1:30 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 5/29/2014 12:25 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 29 of 35 designated as less restrictive because additional time is allowed to restore parameters to within the LCO limits than was allowed in the CTS.

L08 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 3.3-3 ACTION 17 allows in part that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following listed conditions are satisfied but further states that the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1. This allowance is applicable to CTS Table 3.3-3 Functional Units 1.c (Containment Pressure - High); 1.d (Pressurizer Pressure - Low); 1.e (Steam Line Pressure - Low); 4.d.(1) (Steam Line Pressure - Low); 4.d.(2) (Negative Steam Line Pressure Rate - High); and 5.a (Steam Generator Water Level - High-High). ITS 3.3.2 ACTION D Required Actions are modified by a Note that states; "The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels." This allowance is applicable to ITS Table 3.3.2-1 Functional Units 1.c (Containment Pressure - High); 1.d (Pressurizer Pressure - Low); 1.f (Steam Line Pressure -

Low); 4.d (Steam Line Pressure - Low); 4.e (Negative Steam Line Pressure Rate

- High); and 5.a (Steam Generator Water Level - High-High). This changes the CTS by increasing the time allowed for these functions to be bypassed from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The purpose of CTS Table 3.3-3 ACTION 17 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable or prior to being placed in a tripped state. The proposed bypass time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in ITS 3.3.2 ACTION D is a sufficient time to perform train or channel surveillance. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period is acceptable based on TVA's confirmation of applicability and incorporation of insights as described in Enclosure 4 of this submittal, required by the NRC in their letter and enclosed Safety Evaluation Report (SER) dated July 15, 1998, "Review of Westinghouse Owners Group Topical Reports WCAP-14333-P and WCAP-14334-NP, dated May 1995, 'Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times' (TAC NO. M92782)." This change is designated as less restrictive because additional time is allowed for an inoperable channel to be bypassed for maintenance than was allowed in

the CTS. L09 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 3.3-3 ACTION 18, requires, in part, that with the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This action is applicable to CTS Table 3.3-3 Functional Units 2.c (Containment Pressure -- High-High); 3.b.3) (Containment Pressure -- High-High); 4.c (Containment Pressure -- High-High); 9.a (RWST Level - Low); and 9.a (Containment Sump Level - High). ITS Table 3.3.2-1 designates Condition E as the referenced Condition for Functions 2.c (Containment Pressure -- High-High), 3.b.(3)

(Containment Pressure -- High-High), and 4.c (Containment Pressure -- High-High) while designating Condition P as the referenced Condition for Functions 7.b (RWST Level - Low) and 7.b (Containment Sump Level - High). ITS 3.3.2, Licensee Response/NRC Response/NRC Question Closure Id 79NRC Question Number KAB025Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:38 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 49NRC Question Number KAB026Category Technical ITS Section 3.3 ITS Number 3.3.2 DOC Number L-10JFD Number JFD Bases Number Page Number(s) 441NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 441 of Enclosure 2, Volume 8, L10 provides the discussion of the requirements for bypassing in operable channels during surveillance testing as stated in CTS Table 3.3-3 ACTION 18.

L10 states:

ITS 3.3.2 ACTIONS E Required Ac tions are modified by a Note that states; "The inoper able channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels."This allowance is applicable to ITS Table 3.3.2-1 Functional Units-and 7.b (RWST Level -Low).ITS 3.3.2 Required Action Note retains the CTS inoperable channel bypass allowance of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance

testing of other channels.

The note modifying ITS 3.3.2 Required Actions for Condition E is not quoted correctly.The note in ITS 3.3.2 Required Actions for Condition E is not applicable to function 7.b (RWST Level -Low).The last se ntence of the quote above is confusing because the note in ITS 3.3.2 Required Actions for Condition E has an allowance is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Please (1) correct quote of the note modifying ITS 3.3.2 Required Actions for Condition E, (2) remove function 7.b from the discussion of ITS Condition E or revise the sentence Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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to include discussion of ITS Condition P, and (3) explain the meaning of the last sentence.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:52 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 97 NRC Question Number KAB026Select Application Licensee Response Attachment 1 Attachment 1 3.3.2 revised DOC L10.pdf (17KB)Attachment 2 Response Statement In response to KAB026, discussion of change (DOC) L10, on page 441 of Enclosure 2, Volume 8, will be revised.The following changes will be made:(1)The ITS 3.3.2 ACTION S E Required Actions Note will be revised to state, "One additional channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels."(2)ITS function 7.b (RWST Level -Low) will be removed from the discussion concerning the applicatio n of ITS 3.3.2 ACTIONS E Required Actions Note.(3)The sentence, "ITS 3.3.2 Required Action Note retains the CTS inoperable channel bypass allowance of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels."will be revised to state, "ITS 3.3.2 ACTIONS P Required Action Note retains the CTS one additional channel bypass allowance of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels."This sentence is included in DOC L10 to indicate th at CTS ACTION 18 becomes ITS ACTIONS E and P, and although ITS ACTIONS E is increasing the time allowed for an additional channel to be bypassed (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> s to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />); ITS ACTIONS P retains the CTS allowance time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.(4)The sentence, "This changes the CTS by incr easing the time allowed for an additional channel to be bypassed for these Functional Units from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."will be revised to state, "This cha nges the CTS by increasing the time allowed for an additional channel to be bypassed for Functional Units 2.c, 3.b.(3), and 4.c, from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."This sentence will be revised to indicate that the change to CTS, increasing the time allowed for an additional channel to be bypassed, is only applicable to Functional Units 2.c, 3.b.(3), and 4.c.

See Attachment 1 for the draft revised DOC L10.Response Date/Time 6/5/2014 4:20 PMClosure Statement Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 6/5/2014 3:16 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 30 of 35 Required Actions E.1 requires placing the associated channel in bypass with a Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for ITS Table 3.3.2-1 Functions 2.c (Containment Pressure -- High-High), 3.b.(3) (Containment Pressure -- High-High), and 4.c (Containment Pressure -- High-High). ITS 3.3.2 Required Action P.1 retains the CTS Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for placing the associated inoperable channel in bypass. This changes the CTS by increasing the Completion Time for placing an inoperable channel in bypass for these Functional Units from six (6) hours to 72

hours.

The purpose of CTS Table 3.3-3 ACTION 18 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable or prior to being placed in a bypassed state. This change is acceptable because the Completion Time is consistent with safe operation under the specified Condition, considering the OPERABLE status of the redundant systems or features. This includes the capacity and capability of remaining systems or features, a reasonable time for repairs or replacement, and the low probability of a DBA occurring during the allowed Completion Time. Additionally, this change is acceptable based on TVA's confirmation of applicability and incorporation of insights as described in Enclosure 4 of this submittal, required by the NRC in their letter and enclosed Safety Evaluation Report (SER) dated July 15, 1998, "Review of Westinghouse Owners Group Topical Reports WCAP-14333-P and WCAP-14334-NP, dated May 1995, 'Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times' (TAC NO. M92782)." This change is designated as less restrictive because additional time is allowed to restore parameters to within the LCO limits than was allowed in the CTS.

L10 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 3.3-3 ACTION 18 requires, in part, that with the number of OPERABLE channels one less than the Total Number of Channels operation may proceed provide the specified conditions are met but further states that one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1. This allowance is applicable to CTS Table 3.3-3 Functional Units 2.c (Containment Pressure - High-High); 3.b.3) (Containment Pressure - High-High); 4.c (Containment Pressure - High-High); 9.a (RWST Level - Low); and 9.a (Containment Sump Level - High). ITS Table 3.3.2-1 designates Condition E as the referenced Condition for Functions 2.c (Containment Pressure -- High-High), 3.b.(3) (Containment Pressure -- High-High), and 4.c (Containment Pressure -- High-High) while designating Condition P as the referenced Condition for Functions 7.b (RWST Level - Low) and 7.b (Containment Sump Level - High). ITS 3.3.2 ACTIONS E Required Actions are modified by a Note that states; "The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels." This allowance is applicable to ITS Table 3.3.2-1 Functional Units 2.c (Containment Pressure - High-High); 3.b.3) (Containment Pressure - High-High); 4.c (Containment Pressure - High-High);

and 7.b (RWST Level - Low). ITS 3.3.2 Required Action Note retains the CTS

inoperable channel bypass allowance of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels. This changes the CTS by increasing the time allowed for an additional channel to be bypassed for these Functional Units from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Licensee Response/NRC Response/NRC Question Closure Id107NRC Question Number KAB026Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/6/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/6/2014 10:06 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 50NRC Question Number KAB027 Category Editorial ITS Section 3.3 ITS Number 3.3.2DOC Number L-11JFD Number JFD Bases Number Page Number(s) 442NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 442 of Enclosure 2, Volume 8, L 11 provides the discussion of CTS Table 3.3-3 ACTION 23. CTS ACTION 23 is co mpared to ITS 3.3.2 Condition H.

However, in the last paragraph it discu sses ITS 3.3.2 Condition G. Please provide a revised L11 that discusses the approp riate ITS 3.3.2 Condition or explain why both ITS Conditions are correct.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:54 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn Mynatt Ray SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=50 Licensee Response/NRC Response/NRC Question Closure Id 64NRC Question Number KAB027Select Application Licensee Response Attachment 1 revised 3.3.2 DOC L11.pdf (13KB)Attachment 2 Response Statement In response to KAB027, discussion of change (DOC) L11, on page 442 of , Volume 8, will be revised.Specificall y, the reference to ITS 3.3.2 ACTION G will be revised to referen ce ITS 3.3.2 ACTION H.See Attachment 1 for th e draft revised DOC L11.Response Date/Time 5/29/2014 12:45 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 5/29/2014 11:41 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 31 of 35 The purpose of CTS Table 3.3-3 ACTION 18 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable or prior to being placed in a bypassed state. The proposed bypass time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in ITS 3.3.2 ACTION E is a sufficient time to perform train or channel surveillance. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period is acceptable based on TVA's confirmation of applicability and incorporation of insights as described in Enclosure 4 of this submittal, required by the NRC in their letter and enclosed Safety Evaluation Report (SER) dated July 15, 1998, "Review of Westinghouse Owners Group Topical Reports WCAP-14333-P and WCAP-14334-NP, dated May 1995, 'Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times' (TAC NO. M92782)." This change is designated as less restrictive because additional time is allowed for an inoperable channel to be bypassed for maintenance than was allowed in

the CTS.

L11 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports)

CTS Table 3.3-3, ACTION 23 for Functional Units 4.b (Steam Line Isolation, Automatic Actuation Logic), 5.b (Turbine Trip & Feedwater Isolation, Automatic Actuation Logic), and 6.b (Auxiliary Feedwater, Automatic Actuation Logic) states, "With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1." ITS 3.3.2, ACTION H for Functions 4.b (Steam Line Isolation, Automatic Actuation Logic and Actuation Relays), 5.a (Turbine Trip & Feedwater Isolation, Automatic Actuation Logic and Actuation Relays), and 6.a (Auxiliary Feedwater, Automatic Actuation Logic and Actuation Relays) requires restoration of the inoperable train to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in MODE 3 within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />; and is modified by a Note stating, "One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE." This changes the CTS by allowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for train maintenance to restore the train to an OPERABLE status before requiring a power reduction to MODE 3 within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 in additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for an inoperable Steam Line Isolation, Automatic Actuation Logic, Turbine Trip & Feedwater Isolation, Automatic Actuation Logic, or Auxiliary Feedwater, Automatic Actuation Logic, plus increasing the allowed time a train can be bypassed for surveillance testing from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The purpose of CTS Table 3.3-3, ACTION 23 is to allow some time to restore the inoperable train before requiring a unit shut down. ITS LCO 3.3.2 ACTION G allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the train to an OPERABLE status and the Required Actions Note allows placing one train in the bypassed condition for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> while performing routine surveillance testing provided the other train is OPERABLE. These changes are acceptable and are the result of WCAP-14333-P-A, Revision 1 ("Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times"), dated October 1998, or WCAP-15376-P-A, Revision 1 ("Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times"), dated March 2003 (or a combination of the WCAPs). TVA has performed evaluations of the applicable changes associated with the two Licensee Response/NRC Response/NRC Question Closure Id 80NRC Question Number KAB027Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:39 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=80 ITS NRC Questions Id 51NRC Question Number KAB028Category TechnicalITS Section 3.3ITS Number 3.3.2DOC Number L-12JFD Number JFD Bases Number Page Number(s) 443NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 443 of Enclosure 2, Volume 8, L12 provides the discussion of the proposed change that adds required action k.2, whic h allows placing the affected protection set, steam generator water level low low channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. L12 states, "Once the channel is placed in the tripped condition the RCS T TTD circuitry is removed from the active portion of the Steam Generator Low-Low Level channel, reference UFSAR Figure 7.2.1-1, Sheets 17 thro ugh 20 and this action is no longer necessary."Please explain how placing the steam generator low-low level channel in trip, removes the RCS T TTD circuitry. In additi on, explain how placing the steam generator low low level channel in trip will not affect the TTD circuitry for the other operable SG water level low low channels.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:55 AMNotification Scott BowmanMichelle ConnerAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=51 Licensee Response/NRC Response/NRC Question Closure Id 66 NRC Question Number KAB028Select Application Licensee ResponseAttachment 1 Attachment 1 UFSAR and Training Documents for KAB028.pdf (840KB)Attachment 2 Attachment 2 ITS DOC L12 Markup for KAB028.pdf (1MB)Response Statement Placing the Steam Generator Water Level Low-Low Channel in trip does not literally remove the RCS T TTD circuitry from th e active portion of the circuitry, as stated in discussion of change (DOC) L12. In the signal flow path for the Steam Generator Low-Low Level Channel trip, the manual trip is downstream of the RCS T TTD input into the Ea gle 21 System, thereby negating the RCS T TTD effect on the tr ip circuit. The RCS T TTD input remains in the circuit, but with the manual tr ip in place, the RCS T TTD has no effect on the circuit.Therefore, DOC L12 will be revised to replace the sentence, "Once the channel is placed in the tripped condition the RCS T TTD circuitry is removed from the active portion of the Steam Generator Low-Low Level channel, reference UFSAR Figure 7.2.1-1, Sheets 17 through 20 and this action is no longer necessary,"with, "Once the channel is placed in the trippe d condition, the RCS T TTD input has no effect on the circuit, and this action is no longer necessary."Because of the location of the ma nual Steam Generato r Low-Low Level Channel Trip in the circuitry, there is no impact on the RCS T TTD setpoint selection for the other opera ble Steam Generator Low-Low Level channels.Each RCS T TTD channel only impacts Steam Generator Low-Low Level Channels from the same Protection Set channel. contains UFSAR Figure 7.2.1-1, Sheet 19 and 20 along with the Operations training material associated with the Eagle 21 System.The UFSAR figures depict the logic for Auxiliary Feedwater Start and are annotated to show where the manual trip would impact the circuit.It also shows that an RCS T TTD channel only impacts the associated level channels. The Eagle 21 material illustrates the location of the manual trip within the Eagle 21 System.See Attachment 2 for a draft ITS DOC L12 markup.Response Date/Time 5/29/2014 3:30 PM Closure Statement Question Closure Date Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 5/29/2014 2:27 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Eagle 21 OverviewBlock diagram The block diagram of an Eagle 21 channel is shown below. Only one channel is shown, other channels are similar. Tester SubsystemOutputSubsystemPowerSupply&DistributionSubsystemCabinetDiagnostics118 VAC(Non-Vital)EPT(1 TO 7)EAO(1 TO 4)ECO(1 OR 2)MMI SubsystemTouch ScreenDLHMMIPiSCB286/12KeyboardMULTIBUS DDCiSBC519H.P. DACDT-716D(2)TSP iSBC286/12 DLHiSBC88/45FRONT TEST PANELMULTIBUSI/OSubsystemDFP iSBC88/40A(1 or 2)LCP iSBC286/12DLHiSCB88/45MULTIBUSERI(1 TO 8)EAI(1 TO 8)MULT/15PWR SUPLoopProcessorSubsystem+15v+12v+5v-12v+15v+12v+5v-12v118v ACAs many as 16 input/DFP15/MULTPWR SUP118v AC(VITAL)SECISPC 286/12 toFOC+15v RelayRear TestPanelBBC DACMP8316-V(1 or 2)Transmitter orContact Closure RTD orNISRack1, 3, 4, 5, 7,8, 9, 11, 12XHP(0-7)A B+15v A+15v B+15vRelayDaughterBoard+15v A+15v B118v AC DDCiSCB519Control andIndication MCRAnnunciatorsandTest SignalsTrain ATrain BSolid StateProtection SystemField SideField SideSIRBUSSIRBUSSIRBUSPrinterEAGLE 21Block Diagram(Typical of each cabinet)

Loop Processor Subsystem The Loop Processor Subsystem performs the following major functions: Converts analog inputs to numerical representations. Automatically calibrates the input signals and corrects for differences. Provides dynamic compensation (like OPT, OPT calculations) Provides algebraic calculations (Tavg). Compares inputs to trip setpoint values and provides a trip signal to the partial trip bistable (maintains reactor trip setpoints in memory for comparison). Provides analog outputs for indication and control. Provides data to Tester Subsystem.

Eagle 21 Loop Processor SubsystemFunctional diagram of LCP The functional diagram for a typical LCP is shown below. SUMCalc IERIDFPERI DFPERIDFPFilterFilterFilterAverage TcAverage ThTh StreamingTavgTCalc OTTSetpointT TripSummer DDC DDCEPTEPT DAC DACEAOEAOTurbineRunbackCtrl BoardMeterCtrl BoardMeter DACEAOCtrl BoardMeterT TripBistableT RnBkBistableLo TavgBistable DDC EPTFeedwaterIsolationLo-Lo TavgBistableDDC EPTP-12Hot Leg RTDsCold Leg RTDsPzr PressurePwr RangeNeutron FluxLowerUpperCalculatesStreamingEffectsComputerSoftwareFunctionTo OtherRacksRng ChkRng ChkRng Chk 1 2 3 4 5 6 7 8 9LoopCalculationProcessor TE TE TE EAIDFPERIDFPERI DFPFilterFilterRng ChkRng ChkRng Chk TE TE PTERIDFPRng ChkERI DFPRng Chk Eagle-08 Output SubsystemDescription The Output Subsystem consists of three types of output cards: EPT - Eagle Partial Trip board. Th is board provides 118 VAC output to SSPS except for 21 channel receive 118V AC from SSPS. EAO - Eagle Analog Output board. This board provides isolation from and out to the Foxbro control and indications racks. ECO - Eagle Contact Output board. This board provides outputs from the testersysystem.Diagram of EPT board Each EPT board has four EPT circuits. The purpose of the Eagle Partial Trip Boards (EPT) is to: control the 118 VAC to the SSPS input relays. allow the tester subsystem to remotely place any or all of the four channels in a trip or bypass state. allow personnel to manually place any channel in a trip condition. supply channel status information to the tester subsystem and provide local indication of the output state of each channel The EPT circuit is described below. MicroControllerBufferOptoIsolatorDeadmanTimer 2StatusDetect 1StatusDetect 2BoardPowerSupply+8V-8V+15V+5V V Ref15V A15V BCommonPulledCard118 V ACLineNeutTo OtherChannelsOptoIsolatorStatusDetector ToSSPSInputRelaysswcSW5 SSROptoIsolatorSW4ManualTripTrickle0.25 MAMain17 MASW2TesterPartialTripSW1AttemptPartial Trip1 SEC120 MSEC SW3BypassTrip Channel

+5VDeadmanTimer 1 RTesterSubsystem5 VDC PulseTrain fromLCP/DDCCurrent SuppliesLED 3 5 4 2 1 R G The current flow to maintain SW5 energized flows in a loop as follows: the main current supply which prov ides the power to maintain SW5 energized, through Manual Trip switch SW4 wh ich is used to manually trip the channel, to Attempt Partial Trip switch SW 1 which is the automatic trip signal from the LCP/DDC for the channel, DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 32 of 35 WCAPs to justify the above changes. The evaluations supporting these changes are provided in Enclosure 4 of this submittal. This change is designated as less restrictive because more time is allowed in the ITS for the maintenance and testing of trains than was allowed in the CTS.

L12 (Category 4 - Relaxation of Required Action) CTS Table 3.3-3 ACTION 37 requires that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Trip Time Delays (T S and T M) threshold power level for zero seconds time delay is adjusted to 0% RTP. This action is applicable to CTS Functional Unit 6.c.i.c (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Motor-Driven Pumps, RCS Loop T) and Functional Unit 6.c.ii.c (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Turbine-Driven Pump, RCS Loop T). ITS 3.3.2 Required Action K.2 allows an alternative of placing the Steam Generator Water Level -- Low-Low channel in trip instead of adjusting the Trip Time Delays (T S and T M) threshold power level for zero seconds time delay to 0% RTP with the same Completion Time. This changes the CTS by adding an alternative to adjusting the TTD threshold power level for zero seconds.

The purpose of CTS Table 3.3-3 ACTION 37 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable prior to adjusting the affected protection sets Trip Time Delays (T S and T M) threshold power level for zero seconds time delay to 0% RTP. With the trip time delay adjusted to zero seconds the additional operational margin that allows the operator time to recover SG Water level is removed and the associated SG Water level channel is returned to OPERABLE. If the threshold power level for zero seconds time delay is not adjusted from 50% RTP to 0% RTP within the specified Completion Time this proposed change allows placing the affected protection set's SG Water Level Low-Low channels in the tripped condition.

Once the channel is placed in the tripped condition the RCS T TTD circuitry is removed from the active portion of the Steam Generator Low-Low Level channel, reference UFSAR Figure 7.2.1-1, Sheets 17 through 20 and this action is no longer necessary. The action of tripping the channel provides the protection sets input to the 2/3 logic gates located on UFSAR Figure 7.2.1-1 Sheet 19. The ITS Required Action K.2 Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with CTS TABLE 3.3-3 ACTION 37 and the proposed ITS Required Action K.1. This change is designated as less restrictive because less stringent Required Actions are being applied in ITS than were applied in CTS.

L13 (Category 4 - Relaxation of Required Action) CTS Table 3.3-3 ACTION 38 requires that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse). This action is applicable to CTS Functional Unit 6.c.i.d (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Motor-Driven Pumps, Containment Pressure (EAM)) and Functional Unit 6.c.ii.d (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Turbine-Driven Pump, Containment Pressure (EAM)).

Licensee Response/NRC Response/NRC Question Closure Id 81NRC Question Number KAB028Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:39 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=81 ITS NRC Questions Id 52 NRC Question Number KAB029Category TechnicalITS Section 3.3ITS Number 3.3.2DOC Number L-13JFD Number JFD Bases Number Page Number(s) 443 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested N NRC Question On page 443 of Enclosure 2, Volume 8, L13 provides the discussion of the proposed change that adds required action j.2, which allows placing the affected protection set, steam generator water level Low-low channel(s) in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. L13 states, "Once the channel is placed in the tripped condition the Steam Generator Water Level --Low-Low EAM/Adverse circuitry is removed from the active portion of the Steam Generator Water Level --Low-Low channel, reference UFSAR Fi gure 7.2.1-1, Sheets 17 through 20, and these actions are no longer necessary."Please explain how placing the steam generator low low level channel in trip, removes the Steam Generator Low-Low EAM/Adverse circuitry.

In addition, explain how placing the steam generator low low level channel in trip will not affect the EAM setpoint selection for the other operable SG water level low low channels.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy Bucholtz Date Modified Modified By Date Added 5/9/2014 8:56 AMNotification Scott BowmanMichelle Conner Andrew HonLynn Mynatt Ray Schiele

Roger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 67NRC Question Number KAB029 Select Application Licensee ResponseAttachment 1 Attachment 1 UFSAR and Training Documents for KAB029.pdf (362KB)Attachment 2 Attachment 2 ITS DOC L13 Markup for KAB029.pdf (926KB)Response Statement Placing the Steam Generator Low-Low Level Channel in trip does not literally remove the EAM/Adverse circuitry from the active portion of the circuitry, as stated in the discussion of change (DOC) L13. In the signal flow path for the Steam Generator Lo w-Low Level Channel trip, the manual trip is downstream of th e EAM/Adverse input into the Eagle 21 System, thereby negating the EAM/Adverse effect on the trip circuit. The EAM/Adverse input remains in the circuit, but with the manual trip in place, the EAM/Adverse has no effect on the circuit.Therefore, DOC L13 will be revised to replace the sentence, "Once the channel is placed in the tripped condition the Steam Generator Water Level Low-Low EAM/Adverse circuitry is removed from the active portion of the Steam Generator Water Level Low-Low channel, reference UFSA R Figure 7.2.1-1, Sheets 17 through 20 and these actions are no longer necessary,"with, "Once the channel is placed in the tripped condition, the EAM/Adverse input has no effect on the circuit, and these actions are no longer necessary."

Because of the location of the manual Steam Generator Low-Low Level Channel Trip in the circuitry, ther e is no impact on the EAM setpoint selection for the other operable Steam Generator water level low-low channels.Each EAM channel only impacts Steam Generator Level Channels from the same Protection Set channel. contains UFSAR Figure 7.2.1-1, Sh eet 19 and 20 along with the Operations training material associated with the Eagle 21 System.The UFSAR figures depict the logic for Auxiliary Feedwater Start and are annotated to show where the manual trip would impact the circuit.It also shows that an EAM channel only impacts the associated level channels. The Eagle 21 material illu strates the location of the manual trip within the Eagle 21 System.See Attachment 2 for a draft ITS DOC L13 markup.Response Date/Time 5/29/2014 3:30 PM Closure Statement Question Closure Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleAdded By Scott Bowman Date Added 5/29/2014 2:29 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Eagle 21 OverviewBlock diagram The block diagram of an Eagle 21 channel is shown below. Only one channel is shown, other channels are similar. Tester SubsystemOutputSubsystemPowerSupply&DistributionSubsystemCabinetDiagnostics118 VAC(Non-Vital)EPT(1 TO 7)EAO(1 TO 4)ECO(1 OR 2)MMI SubsystemTouch ScreenDLHMMIPiSCB286/12KeyboardMULTIBUS DDCiSBC519H.P. DACDT-716D(2)TSP iSBC286/12 DLHiSBC88/45FRONT TEST PANELMULTIBUSI/OSubsystemDFP iSBC88/40A(1 or 2)LCP iSBC286/12DLHiSCB88/45MULTIBUSERI(1 TO 8)EAI(1 TO 8)MULT/15PWR SUPLoopProcessorSubsystem+15v+12v+5v-12v+15v+12v+5v-12v118v ACAs many as 16 input/DFP15/MULTPWR SUP118v AC(VITAL)SECISPC 286/12 toFOC+15v RelayRear TestPanelBBC DACMP8316-V(1 or 2)Transmitter orContact Closure RTD orNISRack1, 3, 4, 5, 7,8, 9, 11, 12XHP(0-7)A B+15v A+15v B+15vRelayDaughterBoard+15v A+15v B118v AC DDCiSCB519Control andIndication MCRAnnunciatorsandTest SignalsTrain ATrain BSolid StateProtection SystemField SideField SideSIRBUSSIRBUSSIRBUSPrinterEAGLE 21Block Diagram(Typical of each cabinet)

Loop Processor Subsystem The Loop Processor Subsystem performs the following major functions: Converts analog inputs to numerical representations. Automatically calibrates the input signals and corrects for differences. Provides dynamic compensation (like OPT, OPT calculations) Provides algebraic calculations (Tavg). Compares inputs to trip setpoint values and provides a trip signal to the partial trip bistable (maintains reactor trip setpoints in memory for comparison). Provides analog outputs for indication and control. Provides data to Tester Subsystem.

Eagle 21 Loop Processor SubsystemFunctional diagram of LCP The functional diagram for a typical LCP is shown below. SUMCalc IERIDFPERI DFPERIDFPFilterFilterFilterAverage TcAverage ThTh StreamingTavgTCalc OTTSetpointT TripSummer DDC DDCEPTEPT DAC DACEAOEAOTurbineRunbackCtrl BoardMeterCtrl BoardMeter DACEAOCtrl BoardMeterT TripBistableT RnBkBistableLo TavgBistable DDC EPTFeedwaterIsolationLo-Lo TavgBistableDDC EPTP-12Hot Leg RTDsCold Leg RTDsPzr PressurePwr RangeNeutron FluxLowerUpperCalculatesStreamingEffectsComputerSoftwareFunctionTo OtherRacksRng ChkRng ChkRng Chk 1 2 3 4 5 6 7 8 9LoopCalculationProcessor TE TE TE EAIDFPERIDFPERI DFPFilterFilterRng ChkRng ChkRng Chk TE TE PTERIDFPRng ChkERI DFPRng Chk Eagle-08 Output SubsystemDescription The Output Subsystem consists of three types of output cards: EPT - Eagle Partial Trip board. Th is board provides 118 VAC output to SSPS except for 21 channel receive 118V AC from SSPS. EAO - Eagle Analog Output board. This board provides isolation from and out to the Foxbro control and indications racks. ECO - Eagle Contact Output board. This board provides outputs from the testersysystem.Diagram of EPT board Each EPT board has four EPT circuits. The purpose of the Eagle Partial Trip Boards (EPT) is to: control the 118 VAC to the SSPS input relays. allow the tester subsystem to remotely place any or all of the four channels in a trip or bypass state. allow personnel to manually place any channel in a trip condition. supply channel status information to the tester subsystem and provide local indication of the output state of each channel The EPT circuit is described below. MicroControllerBufferOptoIsolatorDeadmanTimer 2StatusDetect 1StatusDetect 2BoardPowerSupply+8V-8V+15V+5V V Ref15V A15V BCommonPulledCard118 V ACLineNeutTo OtherChannelsOptoIsolatorStatusDetector ToSSPSInputRelaysswcSW5 SSROptoIsolatorSW4ManualTripTrickle0.25 MAMain17 MASW2TesterPartialTripSW1AttemptPartial Trip1 SEC120 MSEC SW3BypassTrip Channel

+5VDeadmanTimer 1 RTesterSubsystem5 VDC PulseTrain fromLCP/DDCCurrent SuppliesLED 3 5 4 2 1 R G The current flow to maintain SW5 energized flows in a loop as follows: the main current supply which prov ides the power to maintain SW5 energized, through Manual Trip switch SW4 wh ich is used to manually trip the channel, to Attempt Partial Trip switch SW 1 which is the automatic trip signal from the LCP/DDC for the channel, DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 32 of 35 WCAPs to justify the above changes. The evaluations supporting these changes are provided in Enclosure 4 of this submittal. This change is designated as less restrictive because more time is allowed in the ITS for the maintenance and testing of trains than was allowed in the CTS.

L12 (Category 4 - Relaxation of Required Action) CTS Table 3.3-3 ACTION 37 requires that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Trip Time Delays (T S and T M) threshold power level for zero seconds time delay is adjusted to 0% RTP. This action is applicable to CTS Functional Unit 6.c.i.c (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Motor-Driven Pumps, RCS Loop T) and Functional Unit 6.c.ii.c (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Turbine-Driven Pump, RCS Loop T). ITS 3.3.2 Required Action K.2 allows an alternative of placing the Steam Generator Water Level -- Low-Low channel in trip instead of adjusting the Trip Time Delays (T S and T M) threshold power level for zero seconds time delay to 0% RTP with the same Completion Time. This changes the CTS by adding an alternative to adjusting the TTD threshold power level for zero seconds.

The purpose of CTS Table 3.3-3 ACTION 37 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable prior to adjusting the affected protection sets Trip Time Delays (T S and T M) threshold power level for zero seconds time delay to 0% RTP. With the trip time delay adjusted to zero seconds the additional operational margin that allows the operator time to recover SG Water level is removed and the associated SG Water level channel is returned to OPERABLE. If the threshold power level for zero seconds time delay is not adjusted from 50% RTP to 0% RTP within the specified Completion Time this proposed change allows placing the affected protection set's SG Water Level Low-Low channels in the tripped condition.

Once the channel is placed in the tripped condition the RCS T TTD circuitry is removed from the active portion of the Steam Generator Low-Low Level channel, reference UFSAR Figure 7.2.1-1, Sheets 17 through 20 and this action is no longer necessary. The action of tripping the channel provides the protection sets input to the 2/3 logic gates located on UFSAR Figure 7.2.1-1 Sheet 19. The ITS Required Action K.2 Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with CTS TABLE 3.3-3 ACTION 37 and the proposed ITS Required Action K.1. This change is designated as less restrictive because less stringent Required Actions are being applied in ITS than were applied in CTS.

L13 (Category 4 - Relaxation of Required Action) CTS Table 3.3-3 ACTION 38 requires that with the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse). This action is applicable to CTS Functional Unit 6.c.i.d (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Motor-Driven Pumps, Containment Pressure (EAM)) and Functional Unit 6.c.ii.d (Auxiliary Feedwater, Main Stm. Gen Water Level - Low-Low, Start Turbine-Driven Pump, Containment Pressure (EAM)).

DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 33 of 35 ITS 3.3.2 Required Action J.2 allows an alternative of placing the Steam Generator Water Level -- Low-Low channel in trip instead of adjusting the Steam Generator Water Level -- Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse) with the same Completion Time for placing the channel in trip. This changes the CTS by adding an alternative to adjusting the Steam Generator Water Level -- Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse).

The purpose of CTS Table 3.3-3 ACTION 38 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable prior to adjusting the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse). If the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint is not adjusted to the same value as Steam Generator Water Level --

Low-Low (Adverse) within the specif ied Completion Time this proposed change allows placing the affected protection sets SG Water Level -- Low-Low level channels in the tripped condition. Once the channel is placed in the tripped condition the Steam Generator Water Level -- Low-Low EAM/Adverse circuitry is removed from the active portion of the Steam Generator Water Level -- Low-Low channel, reference UFSAR Figure 7.2.1-1, Sheets 17 through 20, and these actions are no longer necessary. The action of tripping the channel provides the protection sets input to the 2/3 logic gates located on UFSAR Figure 7.2.1-1 Sheet 19. The ITS Required Action J.2 Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with CTS TABLE 3.3-3 ACTION 38 and the proposed ITS Required Action J.1.

This change is designated as less restrictive because less stringent Required Actions are being applied in ITS than were applied in CTS.

L14 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST on a quarterly basis (Q) for Functional Units: 1.c (Containment Pressure-High), 1.d (Pressurizer Pressure--Low); 1.f (Steam Line Pressure-Low); 2.c (Containment Pressure--High-High); 3.b.3) (Containment Pressure--High-High); 4.c (Containment Pressure--High-High); 4.d (Steam Line

Pressure--Low); 4.e (Negative Steam Line Pressure Rate--High); and 5.a (Steam Generator Water Level--High-High). ITS Table 3.3.2-1 requires performance of a COT (ITS SR 3.3.1.7 or SR 3.3.1.8) every 184 days for Functions: 1.c (Containment Pressure-High); 1.d (Pressurizer Pressure--Low); 1.e (Steam Line Pressure-Low); 2.c (Containment Pressure--High-High); 3.b.(3) (Containment Pressure--High-High); 4.c (Containment Pressure--High-High); 4.d.(1) (Steam Line Pressure--Low); 4.d.(2) (Steam Line Pressure Negative Rate--High); and 5.b (SG Water Level--High-High (P-14)). This changes the CTS by changing the

Frequency of the Surveillances from quarterly to 184 days.

The purpose of the CHANNEL FUNCTIONAL TEST/COT is to ensure that the instrumentation is functioning properly. These changes are acceptable and are the result of WCAP-10271, Revision 0 ("Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System"), dated May 1996, and supplements, WCAP-14333-P-A, Revision 1 ("Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times"), dated Licensee Response/NRC Response/NRC Question Closure Id 82NRC Question Number KAB029Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:40 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 53NRC Question Number KAB030 Category EditorialITS Section 3.3ITS Number 3.3.2DOC Number JFD Number JFD Bases Number Page Number(s) 504NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 504 of Enclosure 2, Volume 8, it was noticed that 1 was not included in ITS Table 3.3.2-1 footnote h, as it is in CTS Table 3.3-4 note 2. Please explain if this was intentional and if so, include the reasoning, and if it was not intentional, then provide a correction to ITS 3.3.2 footnote h.

Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 8:57 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 72NRC Question Number KAB030Select Application Licensee ResponseAttachment 1 Attachment 1 revised ISTS pages for tau.pdf (967KB)Attachment 2 Response Statement In response to KAB030, the ISTS markups for SQN, Units 1 and 2, on pages 470 and 504 of Enclosure 2, Volume 8, will be revised.Specifically, Footnote (h) for SQN, Unit 1, will be revised to read, "Time constant utilized in the rate/lag controller is 50 seconds."Footnote (h) for SQN, Unit 2, will be revised to read, "Time constant utilized in the rate/lag controller is 1 50 seconds."This change is consistent wi th CTS Table 3.3-4 Note 2 for SQN, Units 1 and 2.See Attachment 1 for the draft revised ISTS markups for SQN, Units 1 and 2.Response Date/Time 5/29/2014 4:05 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew Hon Ray SchieleAdded By Scott BowmanDate Added 5/29/2014 3:06 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-15 Rev. 4.0 SEQUOYAH UNIT 1 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 5 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS

CONDITIONS

SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 4. Steam Line Isolation

d. Steam Line Pressure (1) Low 1,2 (j),3 (j) (a) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR3.3.2.10 [635](d) psig [675](d) psig (2) Negative Rate - High 3 (h) (j) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR 3.3.2.

10 [121.6](i) psi [110](i) psi (a) Above the P

-11 (Pressurizer Pressure) in terlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.

(h) Below the P

-11 (Pressurizer Pr essure) interlock.

(i) Time constant utilized in the rate/lag controller is [50] seconds.

(j) Except when all MSIVs are closed and [de-activated].


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used b y the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

592.2 600 107.8 100.0Table 3.3-3 4.d 4.e 3.3.2.1, and ACTION 3.3.2.1, and ACTION Table 3.3-4 Note 1 Table 3.3-4 Note 2 DOC L04 Table 3.3-3 Note ## 9 9 4 8 4 8 4 3 2 3 3 3 3 3 3 2UFSAR Section 7.1.2 2 2Note # When Steam Line Isolationon Steam Line Pressure, Low is blocked When Steam Line Isolation on Steam Line Pressure, Negative Rate-High is blocked f f e e e g h g h ESFAS Instrumentation (Without Setpoint Control Program) 3.3.2 A Westinghouse STS 3.3.2 A-15 Rev. 4.0 SEQUOYAH UNIT 2 Amendment XXX 1 2CTS 1Table 3.3.2-1 (page 5 of 11) Engineered Safety Feature Actuation System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS

CONDITIONS

SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 4. Steam Line Isolation

d. Steam Line Pressure (1) Low 1,2 (j),3 (j) (a) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR3.3.2.10 [635](d) psig [675](d) psig (2) Negative Rate - High 3 (h) (j) 3 per steam lineD SR 3.3.2.1 SR 3.3.2.

5 (b)(c)SR 3.3.2.

9 (b)(c)SR 3.3.2.

10 [121.6](i) psi [110](i) psi (a) Above the P

-11 (Pressurizer Pressure) in terlock.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(d) Time constants used in the lead/lag controller are t 1 [50] seconds and t 2 [5] seconds.

(h) Below the P

-11 (Pressurizer Pr essure) interlock.

(i) Time constant utilized in the rate/lag controller is [50] seconds.

(j) Except when all MSIVs are closed and [de-activated].


REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used b y the unit. ------------------------------------------------------------------------------------------------------------------------------------------------------------------------

592.2 600 107.8 100.0Table 3.3-3 4.d 4.e 3.3.2.1, and ACTION 3.3.2.1, and ACTION Table 3.3-4 Note 1 Table 3.3-4 Note 2 DOC L04 Table 3.3-3 Note ## 9 9 4 8 4 8 4 3 2 3 3 3 3 3 3 2UFSAR Section 7.1.2 2 2Note # When Steam Line Isolationon Steam Line Pressure, Low is blocked When Steam Line Isolation on Steam Line Pressure, Negative Rate-High is blocked f f e e e g h g h Licensee Response/NRC Response/NRC Question Closure Id 83NRC Question Number KAB030Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:40 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 54NRC Question Number KAB031 Category EditorialITS Section 3.3ITS Number 3.3.2DOC Number L-14JFD Number JFD Bases Number Page Number(s) 444 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 444 of Enclosure 2, Volume 8, L14 provides the discussion of the channel functional test in CTS Table 4.3-2 as comp ared to the ITS channel operational test in ITS 3.3.2. L14 states, "ITS Table 3.3.2-1 requires performance of a COT (ITS SR 3.3.1.7 or SR 3.3.1.8) every 184 days-"Pl ease explain why ITS SR 3.3.1.7 or SR 3.3.1.8 are being referenced or provide a correction to L14.

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Licensee Response/NRC Response/NRC Question Closure Id 63NRC Question Number KAB031 Select Application Licensee ResponseAttachment 1 Attachment 1 revised 3.3.2 DOC L14.pdf (17KB)Attachment 2 Response Statement In response to KAB031, discussion of change (DOC) L14, on page 444 of , Volume 8, will be revised.Specificall y, the reference to ITS SR 3.3.1.7 and SR 3.3.1.

8 will be revised to re ference ITS SR 3.3.2.4.See Attachment 1 for the draft revised DOC L14.Response Date/Time 5/29/2014 12:15 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 5/29/2014 11:12 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 33 of 35 ITS 3.3.2 Required Action J.2 allows an alternative of placing the Steam Generator Water Level -- Low-Low channel in trip instead of adjusting the Steam Generator Water Level -- Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse) with the same Completion Time for placing the channel in trip. This changes the CTS by adding an alternative to adjusting the Steam Generator Water Level -- Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse).

The purpose of CTS Table 3.3-3 ACTION 38 is to limit the maximum time allowed for maintenance activities, in which the channel is unavailable prior to adjusting the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse). If the Steam Generator Water Level -Low-Low (EAM) channels trip setpoint is not adjusted to the same value as Steam Generator Water Level --

Low-Low (Adverse) within the specif ied Completion Time this proposed change allows placing the affected protection sets SG Water Level -- Low-Low level channels in the tripped condition. Once the channel is placed in the tripped condition the Steam Generator Water Level -- Low-Low EAM/Adverse circuitry is removed from the active portion of the Steam Generator Water Level -- Low-Low channel, reference UFSAR Figure 7.2.1-1, Sheets 17 through 20, and these actions are no longer necessary. The action of tripping the channel provides the protection sets input to the 2/3 logic gates located on UFSAR Figure 7.2.1-1 Sheet 19. The ITS Required Action J.2 Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with CTS TABLE 3.3-3 ACTION 38 and the proposed ITS Required Action J.1.

This change is designated as less restrictive because less stringent Required Actions are being applied in ITS than were applied in CTS.

L14 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST on a quarterly basis (Q) for Functional Units: 1.c (Containment Pressure-High), 1.d (Pressurizer Pressure--Low); 1.f (Steam Line Pressure-Low); 2.c (Containment Pressure--High-High); 3.b.3) (Containment Pressure--High-High); 4.c (Containment Pressure--High-High); 4.d (Steam Line

Pressure--Low); 4.e (Negative Steam Line Pressure Rate--High); and 5.a (Steam Generator Water Level--High-High). ITS Table 3.3.2-1 requires performance of a COT (ITS SR 3.3.1.7 or SR 3.3.1.8) every 184 days for Functions: 1.c (Containment Pressure-High); 1.d (Pressurizer Pressure--Low); 1.e (Steam Line Pressure-Low); 2.c (Containment Pressure--High-High); 3.b.(3) (Containment Pressure--High-High); 4.c (Containment Pressure--High-High); 4.d.(1) (Steam Line Pressure--Low); 4.d.(2) (Steam Line Pressure Negative Rate--High); and 5.b (SG Water Level--High-High (P-14)). This changes the CTS by changing the

Frequency of the Surveillances from quarterly to 184 days.

The purpose of the CHANNEL FUNCTIONAL TEST/COT is to ensure that the instrumentation is functioning properly. These changes are acceptable and are the result of WCAP-10271, Revision 0 ("Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System"), dated May 1996, and supplements, WCAP-14333-P-A, Revision 1 ("Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times"), dated Licensee Response/NRC Response/NRC Question Closure Id 84NRC Question Number KAB031Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:40 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 55NRC Question Number KAB032 Category Editorial ITS Section 3.3 ITS Number 3.3.2DOC Number L-15JFD Number JFD Bases Number Page Number(s) 445NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 445 of Enclosure 2, Volume 8, L15 provides the discussi on of the channel functional test in CTS Table 4.3-2 as comp ared to the ITS actuation logic test in ITS 3.3.2. L15 states, "The ITS STB definition requires an Automatic Actuation Logic and Actuation Relays Function to be tested every 62 days."However, ITS SR 3.3.2.2 is required 92 days on a staggered test basis. Please explain this discrepancy.Attach File 1 Attach File 2 Issue Date 5/9/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 9:01 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 61NRC Question Number KAB032 Select Application Licensee ResponseAttachment 1 Attachment 1 revised 3.3.2 DOC L15.pdf (17KB)Attachment 2 Response Statement In response to KAB032, discussion of change (DOC) L15 will be revised.Specifically, the sentence in the second paragraph of L15 that states, "The ITS STB definition requires an Auto matic Actuation Logic and Actuation Relays Function to be tested every 62 days."will be revised to state, "The ITS STB definition requires an Auto matic Actuation Logic and Actuation Relays Function to be tested every 92 days."T his was a typographical error.During review of DOC L15, the following issue was identified.CTS Functional Unit 9.b (Automatic Sw itchover to Containment Sump, Automatic Actuation Logic) correspondi ng to ITS Function 7.a (Automatic Switchover to Containment Sump , Automatic Actuation Logic and Actuation Relays) should be included in the first paragraph of DOC L15.CTS Table 4.3-2 requir es a CHANNEL FUNCTIONAL TEST on a monthly basis (M) for Functional Unit 9.b (Aut omatic Switchover to Containment Sump, Automatic Actuation Logic).A Note (Note (1)) modifies this Frequency and states, "Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS." The monthly CHANNEL FUNCTIONAL TEST in comb ination with the modifying Note requires testing each Automatic Actuation Logic train every two months.ITS Table 3.3.2-1 requires performance of an ACTUATION LOGIC TEST (ITS SR 3.3.2.2) every 92 days on a STAGGERED TEST BA SIS for Function 7.a (Automatic Switchover to Containment Sump, Au tomatic Actuation Logic and Actuation Relays).

See Attachment 1 for a draft revised DOC L15.Response Date/Time 5/28/2014 9:10 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonPage 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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p h p?re q uestT yp e=areaItemPrint&itemId=61 DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 34 of 35 October 1998, WCAP-15376-P-A, Revision 1 ("Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times"), dated March 2003 (or a combination of the WCAPs), or a unit specific evaluation showing the applic ability of these WCAPs to the change. TVA has performed evaluations of the applicable changes associated with the three WCAPs to justify the above changes. The evaluations supporting these changes are provided in Enclosure 4 of this submittal. This change is designated as less restrictive because less stringent Frequencies are being applied in the ITS than were applied in the CTS.

L15 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST on a monthly basis (M) for Functional Units: 1.b (Safety Injection, Automatic Actuation Logic); 2.b (Containment Spray, Automatic Actuation Logic); 3.b.2) (Containment Isolation, Automatic Actuation Logic); 4.b (Steam Line Isolation, Automatic Actuation Logic); 5.b (Turbine Trip and Feedwater Isolation, Automatic Actuation Logic); 6.b (Auxiliary Feedwater, Automatic Actuation Logic). A Note (Note (1)) modifies this Frequency and states, "Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS." The monthly CHANNEL FUNCTIONAL TEST in combination with the modifying Note requires testing each Automatic Actuation Logic train every two months. ITS Table 3.3.2-1 requires performance of an ACTUATION LOGIC TEST (ITS SR 3.3.2.2) every 92 days on a STAGGERED TEST BASIS for Functions: 1.b (Safety Injection, Automatic Actuation Logic and Actuation Relays); 2.b (Containment Spray, Automatic Actuation Logic and Actuation Relays); 3.b.(2) (Containment Isolation, Automatic Actuation Logic and Actuation Relays); 4.b (Steam Line Isolation, Automatic Actuation Logic and Actuation Relays); 5.a (Turbine Trip and Feedwater Isolation, Automatic Actuation Logic and Actuation Relays); and 6.a (Auxiliary Feedwater, Automatic Actuation Logic and Actuation Relays). This changes the CTS by changing the Frequency of the Surveillances from monthly (every 62 days on a STAGGERED TEST BASIS) for these Automatic Actuation Logics to every 92 days on a STAGGERED TEST BASIS.

The purpose of the Automatic Actuation Logic Test is to ensure that when various simulated or actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit are applied the required logic output is obtained. An important concept in this change is that the definition of STAGGERED TEST BASIS (STB) in CTS is not the same as in ITS.

In CTS STAGGERED TEST BASIS is def ined as, "A STAGGERED TEST BASIS shall consist of: a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval. Using the CTS STB definition there are two (2) Automatic Actuation Logic trains with the Note (1) frequency of 62 days on a STB, 62 days/2 trains = 31 days/train (or monthly),

Table 4.3-2 Frequency. Therefore, in CTS, each month (31 days) an Automatic Actuation Logic train is tested and each Automatic Actuation Logic train is tested every two (2) months (62 days). In ITS, STB is defined as, "A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, DISCUSSION OF CHANGES ITS 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 35 of 35 channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function." Using the ITS definition for the ITS SR 3.3.2.2 Frequency of "92 days on a STAGGERED TEST BASIS," changes the testing of each Automatic Actuation Logic and Actuation Relays train to every 6 months (184 days). The ITS STB definition requires an Automatic Actuation Logic and Actuation Relays Function to be tested every 62 days. Because there are two (2) Automatic Actuation Logic and Actuation Relays trains and the STB definition states that all designated trains are tested during n Surveillance Frequency Intervals where n is the number of trains, 92 days x 2 components = 184 days (or every 6 months). Therefore, this change decreases the Frequency for testing of each Automatic Actuation Logic and Actuation Relays train from every two months to every 6 months with the interaction between trains controlled by the STB definition. These changes are acceptable and are the result of WCAP-10271, Revision 0 ("Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System"), dated May 1996, and supplements, WCAP-14333-P-A, Revision 1 ("Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times"), dated October 1998, or WCAP-15376-P-A, Revision 1 ("Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times"), dated March 2003 (or a

combination of the WCAPs). TVA has performed evaluations of the applicable changes associated with the three WCAPs to justify the above changes. The evaluations supporting these changes are provided in Enclosure 4 of this submittal. This change is designated as less restrictive because less stringent Frequencies are being applied in the ITS than were applied in the CTS.

Licensee Response/NRC Response/NRC Question Closure Id 85NRC Question Number KAB032Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:41 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 56NRC Question Number KAB033 Category EditorialITS Section 3.3ITS Number 3.3.2DOC Number JFD Number JFD Bases Number Page Number(s) 371, 411NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On pages 371 and 411 of Enclosure 2, Volu me 8, CTS Table 4.3-2 note (2) has a reference to L01. Please explain how L01 is applicable.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 9:02 AMNotification Scott BowmanMichelle ConnerAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 35NRC Question Number KAB033Select Application Licensee ResponseAttachment 1 Attachment 1 revised CTS Table 4.3-2 Note (2) reference.pdf (23KB)Attachment 2 Response Statement In response to KAB033, the CTS Ta ble 4.3-2 Note (2) reference to discussion of change (DOC) L01 on pages 371 and 411 of Enclosure 2 will be revised to reference DOC L02.DOC L01 is not applicable because it discusses a change to the CTS Completion Time for the P-4 interlock.

See Attachment 1 for draft revised CTS Table 4.3-2 Note (2) references.Response Date/Time 5/23/2014 11:45 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 5/23/2014 10:42 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS A01 ITS 3.3.2 TABLE 4 .3-2 (Continued)

TABLE NOTATION

(1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (2) The total interlock function shall be demonstrated OPERABLE during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

September 14, 2006 SEQUOYAH - UNIT 1 3/4 3-38 Amendment No. 47, 182, 188, 207, 311 Page 40 of 80 92days on a STAGGERED TEST BASIS L15SR 3.3.2.2 Add proposed SR 3.3.2.6 Note Add proposed SR 3.3.2.7 Note A18Add proposed SR 3.3.2.8 Note A19Add proposed SR 3.3.2.9 Note A20Add proposed SR 3.3.2.10 Note L01In accordance with the Surveillance Frequency Control Program LA02 ITS ITS 3.3.2 A01TABLE 4.3-2 (Continued)

TABLE NOTATION

(1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (2) The total interlock function shall be demonstrated OPERABLE during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

September 14, 2006 SEQUOYAH - UNIT 2 3/4 3-39 Amendment No. 39, 174, 180, 197, 300 Page 80 of 80SR 3.3.2.2 L15Add proposed SR 3.3.2.6 Note Add proposed SR 3.3.2.7 Note A18Add proposed SR 3.3.2.8 Note A19Add proposed SR 3.3.2.9 Note A20Add proposed SR 3.3.2.10 Note L01 92days on a STAGGERED TEST BASISIn accordance with the Surveillance Frequency Control Program LA02 Licensee Response/NRC Response/NRC Question Closure Id 55NRC Question Number KAB033Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/27/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/27/2014 2:18 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 57NRC Question Number KAB034 Category Editorial ITS Section 3.3 ITS Number 3.3.2DOC Number JFD Number JFD Bases Number Page Number(s) 461, 495NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 461 and 495 of Enclosure 2, Volume 8, Insert 8 for ITS Condition R is missing the underlining for the logical connector AND. Please provide a correction for Insert 8.Attach File 1 Attach File 2 Issue Date 5/9/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/9/2014 9:03 AMNotification Scott BowmanMichelle ConnerAndrew HonLynn Mynatt Ray SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 36NRC Question Number KAB034 Select Application Licensee ResponseAttachment 1 Attachment 1 revised Insert 8.pdf (16KB)Attachment 2 Response Statement In response to KAB034, the logical connector fo r Insert 8 on pages 461 and 495, associated with Condition R will be revised to change the connector "AND"to "AND

."See Attachment 1 for draft revised Insert 8.Response Date/Time 5/23/2014 1:30 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott BowmanDate Added 5/23/2014 12:31 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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3.3.2 Insert Page 3.3.2-6 CTS INSERT 8 R. Required Action and associated Completion

Time of Condition I not met.

R.1 Be in MODE 3.

AND

R.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> S. One train inoperable.


NOTE------------------- One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing

provided the other train is OPERABLE.


S.1 Be in MODE 3.

AND S.2 Be in MODE 5.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />

M11 ACTION 15 2 3.3.2 Insert Page 3.3.2-6 CTS INSERT 8 R. Required Action and associated Completion

Time of Condition I not met.

R.1 Be in MODE 3.

AND

R.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> S. One train inoperable.


NOTE------------------- One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing

provided the other train is OPERABLE.


S.1 Be in MODE 3.

AND S.2 Be in MODE 5.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />

M11 ACTION 15 2 Licensee Response/NRC Response/NRC Question Closure Id 56NRC Question Number KAB034Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/27/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/27/2014 2:18 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 58NRC Question Number KAB035 Category EditorialITS Section 3.3 ITS Number 3.3.3DOC Number L-2JFD Number JFD Bases Number Page Number(s) 711NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 711 of Enclosure 2, Volume 8, L02 provides th e discussion of channel calibrations in CTS 4.3.3.7.b as compared to the ITS channel calibration in ITS 3.3.3. L02 states, "ITS 3.3.3.2 requires perfor mance of a channel calibration also but is modified be a Note stating-"However, ITS does not contain a LCO 3.3.3.2.

ITS 3.3.3 does have a surveillance requ irement 3.3.3.2 which requires a channel calibration. Please correct L02 to reference ITS SR 3.3.3.2 or explain why ITS 3.3.3.2 is the correct reference.Attach File 1 Attach File 2 Issue Date 5/13/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/13/2014 12:00 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattLisa RegnerRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=58 Licensee Response/NRC Response/NRC Question Closure Id 39NRC Question Number KAB035Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.3 revised L02.pdf (11KB)Attachment 2 Response Statement In response to KAB035, discussion of change (DOC) L02, on page 711 of Enclosure 2, Volume 8, will be revised.Specifically, the reference to ITS 3.3.3.2 will be revised to, "ITS SR 3.3.3.2."See Attachment 1 for draft revised DOC L02.Response Date/Time 5/23/2014 2:35 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 5/23/2014 1:33 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 9 of 10 respond to the event is low. The addition of a report is acceptable because it advises the NRC of the cause of the inoperability and the plans and schedule for restoring the instrumentation channel to OPERABLE status. This change is designated as less restrictive because additional time is allowed to restore instrument channels to OPERABLE status than was allowed in the CTS.

L02 (Category 6 - Relaxation of Surveillance Requirement Acceptance Criteria) CTS 4.3.3.7.b requires that each accident monitoring instrument be demonstrated OPERABLE by performance of a CHANNEL CALIBRATION every 18 months. ITS 3.3.3.2 requires performance of a CHANNEL CALIBRATION also but is modified by a Note stating, "Neutron detectors are excluded from CHANNEL CALIBRATION." This changes the CTS by excluding Neutron detectors from the Source and Intermediate Range CHANNEL CALIBRATIONS.

The purpose of a CHANNEL CALIBRATION is to ensure that the channel responds within the necessary range and accuracy to known values of the parameter that the channel monitors. Thus, to perform a channel calibration of a neutron flux channel would require including the neutron flux detector in the calibration. Inclusion of neutron flux detectors in the CHANNEL CALIBRATION process is impractical in power reactor applications because to do so would require subjecting the detectors to known neutron fluxes. Because of the hazards associated with exposing the neutron detectors, CTS Table 4.3-1 Note (6) excludes these detectors from CHANNEL CALIBRATION. The detectors excluded from CHANNEL CALIBRATION in CTS Table 4.3-1 are the same channels used to satisfy CTS Table 3.3-10. This proposed change is consistent

with historical and current NRC staff requirem ents as reflected in ISTS. Explicitly stating the neutron detectors are excluded from CHANNEL CALIBRATION reiterates the allowance found in CTS Table 4.3-1. This change is designated as less restrictive because less stringent Surveillance Requirements are being applied in the ITS than were applied in the CTS.

L03 (Category 1 - Relaxation of LCO Requirements)

CTS Table 3.3-10 Note ## is associated with Instrument 19 (Containment Isolation Valve Position) Minimum Required Channels and states, "Not required for isolation valves that are closed and deactivated." ITS includes a similar Footnote for Function 19 (Containment Isolation Valve Position) that states, "Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured." This changes the CTS by reducing the conditions under which the isolation valves indication must be OPERABLE by including exceptions of when the penetration is isolated by a closed manual valve, blind flange, or check valve with flow through the valve secured.

The purpose of CTS Table 3.3-10, Instrument 19 (Containment Isolation Valve Position) is for verification of containment isolation using the ability to monitor containment penetration isolation valve status through valve position indication.

A closed and deactivated isolation valve provides evidence that the penetration is isolated and the requirement to provide indication of the valve position is no longer necessary. Similarly by isolating the penetration using a manual valve, blind flange, or check valve with the flow through it secured provides evidence that the penetration is isolated and the requirement to provide indication of the Licensee Response/NRC Response/NRC Question Closure Id 57NRC Question Number KAB035Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/27/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/27/2014 2:19 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 59NRC Question Number KAB036Category Technical ITS Section 3.3 ITS Number 3.3.3 DOC Number A-3JFD Number JFD Bases Number Page Number(s) 703NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 703 of Enclosure 2, Volume 8, A03 provides the discussi on of the minimum channels required for CTS Table 3.3-10 Instrument 11.b, "Auxiliary Feedwater Valve Position Indication,"which is 3/st eam generator. ITS Table 3.3.3-1 function 11.b, "Auxiliary Feedwater Valve Position Indication,"required channels is 1 per steam generator. A03 states, "This changes the CTS by simplifying the presentation of the requirements for Auxiliary Feed water (Valve Position Indication) instrumentation by requir ing one channel per steam generator."The NRC staff does not agree that this chan ge simplifies the presentati on and does not result in technical changes. Please provide a correction to the required channels in ITS Table 3.3.3-1 for function 11.b, such that it matches the minimum channels required for CTS Table 3.3-10 Instrument 11.b or pr ovide a change equivalent to the CTS Table 3.3-10 Instrument 11.b re quirements such that it cl early describes that there is 1 required valve position indication for each auxiliary feedwater pump associated with each steam generator.

Attach File 1 Attach File 2 Issue Date 5/13/2014Added By Kristy BucholtzDate Modified Modified By Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Date Added 5/13/2014 12:02 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattLisa RegnerRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 130NRC Question Number KAB036 Select Application Licensee ResponseAttachment 1 Attachment 1 for 3.3.3 Footnotes R2.pdf (1MB)Attachment 2 Response Statement In response to KAB036, ITS Table 3.

3.3-1, Post Acci dent Monitoring Instrumentation, will be modified to add a Footnote to Function 11.b. ITS Table 3.3.3-1 Function 11.b, Auxiliary Feedwater Valve Po sition Indication, requires one OPERABLE channel per steam generator.The Footnote will describe that, "a channel consists of three valve position indicators (two level control valves for each motor driven AFW flow path and one level control valve for the turbine driven AFW flow path)."T he footnote is consistent with CTS requirements for e ach AFW flow path associated with each steam generator.During review for the response to KAB036, it was noted that the sequencing of the footnot es for ITS Table 3.3.3

-1 is not in accordance with the Writer's Guide, TSTF-GG-05-0, the footnotes are not sequenced in the order in which they appear in the Table.Therefore, to correct this issue, CTS and ISTS markups will be r evised to correct the sequence of footnotes, as well as, corresponding revisions to the discussion of changes (DOCs).Footnote (d) will not be reflected in Attachment 1 to RAI KAB036. It will be shown in the response to RAI KAB037.Attachment 1 provides the markups for CTS Table 3.3-10 (pages 684 -688 and 694 -698 of Enclosure 2, Volume 8), ISTS Table 3.3.3-1 (pages 719 -721 and 727 -729) and th e changes to DOCs A03, A04, and A06 (pages 703-706).Response Date/Time 6/20/2014 4:45 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott BowmanPage 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=130 Date Added 6/20/2014 3:42 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=130 ITS ITS 3.3.3 A01 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065) 4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083) 4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loops 30

-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops 30

-044,-045) 2 2 1 5. Refueling Water Storage Tank Level (Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range) (Instrument Loops 68

-062,-0 66,-069) 3 3 2 7. Pressurizer Level (Wide Range) (Instrument Loops 68

-320,-335,-339) 3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B,-020A,-020B,-027A,-027B) 2/steam line 2/steam line 1 9. Steam Generator Level - (Wide Range) (Instrument Loops 3

-043,-056,-098,-111) 4(1/steam generator) 4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3-039,-042,-052,-055,-094,-097,-107,-110) 2/steam generator 2/steam generator 1

11. Auxiliary Feedwater
a. Flow Rate (Instrument Loops 3

-163,-155,-147,-170) 1/steam generator 1/steam generator 5 b. Valve Position Indication (Instrument Loops 3

-164,-164A,-172,-156, -156A,-173,-148,-148A,-174,-171,-171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56 Amendment No. 46, 114, 149, 159 1 Table 3.3.3-1 2 3 4 5 6 7 8 9 11 10 ITS ACTION A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA03 LA04 LA04 Page 2 of 20 LA05 1 A03 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION

12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102) 2 2 1 13. Containment Water Level (Wide Range) (Instrument Loops 63

-178,-179) 2 2 1

14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1
b. Core Quadrant (2) 2(1/Train) 1
c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation 6
a. Dynamic Range (Instrument Loops68-367, 370) 2 1
b. Lower Range (Instrument Loops 68

-368, 371) 2 1

c. Upper Range (Instrument Loops 68

-369, 372) 2 1

16. Containment Area Radiation Monitors
a. Upper Compartment (Instrument Loops90-271,-272) 2 1

4 b. Lower Compartment (Instrument Loops90-273,-274) 2 1 4

October 4, 1995 SEQUOYAH - UNIT 1 3/4 3-56a Amendment No. 112, 149, 159, 213 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H LA03Table 3.3.3-1 ITS ACTIONF and I F and I Page 3 of 20 LA05(c) Add proposed Table 3.3.3-1 Footnote (c)

A04 LA04 A04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flux

a. Source Range (Instrument Loops 92

-5001,-5002) 2 2# 1

b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position

a. Motor Driven Pumps (Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1

b. Turbine Driven Pumps (Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1

19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3

_____________ #Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint. ##Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56b Amendment No. 112, 149, 159 Table 3.3.3-1 Footnote (a) Table 3.3.3-1

Footnote (d) whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. 2 per penetration flow path A06 17 18 19 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA03Table 3.3.3-1 ITS ACTION Page 4 of 20 (b)A06 A06 LA05 2 A05 2 LA04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57 Amendment No. 46, 149, 159, 301 ACTION A ACTION A ACTION C ACTION C ACTION H ACTION B ACTION H ACTION B ACTION H ACTION A Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01 A07 A07 A07 ACTION D A06 Page 5 of 20 Table 3.3.3-1 Footnote (a)

ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered.

However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57a Amendment No. 159, 301 ACTION H ACTION C Table 3.3.3-1 Footnote (b)

ACTION B two A06 Page 6 of 20 LA06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a)

A06Initiate action in accordance with Specification 5.6.5 L01 ITS A01 ITS 3.3.3 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED A CTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065)4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083)4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loo p s30-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops30-044,-045) 2 2 1 5. Refueling Water Storage Tank Level

(Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range)

(Instrument Loo p s68-062,-066,-069)3 3 2 7. Pressurizer Level (Wide Range)

(Instrument Loops 68

-320,-335,-339)3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B, -020A,-020B,-027A,-027B) 2/steam line2/steam line 1

9. Steam Generator Level - (Wide Range)

(Instrument Loops 3

-043,-056,-098,-111)4(1/steam generator)4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3

-039,-042,-052,-055,-094, -097,-107,-110) 2/steam generator 2/steam generator 1 11. A uxiliar y Feedwater

a. Flow Rate

(Instrument Loops 3

-163,-155, -147,-170)1/steam generator 1/steam generator 5 b. Valve Position Indication

(Instrument Loops 3

-164,-164A,-172,-156,- 156A,-173,-148,-148A,-174,-171, -171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57 Amendment Nos. 38, 104, 135, 149 Page 12 of 20Table 3.3.3-1 ITS ACTION LA03 LA04 LA04 1 11 2 3 4 5 6 7 8 9 10 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA05 1 A03 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102)2 2 1 13. Containment Water Level (Wide Range)

(Instrument Loo p s63-178,-179) 2 2 1 14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1 b. Core Quadrant (2) 2(1/Train) 1 c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation S ystem 6 a. Dynamic Range (Instrument Loops 68

- 367, 370) 2 1 b. Lower Range

(Instrument Loops 68

-368, 371) 2 1 c. Upper Range

(Instrument Loops 68

-369, 372) 2 1 16. Containment Area Radiation Monitors a. Upper Compartment

(Instrument Loops 90

-271,-272)2 1 4 b. Lower Compartment

(Instrument Loops 90

-273,-274)2 1 4

October 4, 1995 SEQUOYAH - UNIT 2 3/4 3-57a Amendment No. 102, 135, 149, 203 Page 13 of 20 LA03Table 3.3.3-1 ITS ACTION 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and HF and I F and I (c) A04 LA04 LA05Add proposed Table 3.3.3-1 Footnote (c)

A04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flu x a. Source Range (Instrument Loo p s 92-5001,-5002) 2 2# 1 b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position a) Motor Driven Pumps

(Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1 b) Turbine Driven Pumps

(Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1 19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3 # Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

    1. Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57b Amendment Nos. 102, 135, 149

Page 14 of 20 LA03Table 3.3.3-1 ITS ACTION 17 18 19 Table 3.3.3-1 Footnote (d) Table 3.3.3-1

Footnote (a) (b) A062 per penetration flow path A06whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

A06 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA05 2 A05 2 LA04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58 Amendment Nos. 38, 135, 149, 290 Page 15 of 20 ACTION A ACTION B ACTION C ACTION H ACTION A ACTION B ACTION C ACTION H ACTION D ACTION H ACTION A A07 A07 A07 A06Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01Table 3.3.3-1 Footnote (a)

ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued) affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58a Amendment No. 149, 290 Page 16 of 20 ACTION B ACTION C ACTION H LA06two A06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (b)

A06Initiate action in accordance with Specification 5.6.5 L01 DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 10 ADMINISTRATIVE CHANGES

A01 In the conversion of the Sequoyah Nuclear Plant (SQN) Current Technical Specifications (CTS) to the plant specific Improved Technical Specifications (ITS), certain changes (wording preferences, editorial changes, reformatting, revised numbering, etc.) are made to obtain consistency with NUREG-1431, Rev. 4.0, "Standard Technical Specifications-Westinghouse Plants" (ISTS) and additional Technical Specification Task Force (TSTF) travelers included in this

submittal.

These changes are designated as administrative changes and are acceptable because they do not result in technical changes to the CTS.

A02 CTS 3.3.3.7 ACTIONS, as shown in CTS Table 3.3-10, provide the compensatory actions to take when PAM instrumentation is inoperable. ITS 3.3.3 ACTIONS provide the compensatory actions for inoperable PAM Instrumentation. The ITS 3.3.3 ACTIONS include a Note that allows separate Condition entry for each Function. In addition, separate Condition entry is allowed within a Function on a "per" bases as listed for Functions 8 (Steam Line

Pressure (per steam line)), 10 (Steam Generator Level (Narrow Range) (per steam generator)) 11 (Auxiliary Feedwater (per steam generator)), and 19 (Containment Isolation Valve Position (per penetration flowpath)). This modifies the CTS by providing a specific allowance to enter the Action for each inoperable PAM instrumentation Function and for certain Functions on a "per" steam line, steam generator, or penetration flowpath basis.

This change is acceptable because it clearly states the current requirement. The CTS considers each PAM instrumentation Function to be separate and independent from the others. In addition, the channels associated with Functions 8, 10, 11, and 19 are allowed separate Condition entry on a steam line, steam generator, or penetration flowpath basis, which is consistent with the intent of the CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A03 CTS Table 3.3-10 Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)) "Minimum Channels Required" column states that the minimum channels required is 3/steam generator. ITS Table 3.3.3-1 Function 11.b (Auxiliary Feedwater (Valve Position Indication)) "Required Channels" column requires one channel per steam generator (consisting of 3 valve position indications). This changes the CTS by simplifying the presentation of the requirements for Auxiliary Feedwater (Valve Position Indication) instrumentation

by requiring one channel per steam generator.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument per steam generator. CTS Table 3.3-10 "Minimum Required Channels" column lists "3/steam generator" as the minimum required channels for Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)). At SQN a channel consists of

three valves per steam generator, two from the motor driven auxiliary feedwater pump and one from the turbine driven auxilia ry feedwater pump. Therefore, to fulfill the "Minimum Required Channels" requirement for Instrument 11.b DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 2 of 10 requiring one channel per steam generator, all three valves position indication must be OPERABLE. This change is acceptable because the requirements contained in ITS are the same as in CTS when a required auxiliary feedwater valve position indicator is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A04 CTS Table 3.3-10 Instrument 14 (Incore Thermocouples) "Minimum Channels Required" column states, in part, that the minimum channels required is 2 (1 per train) in each of the four core quadrants. ITS Table 3.3.3-1 Function 14 (Incore Thermocouples) "Required Channel" column also requires two channels in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states, "A channel consists of one incore thermocouple. The required channels in each quadrant shall be in different trains." This changes the CTS by explicitly stating the number of incore thermocouples included in a channel. The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "2(1/train)" as the minimum required channels for Instrument 14 (Incore Thermocouples) in each core quadrant. At SQN a channel consists of one incore thermocouple, therefore to fulfill the "Minimum Required Channels" requirement for Instrument 14 requires two incore thermocouples in each core quadrant, one from each train, to be OPERABLE. ITS Table 3.3.3-1 "Required Channel" column for Function 14 (Incore Thermocouples) requires two channels to be OPERABLE in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states that a channel consists of one incore thermocouple from different trains. The addition of Footnote (c) explicitly states the channel requirement of CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A05 CTS Table 3.3-10 Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Minimum Channels Required" column states, in part, that the minimum channels required are 1/Train/Pump (2 Valves/Train). ITS Table 3.3.3-1 Function 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Required Channel" column requires 2 channels. CTS Table 3.3-10 Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Minimum Channels Required" column states that the minimum channels required are 2 Trains (2 Valves/Train). ITS Table 3.3.3-1 Function 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Required Channel" column requires 2 channels. This changes the CTS by simplifying the presentation of the channel requirements for ERCW to AFW Valve Position for the Motor Driven Pumps and the Turbine Driven Pump.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to designate the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "1/Train/Pump (2 Valves/Train)" as the minimum required channels for Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps,)). At SQN

there are two motor driven auxiliary feedwater pumps. Each motor driven pump has two valves in series between the AFW pump and the ERCW supply. CTS Table 3.3-10 lists them as 3-116A and 3-116B, which are in the ERCW supply DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 10 line to the 1A-A AFW Pump, and 3-126A and 3-126B, which are in the ERCW supply line to the 1B-B AFW pump. The ITS Bases defines a channel as consisting of these two valves in series in the ERCW to AFW flow path for each motor driven pump, therefore 2 channels are required. CTS Table 3.3-10 "Minimum Required Channels" column lists "2 Trains (2 Valves/Train)" as the minimum required channels for Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump,)). At SQN there is one turbine driven auxiliary feedwater pump. The turbine driven pump has two supply lines from ERCW, one from each train with two valves in series between the AFW pump and the ERCW supply.

CTS Table 3.3-10 lists them as 3-136A and 3-136B, which are in the ERCW supply line from the 1A ERCW header to the turbine driven AFW Pump, and 3-179A and 3-179B, which are in the ERCW supply line from the 1B ERCW header to the turbine driven AFW pump. The ITS Bases defines a channel as two valves in series for each ERCW supply line to the turbine driven AFW pump, therefore 2 channels are required. This change is acceptable because the requirements contained in ITS are the same as in CTS when an ERCW to AFW Valve Position channel is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A06 CTS Table 3.3-10 Instrument 19 (Containment Isolation Valve Position) "Minimum Channels Required" column requires one valve position indication channel OPERABLE per valve and lists ACTION 3 as the ACTION to follow if one channel per valve is inoperable. CTS Table 3.3-10 ACTION 3.a provides the required ACTIONS for one of the penetration inboard or outboard valve(s) inoperable (i.e., one channel inoperable per penetration) one part of which is restoring the inoperable valve(s) accident indication to OPERABLE status within 30 days. CTS Table 3.3-10 ACTION 3.b provides the required ACTIONS for both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two channels inoperable per penetration) one part of which is restoring at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days. ITS LCO 3.3.3 ACTION A, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with one required channel inoperable restore required channel to OPERABLE status within 30 days. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days. CTS Table 3.3-10 Note ### states, in part, that on a penetration where accident indication is declared inoperable on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Function 19 (Containment Isolation Valve Position)

"Required Channels" column requires two channels to be OPERABLE per penetration and is modified by Footnote (b) which states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 ACTION 3.a references an inboard or outboard valve. CTS Table 3.3-10 ACTION 3.b references both an inboard and outboard valve(s). CTS Table 3.3-10 Note ###, in part, references penetrations whose valves are either both inboard (FCV 63-158 and FCV 63-

172) or both outboard (FCV 30-46 and VLV 30-571, FCV 30-47 and VLV 30-572, FCV 30-48 and VLV 30-573) and states that if both valves (two) have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 4 of 10 accident indication is restored to OPERABLE status. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days, similar to CTS Table 3.3-10 ACTION 3.b. This changes the CTS by simplifying the presentation of the

requirements for Containment Isolation Valve Position instrumentation by requiring two channels per penetration, except where ITS Table 3.3.3-1 Footnote (b) is applicable for those penetration flow paths with only one installed control room indication channel, and eliminating reference to inboard and outboard valve

combinations.

The purpose of CTS Table 3.3-10 is to provide requirements for Post-Accident Monitoring instruments. One of these instruments is Containment Isolation Valve Position. CTS requires one position indication channel per valve to be OPERABLE where normally there are two valves per penetration. Similarly, ITS requires two channels per penetration. CTS Note ###, in part, states that on a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Footnote (b) similarly states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 Note ###, in part, requires entry into ACTION 3.b when two required valve position indicators per penetration are inoperable because ACTION 3.b entry condition is when both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two position indicator per penetration). ITS LCO 3.3.3 ACTION C condition entry is when one or more Functions have two required channels inoperable, similar to CTS. This change is acceptable because the requirements contained in ITS are the same as in CTS when Containment Isolation Valve Position channel are inoperable for penetrations with two isolation valves per penetration and penetrations with one isolation valve per penetration. This change is designated as administrative because it does not result in technical changes to the CTS.

A07 CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 contain a Note referring to applicable action requirements from reference LCOs that may contain more restrictive actions. ITS Table 3.3.3-1 does not retain this information. This changes the CTS by not including the information referring to other potentially applicable action requirements to the Bases.

The purpose of CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 Note is to reference potentially associated Technical Specifications. It is an ITS convention to not include these types of notes or cross-references.

This change is designated as administrative change because it does not result in technical changes to the CTS.

MORE RESTRICTIVE CHANGES

None PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 1 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1 1.Power Ran ge Neutron Flux 2 E 2.Source Ran ge Neutron Flux 2 E 3.Reactor Coolant System (RCS) Hot LegTemperature 2 per loop E 4.RCS Cold Le g Temperature 2 per lo op E 5.RCS Pressure (Wide Ran g e)2 E 6.Reactor Vessel Water Level 2 F 7.Containment Sump Water Level (Wide Ran g e)2 E 8.Containment Pressure (Wide Ran g e)2 E 9.Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b)E 10.Containment Area Radiation (Hi gh Ran g e)2 F 11.Pressurizer Level 2 E 12.Steam Generator Water Level (Wide Ran g e)2 per steam generato r E 13.Condensate Stora ge Tank Level 2 E 14.Core Exit Temperature

- Quadrant [1]2 (c)E 15.Core Exit Temperature

- Quadrant [2]2 (c)E 16.Core Exit Temperature

- Quadrant [3]2 (c)E 17.Core Exit Temperature

- Quadrant [4]2 (c)E 18.Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. (b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. (c) A channel consists of two core exit thermocouple s (CETs). ----------------------------------------------------------------REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1.All Regulatory Guide 1.97, Type A instruments and 2.All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.


INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19 PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 2 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. Power Ran ge Neutron Flux 2 E
2. Source Ran ge Neutron Flux 2 E
3. Reactor Coolant System (RCS) Hot Leg Temperature 2 per loop E
4. RCS Cold Le g Temperature 2 per loop E
5. RCS Pressure (Wide Ran g e) 2 E
6. Reactor Vessel Water Level 2 F
7. Containment Sump Water Level (Wide Ran g e)2 E
8. Containment Pressure (Wide Ran g e)2 E
9. Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b) E
10. Containment Area Radiation (Hi gh Ran g e)2 F
11. Pressurizer Level 2 E
12. Steam Generator Water Level (Wide Ran g e)2 per steam generato r E
13. Condensate Stora ge Tank Level 2 E
14. Core Exit Temperature

- Quadrant [1]2 (c) E

15. Core Exit Temperature

- Quadrant [2]2 (c) E

16. Core Exit Temperature

- Quadrant [3]2 (c) E

17. Core Exit Temperature

- Quadrant [4]2 (c) E

18. Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two core exit thermocouple s (CETs).


REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1. All Regulatory Guide 1.97, Type A instruments and
2. All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.

INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19 Licensee Response/NRC Response/NRC Question Closure Id 138NRC Question Number KAB036 Select Application NRC ResponseAttachment 1 Attachment 2 Response Statement The NRC staff agrees that a footnote would provide the clarity needed for function 11.b. It seems like the proposed footnote wording conflicts with itself. The footnote states that a channel consists of 3 valve position indicators. The NRC staff agrees. However, it then states, in parenthesis, two level control valves for each motor driven AFW flow path. This seems to be inaccurate and implies 4 valves are required for the motor driven AFW flow paths. It seems more appropriate to state one of the following in the parenthesis:two level control valves, one for each motor driven AFW flow path or one level control valve for each motor driven AFW flow pathPlease take this into consideration and review the wording proposed for footnote (a), and confirm that this is the wording you prefer using in ITS.Response Date/Time 6/20/2014 6:00 PM Closure Statement Question Closure Date Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger Scott Added By Kristy Bucholtz Date Added 6/20/2014 7:57 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=138 Licensee Response/NRC Response/NRC Question Closure Id 161NRC Question Number KAB036Select Application Licensee ResponseAttachment 1 Attachment 1 for 3.3.3 Footnotes supplement.pdf (1MB)Attachment 2 Attachment 2 KAB036 Drawing.pdf (806KB)Response Statement This response supplements the first response to KAB036 based on NRC response dated June 29, 2014.Proposed ITS Table 3.3.3-1, Post A ccident Monitoring Instrumentation, Footnote (a) will be revised to state, "a channel consists of three valve position indicators (two level control valves for the motor driven AFW flow path and one level control valve for the turbine driven AFW flow path)."

Each steam generator has an auxiliary feedwater (A FW) flow path from one motor driven AFW pump and from the turbine driven AFW pump. Attachment 2 illustrates the AFW flow paths and the associated level control valves.Attachment 1 provides the markups fo r CTS Table 3.3-10 (pages 684 -688 and 694 -698 of Enclosure 2, Volume 8), ISTS Ta ble 3.3.3-1 (pages 719 -721 and 727 -729) and the changes to DOCs A03, A04, and A06 (pages 703-706).Response Date/Time 6/30/2014 1:15 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanDate Added 6/30/2014 12:14 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=161 ITS ITS 3.3.3 A01 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065) 4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083) 4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loops 30

-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops 30

-044,-045) 2 2 1 5. Refueling Water Storage Tank Level (Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range) (Instrument Loops 68

-062,-0 66,-069) 3 3 2 7. Pressurizer Level (Wide Range) (Instrument Loops 68

-320,-335,-339) 3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B,-020A,-020B,-027A,-027B) 2/steam line 2/steam line 1 9. Steam Generator Level - (Wide Range) (Instrument Loops 3

-043,-056,-098,-111) 4(1/steam generator) 4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3-039,-042,-052,-055,-094,-097,-107,-110) 2/steam generator 2/steam generator 1

11. Auxiliary Feedwater
a. Flow Rate (Instrument Loops 3

-163,-155,-147,-170) 1/steam generator 1/steam generator 5 b. Valve Position Indication (Instrument Loops 3

-164,-164A,-172,-156, -156A,-173,-148,-148A,-174,-171,-171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56 Amendment No. 46, 114, 149, 159 1 Table 3.3.3-1 2 3 4 5 6 7 8 9 11 10 ITS ACTION A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA03 LA04 LA04 Page 2 of 20 LA05 1 A03 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION

12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102) 2 2 1 13. Containment Water Level (Wide Range) (Instrument Loops 63

-178,-179) 2 2 1

14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1
b. Core Quadrant (2) 2(1/Train) 1
c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation 6
a. Dynamic Range (Instrument Loops68-367, 370) 2 1
b. Lower Range (Instrument Loops 68

-368, 371) 2 1

c. Upper Range (Instrument Loops 68

-369, 372) 2 1

16. Containment Area Radiation Monitors
a. Upper Compartment (Instrument Loops90-271,-272) 2 1

4 b. Lower Compartment (Instrument Loops90-273,-274) 2 1 4

October 4, 1995 SEQUOYAH - UNIT 1 3/4 3-56a Amendment No. 112, 149, 159, 213 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H LA03Table 3.3.3-1 ITS ACTIONF and I F and I Page 3 of 20 LA05(c) Add proposed Table 3.3.3-1 Footnote (c)

A04 LA04 A04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flux

a. Source Range (Instrument Loops 92

-5001,-5002) 2 2# 1

b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position

a. Motor Driven Pumps (Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1

b. Turbine Driven Pumps (Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1

19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3

_____________ #Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint. ##Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56b Amendment No. 112, 149, 159 Table 3.3.3-1 Footnote (a) Table 3.3.3-1

Footnote (d) whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. 2 per penetration flow path A06 17 18 19 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA03Table 3.3.3-1 ITS ACTION Page 4 of 20 (b)A06 A06 LA05 2 A05 2 LA04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57 Amendment No. 46, 149, 159, 301 ACTION A ACTION A ACTION C ACTION C ACTION H ACTION B ACTION H ACTION B ACTION H ACTION A Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01 A07 A07 A07 ACTION D A06 Page 5 of 20 Table 3.3.3-1 Footnote (a)

ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered.

However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57a Amendment No. 159, 301 ACTION H ACTION C Table 3.3.3-1 Footnote (b)

ACTION B two A06 Page 6 of 20 LA06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a)

A06Initiate action in accordance with Specification 5.6.5 L01 ITS A01 ITS 3.3.3 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED A CTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065)4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083)4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loo p s30-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops30-044,-045) 2 2 1 5. Refueling Water Storage Tank Level

(Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range)

(Instrument Loo p s68-062,-066,-069)3 3 2 7. Pressurizer Level (Wide Range)

(Instrument Loops 68

-320,-335,-339)3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B, -020A,-020B,-027A,-027B) 2/steam line2/steam line 1

9. Steam Generator Level - (Wide Range)

(Instrument Loops 3

-043,-056,-098,-111)4(1/steam generator)4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3

-039,-042,-052,-055,-094, -097,-107,-110) 2/steam generator 2/steam generator 1 11. A uxiliar y Feedwater

a. Flow Rate

(Instrument Loops 3

-163,-155, -147,-170)1/steam generator 1/steam generator 5 b. Valve Position Indication

(Instrument Loops 3

-164,-164A,-172,-156,- 156A,-173,-148,-148A,-174,-171, -171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57 Amendment Nos. 38, 104, 135, 149 Page 12 of 20Table 3.3.3-1 ITS ACTION LA03 LA04 LA04 1 11 2 3 4 5 6 7 8 9 10 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA05 1 A03 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102)2 2 1 13. Containment Water Level (Wide Range)

(Instrument Loo p s63-178,-179) 2 2 1 14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1 b. Core Quadrant (2) 2(1/Train) 1 c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation S ystem 6 a. Dynamic Range (Instrument Loops 68

- 367, 370) 2 1 b. Lower Range

(Instrument Loops 68

-368, 371) 2 1 c. Upper Range

(Instrument Loops 68

-369, 372) 2 1 16. Containment Area Radiation Monitors a. Upper Compartment

(Instrument Loops 90

-271,-272)2 1 4 b. Lower Compartment

(Instrument Loops 90

-273,-274)2 1 4

October 4, 1995 SEQUOYAH - UNIT 2 3/4 3-57a Amendment No. 102, 135, 149, 203 Page 13 of 20 LA03Table 3.3.3-1 ITS ACTION 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and HF and I F and I (c) A04 LA04 LA05Add proposed Table 3.3.3-1 Footnote (c)

A04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flu x a. Source Range (Instrument Loo p s 92-5001,-5002) 2 2# 1 b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position a) Motor Driven Pumps

(Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1 b) Turbine Driven Pumps

(Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1 19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3 # Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

    1. Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57b Amendment Nos. 102, 135, 149

Page 14 of 20 LA03Table 3.3.3-1 ITS ACTION 17 18 19 Table 3.3.3-1 Footnote (d) Table 3.3.3-1

Footnote (a) (b) A062 per penetration flow path A06whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

A06 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA05 2 A05 2 LA04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58 Amendment Nos. 38, 135, 149, 290 Page 15 of 20 ACTION A ACTION B ACTION C ACTION H ACTION A ACTION B ACTION C ACTION H ACTION D ACTION H ACTION A A07 A07 A07 A06Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01Table 3.3.3-1 Footnote (a)

ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued) affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58a Amendment No. 149, 290 Page 16 of 20 ACTION B ACTION C ACTION H LA06two A06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (b)

A06Initiate action in accordance with Specification 5.6.5 L01 DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 10 ADMINISTRATIVE CHANGES

A01 In the conversion of the Sequoyah Nuclear Plant (SQN) Current Technical Specifications (CTS) to the plant specific Improved Technical Specifications (ITS), certain changes (wording preferences, editorial changes, reformatting, revised numbering, etc.) are made to obtain consistency with NUREG-1431, Rev. 4.0, "Standard Technical Specifications-Westinghouse Plants" (ISTS) and additional Technical Specification Task Force (TSTF) travelers included in this

submittal.

These changes are designated as administrative changes and are acceptable because they do not result in technical changes to the CTS.

A02 CTS 3.3.3.7 ACTIONS, as shown in CTS Table 3.3-10, provide the compensatory actions to take when PAM instrumentation is inoperable. ITS 3.3.3 ACTIONS provide the compensatory actions for inoperable PAM Instrumentation. The ITS 3.3.3 ACTIONS include a Note that allows separate Condition entry for each Function. In addition, separate Condition entry is allowed within a Function on a "per" bases as listed for Functions 8 (Steam Line

Pressure (per steam line)), 10 (Steam Generator Level (Narrow Range) (per steam generator)) 11 (Auxiliary Feedwater (per steam generator)), and 19 (Containment Isolation Valve Position (per penetration flowpath)). This modifies the CTS by providing a specific allowance to enter the Action for each inoperable PAM instrumentation Function and for certain Functions on a "per" steam line, steam generator, or penetration flowpath basis.

This change is acceptable because it clearly states the current requirement. The CTS considers each PAM instrumentation Function to be separate and independent from the others. In addition, the channels associated with Functions 8, 10, 11, and 19 are allowed separate Condition entry on a steam line, steam generator, or penetration flowpath basis, which is consistent with the intent of the CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A03 CTS Table 3.3-10 Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)) "Minimum Channels Required" column states that the minimum channels required is 3/steam generator. ITS Table 3.3.3-1 Function 11.b (Auxiliary Feedwater (Valve Position Indication)) "Required Channels" column requires one channel per steam generator (consisting of 3 valve position indications). This changes the CTS by simplifying the presentation of the requirements for Auxiliary Feedwater (Valve Position Indication) instrumentation

by requiring one channel per steam generator.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument per steam generator. CTS Table 3.3-10 "Minimum Required Channels" column lists "3/steam generator" as the minimum required channels for Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)). At SQN a channel consists of

three valves per steam generator, two from the motor driven auxiliary feedwater pump and one from the turbine driven auxilia ry feedwater pump. Therefore, to fulfill the "Minimum Required Channels" requirement for Instrument 11.b DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 2 of 10 requiring one channel per steam generator, all three valves position indication must be OPERABLE. This change is acceptable because the requirements contained in ITS are the same as in CTS when a required auxiliary feedwater valve position indicator is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A04 CTS Table 3.3-10 Instrument 14 (Incore Thermocouples) "Minimum Channels Required" column states, in part, that the minimum channels required is 2 (1 per train) in each of the four core quadrants. ITS Table 3.3.3-1 Function 14 (Incore Thermocouples) "Required Channel" column also requires two channels in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states, "A channel consists of one incore thermocouple. The required channels in each quadrant shall be in different trains." This changes the CTS by explicitly stating the number of incore thermocouples included in a channel. The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "2(1/train)" as the minimum required channels for Instrument 14 (Incore Thermocouples) in each core quadrant. At SQN a channel consists of one incore thermocouple, therefore to fulfill the "Minimum Required Channels" requirement for Instrument 14 requires two incore thermocouples in each core quadrant, one from each train, to be OPERABLE. ITS Table 3.3.3-1 "Required Channel" column for Function 14 (Incore Thermocouples) requires two channels to be OPERABLE in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states that a channel consists of one incore thermocouple from different trains. The addition of Footnote (c) explicitly states the channel requirement of CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A05 CTS Table 3.3-10 Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Minimum Channels Required" column states, in part, that the minimum channels required are 1/Train/Pump (2 Valves/Train). ITS Table 3.3.3-1 Function 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Required Channel" column requires 2 channels. CTS Table 3.3-10 Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Minimum Channels Required" column states that the minimum channels required are 2 Trains (2 Valves/Train). ITS Table 3.3.3-1 Function 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Required Channel" column requires 2 channels. This changes the CTS by simplifying the presentation of the channel requirements for ERCW to AFW Valve Position for the Motor Driven Pumps and the Turbine Driven Pump.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to designate the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "1/Train/Pump (2 Valves/Train)" as the minimum required channels for Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps,)). At SQN

there are two motor driven auxiliary feedwater pumps. Each motor driven pump has two valves in series between the AFW pump and the ERCW supply. CTS Table 3.3-10 lists them as 3-116A and 3-116B, which are in the ERCW supply DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 10 line to the 1A-A AFW Pump, and 3-126A and 3-126B, which are in the ERCW supply line to the 1B-B AFW pump. The ITS Bases defines a channel as consisting of these two valves in series in the ERCW to AFW flow path for each motor driven pump, therefore 2 channels are required. CTS Table 3.3-10 "Minimum Required Channels" column lists "2 Trains (2 Valves/Train)" as the minimum required channels for Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump,)). At SQN there is one turbine driven auxiliary feedwater pump. The turbine driven pump has two supply lines from ERCW, one from each train with two valves in series between the AFW pump and the ERCW supply.

CTS Table 3.3-10 lists them as 3-136A and 3-136B, which are in the ERCW supply line from the 1A ERCW header to the turbine driven AFW Pump, and 3-179A and 3-179B, which are in the ERCW supply line from the 1B ERCW header to the turbine driven AFW pump. The ITS Bases defines a channel as two valves in series for each ERCW supply line to the turbine driven AFW pump, therefore 2 channels are required. This change is acceptable because the requirements contained in ITS are the same as in CTS when an ERCW to AFW Valve Position channel is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A06 CTS Table 3.3-10 Instrument 19 (Containment Isolation Valve Position) "Minimum Channels Required" column requires one valve position indication channel OPERABLE per valve and lists ACTION 3 as the ACTION to follow if one channel per valve is inoperable. CTS Table 3.3-10 ACTION 3.a provides the required ACTIONS for one of the penetration inboard or outboard valve(s) inoperable (i.e., one channel inoperable per penetration) one part of which is restoring the inoperable valve(s) accident indication to OPERABLE status within 30 days. CTS Table 3.3-10 ACTION 3.b provides the required ACTIONS for both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two channels inoperable per penetration) one part of which is restoring at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days. ITS LCO 3.3.3 ACTION A, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with one required channel inoperable restore required channel to OPERABLE status within 30 days. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days. CTS Table 3.3-10 Note ### states, in part, that on a penetration where accident indication is declared inoperable on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Function 19 (Containment Isolation Valve Position)

"Required Channels" column requires two channels to be OPERABLE per penetration and is modified by Footnote (b) which states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 ACTION 3.a references an inboard or outboard valve. CTS Table 3.3-10 ACTION 3.b references both an inboard and outboard valve(s). CTS Table 3.3-10 Note ###, in part, references penetrations whose valves are either both inboard (FCV 63-158 and FCV 63-

172) or both outboard (FCV 30-46 and VLV 30-571, FCV 30-47 and VLV 30-572, FCV 30-48 and VLV 30-573) and states that if both valves (two) have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 4 of 10 accident indication is restored to OPERABLE status. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days, similar to CTS Table 3.3-10 ACTION 3.b. This changes the CTS by simplifying the presentation of the

requirements for Containment Isolation Valve Position instrumentation by requiring two channels per penetration, except where ITS Table 3.3.3-1 Footnote (b) is applicable for those penetration flow paths with only one installed control room indication channel, and eliminating reference to inboard and outboard valve

combinations.

The purpose of CTS Table 3.3-10 is to provide requirements for Post-Accident Monitoring instruments. One of these instruments is Containment Isolation Valve Position. CTS requires one position indication channel per valve to be OPERABLE where normally there are two valves per penetration. Similarly, ITS requires two channels per penetration. CTS Note ###, in part, states that on a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Footnote (b) similarly states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 Note ###, in part, requires entry into ACTION 3.b when two required valve position indicators per penetration are inoperable because ACTION 3.b entry condition is when both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two position indicator per penetration). ITS LCO 3.3.3 ACTION C condition entry is when one or more Functions have two required channels inoperable, similar to CTS. This change is acceptable because the requirements contained in ITS are the same as in CTS when Containment Isolation Valve Position channel are inoperable for penetrations with two isolation valves per penetration and penetrations with one isolation valve per penetration. This change is designated as administrative because it does not result in technical changes to the CTS.

A07 CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 contain a Note referring to applicable action requirements from reference LCOs that may contain more restrictive actions. ITS Table 3.3.3-1 does not retain this information. This changes the CTS by not including the information referring to other potentially applicable action requirements to the Bases.

The purpose of CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 Note is to reference potentially associated Technical Specifications. It is an ITS convention to not include these types of notes or cross-references.

This change is designated as administrative change because it does not result in technical changes to the CTS.

MORE RESTRICTIVE CHANGES

None PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 1 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1 1.Power Ran ge Neutron Flux 2 E 2.Source Ran ge Neutron Flux 2 E 3.Reactor Coolant System (RCS) Hot LegTemperature 2 per loop E 4.RCS Cold Le g Temperature 2 per lo op E 5.RCS Pressure (Wide Ran g e)2 E 6.Reactor Vessel Water Level 2 F 7.Containment Sump Water Level (Wide Ran g e)2 E 8.Containment Pressure (Wide Ran g e)2 E 9.Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b)E 10.Containment Area Radiation (Hi gh Ran g e)2 F 11.Pressurizer Level 2 E 12.Steam Generator Water Level (Wide Ran g e)2 per steam generato r E 13.Condensate Stora ge Tank Level 2 E 14.Core Exit Temperature

- Quadrant [1]2 (c)E 15.Core Exit Temperature

- Quadrant [2]2 (c)E 16.Core Exit Temperature

- Quadrant [3]2 (c)E 17.Core Exit Temperature

- Quadrant [4]2 (c)E 18.Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. (b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. (c) A channel consists of two core exit thermocouple s (CETs). ----------------------------------------------------------------REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1.All Regulatory Guide 1.97, Type A instruments and 2.All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.


INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19 PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 2 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. Power Ran ge Neutron Flux 2 E
2. Source Ran ge Neutron Flux 2 E
3. Reactor Coolant System (RCS) Hot Leg Temperature 2 per loop E
4. RCS Cold Le g Temperature 2 per loop E
5. RCS Pressure (Wide Ran g e) 2 E
6. Reactor Vessel Water Level 2 F
7. Containment Sump Water Level (Wide Ran g e)2 E
8. Containment Pressure (Wide Ran g e)2 E
9. Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b) E
10. Containment Area Radiation (Hi gh Ran g e)2 F
11. Pressurizer Level 2 E
12. Steam Generator Water Level (Wide Ran g e)2 per steam generato r E
13. Condensate Stora ge Tank Level 2 E
14. Core Exit Temperature

- Quadrant [1]2 (c) E

15. Core Exit Temperature

- Quadrant [2]2 (c) E

16. Core Exit Temperature

- Quadrant [3]2 (c) E

17. Core Exit Temperature

- Quadrant [4]2 (c) E

18. Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two core exit thermocouple s (CETs).


REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1. All Regulatory Guide 1.97, Type A instruments and
2. All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.

INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19

Licensee Response/NRC Response/NRC Question Closure Id168NRC Question Number KAB036Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/2/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/2/2014 3:15 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=168 ITS NRC Questions Id 60NRC Question Number KAB037Category TechnicalITS Section 3.3 ITS Number 3.3.3DOC Number A-4JFD Number JFD Bases Number Page Number(s) 704NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 704 of Enclosure 2, Volume 8, A04 provides the discussion of the minimum channels required for CTS Table 3.3-10 Instrument 18, "ERCW to AFW Valve Position,"which is 1/train/pump (2 valves/

train) for the motor driven pumps and 2 trains (2 valves/train) for the turbine driven pump. ITS Table 3.3.3-1 function 18, "ERCW to AFW Valve Position,"required channels is 2 for the motor driven pump and 2 for the turbine driven pump. A04 states, "This changes the CTS by

simplifying the presentation of the cha nnel requirements for ERCW to AFW Valve Position for the motor driven pumps and the turbine driven pump."The NRC staff does not agree that this change simplifies the presentati on and does not result in technical changes. Please provide a correction to the required channels in ITS Table 3.3.3-1 for function 18, such that it matc hes the minimum channels required for CTS Table 3.3-10 Instrument 18 or provide a change equivalent to the CTS Table 3.3-10 Instrument 18 requirements such that it clearly describes that there is 1 required valve position indication per tr ain per motor driven pump and 2 required valve position indication per train for each train of the turbine driven pump. Attach File 1 Attach File 2 Issue Date 5/13/2014 Added By Kristy BucholtzDate Modified Page 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=60 Modified By Date Added 5/13/2014 12:04 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=60 Licensee Response/NRC Response/NRC Question Closure Id 162NRC Question Number KAB037 Select Application Licensee ResponseAttachment 1 Attachment 1 for KAB037 R2.pdf (2MB)Attachment 2 Response Statement In response to KAB037, ITS Table 3.3.3-1, Post Accident Monitoring Instrumentation, will be modified to add a Foot note to Functions 18.a and 18.b. ITS Function 18.a, ERCW to AFW Valve Position for the Motor Driven Pumps, requires two OPERABLE channels.The foot note describes that a single channel consists of two valve position indicators associated with the in-series valves in a single suction line.ITS Function 18.b, ERCW to AFW Valve Position for the Turbine Driven Pump, requires two OPERABLE channels. The footnote describes that a single channel consists of two valve position indicators associated with the in

-series valves in a single suction line. These footnot es are consistent with CTS requirements for each ERCW to AFW valve position.During the review for the response to KAB036, it was noted that the sequencing of the footnotes for ITS Table 3.3.3

-1 is not in accordance with the Writer's Guide, TSTF-GG-05-0, the footnotes are not sequenced in the order in which they appear in the Table.Therefore, to correct this issue, CTS and ISTS markups wi ll be revised to co rrect the sequence of footnotes, as well as, corresponding revisions to the discussion of changes (DOCs).Attachment 1 will include the ch anges associated with this RAI response, associated changes for footnote sequencing, and the changes associated with th e response to RAI KAB036.Attachment 1 provides the markups for CTS Table 3.3-10 (pages 684 -688 and 694 -698 of Enclosure 2, Volume 8), ISTS Table 3.3.3-1 (pages 719 -721 and 727 -729), and change s to DOCs A03, A04, A05, and A06 (pages 703 -

706).Response Date/Time 6/30/2014 1:20 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzPage 1of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=16 2

Michelle ConnerKhadijah HemphillAndrew Hon Ray SchieleAdded By Scott BowmanDate Added 6/30/2014 12:16 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=16 2

ITS ITS 3.3.3 A01 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065) 4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083) 4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loops 30

-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops 30

-044,-045) 2 2 1 5. Refueling Water Storage Tank Level (Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range) (Instrument Loops 68

-062,-0 66,-069) 3 3 2 7. Pressurizer Level (Wide Range) (Instrument Loops 68

-320,-335,-339) 3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B,-020A,-020B,-027A,-027B) 2/steam line 2/steam line 1 9. Steam Generator Level - (Wide Range) (Instrument Loops 3

-043,-056,-098,-111) 4(1/steam generator) 4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3-039,-042,-052,-055,-094,-097,-107,-110) 2/steam generator 2/steam generator 1

11. Auxiliary Feedwater
a. Flow Rate (Instrument Loops 3

-163,-155,-147,-170) 1/steam generator 1/steam generator 5 b. Valve Position Indication (Instrument Loops 3

-164,-164A,-172,-156, -156A,-173,-148,-148A,-174,-171,-171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56 Amendment No. 46, 114, 149, 159 1 Table 3.3.3-1 2 3 4 5 6 7 8 9 11 10 ITS ACTION A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA03 LA04 LA04 Page 2 of 20 LA05 1 A03 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION

12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102) 2 2 1 13. Containment Water Level (Wide Range) (Instrument Loops 63

-178,-179) 2 2 1

14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1
b. Core Quadrant (2) 2(1/Train) 1
c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation 6
a. Dynamic Range (Instrument Loops68-367, 370) 2 1
b. Lower Range (Instrument Loops 68

-368, 371) 2 1

c. Upper Range (Instrument Loops 68

-369, 372) 2 1

16. Containment Area Radiation Monitors
a. Upper Compartment (Instrument Loops90-271,-272) 2 1

4 b. Lower Compartment (Instrument Loops90-273,-274) 2 1 4

October 4, 1995 SEQUOYAH - UNIT 1 3/4 3-56a Amendment No. 112, 149, 159, 213 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H LA03Table 3.3.3-1 ITS ACTIONF and I F and I Page 3 of 20 LA05(c) Add proposed Table 3.3.3-1 Footnote (c)

A04 LA04 A04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flux

a. Source Range (Instrument Loops 92

-5001,-5002) 2 2# 1

b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position

a. Motor Driven Pumps (Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1

b. Turbine Driven Pumps (Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1

19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3

_____________ #Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint. ##Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 1 3/4 3-56b Amendment No. 112, 149, 159 Table 3.3.3-1 Footnote (a) Table 3.3.3-1

Footnote (d) whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. 2 per penetration flow path A06 17 18 19 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA03Table 3.3.3-1 ITS ACTION Page 4 of 20 (b)A06 A06 LA05 2 A05 2 LA04 ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57 Amendment No. 46, 149, 159, 301 ACTION A ACTION A ACTION C ACTION C ACTION H ACTION B ACTION H ACTION B ACTION H ACTION A Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01 A07 A07 A07 ACTION D A06 Page 5 of 20 Table 3.3.3-1 Footnote (a)

ITS ITS 3.3.3 A01 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued)

affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered.

However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 1 3/4 3-57a Amendment No. 159, 301 ACTION H ACTION C Table 3.3.3-1 Footnote (b)

ACTION B two A06 Page 6 of 20 LA06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a)

A06Initiate action in accordance with Specification 5.6.5 L01 ITS A01 ITS 3.3.3 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS REQUIRED A CTION 1. Reactor Coolant T HOT (Wide Range)

(Instrument Loops 68

-001,-024,-043,-065)4(1/RCS Loop) 4 (1/RCS Loop) 1 2. Reactor Coolant T COLD (Wide Range)

(Instrument Loops 68

-018,-041,-060,-083)4(1/RCS Loop) 4 (1/RCS Loop) 1 3. Containment Pressure (Wide Range)

(Instrument Loo p s30-310,-311) 2 2 1 4. Containment Pressure (Narrow Range)

(Instrument Loops30-044,-045) 2 2 1 5. Refueling Water Storage Tank Level

(Instrument Loops 63

-050,-051) 2 2 1 6. Reactor Coolant Pressure (Wide Range)

(Instrument Loo p s68-062,-066,-069)3 3 2 7. Pressurizer Level (Wide Range)

(Instrument Loops 68

-320,-335,-339)3 3 2 8. Steam Line Pressure (Instrument Loops 1

-002A,-002B,-009A,-009B, -020A,-020B,-027A,-027B) 2/steam line2/steam line 1

9. Steam Generator Level - (Wide Range)

(Instrument Loops 3

-043,-056,-098,-111)4(1/steam generator)4(1/steam generator) 1 10. Steam Generator Level - (Narrow Range) (Instrument Loops 3

-039,-042,-052,-055,-094, -097,-107,-110) 2/steam generator 2/steam generator 1 11. A uxiliar y Feedwater

a. Flow Rate

(Instrument Loops 3

-163,-155, -147,-170)1/steam generator 1/steam generator 5 b. Valve Position Indication

(Instrument Loops 3

-164,-164A,-172,-156,- 156A,-173,-148,-148A,-174,-171, -171A,-175) 3/steam generator 3/steam generator 5

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57 Amendment Nos. 38, 104, 135, 149 Page 12 of 20Table 3.3.3-1 ITS ACTION LA03 LA04 LA04 1 11 2 3 4 5 6 7 8 9 10 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, D, and H A, B, C, D, and H A, B, E, and H A, B, E, and H LA05 1 A03 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 12. Reactor Coolant System Subcooling Margin Monitor (Instrument Loops 94

-101,-102)2 2 1 13. Containment Water Level (Wide Range)

(Instrument Loo p s63-178,-179) 2 2 1 14. Incore Thermocouples 65 a. Core Quadrant (1) 2(1/Train) 1 b. Core Quadrant (2) 2(1/Train) 1 c. Core Quadrant (3) 2(1/Train) 1 d. Core Quadrant (4) 2(1/Train) 1 15. Reactor Vessel Level Instrumentation S ystem 6 a. Dynamic Range (Instrument Loops 68

- 367, 370) 2 1 b. Lower Range

(Instrument Loops 68

-368, 371) 2 1 c. Upper Range

(Instrument Loops 68

-369, 372) 2 1 16. Containment Area Radiation Monitors a. Upper Compartment

(Instrument Loops 90

-271,-272)2 1 4 b. Lower Compartment

(Instrument Loops 90

-273,-274)2 1 4

October 4, 1995 SEQUOYAH - UNIT 2 3/4 3-57a Amendment No. 102, 135, 149, 203 Page 13 of 20 LA03Table 3.3.3-1 ITS ACTION 12 13 14 15 16 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and HF and I F and I (c) A04 LA04 LA05Add proposed Table 3.3.3-1 Footnote (c)

A04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

INSTRUMENT TOTAL NO. OF CHANNELS MINIMUM CHANNELS REQUIRED ACTION 17. Neutron Flu x a. Source Range (Instrument Loo p s 92-5001,-5002) 2 2# 1 b. Intermediate Range (Instrument Loops 92

-5003,-5004) 2 2 1 18. ERCW to AFW Valve Position a) Motor Driven Pumps

(Instrument Loops 3

-116A, -116B, -126A, -126B) 1/Train/Pump (2 Valves/Train) 1/Train/Pump (2 Valves/Train) 1 b) Turbine Driven Pumps

(Instrument Loops 3

-136A, -136B, -179A, -179B) 2 Trains (2 Valves/Train) 2 Trains (2 Valves/Train) 1 19. Containment Isolation Valve Position (Panels TR

-A XX-55-6K & TR-B XX-55-6L) 1/Valve 1/Valve## 3 # Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

    1. Not required for isolation valves that are closed and deactivated.

July 9, 1992 SEQUOYAH - UNIT 2 3/4 3-57b Amendment Nos. 102, 135, 149

Page 14 of 20 LA03Table 3.3.3-1 ITS ACTION 17 18 19 Table 3.3.3-1 Footnote (d) Table 3.3.3-1

Footnote (a) (b) A062 per penetration flow path A06whose associated penetration is isolated b y at least one automatic valve, closed manual valve, blind flange, or check valve with flow through the

v a lv e secu r ed.L03(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

A06 A, B, C, and H A, B, C, and H A, B, C, and H A, B, C, and H A, C, and H LA05 2 A05 2 LA04 ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 1 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 and 3.3-3, and LCO 3.3.3.5 since they may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

NOTE: Also refer to the applicable action requirements from Tables 3.3

-1 since it may contain more restrictive actions.

a. With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

NOTE: Also refer to the applicable action requirements from LCO 3.6.3 since it may contain more restrictive actions.

      1. a. With the accident monitoring indication for one of the penetration inboard or outboard valve (s) inoperable, restore the inoperable valve(s) accident indication to OPERABLE status within 30 days, or isolate each affected penetration within 30 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58 Amendment Nos. 38, 135, 149, 290 Page 15 of 20 ACTION A ACTION B ACTION C ACTION H ACTION A ACTION B ACTION C ACTION H ACTION D ACTION H ACTION A A07 A07 A07 A06Initiate action in accordance with Specification 5.6.5 L01Initiate action in accordance with Specification 5.6.5 L01Table 3.3.3-1 Footnote (a)

ITS A01 ITS 3.3.3 TABLE 3.3-10 (Continued)

ACTION STATEMENTS (Continued) affected penetration within 30 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ### b. With the accident monitoring indication for both an inboard and outboard valve (s) on the same penetration inoperable, restore at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days, or isolate each affected penetration within 7 days by use of at least one deactivated automatic valve secured in the isolated position, or isolate each affected penetration within 7 days by use of at least one closed manual valve or blind flange, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

      1. On a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. However, valves FCV 158 & -172 are both inboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status. Valves FCV 46 & VLV-30-571, FCV-30-47 & VLV-30-572, and FCV 48 & VLV-30-573 are all outboard penetration valves, but if both valves have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's accident indication is restored to OPERABLE status.

April 11, 2005 SEQUOYAH - UNIT 2 3/4 3-58a Amendment No. 149, 290 Page 16 of 20 ACTION B ACTION C ACTION H LA06two A06Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (a) Table 3.3.3-1 Footnote (b)

A06Initiate action in accordance with Specification 5.6.5 L01 DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 10 ADMINISTRATIVE CHANGES

A01 In the conversion of the Sequoyah Nuclear Plant (SQN) Current Technical Specifications (CTS) to the plant specific Improved Technical Specifications (ITS), certain changes (wording preferences, editorial changes, reformatting, revised numbering, etc.) are made to obtain consistency with NUREG-1431, Rev. 4.0, "Standard Technical Specifications-Westinghouse Plants" (ISTS) and additional Technical Specification Task Force (TSTF) travelers included in this

submittal.

These changes are designated as administrative changes and are acceptable because they do not result in technical changes to the CTS.

A02 CTS 3.3.3.7 ACTIONS, as shown in CTS Table 3.3-10, provide the compensatory actions to take when PAM instrumentation is inoperable. ITS 3.3.3 ACTIONS provide the compensatory actions for inoperable PAM Instrumentation. The ITS 3.3.3 ACTIONS include a Note that allows separate Condition entry for each Function. In addition, separate Condition entry is allowed within a Function on a "per" bases as listed for Functions 8 (Steam Line

Pressure (per steam line)), 10 (Steam Generator Level (Narrow Range) (per steam generator)) 11 (Auxiliary Feedwater (per steam generator)), and 19 (Containment Isolation Valve Position (per penetration flowpath)). This modifies the CTS by providing a specific allowance to enter the Action for each inoperable PAM instrumentation Function and for certain Functions on a "per" steam line, steam generator, or penetration flowpath basis.

This change is acceptable because it clearly states the current requirement. The CTS considers each PAM instrumentation Function to be separate and independent from the others. In addition, the channels associated with Functions 8, 10, 11, and 19 are allowed separate Condition entry on a steam line, steam generator, or penetration flowpath basis, which is consistent with the intent of the CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A03 CTS Table 3.3-10 Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)) "Minimum Channels Required" column states that the minimum channels required is 3/steam generator. ITS Table 3.3.3-1 Function 11.b (Auxiliary Feedwater (Valve Position Indication)) "Required Channels" column requires one channel per steam generator (consisting of 3 valve position indications). This changes the CTS by simplifying the presentation of the requirements for Auxiliary Feedwater (Valve Position Indication) instrumentation

by requiring one channel per steam generator.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument per steam generator. CTS Table 3.3-10 "Minimum Required Channels" column lists "3/steam generator" as the minimum required channels for Instrument 11.b (Auxiliary Feedwater (Valve Position Indication)). At SQN a channel consists of

three valves per steam generator, two from the motor driven auxiliary feedwater pump and one from the turbine driven auxilia ry feedwater pump. Therefore, to fulfill the "Minimum Required Channels" requirement for Instrument 11.b DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 2 of 10 requiring one channel per steam generator, all three valves position indication must be OPERABLE. This change is acceptable because the requirements contained in ITS are the same as in CTS when a required auxiliary feedwater valve position indicator is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A04 CTS Table 3.3-10 Instrument 14 (Incore Thermocouples) "Minimum Channels Required" column states, in part, that the minimum channels required is 2 (1 per train) in each of the four core quadrants. ITS Table 3.3.3-1 Function 14 (Incore Thermocouples) "Required Channel" column also requires two channels in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states, "A channel consists of one incore thermocouple. The required channels in each quadrant shall be in different trains." This changes the CTS by explicitly stating the number of incore thermocouples included in a channel. The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to list the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "2(1/train)" as the minimum required channels for Instrument 14 (Incore Thermocouples) in each core quadrant. At SQN a channel consists of one incore thermocouple, therefore to fulfill the "Minimum Required Channels" requirement for Instrument 14 requires two incore thermocouples in each core quadrant, one from each train, to be OPERABLE. ITS Table 3.3.3-1 "Required Channel" column for Function 14 (Incore Thermocouples) requires two channels to be OPERABLE in each of the four core quadrants and is modified by Footnote (c). ITS Table 3.3.3-1 Footnote (c) states that a channel consists of one incore thermocouple from different trains. The addition of Footnote (c) explicitly states the channel requirement of CTS. This change is designated as administrative because it does not result in technical changes to the CTS.

A05 CTS Table 3.3-10 Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Minimum Channels Required" column states, in part, that the minimum channels required are 1/Train/Pump (2 Valves/Train). ITS Table 3.3.3-1 Function 18.a (ERCW to AFW Valve Position (Motor Driven Pumps)), "Required Channel" column requires 2 channels. CTS Table 3.3-10 Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Minimum Channels Required" column states that the minimum channels required are 2 Trains (2 Valves/Train). ITS Table 3.3.3-1 Function 18.b (ERCW to AFW Valve Position (Turbine Driven Pump)), "Required Channel" column requires 2 channels. This changes the CTS by simplifying the presentation of the channel requirements for ERCW to AFW Valve Position for the Motor Driven Pumps and the Turbine Driven Pump.

The purpose of CTS Table 3.3-10 "Minimum Channels Required" column is to designate the number of channels required to be OPERABLE for the associated instrument. CTS Table 3.3-10 "Minimum Required Channels" column lists "1/Train/Pump (2 Valves/Train)" as the minimum required channels for Instrument 18.a (ERCW to AFW Valve Position (Motor Driven Pumps,)). At SQN

there are two motor driven auxiliary feedwater pumps. Each motor driven pump has two valves in series between the AFW pump and the ERCW supply. CTS Table 3.3-10 lists them as 3-116A and 3-116B, which are in the ERCW supply DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 10 line to the 1A-A AFW Pump, and 3-126A and 3-126B, which are in the ERCW supply line to the 1B-B AFW pump. The ITS Bases defines a channel as consisting of these two valves in series in the ERCW to AFW flow path for each motor driven pump, therefore 2 channels are required. CTS Table 3.3-10 "Minimum Required Channels" column lists "2 Trains (2 Valves/Train)" as the minimum required channels for Instrument 18.b (ERCW to AFW Valve Position (Turbine Driven Pump,)). At SQN there is one turbine driven auxiliary feedwater pump. The turbine driven pump has two supply lines from ERCW, one from each train with two valves in series between the AFW pump and the ERCW supply.

CTS Table 3.3-10 lists them as 3-136A and 3-136B, which are in the ERCW supply line from the 1A ERCW header to the turbine driven AFW Pump, and 3-179A and 3-179B, which are in the ERCW supply line from the 1B ERCW header to the turbine driven AFW pump. The ITS Bases defines a channel as two valves in series for each ERCW supply line to the turbine driven AFW pump, therefore 2 channels are required. This change is acceptable because the requirements contained in ITS are the same as in CTS when an ERCW to AFW Valve Position channel is inoperable. This change is designated as administrative because it does not result in technical changes to the CTS.

A06 CTS Table 3.3-10 Instrument 19 (Containment Isolation Valve Position) "Minimum Channels Required" column requires one valve position indication channel OPERABLE per valve and lists ACTION 3 as the ACTION to follow if one channel per valve is inoperable. CTS Table 3.3-10 ACTION 3.a provides the required ACTIONS for one of the penetration inboard or outboard valve(s) inoperable (i.e., one channel inoperable per penetration) one part of which is restoring the inoperable valve(s) accident indication to OPERABLE status within 30 days. CTS Table 3.3-10 ACTION 3.b provides the required ACTIONS for both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two channels inoperable per penetration) one part of which is restoring at least the inboard or outboard inoperable valve(s) indication to OPERABLE status within 7 days. ITS LCO 3.3.3 ACTION A, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with one required channel inoperable restore required channel to OPERABLE status within 30 days. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days. CTS Table 3.3-10 Note ### states, in part, that on a penetration where accident indication is declared inoperable on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Function 19 (Containment Isolation Valve Position)

"Required Channels" column requires two channels to be OPERABLE per penetration and is modified by Footnote (b) which states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 ACTION 3.a references an inboard or outboard valve. CTS Table 3.3-10 ACTION 3.b references both an inboard and outboard valve(s). CTS Table 3.3-10 Note ###, in part, references penetrations whose valves are either both inboard (FCV 63-158 and FCV 63-

172) or both outboard (FCV 30-46 and VLV 30-571, FCV 30-47 and VLV 30-572, FCV 30-48 and VLV 30-573) and states that if both valves (two) have inoperable accident indication, ACTION 3(b) must be entered until at least one of the valve's DISCUSSION OF CHANGES ITS 3.3.3, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 4 of 10 accident indication is restored to OPERABLE status. ITS LCO 3.3.3 ACTION C, applicable to Function 19 (Containment Isolation Valve Position), states that with one or more Functions with two required channels inoperable to restore one channel to OPERABLE status within 7 days, similar to CTS Table 3.3-10 ACTION 3.b. This changes the CTS by simplifying the presentation of the

requirements for Containment Isolation Valve Position instrumentation by requiring two channels per penetration, except where ITS Table 3.3.3-1 Footnote (b) is applicable for those penetration flow paths with only one installed control room indication channel, and eliminating reference to inboard and outboard valve

combinations.

The purpose of CTS Table 3.3-10 is to provide requirements for Post-Accident Monitoring instruments. One of these instruments is Containment Isolation Valve Position. CTS requires one position indication channel per valve to be OPERABLE where normally there are two valves per penetration. Similarly, ITS requires two channels per penetration. CTS Note ###, in part, states that on a penetration where accident indication is declared INOPERABLE on a valve but on the opposite side of the penetration an accident indication valve does not exist (such as with a closed system or a check valve), only ACTION 3(a) must be entered. ITS Table 3.3.3-1 Footnote (b) similarly states that only one position indication channel is required for penetration flow paths with only one installed control room indication channel. CTS Table 3.3-10 Note ###, in part, requires entry into ACTION 3.b when two required valve position indicators per penetration are inoperable because ACTION 3.b entry condition is when both an inboard and outboard valve(s) on the same penetration inoperable (i.e., two position indicator per penetration). ITS LCO 3.3.3 ACTION C condition entry is when one or more Functions have two required channels inoperable, similar to CTS. This change is acceptable because the requirements contained in ITS are the same as in CTS when Containment Isolation Valve Position channel are inoperable for penetrations with two isolation valves per penetration and penetrations with one isolation valve per penetration. This change is designated as administrative because it does not result in technical changes to the CTS.

A07 CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 contain a Note referring to applicable action requirements from reference LCOs that may contain more restrictive actions. ITS Table 3.3.3-1 does not retain this information. This changes the CTS by not including the information referring to other potentially applicable action requirements to the Bases.

The purpose of CTS Table 3.3-10 ACTION 1, ACTION 2, ACTION 3, and ACTION 5 Note is to reference potentially associated Technical Specifications. It is an ITS convention to not include these types of notes or cross-references.

This change is designated as administrative change because it does not result in technical changes to the CTS.

MORE RESTRICTIVE CHANGES

None PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 1 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. Power Ran ge Neutron Flux 2 E
2. Source Ran ge Neutron Flux 2 E
3. Reactor Coolant System (RCS) Hot Leg Temperature 2 per loop E
4. RCS Cold Le g Temperature 2 per loop E
5. RCS Pressure (Wide Ran g e) 2 E
6. Reactor Vessel Water Level 2 F
7. Containment Sump Water Level (Wide Ran g e)2 E
8. Containment Pressure (Wide Ran g e)2 E
9. Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b) E
10. Containment Area Radiation (Hi gh Ran g e)2 F
11. Pressurizer Level 2 E
12. Steam Generator Water Level (Wide Ran g e)2 per steam generato r E
13. Condensate Stora ge Tank Level 2 E
14. Core Exit Temperature

- Quadrant [1]2 (c) E

15. Core Exit Temperature

- Quadrant [2]2 (c) E

16. Core Exit Temperature

- Quadrant [3]2 (c) E

17. Core Exit Temperature

- Quadrant [4]2 (c) E

18. Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two core exit thermocouple s (CETs).


REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1. All Regulatory Guide 1.97, Type A instruments and
2. All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.

INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19 PAM Instrumentation 3.3.3 Westinghouse STS 3.3.3-4 Rev. 4.0, SEQUOYAH UNIT 2 Amendment XXXCTS 1Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. Power Ran ge Neutron Flux 2 E
2. Source Ran ge Neutron Flux 2 E
3. Reactor Coolant System (RCS) Hot Leg Temperature 2 per loop E
4. RCS Cold Le g Temperature 2 per loop E
5. RCS Pressure (Wide Ran g e) 2 E
6. Reactor Vessel Water Level 2 F
7. Containment Sump Water Level (Wide Ran g e)2 E
8. Containment Pressure (Wide Ran g e)2 E
9. Penetration Flow Path Containment Isolation Valve Position 2 per penetration flow path (a)(b) E
10. Containment Area Radiation (Hi gh Ran g e)2 F
11. Pressurizer Level 2 E
12. Steam Generator Water Level (Wide Ran g e)2 per steam generato r E
13. Condensate Stora ge Tank Level 2 E
14. Core Exit Temperature

- Quadrant [1]2 (c) E

15. Core Exit Temperature

- Quadrant [2]2 (c) E

16. Core Exit Temperature

- Quadrant [3]2 (c) E

17. Core Exit Temperature

- Quadrant [4]2 (c) E

18. Auxiliary Feedwater Flow 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two core exit thermocouple s (CETs).


REVIEWER'S NOTE----------------------------------------------------------------

Table 3.3.3-1 shall be amended for each unit as necessary to list:

1. All Regulatory Guide 1.97, Type A instruments and
2. All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory Guide 1.97, Safety Evaluation Report.

INSERT 4(d) Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

Gone incore 1 1 1 3Note ## ACTION 3.a ACTION 3.b Note ### Table 3.3-10 DOC A03 Note # 1The required channels in each quadrant shall be in different trains.

ITS 3.3.3 ITS Insert Page 3.3.3-4a CTS INSERT 4 FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

1. Reactor Coolant THOT (Wide Range) 4 H
2. Reactor Coolant TCOLD (Wide Range) 4 H 3. Containment Pressure (Wide Range) 2 H
4. Containment Pressure (Narrow Range) 2 H
5. Refueling Water Storage Tank Level 2 H
6. Reactor Coolant Pressure (Wide Range) 3 H 7. Pressurizer Level (Wide Range) 3 H 8. Steam Line Pressure 2 per steam line H
9. Steam Generator Level - (Wide Range) 4 H
10. Steam Generator Level - (Narrow Range) 2 per steam generator H
11. Auxiliary Feedwater
a. Flow Rate

1 per steam generator

H b. Valve Position Indication 1 per steam generator H 1Table 3.3-10 1 2 3 4 5 6 7 8 9 10 11 ITS 3.3.3 ITS Insert Page 3.3.3-4b CTS INSERT 4 continued

FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION G.1

12. Reactor Coolant System Subcooling Margin Monitor 2 H 13. Containment Water Level (Wide Range) 2 H
14. Incore Thermocouples
a. Core Quadrant (1) 2 (c) H
b. Core Quadrant (2) 2 (c) H
c. Core Quadrant (3) 2 (c) H
d. Core Quadrant (4) 2 (c) H
15. Reactor Vessel Level Instrumentation
a. Dynamic Range 2 H
b. Lower Range 2 H
c. Upper Range 2 H
16. Containment Area Radiation Monitors
a. Upper Compartment

1 I b. Lower Compartment 1 I

17. Neutron Flux
a. Source Range

2(d) H b. Intermediate Range 2 H

18. ERCW to AFW Valve Position
a. Motor Driven Pumps 2 H
b. Turbine Driven Pump 2 H
19. Containment Isolation Valve Position 2 per penetration flowpath(a)(b) H 1Table 3.3-10 12 13 14 15 16 17 18 19 Licensee Response/NRC Response/NRC Question Closure Id169NRC Question Number KAB037Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/2/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/2/2014 3:16 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/20/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 64 NRC Question Number KAB038 Category TechnicalITS Section 3.3ITS Number 3.3.5 DOC Number L-1JFD Number JFD Bases Number Page Number(s) 837 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested N NRC Question On page 837 of Enclosure 2, Volume 8, L01 provides the discussion of engineered safety features response time verification in CTS 4.3.3.11.2.L01 proposes to delete the engineered safety features response time verification.L01 states, "This change is acceptable because the DG loading has been included in the delay time associated with each safety system component requiring DG supplied power following a loss of offsite power."

Sequoyah's current licensing basis fo r CTS 3.3.3.11 does not require a channel check, but it does require a channel calibration, channel functional test, and engineered safety features response time verification.TVA is proposing to delete the ISTS channel check, and modify the ISTS TADOT to be equivalent to a CTS channel functional test.These changes ar e consistent with the current licensing basis for Sequoyah.Howev er, TVA is not proposing to add the engineered safety features response time verification to the surveillance requirements in ITS.This is not consistent with Sequoyah's current licensing basis.

Please correct ITS 3.3.5 to be consistent wi th Sequoyah's current licensing basis, by adding the engineered safety features response time verification or provide a technical evaluation that includes hist orical data and explains why this instrumentation no longer needs the performa nce of a response time verification.

Note that removing the engineered safety features response time test is a beyond scope change and will be reviewed by the associated technical branch. Page 1of 2 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

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Attach File 1 Attach File 2 Issue Date 5/14/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/14/2014 10:23 AMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 98 NRC Question Number KAB038Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement Sequoyah License Amendment 190 and 182, for Unit 1 and Unit 2 respectively, relocated the Engineered Safety Feature Actuation System (ESFAS) response time limits to the Updated Final Safety Analysis Report (UFS AR) (ADAMS Accession No. ML013300393). UFSAR Table 7.3.1-4 contains these limits. Item 12.a, Loss of Power, 6.9 kV Shutdown Board -Degraded Voltage or Loss of Voltage, response time is listed as 10 seconds, and is modified by Note 10.Note 10 states that the response time for loss of voltage is measured from the time the diesel start signal is initiated until the time full voltage is restored by the diesel. The response time for degraded voltage is measured from the time the load shedding signal is generated, either from the degraded voltage or the safety injection (SI) enable timer, to the time full voltage is restored by the diesel. The response time of the timers is covered by the requirements on their setpoints.UFSAR Table 7.3.1-4, item 2.a, Containment Pressure -High, Safety Injection (ECCS); item 3.a, Pressurizer Pressure -Low, Safety Injection (ECCS); and item 6.a, Steam Line Pressure -Low, Safety Injection (ECCS), each indicate the assumed response time for the respective actuation signal and are each modified by Note 1.Note 1 states that the response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps, SI, and RHR pumps.Furthermore, Note 1 states that DG starting and sequence loading delays are included. Therefore, each SI actuation signal response time contains the response time of the LOP DG Start Instrumentation.In WCAP-12159, MERITS Program Phase II, NUREG-0452, Tables 3.3-4 and 4.3-2, Functions 8.a Loss of Power, 4 kV Bus Undervoltage (Loss of Voltage), and 8.b, Loss of Power, 4 kV Bus Undervoltage (Grid Degraded Voltage), were relocated from NUREG-0452 with the justification that, "The safeguards 4 kV bus undervoltage and degraded voltage functions only start the emergency diesel generators.These functions have been relocated to LCO 3.7.1, AC Sources -Operating." Therefore, the surveillance requirements within ITS 3.8.1 will continue to verify that each required DG will upon receipt of an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal, auto-start from a standby condition and energize permanently connected loads in 10 seconds.In conclusion, ITS will continue to verify that the ESF response times, including the DG start and load shedding times, assumed in the accident analysis are satisfied.Response Date/Time 6/5/2014 4:30 PMPage 1of 2 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=98 Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/5/2014 3:28 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=98 Licensee Response/NRC Response/NRC Question Closure Id147NRC Question Number KAB038Select Application NRC ResponseAttachment 1 Attachment 2 Response Statement Please provide a copy (or excerpt) of the procedure currently used for conducting the CTS SR 4.3.3.11.2.Response Date/Time 6/24/2014 6:00 PMClosure Statement Question Closure Date Notification Scott BowmanMichelle ConnerVijay GoelKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger Scott Added By Kristy BucholtzDate Added 6/24/2014 6:34 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 278NRC Question Number KAB038 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement Surveillance Instruction, 1-SI-IRT-099-699.A, Response Time Test of ESFAS Safety Injection Signal with Statio n Blackout Train A, is performed to measure and verify 6.

9 kV Shutdown Board bus regeneration after Blackout for the SQN Unit 1, A Train.This procedur e in conjunct ion with 1-SI-IRT-099-400.0 (Attachment 2) satisfies CTS 4.3.3.11.2 for SQN UFSAR Table 7.3.1-4, Function 12.

a, 6.9 kV Shutdown Board - Degraded Voltage or Loss of Voltage.Surveillance Instruction, 1-SI-IRT

-099-400.0, Response Time Scheduling and Verification of Reactor Trip and Engineered Safety Feature Systems, establishes the Acceptanc e Criteria required in each individual Response Time Instruction for SQN Unit 1.Surveillance Instruction, 1-SI-EDC-082-307.A, Undervoltage/Degraded Voltage, DG Start, and Load Shedding Time Response Relay Test.1-SI-EDC-082-307.A is a calibration performed to determine the operability of Diesel Generator start and load shedding and SI/degraded voltage logic enable timers for SQN Unit 1.Response Date/Time 8/21/2014 9:25 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 8/21/2014 8:24 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=278 Licensee Response/NRC Response/NRC Question Closure Id301NRC Question Number KAB038Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 8/27/2014Notification Scott BowmanMichelle ConnerVijay GoelKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 8/27/2014 1:54 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 9/9/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=301 ITS NRC Questions Id 66NRC Question Number KAB039Category TechnicalITS Section 3.3ITS Number 3.3.4DOC Number JFD Number JFD Bases Number Page Number(s) 786, 791, 814, 823NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 786 and 791 of Enclosure 2, Volu me 8, shows the CTS Table 3.3-9. On these pages instrument 1 has a me asurement range of 1 to 1 x 10 6 cps and the CTS page states that it is Amendment N

o. 113 May 4, 1989 for unit 1 and Amendment No. 67, 103 May 4, 1989 for unit 2. Howev er, the record copy of Sequoyah's CTS states that instrument 1 has a measurement range of 0.1 to 1 x 10 5 cps and the CTS page states that it is Amendment No. 113, 278 September 30, 2002 for unit 1 and Amendment No. 67, 103, 269 September 30, 2002 fo r unit 2. In a ddition, pages 814 and 823, the ITS Bases, states that instrume nt 1 has a measurement range of 1 to 1 x 10 6 cps. Please explain why there is a difference in the measurement range for instrument 1. In addition, explain if this instrument has been replaced from the original instrument to a new instrument, if so was the replacement the same make and model, and what is the measured rang e of the currently in stalled instrument (0.1 to 1 x 10 5 cps) or (1 to 1 x 10 6 cps)?Attach File 1 Attach File 2 Issue Date 5/19/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:05 AMPage 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 133NRC Question Number KAB039Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement As stated in the ITS license amendment request (LAR) cover letter, "the CTS marked-up pages do not include NRC-approved Amendments 278 and 289 for Unit 1 and Amendments 269 and 279 for Unit 2.These amendments are not to be implemente d until start up from the outage where SQN inserts tritium-producing burnable rods in the core.At this time, the production of tritium in the SQN reactors has b een delayed indefinitely."The ADAMS record copy of the CTS reflects all NRC-approved amendments and therefore, the record copy differs from SQN's operating copy of technical specifications because the listed amendments (278, 289, 269 and 279) have not been implemented at SQN.

On September 21, 2001, SQN submitted an LAR (ML012890063) to change the TSs for Units 1 and 2 to allow SQ N to provide irradiation services for the U.S. Department of Energy.One of the proposed changes involved revising the measurement range for the source range monitors (identified in the RAI as Instrument 1) in TS Table 3.3-9.The LAR was approved by issuance of Amendments 278 and 269.Although approved, SQN has not implemented the TS change.Therefore, the instrument has not been replaced by a new instrume nt and there has been no revision to the source range instrumentation measurement range. The correct measurement range for the source range monitors is 1 to 1x10 6 cps.Response Date/Time 6/20/2014 5:10 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanPage 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Date Added 6/20/2014 4:07 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id140NRC Question Number KAB039Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/20/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/20/2014 1:16 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=140 ITS NRC Questions Id 67NRC Question Number KAB040 Category EditorialITS Section 3.3ITS Number 3.3.6DOC Number JFD Number JFD Bases Number Page Number(s) 903NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 903 of Enclosure 2, Volume 8, A05 provides the discussion for CTS 4.3.2.1.3 ESFAS Response Time of each ES FAS function. However, in the discussion it refers to reactor trip functi on instead of the ESFAS function. Please explain this discrepancy.

Attach File 1 Attach File 2 Issue Date 5/19/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:07 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 68NRC Question Number KAB040 Select Application Licensee ResponseAttachment 1 Attachment 1 revised 3.3.6 DOC A05.pdf (17KB)Attachment 2 Response Statement In response to KAB040, discussion of change (DOC) A05 on page 903 of Enclosure 2, Volume 8, will be revised.Specifically, the sentence, "The requirement specifies that each test shall include at leas t one logic train such that both logic trains are tested at least once per 36 months, and one channel per function such that all chan nels are tested at least once every N times 18 months where N is the tota l number of redundant channels in a specific reactor trip function as shown in the

'Total No. of Channels'column of Table 3.3-3[.]"will be revised to, "The requirement specifies that each test shall include at least one logic train such that both logic trains are tested at least once per 36 months, and one cha nnel per function such that all channels are te sted at least once every N times 18 months where N is the total number of redunda nt channels in a specific ESFAS function as shown in the 'Total No. of Channels'column of Table 3.3-3."See Attachment 1 for th e draft revised DOC A05.Response Date/Time 5/29/2014 3:40 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 5/29/2014 2:37 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=68 DISCUSSION OF CHANGES ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 12 as is delineated in UFSAR Table 7.3.1-4. This change is designated as administrative because it does not result in technical changes to the CTS.

A05 CTS 4.3.2.1.3 states, in part, that the ESF RESPONSE TIME of each ESFAS function shall be demonstrated to be within its limit at least once per 18 months.

The requirement specifies that each test shall include at least one logic train such that both logic trains are tested at least once per 36 months, and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-3 ITS SR

3.3.6.8 requires the verification of ESF RESPONSE TIMES every 18 months "on a STAGGERED TEST BASIS." The ITS definition of STAGGERED TEST BASIS is consistent with the CTS testing Frequency. This changes the CTS by utilizing the ITS definition of STAGGERED TEST BASIS for the Frequency of the ESF

RESPONSE TIME testing.

This change is acceptable because the requirements for ESF RESPONSE TIME testing for the ESFAS channels remain unchanged. The ITS definition of STAGGERED TEST BASIS and its application in this requirement do not change the current testing Frequency requirements. This change is designated as administrative because it does not result in technical changes to the CTS.

A06 ITS 3.3.6 ACTIONS contains a Note which states that separate Condition entry is allowed for each Function. The ACTIONS for CTS 3.3.2.1 (Unit 1), CTS 3.3.2 (Unit 2), and CTS 3.3.3.1 do not contain this Note. This changes the CTS by specifically allowing separate Condition entry for each Function in ITS Table 3.3.6-1.

This change is acceptable because it clearly states the current requirement. The CTS considers each ESFAS and radiation monitoring instrument Function to be separate and independent. This change is designated as administrative because it does not result in a technical change to the CTS.

A07 CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST for Functional Unit c.1 (Manual). ITS Table 3.3.6-1 requires a similar test; ITS SR 3.3.6.6 (TADOT) to be performed for Function 1 (Manual Initiation) with the addition of a Note that states, "Verification of setpoint is not required." This changes the CTS by requiring a TADOT without setpoint verification instead of a CHANNEL FUNCTIONAL TEST.

CTS 1.6 states that for an analog channel a CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

ITS 1.1 defines a TADOT as consisting of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. ITS further states that the TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. Because the TADOT includes adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy, which is not included in the CTS CHANNEL FUNCTIONAL TEST, ITS SR 3.3.3.6 includes the Note, "Verification Licensee Response/NRC Response/NRC Question Closure Id 86NRC Question Number KAB040Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:42 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 68 NRC Question Number KAB041 Category TechnicalITS Section 3.3ITS Number 3.3.6 DOC Number LA-1JFD Number JFD Bases Number Page Number(s) 905, 907 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested N NRC Question On pages 905 and 907 of Enclosure 2, Volume 8, LA01 in part, and M04 provides the discussion of adding a surveillance requirement fo r master and slave relay testing. This discussion states that the slave relay testing ITS SR 3.3.6.5 has a frequency of 18 months. However, IS TS and ITS slave relay testing has a frequency of 92 days. Please explain whic h frequency is proposed. If Sequoyah is proposing to adopt the ISTS frequency, then please correct the frequency in LA01 and M04. If Sequoyah is proposing to ad opt a frequency of 18 months, which is a beyond scope change then please provide the technical evaluation for NRC review.

Attach File 1 Attach File 2 Issue Date 5/19/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:09 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=68 Licensee Response/NRC Response/NRC Question Closure Id 242NRC Question Number KAB041Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement SQN proposes to add ITS 3.3.6, Surveillance Requirement (SR) 3.3.6.5, slave relay testing requirements, for Functional Unit 2 at a frequency of every 18 months. This change is annotated on CTS pages 882 and 894 of Enclosure 2, Volume 8 and justified by ITS 3.3.6 discussion of change (DOC) M04 on pages 905-906.The proposed surveillance Frequency for slave relay testing, 18 months, is consistent with SQN's current testing practices.SQN's current testing practice, although not required by CTS, ensures the slave relays are tested each refueling outage (18 months).Additionally, Westinghouse perfo rmed a reliability assessment of Westinghouse Type AR relays used as SSPS slave relays.

The objective of WCAP-13877, "Reliability Assessment of Westinghouse Type AR Relays Used as SSPS Slave Relays WOG Program MUHP-7040,"was to establish the basis for determining the reliabilit y of the Westinghou se type AR relay.The evaluation was in tended to aid in the determination of maintenance and surveillance intervals consistent with reliability goals.A particular objective was to demonstrate that a refueling-based surveillance interval (18 months to 24 months) would not adversely affect the reliability of Solid State Protection System (S SPS) slave relays used in Engineered Safety Feature Actuation System (ESFAS) functions.The WCAP used SQN slave relay failure history, in addition to failure hist ory from other utilities, to conclude that the assumed initial quarterly test interval (92 days) supported by WCAP-10271-P-A, Supplement 2, Revision 1 was overly conservative.WCAP-13877 concluded that slave relay testing could be extended to a refueling basis wi thout impact or conseque nce to relay reliability.Therefore, based on the conclusion of WCAP-13877, that slave relay testing could be extended to a refueling basis without impact to relay reliability, and SQN's current slave relay test ing frequency of 18 months, SQN proposes to adopt ITS SR 3.3.6.5 with an 18 month Frequency.Response Date/Time 8/5/2014 9:25 AM Closure Statement Question Closure Page 1of 2 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 8/5/2014 8:24 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 310NRC Question Number KAB041Select Application NRC ResponseAttachment 1 Attachment 2 Response Statement Did TVA get approval for the existing 18 month surveillance interval by submitting a LAR that was approved by NRC staff. If so, please provide the information of submittal of the LAR and NRC staff safety evaluation for our confirmation.If not then provide the following information as requested in the safety evaluation issued by NRC staff when approving Westinghouse WCAP13877:a. Confirm the applicability of WCAP13877 (Rev. 1 and Rev. 2) analysis for Sequoyah plants.b. Ensure that contact loading analysis for Type AR relays has been performed to determine the acceptability of this analysis.c. Determine that the qualified life for the Type AR relays based on plant specific environmental conditions.d. Establish a program to evaluate the adequacy of the proposed test interval if two or more AR relays fail in a 12month period.Response Date/Time 9/3/2014 6:00 PMClosure Statement Question Closure Date Notification Scott BowmanMichelle Conner Khadijah Hemphill Andrew HonLynn Mynatt Ray Schiele

Roger ScottAdded By Kristy BucholtzDate Added 9/3/2014 7:03 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=310 Licensee Response/NRC Response/NRC Question Closure Id 355 NRC Question Number KAB041Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement SQN's current technical specifications (CTS) do not contain a Surveillance Requirement to specifically test slave relays.SQN is proposing to add ISTS 3.3.6.7 (ITS SR 3.3.6.5), SLAVE RELAY TEST, as part of the ITS conversion, for ITS Table 3.3.6-1, Function 2 (Automatic Actuation Logic and Actuation Relays).This is a more restrictive change to CTS and is justified in Discussion of Change M04.The proposed Frequency for ITS SR 3.3.2.5 is every 18 months.Currently, SQN performs slave relay testing every refueling outage (18 months) which corresponds to the proposed 18-month Surveillance Frequency for ITS SR 3.3.6.5.SQN is not proposing to adopt WCAP-13877 as a basis for extending slave relay testing from 92 days to an 18 month frequency, because SQN does not have a Surveillance Requirement to perform slave relay testing in CTS, and slave relays are already tested at an 18-month frequency.However, it should be recognized that SQN was used as one of the reference plants for the development of WCAP-13877.SQN slave relay failure history, in addition to failure history from other plants, was used in WCAP-13877 to conclude that testing on an 18-month Surveillance Frequency was acceptable.Response Date/Time 9/26/2014 9:25 AMClosure Statement Question Closure Date Notification Scott BowmanKristy Bucholtz Michelle ConnerKhadijah Hemphill Andrew HonLynn Mynatt Ray SchieleAdded By Scott BowmanDate Added 9/26/2014 8:19 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id359NRC Question Number KAB041Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 9/26/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 9/26/2014 9:19 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 10/15/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 69NRC Question Number KAB042Category EditorialITS Section 3.3 ITS Number 3.3.6DOC Number L-1JFD Number JFD Bases Number Page Number(s) 909NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 909 of Enclosure 2, Volume 8, L01 pr ovides the discussion of adding a note to the engineered safety features (ESF) response time of the engineered safety features actuation system functions in CT S and ITS. L01 states, "This changes the CTS by excluding the radiation monitor from the ESF RESPONSE TIME testing for the Containment Ventilation Isolation High Radiation Function."However, note (6) in the updated final safety anal ysis report Table 7.3.1-4 states, "Radiation detectors for Containment Ventilation Iso lation may be excluded from Response Time Testing."Please cor rect the sentence in L01 to reference the radiation detector instead of the radiation monitor.Attach File 1 Attach File 2 Issue Date 5/19/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:10 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 70 NRC Question Number KAB042Select Application Licensee ResponseAttachment 1 SQN ITS Attachment 1 revised 3.3.6 DOC L01.pdf (21KB)Attachment 2 Response Statement In response to KAB042, discussion of change (DOC)

L01 will be revised. Specifically, the senten ce, "This changes the CTS by excluding the radiation monitor from the ESF RESPONSE TIME testing for the Containment Ventilation Is olation High Radiation Function."will be revised to, "This changes the CTS by e xcluding the radiation detector from the ESF RESPONSE TIME testi ng for the Containment Ventilat ion Isolation High Radiation Function."See Attachment 1 for the draft revised DOC L01.Response Date/Time 5/29/2014 4:00 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 5/29/2014 2:58 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=70 DISCUSSION OF CHANGES ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 9 of 12 necessary to be included in the Technical Specifications to provide adequate protection of public health and safety. The ITS still retains the requirement for the number of required channels and the appropriate Condition to enter if a required channel becomes inoperable. Also, this change is acceptable because the removed information will be adequately controlled in the ITS Bases.

Changes to the Bases are controlled by the Technical Specification Bases Control Program in Chapter 5. This program provides for the evaluation of changes to ensure the Bases are properly controlled. This change is designated as a less restrictive removal of detail change because information relating to system design is being removed from the Technical Specifications.

LESS RESTRICTIVE CHANGES

L01 (Category 6 - Relaxation of Surveillance Requirement Acceptance Criteria)

CTS 4.3.2.1.3 states, in part, that the ESF RESPONSE TIME of each ESFAS function shall be demonstrated to be within its limit at least once per 18 months. ITS SR 3.3.6.8 Note states that the radiation detectors are excluded from response time testing. This changes the CTS by excluding the radiation monitor from the ESF RESPONSE TIME testing for the Containment Ventilation Isolation High Radiation Function.

The purpose of CTS 4.3.2.1.3 is to ensure that the actuation response times are less than or equal to the maximum values assumed in the accident analysis. UFSAR Table 7.3.1-4 specifies response times and exceptions allowed for the Containment Ventilation Isolation Function initiated by the Containment Purge Air Exhaust Radioactivity -High signal. Sequoyah License Amendment 190 and 182, for Unit 1 and Unit 2 respectively, relocated the ESFAS response time limits to the UFSAR (ADAMS Accession No. ML013300393). UFSAR Table 7.3.1-4 contains these limits listing the information in two columns, "Initiating Signal and Function," and "Response Time in Seconds." The Initiating Signals listed in UFSAR Table 7.3.1-4 includes Containment Purge Air Exhaust Radioactivity -

High for Function Containment Ventilation Isolation. The Response Time column in UFSAR Table 7.3.1-4 for Containment Ventilation Isolation is modified by Note (6). UFSAR Table 7.3.1-4 Note (6) states that the radiation detectors for Containment Ventilation Isolation Function may be excluded from Response Time Testing. This Note modifies the CTS definition of an ESF RESPONSE TIME test and was removed from CTS by License Amendment 190 and 182. ITS SR 3.3.6.8 is modified by a similar Note that excludes the radiation detector from ESF RESPONSE TIME testing. This change is acceptable because ITS 3.3.6, Table 3.3.6-1 retains the CTS intent of requiring ESF RESPONSE TIME testing (ITS SR 3.3.6.8) for those ESFAS Functions listed in UFSAR Table 7.3.1-4 as modified by the associated Table 7.3.1-4 Note. This change is designated as less restrictive because less stringent Surveillance Requirements are being applied in the ITS than were applied in the CTS.

L02 (Category 4 - Relaxation of Required Action) CTS Table 3.3-3 ACTION 15 requires that when one channel of Containment Ventilation Isolation - Automatic Isolation Logic (Functional Unit 3.c.2) is inoperable to be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Additionally, CTS Table 3.3-3 ACTION 15 allows one channel of the Licensee Response/NRC Response/NRC Question Closure Id 87NRC Question Number KAB042Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 5/30/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 5/30/2014 8:42 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 70NRC Question Number KAB043 Category EditorialITS Section 3.3 ITS Number 3.3.6DOC Number A-7JFD Number JFD Bases Number Page Number(s) 903NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 903 of Enclosure 2, Volume 8, A07 provides the discussion of the channel functional test in CTS Table 4.3-2 as comp ared to the ITS trip actuating device operational test in ITS 3.3.6. A07 stat es, "CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST for Functional Unit c.1 (Manual)."The functional unit is missing part of its designation. Please co rrect the designator fo r the functional unit being referenced in A07.Attach File 1 Attach File 2 Issue Date 5/19/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:12 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=70 Licensee Response/NRC Response/NRC Question Closure Id 108NRC Question Number KAB043Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.6 revised DOC A07.pdf (11KB)Attachment 2 Attachment 2 revised CTS pages.pdf (39KB)Response Statement In response to KAB043, discussion of change (DOC) A07, on page 903 of Enclosure 2, Volume 8, will be revised.Specifically, the sentence, "CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST for Functional Unit c.1 (Manual)."

will be revised to read, "CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST for Functional Unit 3.c.1 (Containment Isolation, Cont ainment Ventilation Isolation, Manual)."During review for the RAI response, the following issue was identified.The Unit 1 CTS page is missing the first level of numerical designation.Specifically, CTS Table 4.3-2, Functional Unit Containment Isolation, should be preceded by a 3 to read, "3.Containment Isolation."The missing numerical designator is a typographical error that was introduced when the word files were converted from Word95 to the present version.The current plant operating technical specifications, as well as, the retrievable version of technical specifications from the NRC website, contain the correct designator.The same issue exists on page 367 of Enclosure 2, Volume 8.The CTS pages will be revised to reflect the

numerical designator.See Attachment 1 for the draft revised DOC A07.

See Attachment 2 for the revised CTS pages.Response Date/Time 6/6/2014 11:20 AMClosure Statement Question Closure Date Notification Scott BowmanKristy Bucholtz Michelle ConnerKhadijah HemphillAndrew Hon

Ray SchieleAdded By Scott Bowman Date Added 6/6/2014 10:18 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=108 DISCUSSION OF CHANGES ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 12 as is delineated in UFSAR Table 7.3.1-4. This change is designated as administrative because it does not result in technical changes to the CTS. A05 CTS 4.3.2.1.3 states, in part, that the ESF RESPONSE TIME of each ESFAS function shall be demonstrated to be within its limit at least once per 18 months.

The requirement specifies that each test shall include at least one logic train such that both logic trains are tested at least once per 36 months, and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-3 ITS SR

3.3.6.8 requires the verification of ESF RESPONSE TIMES every 18 months "on a STAGGERED TEST BASIS." The ITS definition of STAGGERED TEST BASIS is consistent with the CTS testing Frequency. This changes the CTS by utilizing the ITS definition of STAGGERED TEST BASIS for the Frequency of the ESF

RESPONSE TIME testing. This change is acceptable because the requirements for ESF RESPONSE TIME testing for the ESFAS channels remain unchanged. The ITS definition of STAGGERED TEST BASIS and its application in this requirement do not change the current testing Frequency requirements. This change is designated as administrative because it does not result in technical changes to the CTS. A06 ITS 3.3.6 ACTIONS contains a Note which states that separate Condition entry is allowed for each Function. The ACTIONS for CTS 3.3.2.1 (Unit 1), CTS 3.3.2 (Unit 2), and CTS 3.3.3.1 do not contain this Note. This changes the CTS by specifically allowing separate Condition entry for each Function in ITS Table 3.3.6-1. This change is acceptable because it clearly states the current requirement. The CTS considers each ESFAS and radiation monitoring instrument Function to be separate and independent. This change is designated as administrative because it does not result in a technical change to the CTS. A07 CTS Table 4.3-2 requires a CHANNEL FUNCTIONAL TEST for Functional Unit c.1 (Manual). ITS Table 3.3.6-1 requires a simila r test; ITS SR 3.3.6.6 (TADOT) to be performed for Function 1 (Manual Initiation) with the addition of a Note that states, "Verification of setpoint is not required." This changes the CTS by requiring a TADOT without setpoint verification instead of a CHANNEL FUNCTIONAL TEST. CTS 1.6 states that for an analog channel a CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

ITS 1.1 defines a TADOT as consisting of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. ITS further states that the TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. Because the TADOT includes adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy, which is not included in the CTS CHANNEL FUNCTIONAL TEST, ITS SR 3.3.3.6 includes the Note, "Verification ITS A01 ITS 3.3.2 TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE IS REQUIRED FUNCTIONAL UNIT CONTAINMENT ISOLATION a.Phase "A" Isolation1)Manual N.A. N.A. R 1, 2, 3, 4 2)From Safety Inject ion Automatic Actuation Logi c N.A. N.A. M(1) 1, 2, 3, 4 b.Phase "B" Iso lation1)Manual N.A. N.A. R 1, 2, 3, 4 2)Automatic Actuation Logi c N.A. N.A. M(1) 1, 2, 3, 4 3)Containment Pressure-- High-High S R Q 1, 2, 3 c.Containment Ventilation Isolation1)Manual N.A. N.A. R 1, 2, 3, 4 2)Automatic Isolation Logi c N.A. N.A. M(1) 1, 2, 3, 4 3)Containment Purge Air Exhaust Monitor Radio-ac tivity-High S R Q 1, 2, 3, 4 March 4, 1996 SEQUOYAH - UNIT 1 3/4 3-35 Amendment No. 47, 168, 220 Page 36 of 80 M02Table 3.3.2-1 3.a 3.a.(1) 3.a.(3) 3.b. 3.b.(1) 3.b.(2) 3.b.(3) See ITS 3.3.6 184 days 92 days on a STAGGERED TEST BASES SR 3.3.2.7 L15 L14In accordance with the Surveillance Frequency Control Program LA02SR 3.3.2.7 SR 3.3.2.2 SR 3.3.2.1 SR 3.3.2.8 SR 3.3.2.4 A04 A09 A09 A01ITS ITS 3.3.6 TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE IS REQUIRED FUNCTIONAL UNIT CONTAINMENT ISOLATION a.Phase "A" Isolation1)Manual N.A. N.A. R 1, 2, 3, 4 2)From Safety InjectionAutomatic Actuation Logic N.A. N.A.

M(1) 1, 2, 3, 4 b.Phase "B" Isolation1)Manual N.A. N.A. R 1, 2, 3, 4 2)Automatic Actuation Logic N.A. N.A.

M(1) 1, 2, 3, 4 3)Containment Pressure-- High-High S R Q 1, 2, 3 c.Containment Ventilation Isolation1)Manual N.A. N.A. R 1, 2, 3, 4 2)Automatic Isolation Logi c N.A. N.A. M(1) 1, 2, 3, 4 3)Containment Purge Air Exhaust Monitor Radio-ac tivity-High S R Q 1, 2, 3, 4 March 4, 1996 SEQUOYAH - UNIT 1 3/4 3-35 Amendment No. 47, 168, 220 Page 6 of 24 ACTUATION LOGIC TEST / COT / TADOT M01SR 3.3.6.1 SR 3.3.6.7 A02Containment Ventilation Isolation 92 days on a STAGGERED TEST BASIS L03Table 3.3.6-1 Function 1 Function 2 Function 3 M04Add proposed SR 3.3.6.3 with a Frequency of 92 days on a STAGGERED TEST BASIS for ITS Table 3.3.6-1 Function 2 Add proposed SR 3.3.6.5 with a of Frequency of every 18 months for ITS Table 3.3.6-1 Function 2 M04In accordance with the Surveillance Frequency Control Program LA01 See ITS 3.3.2 SR 3.3.6.6SR 3.3.6.2SR 3.3.6.4In accordance with the Surveillance Frequency Control Program LA01Add proposed SR 3.3.6.6 Note A07 Licensee Response/NRC Response/NRC Question Closure Id119NRC Question Number KAB043Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:27 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 71 NRC Question Number KAB044 Category TechnicalITS Section 3.3 ITS Number 3.3.6 DOC Number L-4JFD Number JFD Bases Number Page Number(s) 911 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested N NRC Question On page 911 of Enclosure 2, Volume 8, L 04 provides the discussion of converting applicable mode 6 for the Containm ent purge air process monitors in CTS Table 3.3-6 to ITS Table 3.3.6-1.CTS defines mode 6 as

refueling, which is fuel in the re actor vessel with the vessel head closure bolts less than fully tens ioned or with the head removed, reactivity condition less than or equal to 0.95, 0% rated thermal power excluding decay heat, and average coolant temperature less than or equal to 140 °F. TVA is requesting to replace the mode 6 applicability for the containment purge air process monitors with the ITS applicability during movement of recently irradiated fuel assemblies within containment.L04 states:

TVA has performed a Fuel Handling Accident Radiological Accident Analysis for SQN using the

alternate source term analysis methodology described in Regulatory Guide 1.183 obtaining acceptable results.The SQN fuel handling

analysis assumes, in part, that the accident occurs within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after a plant shut down, radioactive decay during the interval between shut down and movement of the first spent fuel

assembly is taken into account, and a single fuel Page 1of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=71 assembly is damaged. As a result of the analysis, it has been determined th at the handling of spent fuel assemblies can take place with the containment open and th e Auxiliary Building Gas Treatment System out of service (i.e., no credit for filtration of releases) when handling fuel that has not occupied part of a critical reactor core

within the previous 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. The NRC

approved use of this analysis for SQN under License Amendment 288/278 (Unit 1/Unit 2)

(ADAMS Accession No. ML033070057).

The cover letter for License Ame ndment 288/278 (ADAMS Accession No.

ML033030206) states, "The selective use of the AST and the total effective dose equivalent criteria may not be extended to other aspect s of the plant design or operation without prior NRC review and approval under 10 CFR 50.67."Please confirm that you are requesting the NRC st aff to extend the review performed in license amendment 288/278 to this requested change in Sequoyah's conversion. Note that request is a beyond scope change an d will be reviewed by the associated technical branch.Attach File 1 Attach File 2 Issue Date 5/19/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:14 AMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=71 Licensee Response/NRC Response/NRC Question Closure Id 99NRC Question Number KAB044 Select Application Licensee Response Attachment 1 Attachment 1.pdf (8KB)Attachment 2 Attachment 2 Radiological Consequences of FHA.pdf (228KB)Response Statement In response to KAB044, SQN request s that the NRC st aff extend their review performed in support of lice nse amendments 288 and 278 for SQN, Units 1 and 2, to proposed changes in the SQN ITS conversion.Specifically, SQN requests NRC review and approval for ITS Specifications that have revised the Mode of Applicability to in clude the term, "recently,"with the current AST analysis as the b asis for using the term, "recently."See Attachment 1 for additional information concerning SQN's current AST analysis for a fuel ha ndling accident (FHA). See Attachment 2 for SQN's current AST analysis for an FHA.Response Date/Time 6/5/2014 4:35 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 6/5/2014 3:32 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Background NRC approval for the use of an alternative source term (AST) for the SQN Design Basis Fuel Handling Accident (FHA) is contained in the Safety Evaluation (SE) dated October 28, 2003 (ML033030206). The FHA SE states: With this approval, the selected characteristics of the AST and TEDE criteria become the design basis for the DBA FHA within the containment and outside containment. The FHA SE also states:

Additionally, the NRC staff finds that the EAB, LPZ and control room doses will continue to comply with the applicable regulatory criteria without credit being taken for containment isolation if the irradiated fuel has been allowed to decay for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to being moved.

Therefore, at the time of the NRC review and approval of the AST submittal, NRC acknowledged that the AST FHA analysis did not credit containment isolation, with the above proviso on irradiated fuel. This analysis was revised in 2012 to support removal of the purge isolation function.

Current AST FHA Analysis Table 1 of the FHA SE summarizes the parameters that were deemed acceptable in the NRC-approved FHA analysis. From that table, only the containment purge isolation time is different in the current FHA analysis. Specifically, the containment purge isolation time used in the current FHA analysis was increased from 30 seconds to 5 minutes. However, as discussed below the control room and offsite doses are higher for shorter purge isolation times, i.e., the current FHA analysis is conservative with respect to the previously reviewed, NRC-approved FHA analysis. In addition, if the purge is isolated at the initiation of an FHA inside containment, the control room and offsite doses would be no higher than for an FHA outside containment.

Removing the purge isolation function If containment purge isolates at the initiation of an FHA inside containment, then the entire release is modeled as originating from the Auxiliary Building (AB). Therefore, the results of the FHA inside containment analysis are the same as the results of the FHA outside containment analysis. Because neither scenario credits filtration before being released, the only parameters of interest are the release rate and the meteorology (X/Q). The AB release has a higher control room X/Q than the containment release so it produces higher control room doses when the release rates are the same. However, the difference in release rates has the potential for the containment purge release to be more limiting because the amount of iodine released before control room isolation could be more. As outlined in RG 1.183, all of the activity is required to be released within 2 hrs. Consequently, after the control room isolates, the pathway with the higher X/Q becomes the more conservative pathway. Thus , it is more conservative to assume purge ventilation isolates and the activity exhausts through the AB vent. Because isolation was assumed to make the FHA inside containment more limiting and not to reduce offsite and control room doses, the purge ventilation isolation function is not required.

Westinghouse Non-Proprietary Class 3* Westinghouse Radiological Consequences of Fuel Handling Accidents for the Sequoyah Nuclear Plant Units 1 and 2 Addressing:

1) Implementation of Alternate Source Term 2) Permitting Open Equipment Hatch During Fuel Movement 3) No credit for Operation of the Auxiliary Building Gas Treatment System Document ID: LTR-CRA-02-219, Revision 1 Prepared for Tennessee Valley Authority by Westinghouse Electric Company January 30, 2012@2012 Westinghouse Electric Company LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 1.0 USE OF ALTERNATE SOURCE TERM METHODOLOGY

1.1 Introduction

Alternate source term (AST) methodology is described in Regulatory Guide 1.183 (Reference

1) and it is being implemented at Sequoyah Units 1 and 2 in a limited-scope application that will only affect the determination of design basis accident doses for the Fuel Handling Accident (occurring either outside containment or inside containment).

With the use of the AST methodology, it can be demonstrated that handling of spent fuel assemblies and performing core alterations can take place with the containment equipment hatch open and with the Auxiliary Building Gas Treatment System out of service (no credit for filtration of releases).

1 .2 Dose Models and Timing Doses are determined at the exclusion area boundary (EAB) and at the low population zone boundary (LPZ) for the two-hour interval over which releases are assumed to take place and in the control room for an extended period of time after termination of releases in order to address the continued presence of activity in the control room atmosphere.

The accident doses were calculated using the dose model consistent with the use of the alternate source term methodology (Regulatory Guide 1 .183) and are reported as Total Effective Dose Equivalent (TEDE).The TEDE dose is the sum of the Committed Effective Dose Equivalent (CEDE) and the Effective Dose Equivalent (EDE) which are calculated using the following equations:

DOEDE = (A)(XIQ)(BR)(DCFCEDE)

DEDE = (A)(XIQ)(DCFEDE) where: A = Activity of the nuclide released (Ci)X/Q =atmospheric dispersion factor (sec/in 3 BR =breathing rate (m 3/sec)DCFCEDE = CEDE dose conversion factor (rem/Ci inhaled)DCFEDE = EDE dose conversion factor (rem-in3 /Ci-s)Nuclide data is provided in Table 1. The decay constants for the iodines and noble gases were provided by TVA. The dose conversion factors for the CEDE doses are taken from Table 2.1 of EPA Federal Guidance Report No. 11 (Reference 2). The dose conversion factors for the EDE doses are from Table 111.1 of EPA Federal Guidance Report No. 12 (Reference 3).The tritium decay constant is derived from the half-life reported in ICRP Publication 38 (Reference 4).2 LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 2.0 FUEL HANDLING ACCIDENT ANALYSIS A fuel assembly is assumed to be dropped and damaged during refueling.

Activity released from the damaged assembly is released to the outside atmosphere through either the containment purge system or the fuel-handling building ventilation system to the plant vent.2.1 Input Parameters and Assumptions The analysis of the radiological consequences following a fuel handling accident (FHA) uses the methodology outlined in Regulatory Guide 1. 183 (Reference 1). The major assumptions and parameters used in the analysis are itemized in Table 2.It is assumed that all of the fuel rods in the equivalent of one fuel assembly are damaged to the extent that all the gap activity in the rods is released.

Also, the assembly inventory is based on the assumption that the subject fuel assembly has been operated at 1.7 times core average power. The core fission product source term bounds operation with or without the presence of TPBARs (Tritium Producing Burnable Absorber Rods) in the reactor core.The damaged fuel assembly is assumed to be one with 24 TPBARs which are also assumed to be damaged. Although the release of tritium to the water pool is expected to take place relatively slowly, it is conservatively assumed that all of the tritium is released from the TPBARs immediately.

Since tritium in the gaseous form is not a significant dose contributor (minor beta radiation emitter with no retention in the body), it is assumed that all tritium is in the form of water -either as T 2 0 or HTO. In the water vapor form the tritium is readily absorbed into the body tissues where there can be a significant dose contribution.

The decay time prior to the accident is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.The analysis assumes that the iodine released from the fuel is 99.85% elemental and 0. 15%organic. This is consistent with Regulatory Guide 1. 183. The water pool provides retention of a large portion of the elemental iodine but there is no retention of the organic iodine credited.From Regulatory Guide 1. 183, a decontamination factor (DF) of 200 specified is applied to the overall iodine inventory released to the pool. No retention in the water pool is assumed for noble gases (DF = 1.0).While the tritium is assumed to be chemically combined with oxygen to form tritiated water and would thus be readily retained in the water pool, no credit is taken for retention in the pool.For the FHA occurring outside of containment, all of the activity released from the damaged fuel and not retained in the water pool is assumed to be released within two hours. No credit is taken for filtration of iodine in the release path. This allows the Auxiliary Building Gas Treatment System to be out of service during spent fuel handling operations.

For the FHA occurring inside containment it is assumed that only a fraction of the containment volume is included in the mixing volume and that the purge line is isolated within 300 seconds.No credit is taken for filtration of the purge flow. After isolation of the containment purge line, it 3 LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 is assumed that all of the activity remaining in the containment is released within two hours of the fuel damage occurrence.

2.2 Acceptance Criteria The offsite dose limit is defined in Regulatory Guide 1.183 to be 6.3 rem TEDE and, from 1 0CFR50.67, the dose limit for the control room is 5.0 rem TEDE.2.3 Results FHA Occurring in the FHA Occurring inside__________

Auxiliary Building Primary Containment EAB 4.5 rem TEDE 4.5 rem TEDE LPZ 0.8 rem TEDE 0.8 rem TEDE jControl room j 4.1 rem TEDE 3.9 rem TEDE The doses are all within the acceptance criteria.

3.0 REFERENCES

1 .Regulatory Guide 1. 183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000 2. EPA Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," E PA-520/1 020, September 1988 3. EPA Federal Guidance Report No. 12, "External Exposure to Radionuclides in Air, Water, and Soil," EPA 402-R-93-081, September 1993 4. ICRP Publication 38, "Radionuclide Transformations, Energy and Intensity of Emissions," 1983 LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 Table 1: Nuclidie Data Committed Effective Effective Dose Dose Equivalent Equivalent DCF from Decay DCF from EPA EPA Federal Nuclide Constant Federal Guidance Guidance Report (hr-) Report No. 11 No.12___________

_____________ (rem/Ci inhaled) (rem-m 3/Ci-s)1-131 3.5833E-3 3.29E4 6.734E-2 1-132 3.0401 E-1 3.81 E2 4.144E-1 1-133 3.3320E-2 5.85E3 1.088E-1 1-135 1.0486E-1 1.23E3 2.953E-1 Kr-85 7.3692E-6 N/A 4.403E-4 Xe-131m 2.4269E-3 N/A 1.439E-3 Xe-133m 1.2836E-2 N/A 5.069E-3 Xe-133 5.4594E-3 N/A 5.772E-3 Xe-135 7.5755E-2 N/A 4.403E-2 H-3 (tritium) 6.407E-6 64.01 1 .225E-6 LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 Table 2: Fuel Handling Accident Assumptions Delay after shutdown before fuel movement 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Average fuel assembly activity at shutdown (no decay)'1-131 4.90E5 1-132 7.18E5 1-133 1.01 E6 1-135 9.65E5 Kr-85 5.35E3 Xe- 131 m 5.43E3 Xe-i 33m 3.19E4 Xe-133 9.92 E5 Xe-135 3.33 E5 Te-1 31 m 9.62E4 Te-1 32 7.05E5 Radial peaking factor 1.7 Fuel rod gap fraction 2 1-131 0.08 Kr-85 0.10 Other iodines and noble gases 0.05 Fuel damaged One assembly with 24 TPBARs Iodine species split Elemental 99.85%Organic 0.15%Tritium release from 24 damaged TPBARs 84,000 Ci Pool scrubbing factor Iodine 200 Noble gases 1 Tritium 1 Breathing rate 3.5E-4 M 3 /sec 1Only the iodines and noble gases having a significant presence after 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> are included in the list. The Te-1 31 m and Te-1 32 are included since they produce 1-131 and 1-132 respectively as decay products.2 These gap fractions are dependent on limiting the high burnup fuel rods (>54,000 MWD/Mtu) to a maximum linear heat generation rate of 56.3 kw/ft, peak rod average power.6 LTR-CRA-02-219, Revision 1 Westinghouse Non-Proprietary Class 3 Table 2 (continued)

Atmospheric dispersion factor EAB 8.59E-4 sec/rn 3 LPZ outer boundary 1 .39E-4 sec/rn 3 FHA Outside Containment Release path filter efficiency for iodines No credit assumed Isolation of release path None Duration of releases 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> FHA Inside Containment Mixing volume 325,500 ft 3 Purge flow rate 16,000 cfm Release path filter efficiency for iodines None Isolation of purge release path 300 seconds Duration of releases via the equipment hatch 300 sec -2 hr Control Room Dose Analysis Parameters Vol ume 2.6E5 cubic feet Normal operation inflow (unfiltered) 3200 cfm Air intake high radiation setpoint to actuate HVAC emergency mode 400 cpm Time to switch to emergency mode after signal 5 min Emergency mode filtered intake flow 1000 cfm Emergency mode filtered recirculation flow 2600 cfm Filter efficiency for iodine 95%Unfiltered inleakage 51 cfm Atmospheric dispersion factor (XIQ)FHA outside containment (0 -2 hr) 1 .80E-3 sec/in 3 FHA inside containment 0 -300 sec 5.63 E-4 sec/in 3 300 sec -2 hr 1 .80E-3 sec/in 3 Occupancy factor 0 -24 hours 1.0 24 -96 hours 0.6 96 -720 hours 0.4 Breathing rate 3.5E-4 M 3/sec Licensee Response/NRC Response/NRC Question Closure Id 273NRC Question Number KAB044 Select Application NRC ResponseAttachment 1 Attachment 2 Response Statement Regarding TVA's proposed changes related to the adoption of TSTFs-51, -286 and -471, in a 8/12/14 meeting between the NRC and TVA at the NRC HQ followed by 8/19/14 phone call between the NRC and TVA, the NRC was informed of the TVA's decision for rescinding all changes associated with the subject TSTFs as currently specified in its TS conversion amendment.Please submit the revised pages for the NRC's review.Response Date/Time 8/20/2014 6:00 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerRobert ElliottRavinder GroverKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger Scott Added By Ravinder Grover Date Added 8/20/2014 2:20 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id373NRC Question Number KAB044Select Application Licensee Response Response Statement Per discussion, on October 7, 2014, between SQN and NRC staff, SQN proposes that changes incorporated in NUREG-1431, Revision 4, associated with TSTFs-51, -286, and -471 be reviewed as submitted in the SQN ITS conversion submittal.SQN understands, that during staff review, there may be additional requests for information related to the changes made to NUREG-1431, Revision 4.Response Date/Time 10/16/2014 2:15 PMClosure Statement Question Closure Date Notification Mark BlumbergScott BowmanKristy BucholtzMichelle ConnerRavinder GroverKhadijah HemphillAndrew HonLynn Mynatt Ray SchieleAdded By Scott Bowman Date Added 10/16/2014 1:12 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id376NRC Question Number KAB044Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement The NRC staff will perform the review as requested. This RAI is being closed at this time and other RAIs, as necessary, will be entered into the database as the review progresses. AST RAIs have been entered as KAB-066 through KAB-071.Question Closure Date 10/17/2014Notification Mark BlumbergScott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 10/17/2014 7:11 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 72 NRC Question Number KAB045 Category TechnicalITS Section 3.3 ITS Number 3.3.6 DOC Number L-6JFD Number JFD Bases Number Page Number(s) 912 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested N NRC Question On page 912 of Enclosure 2, Volume 8, L06 provides the discussion of the CTS requirement to demonstrate operability within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to th e start of movement of irradiated fuel within cont ainment by verifying that containment ventilation isol ation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring

instrumentation channels.This CTS requirement requires performance of the surveillance requirements (SRs) that demonstrate the operability within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of moving irradiated fuel.The ITS requires the SRs to be met prior to movement of recently irradiated fuel.

In ITS there is a difference between "met"and "performed."A Surveillance is "met" only when the acceptance criteria are satisfied. "Performanc e" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.ITS SR 3.3.6.2 ALT has a frequency of 92 days on a st aggered test basis, ITS SR 3.3.6.4 COT has a frequenc y of 92 days, and ITS SR 3.3.6.6 TADOT has a frequency of 18 months.ITS SR Page 1of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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3.3.6.2 and 3.3.6.6 have a longer frequency and may be still "met" within a 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of moving fuel therefore, ITS will not require them to be "performed

."Please provide a technical evaluation that explains the safety basis for deleting the requirement to "perform"the CTS SRs that demonstrate the operability of the containment ventilation isolation system within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of moving irradiated fuel. In addition, add the manual initiation ITS SR 3.3.6.6 to the discussion in L06 sin ce it is applicable.Attach File 1 Attach File 2 Issue Date 5/19/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/19/2014 8:17 AMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id220NRC Question Number KAB045 Select Application Licensee Response Attachment 1 Attachment 1 KAB-045.pdf (109KB)Attachment 2 Response Statement In response to KAB045, discussion of change (DOC) L06, on page 912 of Enclosure 2, Volume 8, will be deleted.In addition, changes to CTS 4.9.9 associated with DOC L06 will be deleted and the corresponding Surveillance Requirement Frequencies for ITS SRs 3.3.6.4 and 3.3.6.6, on pages 918, 919, 927, and 928, will be revised to include the conditional performance of CTS 4.9.9, "within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of."During review for the RAI response, th e following issues were identified.1.The CTS 4.9.9 reference to, "during movement of irradiated fuel within containment,"should state, "during movement of recently irradiated fuel within containment."The addition of the term "recently"is justified in DOC L04 which discusses the change for the CTS 3.9.9 Applicability from, "During movement of irradiated fuel within containment,"to, "During movement of recently irradiated fuel within containment."The CTS markups for CTS 4.9.9, on pages 888 and 900, will be revised to add "recently"and include a DOC L04 indicator.2.ITS Table 3.3.6-1, Func tion 2 (Automatic Actuat ion Logic and Actuation Relays) requires Surveillance Requirem ents to be performed in Modes 1, 2, 3, 4, (a), where Footnote (a) states, "D uring movement of recently irradiated fuel assemblies within containment."CTS Table 4.3-2, Function 3.c.2 (Contai nment Ventilation Isolati on, Automatic Isolation Logic) requires Surveillan ce Requirements to be performed in Modes 1, 2, 3, 4.ITS Function 2 corresponds to CTS Function 3.c.2.ITS Table 3.3.6-1, Function 2 shoul d require Surveillance Requirements to be performed in Modes 1, 2, 3, 4.The ISTS markups, on pages 921 and 930, will be revised to delete Mode (a) associated with IT S Table 3.3.6-1, Function 2, and an associated JFD 2 indicator will be added.3.The CTS markups (left hand margin) should indicate that CTS 4.9.9 corresponds to ITS SRs 3.3.6.4 and 3.3.6.6.The CTS markups, on pages 888 and 900, will be revised to re place ITS SR 3.3.6.

2 with 3.3.6.6.

See Attachment 1 for the draft revised CTS and IS TS markups and deletion of DOC L06.Page 1of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=220 Response Date/Time 8/4/2014 6:55 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 8/4/2014 5:51 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=220 A01ITS ITS 3.3.6 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation isolation system shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel within the containment.

ACTION:

With the Containment Ventilation isolation system inoperable, close each of the Ventilation penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during movement of irradiated fuel within containment by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

April 11, 2005 SEQUOYAH - UNIT 1 3/4 9-9 Amendment No. 260, 301 Page 12 of 24 ACTION B 92 days for containment radiation monitors 18 months for manual initiation L05 L05In accordance with the Surveillance Frequency Control Program LA01 L06 See ITS 3.9.4 INSTRUMENTATIONinstrumentation instrumentation instrumentation A02 A02 A02 A02LCO 3.3.6 Applicabilit y SR 3.3.6.2, SR 3.3.6.4 M06recently L04 A01ITS ITS 3.3.6 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel within the containment.

ACTION:

With the Containment Ventilation Isolation System inoperable, close each of the Ventilation penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation Isolation System shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during movement of irradiated fuel within containment by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

April 11, 2005 SEQUOYAH - UNIT 2 3/4 9-11 Amendment No. 251, 290

ACTION B LCO 3.3.6 Applicabilit y SR 3.3.6.2, SR 3.3.6.4 See ITS 3.9.4 92 days for containment radiation monitors 18 months for manual initiation INSTRUMENTATIONinstrumentationinstrumentationinstrumentation A02 A02 A02 A02 L05 L05 L06In accordance with the Surveillance Frequency Control Program LA01 M06Page 24 of 24recently L04 DISCUSSION OF CHANGES ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 12 of 12 L05 (Category 7 - Relaxation of Surveillance Frequency) CTS 4.9.9 includes a Surveillance Frequency of "once per 7 days" during conditions specified in the Applicability for performing Surveillances of the Containment Ventilation Isolation System on the manual initiation channels and the high radiation monitoring instrumentation channels. The ITS SR 3.3.6.4 requires the performance of a COT on the Containment Purge Air Radiation Monitoring Instrumentation, every 92 days. ITS SR 3.3.6.6 requires the performance of a TADOT on the manual initiation channels every 18 months. This changes the CTS by changing the Surveillance Frequency from 7 days to 92 days for the Containment Purge Air Radiation monitoring channels and 18 months for the manual initiation channels.

(See DOC LA01 for a discussion on moving the Surveillance Frequencies to the Surveillance Frequency Control Program.)

The purpose of CTS 4.9.9 is to verify t he equipment required to meet the LCO is OPERABLE. This change is acceptable because the new Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. Containment ventilation isolation instrumentation testing is still required, but at a Frequency consistent with the testing Frequency for containment isolation instrumentation required in CTS Table 4.3-2 and CTS Table 4.3-3. This Frequency provides an appropriate degree of assurance that the instruments are OPERABLE. This change is designated as less restrictive because Surveillances will be performed less frequently under the ITS than under the CTS.

L06 (Category 7 - Relaxation of Surveillance Frequency) CTS 4.9.9 states, in part, that the Containment Ventilation isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of movement of irradiated fuel within containment. ITS SR 3.3.6.2 and ITS SR 3.3.6.4 do not include the Frequency of within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of movement of irradiated fuel within containment. ITS SR 3.0.1 states "SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR." Therefore, the ITS requires the Surveillance be met prior to initiation of movement of recently irradiated fuel. (See DOC L04 for discussion on changing the Applicability from during movement of irradiated fuel to during movement of recently irradiated fuel.) This changes the CTS by eliminating the stipulation that the Surveillances be met within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to entering the conditions specified in the Applicability.

The purpose of CTS 4.9.9 is to verify that the Containment Ventilation Isolation System is OPERABLE. This change is acceptable because the new Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. The periodic Surveillance Frequency for verifying that Containment Ventilation isolation occurs is acceptable during the conditions specified in the Applicability, and is also acceptable during the period prior to entering the conditions specified in the Applicability. This change is designated as less restrictive because Surveillance will be performed less frequently under the ITS than under the CTS.

Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-5 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY


REVIEWER'S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is applicable to the master rela ys processed through the Solid State Protection Sys tem. -----------------------------------------------------------------------------------------------

[SR 3.3.6.

5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master

relays of the ESFAS Instrumentation. ---------------------------------------------------------------------

Perform MASTER RELAY TEST.

[ 92 days on a STAGGERED TEST BASIS OR In accordance

with the Surveillance Frequency Control Program ] ]

SR 3.3.6.

6 Perform COT.

[ 92 days OR In accordance with the Surveillance

Frequency

Control Program

] 4 3 DOC M04 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a, 4.9.9 6 4 4 3 5 3 5 4 4 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-6 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.

7 Perform SLAVE RELAY TEST.

[ [92] days OR In accordance with the Surveillance

Frequency

Control Program

] SR 3.3.6.

8 -------------------------------NOTE------------------------------

Verification of setpoint is not required. ---------------------------------------------------------------------

Perform TADOT.

[ [18] months OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.6.

9 Perform CHANNEL CALIBRATION.

[ [18] months OR In accordance with the Surveillance

Frequency

Control Program

] 6 7 5 DOC M04 Table 4.3-2 Function 3.c.1, 4.9.9 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a 5 4 4 5 4 4 5 4 4 DOC A07 INSERT 1 2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-7 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1Table 3.3.6-1 (page 1 of 1) Containment Purge and Exhaust Isolation Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

TRIP SETPOINT

1. Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.

8 NA

2. Automatic Actuation Logic and Actuation Relays 1,2,3,4, (a) 2 trains SR 3.3.6.2 SR 3.3.6.3 [SR 3.3.6.

4] [SR 3.3.6.

5] SR 3.3.6.

7 NA 3. [ Containment Radiation

a. Gaseous 1,2,3,4 , (a) [1] SR 3.3.6.1 SR 3.3.6.

6 SR 3.3.6.

9 [2 x background]

b. Particulate 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

c. Iodine 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

d. Area Radiation 1,2,3,4, (a)

[1] S R 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

]

4. Containment Isolation

- Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and requirements.

(a) During movement of

[recently] irradiated fuel assemblies within containment.

6 4 7 Purge Air Monitor 8.5 x 10-3 µCi/ccVentilation 2 3 5 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.1 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.2 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.3, and Table 3.3-6 Instrument 2.a DOC M02 1 5 5 3 5 3Safety Injection 1 2SR 3.3.6.8INSERT 2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-5 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY


REVIEWER'S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is applicable to the master rela ys processed through the Solid State Protection Sys tem. -----------------------------------------------------------------------------------------------

[SR 3.3.6.

5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master

relays of the ESFAS Instrumentation. ---------------------------------------------------------------------

Perform MASTER RELAY TEST.

[ 92 days on a STAGGERED TEST BASIS OR In accordance

with the Surveillance Frequency Control Program ] ]

SR 3.3.6.

6 Perform COT.

[ 92 days OR In accordance with the Surveillance

Frequency

Control Program

] 4 3 DOC M04 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a, 4.9.9 6 4 4 3 5 3 5 4 4 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-6 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.

7 Perform SLAVE RELAY TEST.

[ [92] days OR In accordance with the Surveillance

Frequency

Control Program

] SR 3.3.6.

8 -------------------------------NOTE------------------------------

Verification of setpoint is not required. ---------------------------------------------------------------------

Perform TADOT.

[ [18] months OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.6.

9 Perform CHANNEL CALIBRATION.

[ [18] months OR In accordance with the Surveillance

Frequency

Control Program

] 6 7 5 DOC M04 Table 4.3-2 Function 3.c.1, 4.9.9 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a 5 4 4 5 4 4 5 4 4 DOC A07 INSERT 1 2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-7 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1Table 3.3.6-1 (page 1 of 1) Containment Purge and Exhaust Isolation Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

TRIP SETPOINT

1. Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.

8 NA

2. Automatic Actuation Logic and Actuation Relays 1,2,3,4, (a) 2 trains SR 3.3.6.2 SR 3.3.6.3 [SR 3.3.6.

4] [SR 3.3.6.

5] SR 3.3.6.

7 NA 3. [ Containment Radiation

a. Gaseous 1,2,3,4 , (a) [1] SR 3.3.6.1 SR 3.3.6.

6 SR 3.3.6.

9 [2 x background]

b. Particulate 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

c. Iodine 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

d. Area Radiation 1,2,3,4, (a)

[1] S R 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

]

4. Containment Isolation

- Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and requirements.

(a) During movement of

[recently] irradiated fuel assemblies within containment.

6 4 7 Purge Air Monitor 8.5 x 10-3 µCi/ccVentilation 2 3 5 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.1 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.2 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.3, and Table 3.3-6 Instrument 2.a DOC M02 1 5 5 3 5 3Safety Injection 1 2SR 3.3.6.8INSERT 2 Licensee Response/NRC Response/NRC Question Closure Id243 NRC Question Number KAB045Select Application NRC Response Attachment 1 Attachment 2 Response Statement Sequoyah CTS requires the cont ainment ventilation isolation system shall be operable during movement of

irradiated fuel within the containment. CTS requires verification that the contai nment ventilation isolation occurs on manual initiation and on a high radiation test signal from each of th e containment radiation monitoring instrumentation channels within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

prior to the start of and at least once per 7 days during the movement of irradiated fuel within containment.

Please explain if the high ra diation test signal from each containment purge air radiation monitor can isolate the containment ventilation system without the automatic actuation logic an d actuation relays being operable (during movement of irradiated fuel within contai nment). If the isolation of the containment ventilation system cannot occur without operability of the automatic actuation logic and actuation relays then please return footno te (a) to function 2 in TS Table 3.3.6-1.Response Date/Time 8/6/2014 6:00 PMClosure Statement Question Closure Date Notification Scott BowmanMichelle ConnerMatthew Hamm Khadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger Scott Added By Kristy Bucholtz Date Added 8/6/2014 8:41 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 394NRC Question Number KAB045Select Application Licensee ResponseAttachment 1 RAI KAB045 revised Attachment 1.pdf (2MB)Attachment 2 Response Statement This response supplements the response to RAI KAB045 based on NRC response d ated August 6, 2014.

The containment purge air radiation monitors will isolate the containment ventilation isolation system without the automatic actuati on logic being OPERABLE; however, the master and slave relays are required to be OPERABLE for the isolation to occur.The high radiation signal from the containment purge air radiation

monitors goes directly to a safeguards driver card bypassing the automatic actuation logic.The

safeguards driver card w ill actuate the master relay which will, in turn, pick up the slave relays, initiating the containment ventilation isolation.Because the

automatic actuation logic is bypassed, there is no need for the logic to be OPERABLE during the movement of recently irradiated fuel within containment.Therefore, ITS Table 3.3.6-1, on pages 921 and 930 of Enclosure 2, Volume 8, will be revised to include a new Insert 3 that addresses the separation of ITS 3.3.6, Function 2 into two sub-functions.Specifically, ITS Table 3.3.6-1, Function 2 (Automatic Actuation Logic and Actuation Relays) will be divided into two sub

-functions (a. Logic and b. Relays) to align with the required applicable MODES.ITS 3.3.6, Function 2.a (Automatic Actuation Logic) will be required OPERAB LE in MODES 1, 2, 3, and 4.For ITS Function 2.a, SR 3.3.6.2 (ACTUATION LOGIC TEST) will be required in MODES 1, 2, 3, and 4.ITS 3.3.6, Function 2.b (Automatic Actuation Relays) will be required OPERABLE in MODES 1, 2, 3, 4, and (a), where Page 1of 3 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Footnote (a) is during the movement of recently irradiated fuel assemblies within containment.For ITS 3.3.6, Function 2.b, SRs 3.

3.6.3 (MASTER RELAY TEST) and 3.3.6.5 (SLAVE RELAY TE ST) will be required in MODES 1, 2, 3, 4, and (a).Th is revision will ensure the master and slave relays are verified to be OPERABLE

during the movement of recently irradiated fuel

assemblies within containment.Additionally, Justification for Deviation (JFD) 7 will be added to the

Justification for Deviations Section on page 932 to justify the change to ISTS.

Additional changes associated with the discussion above include:1.CTS 4.9.9 will be added as a cross reference for Insert 3.(Pages 921 and 930)2.JFD 7 indicators will be added to the associated changes.(Pages 921, 922, 930, and 931)3.The ITS 3.3.6 Bases Applicability Section will be revised to indicate that ITS Table 3.3.6-1 specifies the re quired Mode of Applicability for Manual Initia tion, Automatic Actuation Logic and Actuation Relays, Safety Injection, and Containment Radiation Functions.(Pages 937 and 952)

Additionally, during review fo r KAB045, it was identified that CTS 4.9.9 requires verifying that each of the

containment radiation monitoring instrumentation

channels is OPERABLE during movement of irradiated fuel within containment.As originally proposed, ITS

Table 3.3.6-1 requires only one Containment Purge Air

Radiation Monitor to be OPERABLE during the movement

of recently irradiated fuel assemblies within

containment. Therefore, ITS Table 3.3.6-1, Insert 2 on pages 922 and 931, will be revised to require two Containment Purge Air Radiation Monitors to be

OPERABLE during the movement of recently irradiated

fuel assemblies within co ntainment. The ITS 3.3.6 Bases, LCO Section for Function 3 (Containment Page 2of 3 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Radiation) on pages 937 and 95 2, will also be revised to reflect that ITS Table 3.3.6-1 specifies the number of required channels.

Additional changes associated with the number of required Radiation Monitors include:1.The ITS 3.3.6 Bases APPLICABI LITY discussion on pages 937 and 952 will be revised to refl ect that the number of required channels is annotated on Table 3.3.6-1.2.The pointer to ITS 3.3.6 Bases Insert 2 on pages 937 and 952 will be removed and ITS Bases 3.3.6 Insert 2 on pages 938 and 953 will be deleted.3.The ITS 3.3.6 Bases Actions Section discussions associated with Conditions A.1 and B.1, on pages 940 and 955, will be revised to address the require d radiation monitoring channel.

See Attachment 1 for the final version of changes to be made to ITS 3.3.6 in response to KAB045.Response Date/Time 12/12/2014 9:50 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleAdded By Scott Bowman Date Added 12/12/2014 8:49 AMDate Modified Modified By Page 3of 3 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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A01ITS ITS 3.3.6 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation isolation system shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel within the containment.

ACTION:

With the Containment Ventilation isolation system inoperable, close each of the Ventilation penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during movement of irradiated fuel within containment by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

April 11, 2005 SEQUOYAH - UNIT 1 3/4 9-9 Amendment No. 260, 301 Page 12 of 24 ACTION B 92 days for containment radiation monitors 18 months for manual initiation L05 L05In accordance with the Surveillance Frequency Control Program LA01 L06 See ITS 3.9.4 INSTRUMENTATIONinstrumentation instrumentation instrumentation A02 A02 A02 A02LCO 3.3.6 Applicabilit y SR 3.3.6.2, SR 3.3.6.4 M06recently L04 A01ITS ITS 3.3.6 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel within the containment.

ACTION:

With the Containment Ventilation Isolation System inoperable, close each of the Ventilation penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation Isolation System shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during movement of irradiated fuel within containment by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

April 11, 2005 SEQUOYAH - UNIT 2 3/4 9-11 Amendment No. 251, 290

ACTION B LCO 3.3.6 Applicabilit y SR 3.3.6.2, SR 3.3.6.4 See ITS 3.9.4 92 days for containment radiation monitors 18 months for manual initiation INSTRUMENTATIONinstrumentationinstrumentationinstrumentation A02 A02 A02 A02 L05 L05 L06In accordance with the Surveillance Frequency Control Program LA01 M06Page 24 of 24recently L04 DISCUSSION OF CHANGES ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 12 of 12 L05 (Category 7 - Relaxation of Surveillance Frequency) CTS 4.9.9 includes a Surveillance Frequency of "once per 7 days" during conditions specified in the Applicability for performing Surveillances of the Containment Ventilation Isolation System on the manual initiation channels and the high radiation monitoring instrumentation channels. The ITS SR 3.3.6.4 requires the performance of a COT on the Containment Purge Air Radiation Monitoring Instrumentation, every 92 days. ITS SR 3.3.6.6 requires the performance of a TADOT on the manual initiation channels every 18 months. This changes the CTS by changing the Surveillance Frequency from 7 days to 92 days for the Containment Purge Air Radiation monitoring channels and 18 months for the manual initiation channels.

(See DOC LA01 for a discussion on moving the Surveillance Frequencies to the Surveillance Frequency Control Program.)

The purpose of CTS 4.9.9 is to verify t he equipment required to meet the LCO is OPERABLE. This change is acceptable because the new Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. Containment ventilation isolation instrumentation testing is still required, but at a Frequency consistent with the testing Frequency for containment isolation instrumentation required in CTS Table 4.3-2 and CTS Table 4.3-3. This Frequency provides an appropriate degree of assurance that the instruments are OPERABLE. This change is designated as less restrictive because Surveillances will be performed less frequently under the ITS than under the CTS.

L06 (Category 7 - Relaxation of Surveillance Frequency) CTS 4.9.9 states, in part, that the Containment Ventilation isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of movement of irradiated fuel within containment. ITS SR 3.3.6.2 and ITS SR 3.3.6.4 do not include the Frequency of within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of movement of irradiated fuel within containment. ITS SR 3.0.1 states "SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR." Therefore, the ITS requires the Surveillance be met prior to initiation of movement of recently irradiated fuel. (See DOC L04 for discussion on changing the Applicability from during movement of irradiated fuel to during movement of recently irradiated fuel.) This changes the CTS by eliminating the stipulation that the Surveillances be met within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to entering the conditions specified in the Applicability.

The purpose of CTS 4.9.9 is to verify that the Containment Ventilation Isolation System is OPERABLE. This change is acceptable because the new Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. The periodic Surveillance Frequency for verifying that Containment Ventilation isolation occurs is acceptable during the conditions specified in the Applicability, and is also acceptable during the period prior to entering the conditions specified in the Applicability. This change is designated as less restrictive because Surveillance will be performed less frequently under the ITS than under the CTS.

Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-5 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY


REVIEWER'S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is applicable to the master rela ys processed through the Solid State Protection Sys tem. -----------------------------------------------------------------------------------------------

[SR 3.3.6.

5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master

relays of the ESFAS Instrumentation. ---------------------------------------------------------------------

Perform MASTER RELAY TEST.

[ 92 days on a STAGGERED TEST BASIS OR In accordance

with the Surveillance Frequency Control Program ] ]

SR 3.3.6.

6 Perform COT.

[ 92 days OR In accordance with the Surveillance

Frequency

Control Program

] 4 3 DOC M04 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a, 4.9.9 6 4 4 3 5 3 5 4 4 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-6 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.

7 Perform SLAVE RELAY TEST.

[ [92] days OR In accordance with the Surveillance

Frequency

Control Program

] SR 3.3.6.

8 -------------------------------NOTE------------------------------

Verification of setpoint is not required. ---------------------------------------------------------------------

Perform TADOT.

[ [18] months OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.6.

9 Perform CHANNEL CALIBRATION.

[ [18] months OR In accordance with the Surveillance

Frequency

Control Program

] 6 7 5 DOC M04 Table 4.3-2 Function 3.c.1, 4.9.9 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a 5 4 4 5 4 4 5 4 4 DOC A07 INSERT 1 2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-7 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 1 Amendment XXX CTS 1Table 3.3.6-1 (page 1 of 1) Containment Purge and Exhaust Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT 1.Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.

8 NA2.Automatic Actuation Logic andActuation Relays 1,2,3,4, (a) 2 trains SR 3.3.6.2 SR 3.3.6.3 [SR 3.3.6.

4] [SR 3.3.6.

5] SR 3.3.6.

7 NA 3.[ Containment Radiationa.Gaseous 1,2,3,4 , (a) [1] SR 3.3.6.1 SR 3.3.6.

6 SR 3.3.6.

9 [2 x background]

b.Particulate 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

c.Iodine 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

d.Area Radiation 1,2,3,4, (a)

[1] S R 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

] 4.Containment Isolation

-Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and requirements. (a) During movement of

[recently] irradiated fuel assemblies within containment.

6 4 7 Purge Air Monitor 8.5 x 10-3 µCi/ccVentilation 2 3 5 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.1 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.2 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.3, and Table 3.3-6 Instrument 2.a DOC M02 1 5 5 3 5 3Safety Injection 1 2SR 3.3.6.8INSERT 2 ITS 3.3.6 Insert Page 3.3.6-7 INSERT 2 FUNCTION APPLICABLE MODES OR OTHE R SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT (a) 1 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 8.5 x 10-3 µCi/cc 3FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT (a)

SR 3.3.6. SR 3.3.6.

INSERT

Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-5 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY


REVIEWER'S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is applicable to the master rela ys processed through the Solid State Protection Sys tem. -----------------------------------------------------------------------------------------------

[SR 3.3.6.

5 -------------------------------NOTE------------------------------ This Surveillance is only applicable to the master relays of the ESFAS Instrumentation.



Perform MASTER RELAY TEST.

[ 92 days on a STAGGERED TEST BASIS OR In accordance

with the Surveillance Frequency Control Program ] ] SR 3.3.6.

6 Perform COT.

[ 92 days OR In accordance

with the Surveillance

Frequency

Control Program

] 4 3 DOC M04 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a, 4.9.9 6 4 4 3 5 3 5 4 4 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-6 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.6.

7 Perform SLAVE RELAY TEST.

[ [92] days OR In accordance with the Surveillance

Frequency

Control Program

] SR 3.3.6.

8 -------------------------------NOTE------------------------------ Verification of setpoint is not required.



Perform TADOT.[ [18] months OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.6.

9 Perform CHANNEL CALIBRATION.

[ [18] months OR In accordance

with the Surveillance

Frequency

Control Program

] 6 7 5 DOC M04 Table 4.3-2 Function 3.c.1, 4.9.9 Table 4.3-2 Function 3.c.3, Table 4.3-3 Instrument 2.a 5 4 4 5 4 4 5 4 4 DOC A07 INSERT 1 2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 3.3.6 A Westinghouse STS 3.3.6 A-7 Rev. 4.0 Ventilation 2SEQUOYAH UNIT 2 Amendment XXX CTS 1Table 3.3.6-1 (page 1 of 1) Containment Purge and Exhaust Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT 1.Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.

8 NA2.Automatic Actuation Logic andActuation Relays 1,2,3,4, (a) 2 trains SR 3.3.6.2 SR 3.3.6.3 [SR 3.3.6.

4] [SR 3.3.6.

5] SR 3.3.6.

7 NA 3.[ Containment Radiationa.Gaseous 1,2,3,4 , (a) [1] SR 3.3.6.1 SR 3.3.6.

6 SR 3.3.6.

9 [2 x background]

b.Particulate 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

c.Iodine 1,2,3,4, (a)

[1] SR 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

d.Area Radiat ion 1,2,3,4, (a)

[1] S R 3.3.6.1 SR 3.3.6.6 SR 3.3.6.9 [2 x background]

] 4.Containment Isolation

-Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and requirements. (a) During movement of

[recently] irradiated fuel assemblies within containment.

6 4 7 Purge Air Monitor 8.5 x 10-3 µCi/ccVentilation 2 3 5 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.1 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.2 Tables 3.3-3, 4.3-2, and 3.3-4, Function 3.c.3, and Table 3.3-6 Instrument 2.a DOC M02 1 5 5 3 5 3Safety Injection 1 2SR 3.3.6.8INSERT 2 ITS 3.3.6 Insert Page 3.3.6-7 INSERT 2 FUNCTION APPLICABLE MODES OR OTHE R SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT (a) 1 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 8.5 x 10-3 µCi/cc 3FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT SR 3.3.6. SR 3.3.6. INSERT (a) S R 3.3.6.

JUSTIFICATION FOR DEVIATIONS ITS 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 1 1.The type of Setpoint Control Program (Without Setpoint Control Program) and the Specification designator "A" are deleted since they are unnecessary. Th is information is provided in NUREG 1 431, Re v. 4.0 to assist in identifying the appropriate Specification to be used as a model for the plant specific ITS conversion, but serves no purpose in the plant specific implementation. In addition, IS TS 3.3.6B (with Setpoint Control Program Specification) is not used and is not show n.Furthermore, the title of the Specification has been changed from "Containm ent Purge and Exhaust Isolation Instrumentation" to " Containment Ventilatio n Isolation Instrumentation" since Sequoyah Nuclear Plant (SQN) does not have a Containmen t Purge and Exhaust Isola tion Instrumentation.

2.Changes are made (additions, deletions, and/or changes) to the ISTS that reflect theplant specific nomenclature, number, refer ence, system description, analysis, or licensing ba sis description.

3.The ISTS contains bracketed information and/or values that ar e generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect th e current licensing basis.

4.ISTS SR 3.3

.6.1, SR 3.3.6.4, SR 3.3.6.5, SR 3.3.6.6, SR 3.3.6.7, SR 3.3.6.8 and SR 3.3.6.9 (ITS SR 3.3.

6.1, SR 3.3.6.2, SR 3.3.6.3, SR 3.3.6.4, SR 3.3.6.5, SR 3.3.6.6, and SR 3.3.6.7, respectively) pro v ide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposi ng to control the Surveillance Frequencie s under the Surveillance Frequency Control Program.

5.The ACTUATION LOGIC TEST and MASTER RELAY TEST for SQN are processedthrough the Solid State Protection System. Since ISTS SR 3.3.6.4 and IS TS SR 3.3.6.5 are the appropriate Surveillances for the ACTUATION LOGIC TEST and MASTER RELAY TEST when they are processed through the Solid State Protectio n System, ISTS SR 3.3.6.2 and SR 3.3.6.3 have been deleted and the subs equent Surveillance Requireme nts have been renumbered.

6.The Reviewer's Note has been deleted. Thi s information is for the NRC reviewer to be keyed into what is needed to meet this requirement. This Note is not meant to be retained in the final version of the plant specific submittal.

Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program)

B 3.3.6 A Westinghouse STS B 3.3.6 A-3 Rev. 4.0 1SEQUOYAH UNIT 1 Revision XXX Ventilation 1 2BASES

LCO (continued)

Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b, SI , and ESFAS Function 3.a, Containment Phase A Isolation. The applicable MODES and specified conditions for the containment purge isolation portion of these Functions are different and less restrictive than those for the ir Phase A isolation and SI role s. If one or more of the SI or Phase A isolation Functions becomes inoperable in such a manner that only the Containment

Purge Isolation Function is affected, the Conditions applicable to the ir SI and Phase A is olation Functions need not be entered. The less restrictive Actions specified for inoperability of the Containment Purge Isolation Functions specify sufficient compensatory measures for this case.

3. Containment Radiation

The LCO specifies four required channel s of radiation monitors to ensure that the radiation monitoring instrumentation necessary to initiate Containment Purge Isolation remains OPERABLE.

For sampling systems, channel OPERABILITY involves more than OPERABILITY of the channel electronics. OPERABILITY may also require correct valve lineup s , sample pump operation, and filter motor operation, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses.

4. Containment Isolation

- Phase A Refer to LCO 3.3.2, Function 3.a., for all initiating Functions and requirements.

APPLICABILITY The Manual Initiation, Automatic Actuation Logic and Actuation Relays, Containment Isolation

- Phase A, and Containment Radiation Functions are required OPERABLE in MODES 1, 2, 3, and 4, and during movement

of [recently] irradiated fuel assemblies

[(i.e., fuel that has occupied part of a critical reactor core within the previous [X] days)] within containment. Under these conditions, the potential exists for an accident that could release significant fission product radioactivity into containment.

Therefore, the containment purge and exhaust isolation instrumentation must be OPERABLE in these MODES. 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Ventilation 3 1ventilation the SI Function is Ventilation Ventilation Ventilation one Safety Injection (SI) 1 2 2 2 4Safety Injection INSERT 2 4 4 and s 2 B 3.3.6 Insert Page B 3.3.6-3 INSERT 2 Since the movement of recently irradiated fuel assemblies in containment can only occur in MODE 6 or with the unit defueled, only one Containment Purge Air Radiation Monitor is required to be OPERABLE during the movement of recently irradiated fuel assemblies in containment.

2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program)

B 3.3.6 A Westinghouse STS B 3.3.6 A-5 Rev. 4.0 1SEQUOYAH UNIT 1 Revision XXX Ventilation 1 2BASES

ACTIONS (continued)

B.1 Condition B applies to all Containment Purge and Exhaust Isolation Functions and addresses the train orientation of the Solid State Protection System (SSPS) and the master and slave relays for these Functions. It also addresses the failure of multiple radiation monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for Required Action A.1.

If a train is inoperable

, multiple channels are inoperable, or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action for the applicable Conditions of LCO 3.6.3 is met for each valve made inoperable by failure

of isolation instrumentation.

A Note is added stating that Condition B is only applicable in MODE 1, 2, 3, or 4.

C.1 and C.2 Condition C applies to all Containment Purge and Exhaust Isolation Functions and addresses the train orientation of the SSPS and the master and slave relays for these Functions. It also addresses the failure of

multiple radiation monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for Required Action A.1. If a train is inoperable, multiple channels are inoperable, or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action to place and maintain containment purge and exhaust isolation valves in their closed position is met or the applicable Conditions of LCO 3.9.4, "Containment Penetrations," are met for each valve made inoperable by failure of isolation instrumentation. The Completion Time for these Required Actions is Immediately.

A Note states that Condition C is applicable during movement of

[recently] irradiated fuel assemblies within containment.

SURVEILLANCE A Note has been added to the SR Table to clarify that Table 3.3.6-1 REQUIREMENTS determines which SRs apply to which Containment Purge and Exhaust Isolation Functions. VentilationVentilationventilation Ventilation 1 1 1 1 3the single required or the required radiation monitoring channel is 4 A B A or A B B 4 4 4 4 4 4 4 4 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program)

B 3.3.6 A Westinghouse STS B 3.3.6 A-3 Rev. 4.0 1SEQUOYAH UNIT 2 Revision XXX Ventilation 1 2BASES

LCO (continued)

Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b, SI , and ESFAS Function 3.a, Containment Phase A Isolation. The applicable MODES and specified conditions for the containment purge isolation portion of these Functions are different and less restrictive than those for the ir Phase A isolation and SI role s. If one or more of the SI or Phase A isolation Functions becomes inoperable in such a manner that only the Containment

Purge Isolation Function is affected, the Conditions applicable to the ir SI and Phase A is olation Functions need not be entered. The less restrictive Actions specified for inoperability of the Containment Purge Isolation Functions specify sufficient compensatory measures for this case.

3. Containment Radiation

The LCO specifies four required channel s of radiation monitors to ensure that the radiation monitoring instrumentation necessary to initiate Containment Purge Isolation remains OPERABLE.

For sampling systems, channel OPERABILITY involves more than OPERABILITY of the channel electronics. OPERABILITY may also require correct valve lineup s , sample pump operation, and filter motor operation, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses.

4. Containment Isolation

- Phase A Refer to LCO 3.3.2, Function 3.a., for all initiating Functions and requirements.

APPLICABILITY The Manual Initiation, Automatic Actuation Logic and Actuation Relays, Containment Isolation

- Phase A, and Containment Radiation Functions are required OPERABLE in MODES 1, 2, 3, and 4, and during movement

of [recently] irradiated fuel assemblies

[(i.e., fuel that has occupied part of a critical reactor core within the previous [X] days)] within containment. Under these conditions, the potential exists for an accident that could release significant fission product radioactivity into containment.

Therefore, the containment purge and exhaust isolation instrumentation must be OPERABLE in these MODES. 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Ventilation 3 1ventilation the SI Function is Ventilation Ventilation Ventilation one Safety Injection (SI) 1 2 2 2 4Safety Injection INSERT 2 4 4 and s 2 B 3.3.6 Insert Page B 3.3.6-3 INSERT 2 Since the movement of recently irradiated fuel assemblies in containment can only occur in MODE 6 or with the unit defueled, only one Containment Purge Air Radiation Monitor is required to be OPERABLE during the movement of recently irradiated fuel assemblies in containment.

2 Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program)

B 3.3.6 A Westinghouse STS B 3.3.6 A-5 Rev. 4.0 1SEQUOYAH UNIT 2 Revision XXX Ventilation 1 2BASES

ACTIONS (continued)

B.1 Condition B applies to all Containment Purge and Exhaust Isolation Functions and addresses the train orientation of the Solid State Protection System (SSPS) and the master and slave relays for these Functions. It also addresses the failure of multiple radiation monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for Required Action A.1.

If a train is inoperable

, multiple channels are inoperable, or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action for the applicable Conditions of LCO 3.6.3 is met for each valve made inoperable by failure

of isolation instrumentation.

A Note is added stating that Condition B is only applicable in MODE 1, 2, 3, or 4.

C.1 and C.2 Condition C applies to all Containment Purge and Exhaust Isolation Functions and addresses the train orientation of the SSPS and the master and slave relays for these Functions. It also addresses the failure of

multiple radiation monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for Required Action A.1. If a train is inoperable, multiple channels are inoperable, or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action to place and maintain containment purge and exhaust isolation valves in their closed position is met or the applicable Conditions of LCO 3.9.4, "Containment Penetrations," are met for each valve made inoperable by failure of isolation instrumentation. The Completion Time for these Required Actions is Immediately.

A Note states that Condition C is applicable during movement of

[recently] irradiated fuel assemblies within containment.

SURVEILLANCE A Note has been added to the SR Table to clarify that Table 3.3.6-1 REQUIREMENTS determines which SRs apply to which Containment Purge and Exhaust Isolation Functions. VentilationVentilationventilation Ventilation 1 1 1 1 3the single required or the required radiation monitoring channel is 4 A B A or A B B 4 4 4 4 4 4 4 4 Licensee Response/NRC Response/NRC Question Closure Id 396NRC Question Number KAB045Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation. The change to recently irradiated fuel will be addressed under the AST review, and further questions on this will be included in the AST RAIs.Question Closure Date 12/12/2014Notification Mark BlumbergScott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 12/12/2014 10:00 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 85 NRC Question Number KAB046 Category TechnicalITS Section 3.3ITS Number 3.3.8 DOC Number JFD Number JFD Bases Number Page Number(s) 1050, 1055 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested N NRC Question On pages 1050 and 1055 of Enclosure 2, Volume 8, has ITS 3.3.8 Table 3.3.8-1.

CTS 3.7.8 requires two independen t auxiliary building gas treatment filter trains be operable in Modes 1, 2, 3, and 4 for th e loss of coolant accident design basis accident.CTS 3.9.12 requires one auxiliary building gas treatment filter trains be operable wh enever irradiated fuel in in the storage pool for the fuel handling accident (FHA). CTS 3.3.3.1 requires the radiation monitoring instrumentation channels in Table 3.3-6 to be operable.CTS Table 3.3-6 requires a minimum of 1 channel of the fuel storage pool area monitor to be operable with fuel in the storage pool or building.

ITS LCO 3.7.12, "Auxiliary Building Gas Treatment System (ABGTS),"requires that two ABGTS trains are operable in Modes 1, 2, 3, 4, and during movement of recently ir radiated fuel assemblies in the auxiliary building. ITS 3.3.8 requires one channe l of Spent Fuel Pool Area Radiation Monitor during movement s of recently irradiated fuel assemblies in the auxiliary buildin g to be operable and footnote (b) clarifies that the Required Channel shall be associated with ABGTS train required to be OPERABLE per LCO 3.7.12.

The ITS definition of Oper able-Operability states:

A system, subsystem, train, co mponent, or device shall be OPERABLE or have OPERABILITY when it is capable Page 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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of performing its sp ecified safety function(s) and when all necessaryattendant instrumentation , controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxi liary equipment that are required for the system, subsys tem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

ITS 3.7.12 reflects the combinat ion of CTS 3.7.8 and CTS 3.9.12. However, all the instrumentation needed for ABGTS does not seem to be reflected in ITS 3.3.8.

ABGTS is started by high radiatio n signal from the Area Monitor Fuel Storage pool area and is based on FHA.In addition, the ABGTS is started by a high radiation si gnal from the Auxiliary Building Exhaust Ventilation monitor and a high temperature signal from

Auxiliary Building air intakes.

Please explain if the high radiation signal from the Auxiliary Building Exhaust Ventilation monitor and a high temperature signal from

Auxiliary Building air intakes are credited for star ting the ABGTS following a loss of coolant accident.If these instruments are not credited for starting the ABGTS foll owing a loss of coolant accident than explain which instruments are credited to start ABGTS following a loss of coolant accident.In addition, if there is other credited in strumentation that starts the ABGTS, other than the Spent Fuel Pool Area Radiation Monitor, please explain why it was not added to ITS 3.3.8 or add it to ITS 3.3.8.Attach File 1 Attach File 2 Issue Date 5/23/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 6:45 AMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id134 NRC Question Number KAB046Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement The auxiliary building exhaust venti lation monitor is not credited for starting the auxiliary building gas treatment system (ABGTS) following a loss of coolant accident (LOCA).The automatic initiation of the ABGTS associated with the auxiliary building ventilation monitor is not a primary safety function; rather, it is provided for AL ARA offsite dose purposes.A high temperature signal from the auxiliary building air intake is not credited for starting ABGTS following a LOCA.The high temperature initiation of the ABGTS is associat ed with protecting the environmental qualification of certain equipment in the auxiliary building during a high energy line break located near the auxiliary building air intake canopy.For a LOCA, the Phase A containment isolation signal is the only credited signal for starting the ABGTS.Automatic Phase A containment isolation is initiated by a safety injection signal.

All credited ABGTS start signals are listed in ITS Table 3.3.8.Response Date/Time 6/20/2014 5:15 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/20/2014 4:11 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 139NRC Question Number KAB046Select Application NRC Response Response Statement is the high radiation signal from the auxiliary building exhaust ventilation monitor or high temperature signal from the auxiliary building air intake credited for any of the accidents and/or transient analyses in Sequoyah UFSAR? In order for ABGTS to be considered operable, ITS LCO 3.7.12 will require all the ABGTS necessary attendant instrumentation to be capable of performing their related support functions in modes 1, 2, 3, 4, and during movement of recently irradiated fuel assemblies in the Auxiliary building. Please explain which instrumentation Sequoyah considered to be necessary for ABGTS operabliity and state what the function it supports? Response Date/Time 6/20/2014 6:00 PM Closure Statement Question Closure Date Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/20/2014 8:36 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 253NRC Question Number KAB046Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement The auxiliary building exhaust ventilation monitor is not credited for starting the auxiliary building ga s treatment system (ABGTS) in the accidents and/or transient analyses in the SQN UFSAR.The automatic initiation of the ABGTS associated with the auxili ary building ventilation monitor is not a primary safety function; rather, it is provided for ALARA offsite dose purposes.A high temperature signal from the auxi liary building air intake is not credited for starting ABGTS in the accidents and/or transient analyses in the SQN UFSAR.The high temperature initiation of the ABGTS is associated with protecting the environmental qualification (EQ) of certain equipment in the auxiliary building during a high energy line break (HELB) located near the auxili ary building air intake canopy.ABGTS is not credited in any steam or feedwater line break.The instrumentation and functions necessary for ABGTS operability are:1.ITS Table 3.3.8-1, Functi on 1, Manual Initiation.2.ITS Table 3.3.8-1, Function 2, Spen t Fuel Pool Radiat ion Monitor, for a Fuel Handling Accident.3.ITS Table 3.3.8-1, Function 3, Containment Isolation - Phase A, for a Loss of Coolant Accident.All credited ABGTS start signals are listed in ITS Table 3.3.8.Response Date/Time 8/8/2014 11:20 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanPage 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Date Added 8/8/2014 10:19 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id265NRC Question Number KAB046Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 8/14/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 8/14/2014 9:55 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 86NRC Question Number KAB047Category EditorialITS Section 3.3ITS Number 3.3.8DOC Number M-6JFD Number JFD Bases Number Page Number(s) 1041NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 1041 of Enclosure 2, Volume 8, M06 provides the discussion of CTS Table 3.3-6 action 26 compared to ITS 3.3.8 Condition b.M06 states, "ITS Table 3.3.8-1 Function 2 requires one Spent Fuel Pool Area Radiation Monitor to be OPERABLE during movement of irradiated fuel assemblies in the auxiliary building.However, ITS Table 3.3.8-1 Function 2 requires one Spent Fuel Pool Area Radiation Monitor to be oper able during movement of recentlyirradiated fuel assemblies in the auxiliary building.

Please provide a correction to M06 so that it is accurate, or explain the discrepancy.Attach File 1 Attach File 2 Issue Date 5/23/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 6:47 AMNotification Scott BowmanMichelle Conner Khadijah Hemphill Andrew Hon

Lynn Mynatt Ray Schiele

Roger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 103NRC Question Number KAB047 Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.8 revised DOC M08.pdf (15KB)Attachment 2 Response Statement In response to KAB047, discussion of change (DOC) M06, on page 1041 of Enclosure 2, Volume 8, will be revised.Specifically, the sentence, "ITS Table 3.3.8-1 Function 2 requires on e Spent Fuel Pool Area Radiation Monitor to be OPERABLE during movement of irradiated fuel assemblies in the auxiliary building."will be revised to read, "ITS Tabl e 3.3.8-1 Function 2 requires one Spent Fuel Pool Area Ra diation Monitor to be OPERABLE during movement of recently irradiated fuel assemblies in the auxiliary building."See Attachment 1 for a draft revised DOC M06.Response Date/Time 6/6/2014 6:40 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanDate Added 6/6/2014 5:39 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.8, AUXILIARY BUILDING GAS TREATMENT SYSTEM (ABGTS) ACTUATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 4 of 7 M05 CTS 3.3.3.1 states that the Radiation Monitoring Instrumentation channels shown in Table 3.3-6 shall be OPERABLE. CTS Table 3.3-6 lists the radiation monitor required for the fuel storage pool area. ITS LCO 3.3.8 states that the ABGTS actuation instrumentation for each Function in Table 3.3.8-1 shall be OPERABLE. ITS Table 3.3.8-1 lists the required ABGTS instrument Functions which includes Containment Isolation - Phase A (Function 3). ITS Table 3.3.8-1 Function 3 provides a statement referring to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a for all initiation functions and requirements. This changes the CTS by specifying an additional instrumentation actuation Function

for the ABGTS.

The purpose of CTS 3.3.3.1 and Table 3.3-6 is to specify the required Functions and instrumentation to ensure the ABGTS actuates as assumed in the accident analysis. The Containment Isolation - Phase A signal from the ESFAS provides an actuation of ABGTS that is credited in the loss of coolant accident. This change is acceptable because it will result in a more complete listing of the Functions that actuate ABGTS. The inclusion of the Containment Isolation -

Phase A signal with the other credited ABGTS instrumentation provides a complete list of the required ABGTS instrumentation with a common set of Actions to assure the unit is placed in a safe condition when the required instrumentation is inoperable. Therefore, the proposed change ensures the radioactive materials in the Auxiliary Building Secondary Containment Enclosure atmosphere following an accident are filtered and adsorbed prior to being exhausted to the environment. This change is designated as more restrictive because more ABGTS actuation instrumentation will be required in ITS than was required in CTS.

M06 CTS Table 3.3-6 "MINIMUM CHANNELS OPERABLE" column, for Instrument 1.a, only requires one Area Monitor - Fuel Storage Pool Area channel to be OPERABLE with fuel in the storage pool or building. CTS Table 3.3-6 ACTION 26 applies when the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement. ACTION 26 requires the performance of an area survey of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ITS Table 3.3.8-1 Function 2 requires one Spent Fuel Pool Area Radiation Monitor to be OPERABLE during movement of irradiated fuel assemblies in the auxiliary building. ITS 3.3.8 ACTION B requires that when one required channel is inoperable, to place one ABGTS train in operation and to enter the applicable Conditions and Required Action for LCO 3.7.12 for one train made inoperable by inoperable actuation instrumentation. This changes the CTS by requiring more stringent ACTIONS for the inoperable channels. (See DOC L01 for a discussion on the change to the Applicability.)

The purpose of the Spent Fuel Pool Ar ea Radiation Monitor is to provide indication of high radiation in the Fuel Storage Pool area. This change is acceptable because when one required Spent Fuel Pool Area Radiation Monitor channel is inoperable, placing the ABGTS in operation accomplishes the Spent Fuel Pool Area Radiation Monitor instrum ent function. Additionally, entering the Conditions and Required Actions for the ABGTS Specification (ITS 3.7.12) will allow 7 days to restore one inoperable ABGTS train to OPERABLE status. This DISCUSSION OF CHANGES ITS 3.3.8, AUXILIARY BUILDING GAS TREATMENT SYSTEM (ABGTS) ACTUATION INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 5 of 7 change is designated as more restrictive because more stringent Required Actions and Completion Times are required in the ITS than were required in the CTS.

M07 CTS 3.3.3.1, Table 3.3-6, ACTION 26, is associated with Functional Unit 1.a (Area Monitor, Fuel Storage Pool Area) and requires that with the number of OPERABLE channels less than required by the Minimum Channels OPERABLE

requirement, to perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ITS 3.3.8 ACTION C requires if the Required Action and associated Completion Time for Condition B, one required radiation monitor inoperable, is not met during movement of recently irradiated fuel assemblies in the auxiliary building, to immediately suspend movement of recently irradiated fuel assemblies in the auxiliary building.

This changes the CTS by adding explicit Required Actions to exit the MODE of Applicability if remedial action cannot be completed within the allotted time.

The purpose of Required Actions is to establish remedial measures that must be taken in response to the degraded conditions in order to minimize risk associated with continued operation while providing time to repair inoperable features. This change is acceptable because it provides Required Actions to exit the MODE of Applicability that must be taken if the time allotted to establish the required remedial measures or complete the repair of inoperable features is exceeded. This change is designated as more restrictive because more stringent Required Actions and Completion Times are required in the ITS than were required in the CTS. RELOCATED SPECIFICATIONS

None

REMOVED DETAIL CHANGES LA01 (Type 1 - Removing Details of System Design and System Description, Including Design Limits) CTS Table 3.3-6 for Radiation Monitoring Instrumentation has five columns stating various requirements for the Radiation Monitoring Instrumentation. These columns are labeled "MINIMUM CHANNELS OPERABLE," "APPLICABLE MODES," ALARM/TRIP SETPOINT,"

"MEASUREMENT RANGE," AND "ACTION." ITS Table 3.3.8-1 does not contain the "MEASUREMENT RANGE" column. This changes the CTS by moving the information of the "MEASUREMENT RANGE" column to the Bases.

The removal of these details, which are related to system design, from the Technical Specifications, is acceptable because this type of information is not necessary to be included in the Technical Specifications to provide adequate protection of public health and safety. The ITS still retains the requirement for the number of required channels, the Applicable MODES, the alarm/trip setpoint, and the appropriate Condition to enter if a required channel becomes inoperable. Also, this change is acceptable because the removed information will be Licensee Response/NRC Response/NRC Question Closure Id116NRC Question Number KAB047Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:02 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 87NRC Question Number KAB048 Category EditorialITS Section 3.3 ITS Number 3.3.9DOC Number LA-2JFD Number JFD Bases Number Page Number(s) 1097NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 1097 of Enclosure 2, Volume 8, LA02 provides the discussion of surveillance requirements in CTS 4.3.1.1.1 and Table 4.3-1 as compared to ITS 3.3.9.LA02 st ates, "Also, see DOC L01 for discussion on changing th e COT Surveillance Frequency from monthly to 184 days."Howe ver, L01 does not discuss the surveillance frequency chan ge from monthly to 184 days.

Please provide a correction to LA02 so that it is accurate, or explain the discrepancyAttach File 1 Attach File 2 Issue Date 5/23/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 2:48 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 104NRC Question Number KAB048Select Application Licensee Response Attachment 1 3.3.9 revised DOC LA02.pdf (15KB)Attachment 2 Response Statement In response to KAB048, discussion of change (DOC) LA02, beginning on page 1097 of Enclosure 2, Volume 8, will be revised.Specifically, the reference to DOC L01 concerning the COT Surveillance Frequency changing from monthly to 184 days, will be revised to reference DOC L03.

See Attachment 1 for a draft revised DOC LA02.Response Date/Time 6/6/2014 6:45 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanDate Added 6/6/2014 5:42 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 6 that must be taken in response to the degraded conditions in order to minimize risk associated with continued operation while providing time to repair inoperable features. Furthermore, the Required Actions are consistent with safe operation under the specified Conditions. This change is considered more restrictive because additional Required Actions are required in the ITS that were not required in the CTS.

RELOCATED SPECIFICATIONS

None REMOVED DETAIL CHANGES

LA01 (Type 1 - Removing Details of System Design and System Description, Including Design Limits) CTS Table 3.3-1, "Reactor Trip System Instrumentation," includes three columns stating various requirements for the Source Range Neutron Flux Shutdown Function. These columns are labeled "TOTAL NO. OF CHANNELS," "CHANNELS TO TRIP," and "MINIMUM CHANNELS OPERABLE." For CTS Table 3.3.1 Functional Unit 6.B, the "CHANNELS TO TRIP COLUMN" is "0" (i.e., the Function is required to provide an indication only function and is not required to have a trip function). ITS 3.3.9 does not include the "TOTAL NO. OF CHANNELS" and "CHANNELS TO TRIP" columns. This changes the CTS by moving the information of the "TOTAL NO. OF CHANNELS" and "CHANNELS TO TRIP" columns to the Bases.

The removal of these details, which are related to system design, from the Technical Specifications, is acceptable because this type of information is not necessary to be included in the Technical Specifications to provide adequate protection of public health and safety. The ITS still retains the requirement for the number of required channels and the appropriate Condition to enter if a required channel becomes inoperable. Also, this change is acceptable because the removed information will be adequately controlled in the ITS Bases. Changes to the Bases are controlled by the Technical Specification Bases Control Program in Chapter 5. This program provides for the evaluation of changes to ensure the Bases are properly controlled. This change is designated as a less restrictive removal of detail change because information relating to system design is being removed from the Technical Specifications.

LA02 (Type 5 - Removal of SR Frequency to the Surveillance Frequency Control Program) CTS 4.3.1.1.1 requires that each reactor trip system instrumentation channel be demonstrated OPERABLE by performance of a CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST for the MODES and Frequencies shown in Table 4.3-1. CTS Table 4.3-1 Functional Unit 6 requires performance of a CHANNEL CHECK every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL CALIBRATION every refueling outage, and a CHANNEL FUNCTIONAL TEST every month for the source range neutron flux monitors during MODES 3, 4, and

5. ITS SR 3.3.9.1, SR 3.3.9.2, and SR 3.3.9.3 require similar Surveillances and specify the periodic Frequency as, "In accordance with the Surveillance Frequency Control Program." (See DOC M01 for the discussion on changing the DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 4 of 6 CHANNEL FUNCTIONAL TEST to a COT. Also, see DOC L01 for discussion on changing the COT Surveillance Frequency from monthly to 184 days.) This changes the CTS by moving the specified Frequencies for the SRs and associated Bases to the Surveillance Frequency Control Program.

The removal of these details related to Surveillance Requirement Frequencies from the Technical Specifications is acceptable, because this type of information is not necessary to be included in the Technical Specifications to provide adequate protection of public health and safety. The existing Surveillance Frequencies are removed from Technical Specifications and placed under licensee control pursuant to the methodology described in NEI 04-10. A new program (Surveillance Frequency Control Program) is being added to the Administrative Controls section of the Technical Specifications describing the control of Surveillance Frequencies. The surveillance test requirements remain in the Technical Specifications. The control of changes to the Surveillance Frequencies will be in accordance with the Surveillance Frequency Control Program. The Program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met. This change is designated as a less restrictive removal of detail change, because the Surveillance Frequencies are being removed from the Technical Specifications.

LESS RESTRICTIVE CHANGES

L01 (Category 2 - Relaxation of Applicability) CTS 3.3.1.1 [3.3.1 Unit 2] Applicability states that the Applicability of each Functional Unit is as shown in Table 3.3-1. For CTS Table 3.3-1 Functional Unit 6.B (Source Range, Neutron Flux, Shutdown) the "Applicable MODES" column lists MODES 3, 4, and 5. ITS 3.3.9, Boron Dilution Monitoring Instrumentation, provides requirements for the Source Range Neutron Flux instruments. ITS 3.3.

9 Applicability similarly lists MODES 3, 4, and 5 but is modified by a Note that states, "The high flux at shutdown alarm may be blocked in MODE 3 during reactor startup." This changes the CTS Mode of Applicability for the high flux at shutdown alarm by allowing blocking of the alarm in MODE 3 during reactor startup.

The purpose of CTS Table 3.3-1 Functional Unit 6.B (Source Range, Neutron Flux, Shutdown) is to provide indication of a dilution accident in sufficient time for the operators to respond and mitigate the accident. This change is acceptable because the requirements continue to ensure that the operators would be made aware of a dilution accident in sufficient time to respond and mitigate the accident. A reactor startup is a controlled activity where operator's attention is focused on the reactivity condition of the reactor core. Boron concentration is also monitored as one of the inputs to the estimated critical position calculation. In addition, the source range and intermediate range nuclear instruments are monitored closely specifically looking for indications of an unplanned reactivity rate of change. This change is designated as less restrictive because the LCO requirements are applicable in fewer operating conditions than in the CTS.

Licensee Response/NRC Response/NRC Question Closure Id117NRC Question Number KAB048Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Ray SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:02 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 88NRC Question Number KAB049Category TechnicalITS Section 3.3ITS Number 3.3.9DOC Number L-4JFD Number JFD Bases Number Page Number(s) 1099NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 1099 of Enclosure 2, Volume 8, L04 provides the discussion of the addition of a surveillance note to ITS SR 3.3.9.2.The added note states, "Not requi red to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3,"and it is app lied to the channel operational test.Please explain which instruments ar e tested, including the instrument designations/nomenclature, for ITS SR 3.3.9.2, ITS SR 3.3.1.7, and ITS 3.3.1.8.In additi on, please explain if the test procedure performed for ITS SR 3.3.9.2 is the same test procedure that is used to perf orm ITS SR 3.3.1.7 and/or ITS SR 3.3.1.8.

If the same instruments are tested usin g the same test procedure then please explain why there is a time difference (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) in the note for ITS SR 3.3.9.2 versus (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) that allowed in ITS/ISTS SR 3.3.1.7 and 3.3.1.8.Attach File 1 Attach File 2 Issue Date 5/23/2014Added By Kristy BucholtzDate Modified Page 1of 2 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=88 Modified By Date Added 5/23/2014 2:50 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=88 Licensee Response/NRC Response/NRC Question Closure Id 330NRC Question Number KAB049 Select Application Licensee ResponseAttachment 1 Attachment 1 RAI KAB049.pdf (1MB)Attachment 2 Response Statement In response to RAI KAB049, the Note for ITS SR 3.3.9.2, on pages 1103 and 1106 of Enclosure 2, Volume 8, will be deleted.Additionally, ITS Required Actions A.1, A.2.1, A.2.

2.1, and A.2.2.2 will be replaced with Required Action A.1 (Perform SR 3.1.1.1). The proposed ch ange will replace ITS Required Actions with Ac tions equivalent to CTS Table 3.3-1 ACTION 5.

The proposed Note to ITS SR 3.3.9.2 allowed a delay of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 to perform a CHANNE L OPERABILITY TEST (COT) for the source range neutron flux monitoring channel.The intention of the proposed Note was to preve nt entering ITS 3.3.9 Co ndition A when ITS LCO 3.3.9 was not met because the unit transitioned from MODE 1 to MODE 3 and ITS SR 3.3.9.2 was not within the specified Frequency (portions of the COT cannot be performed above the P-6 interlock).Required Actions associated with ITS 3.3.9 Condition A required suspending operations involving positive reactivity additions and restoring one required channel to OPERABLE status or closing one combination of unborated water source isolation valves and performing ITS SR 3.1.1.1 (Verify SHUTDOWN MARGIN).In CTS, if LCO 3.3.1.1 (Unit 1 and LCO 3.3.1 for Unit 2) is not met for the source range neutron flux instrumentation, then CTS Table 3.3-1 ACTION 5 requires verifying compliance with the SHUTDOWN MARGIN requirements of CTS 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.Based on the revision to ITS SR 3.3.

9.2 and Required Actions for ITS 3.3.9 Condition A, the following changes will be necessary:1.Discussion of change (DOC) M02 will be deleted, as well as, DOC M02 inserts and indicators.(Pag es 1087, 1092, 1096, and 1097)2.DOC L04 will be dele ted, as well as, DOC L04 inserts and indicators.(Pages 1089, 1094, 1099, and 1100)3.DOC A03 will be revised to repl ace ITS 3.3.9 Required Action "A.2.2.2"with "A.1".(Page 1095)Page 1of 3 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=330 4.The ISTS markups will be revised to correct the CTS cross-references in the left hand margin. (Pag es 1102, 1103, 1105, and 1106)5.Justification for deviation (JFD) 9 wi ll be added to ju stify changes made to ISTS Required Actions B.1, B.2.1, B.2.2.1, and B.2.2.2.JFD indicators in the right hand margin will be deleted where the associated changes are deleted and replaced with JFD 9 indicators.(Pages 1102, 1103, 1105, 1106, and 1109)6.JFD 7 will be deleted, as well as, JFD 7 indicators.(Pages 1103, 1106,1108 and 1109)7.JFD 8 will be deleted.In respons e to KAB051, ISTS markups were provided showing JFD 4 should be JFD 8 for ch anges made to ISTS Required Action B.2.2.1.ISTS Requir ed Action B.2.2.1 will be deleted and justified by the new JFD 9.(Pages 1103, 1106, and 1109)8.The ISTS Bases markups will be revised to reflect the changes made to ISTS Required Actions B.1, B.2.1, B.2.2.1, and B.2.2.2.JFD indicators in the right hand margin will be deleted where the associated changes are deleted.(Pages 1116 and 1125)9.ISTS Bases JFD 5 will be deleted, as well as, JFD 5 indicators.(Pages 1116, 1125, and 1129)See Attachment 1 for the revised CTS and ISTS markups; deletion of DOCs M02, L04, JFD 7, Bases JF D 5; revision of DOC A03; and addition of JFD 9.

The following information is provided for RAI KA B049 concerning which instruments are tested and the procedures used to perform the tests for ITS SRs 3.3.1.7, 3.

3.1.8, and 3.3.9.2.

ITS SR 3.3.1.7 is a CHANNEL OPERAT IONAL TEST (COT) applicable to source range instrumentati on (ITS Table 3.3.1-1, Functi on 5) in MODES 3, 4, and 5 with the Rod Control System capab le of withdrawal or one or more rods not fully inserted.The applicable instruments for SQN Unit 1 are 1-XX-92-5001 and 1-XX-92-5002.The applicable proc edures for SQN Unit 1 are 1-SI-IFT-092-N31.1 for Channel I and 1-SI-IFT-092-N32.2 for Channel II.ITS SR 3.3.1.8 is a COT applicable to source range instrumentation (ITS Table 3.3.1-1, Function 5) in MODE 2 below the P-6 interlock.The applicable instruments for SQN Unit 1 are 1-XX-92-5001 and 1-XX-92-5002.

The applicable procedures for SQN Unit 1 are 1-SI-IFT-092-N31.1 for Channel I and 1-SI-IFT-092-N32.2 for Channel II.ITS SR 3.3.9.2 is a COT applicable to source range instrumentation in MODES 3, 4, and 5.The applicable instruments for SQN Unit 1 are 1-XX-92-5001 and 1-XX-92-5002.The applicable procedures for SQN Unit 1 are 1-SI-IFT-092-N31.1 for Channel I and 1-SI-IFT-092-N32.2 for Channel II. Response Page 2of 3 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=330 Date/Time 9/10/2014 3:15 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerRobert ElliottKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger Scott Added By Lynn MynattDate Added 9/10/2014 2:11 PMDate Modified Modified By Page 3of 3 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=330 A01ITS ITS 3.3.9 TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.
b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.
c. Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.
d. Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.
b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the

following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or THERMAL POWER is reduced to less than P-9 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. September 2, 2005 SEQUOYAH - UNIT 1 3/4 3-6 Amendment No. 47, 141, 304 See ITS 3.3.1 See ITS 3.3.1 ACTION A Add proposed Required Actions A.1, A.2.1, and A.2.2.1 M02 A03SR 3.1.1.1 Page 3 of 10 , Volume 8, Rev. 0, Pa g e 1087 of 1148 , Volume 8, Rev. 0, Pa g e 1087 of 1148Add proposed pp Required qActions A.1, A.2.1, andA.2.2.1 M02 A01ITS ITS 3.3.9 TABLE 4.3-1 (Continued)

NOTATION * - With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

    • - Above the P-9 (Power Range Neutron Flux) interlock.

(1) - If not performed in previous 31 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.

(3) - Compare incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference greater than or equal to 3 percent. The frequency of this surveillance is every 31 EFPD. This surveillance is not required to be performed until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after thermal power is > 15% RTP.

(4) - Deleted.

(5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. The test shall independently verify the OPERABILITY of the undervoltage and automatic shunt trip circuits.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8) - Deleted.

(9) - The CHANNEL FUNCTIONAL TEST shall independently verify the operability of the undervoltage and shunt trip circuits for the manual reactor trip function.

(10) - Local manual shunt trip prior to placing breaker in service. Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(11) - Automatic and manual undervoltage trip.

(12) - Prior to exceeding the P-9 interlock whenever the unit has been in HOT STANDBY.

April 2, 2008 SEQUOYAH - UNIT 1 3/4 3-13 Amendment No. 54, 114, 141, 199, 304, 318 See ITS 3.3.1 See ITS 3.3.1 SR 3.3.9.3 Note Page 5 of 10 See ITS 3.3.1 L02Add proposed SR 3.3.9.2 Note L04 Enclosure 2, Volume 8, Rev. 0, Pa g e 1089 of 1148 , Volume 8, Rev. 0, Pa g e 1089 of 1148 L04Add proposed SR 3.3.9.2 Note A01ITS ITS 3.3.9TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.
b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER. c. Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.
d. Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.
b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or THERMAL POWER is reduced to less than P-9 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. . September 2, 2005 SEQUOYAH - UNIT 2 3/4 3-6 Amendment No. 39, 132, 294 See ITS 3.3.1 See ITS 3.3.1 ACTION A Add proposed Required Actions A.1, A.2.1, and A.2.2.1 M02 A03SR 3.1.1.1 Page 8 of 10 , Volume 8, Rev. 0, Pa g e 1092 of 1148 , Volume 8, Rev. 0, Pa g e 1092 of 1148Add proposed pp Required qActions A.1, A.2.1, andA.2.2.1 M02 A01ITS ITS 3.3.9 Table 4.3-1 (Continued)

NOTATION * - With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

    • - Above the P-9 (Power Range Neutron Flux) interlock.

(1) - If not performed in previous 31 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.

(3) - Compare incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference greater than or equal to 3 percent. The frequency of this surveillance is every 31 EFPD. This surveillance is not required to be performed until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after thermal power is > 15% RTP.

(4) - Deleted.

(5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. The test shall independently verify the OPERABILITY of the undervoltage and automatic shunt trip circuits.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8) - Deleted.

(9) - The CHANNEL FUNCTIONAL TEST shall independently verify the operability of the undervoltage and shunt trip circuits for the manual reactor trip function.

(10) - Local manual shunt trip prior to placing breaker in service. Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(11) - Automatic and manual undervoltage trip.

(12) - Prior to exceeding the P-9 interlock whenever the unit has been in HOT STANDBY.

April 2, 2008 SEQUOYAH - UNIT 2 3/4 3-13 Amendment No. 46, 104, 132, 190, 294, 310 See ITS 3.3.1 SR 3.3.9.3 Note See ITS 3.3.1 Page 10 of 10 See ITS 3.3.1 L02Add proposed SR 3.3.9.2 Note L04 Enclosure 2, Volume 8, Rev. 0, Pa g e 1094 of 1148 , Volume 8, Rev. 0, Pa g e 1094 of 1148 L04Add proposed SR 3.3.9.2 Note DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 6 ADMINISTRATIVE CHANGES

A01 In the conversion of the Sequoyah Nuclear Plant (SQN) Current Technical Specifications (CTS) to the plant specific Improved Technical Specifications (ITS), certain changes (wording preferences, editorial changes, reformatting, revised numbering, etc.) are made to obtain consistency with NUREG-1431, Rev. 4.0, "Standard Technical Specifications-Westinghouse Plants" (ISTS) and additional Technical Specification Task Force (TSTF) travelers included in this

submittal.

These changes are designated as administrative changes and are acceptable because they do not result in technical changes to the CTS.

A02 CTS LCOs 3.3.1.1 (Unit 1) and 3.3.1 (Unit 2), requires the Reactor Trip System Instrumentation channels and interlocks shown in Table 3.3-1 to be OPERABLE and requires that each channel be demonstrated OPERABLE by performance of the tests specified in CTS Table 4.3-1, including Functional Unit 6.B (Source Range, Neutron Flux, Shutdown). ITS 3.3.9, "Boron Dilution Monitoring

Instrumentation (BDMI)," provides similar OPERABILITY and testing

requirements for the source range neutron flux monitoring channels. This changes the CTS by providing a separate Specification for the Source Range, Neutron Flux, Shutdown Function (Boron Dilution Monitoring Instrumentation), in lieu of including it with the Reactor Trip System Instrumentation Specification.

This change is acceptable because the technical requirements for the Source Range, Neutron Flux, Shutdown Instrumentation are maintained with the change in format. The Boron Dilution Monitoring Instrumentation Specification continues to require the OPERABILITY and testing of the source range neutron flux monitoring instrumentation. This change is designated as administrative because it does not result in a technical change to the CTS.

A03 CTS Table 3.3-1 ACTION 5, which is the ACTION referenced in Table 3.3-1 for Functional Unit 6.B (Source Range, Neutron Flux - Shutdown), requires within one hour and every twelve hours thereafter, that when both channels are inoperable in MODES 3, 4, and 5 to verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable.

ITS 3.3.9 Required Action A.2.2.2 requires, in part, that when the required source range neutron flux monitoring channel is inoperable, to perform SR 3.1.1.1. This changes the CTS by changing the presentation of how to perform the verification of compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2.

This change is acceptable because the requirement have not changed. In CTS, the SHUTDOWN MARGIN specification was in two separate Specifications. CTS 3.1.1.1 contained the requirements for the SHUTDOWN MARGIN when Tavg was greater than or equal to 200 degrees Fahrenheit. CTS 3.1.1.2 contained the requirements for the SHUTDOWN MARGIN when Tavg was less than or equal to 200 degrees Fahrenheit. The ITS combined these two CTS Specifications into ITS 3.1.1, "SHUTDOWN MARGIN." Therefore, stating in ITS 3.3.9 Required Action A.2.2.2, to perform SR 3.1.1.1 is the same as the CTS Table 3.3-1 ACTION 5 statement to verify compliance with the SHUTDOWN MARGIN , Volume 8, Rev. 0, Pa g e 1095 of 1148 , Volume 8, Rev. 0, Pa g e 1095 of 1148 A.1 A.1 DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 2 of 6 requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable. This change is considered a change in presentation and, therefore, is considered as an administrative change since it does not result in a technical change to the CTS.

MORE RESTRICTIVE CHANGES M01 CTS 4.3.1.1.1 requires, in part, the reactor trip system instrumentation shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST for the MODES and Frequencies shown in Table 4.3-1. Table 4.3-1 Functional

Unit 6 requires a CHANNEL FUNCTIONAL TEST of the Source Range Neutron Flux. ITS SR 3.3.9.1 requires performance of a CHANNEL OPERABILITY TEST (COT) for each source range neutron flux monitoring channel. This changes the CTS by requiring a COT instead of a CHANNEL FUNCTIONAL TEST.

This change is acceptable because the COT continues to perform a test similar to the current CHANNEL FUNCTIONAL TEST. CTS defines a CHANNEL FUNCTIONAL TEST based on the type of channel. In CTS a CHANNEL FUNCTIONAL TEST shall be: for Analog channels, the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions; for Bistable channels, the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions; and for digital channels, the injection of a simulated signal into the channel as close to the sensor input to the process racks as practicable to verify OPERABILITY including alarm and/or trip functions. The CHANNEL OPERATIONAL TEST (COT) provides a similar test with the addition that the COT includes adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. This change is designated as more restrictive because the ITS requires additional acceptance criteria that is not required in the CTS.

M02 CTS Table 3.3-1 ACTION 5, which is the ACTION referenced in Table 3.3-1 for Functional Unit 6.B (Source Range, Neutron Flux - Shutdown), requires when both channels are inoperable in MODES 3, 4, and 5 to verify compliance with the SHUTDOWN MARGIN requirements within one hour and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. ITS 3.3.9 ACTION A requires that when the required source range neutron flux monitoring channel is inoperable, to suspend operations involving positive reactivity additions immediately except when plant temperature changes are accounted for in the calculated SDM (Required Action A.1). ITS 3.3.9 ACTION A also requires either the restoration of the required source range neutron flux monitoring channel to OPERABLE status within one hour OR to initiate action to close one combination of unborated water source isolation valves and perform SR 3.1.1.1 within one hour (Required Actions A.2.1, A.2.2.1 and A.2.2.2, respectively). This changes the CTS by adding Required Actions (Required Actions A.1 and A.2.2.1) when the required channel is inoperable.

The purpose of Table 3.3-1 ACTION 5 is to verify that SHUTDOWN MARGIN is

still within the required limits when the required source range channel is not available to monitor for changes in core reactivity. This change is acceptable because the added Required Actions are used to establish remedial measures , Volume 8, Rev. 0, Pa g e 1096 of 1148 , Volume 8, Rev. 0, Pa g e 1096 of 1148 DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 3 of 6 that must be taken in response to the degraded conditions in order to minimize risk associated with continued operation while providing time to repair inoperable features. Furthermore, the Required Actions are consistent with safe operation

under the specified Conditions. This change is considered more restrictive because additional Required Actions are required in the ITS that were not required in the CTS.

RELOCATED SPECIFICATIONS

None REMOVED DETAIL CHANGES

LA01 (Type 1 - Removing Details of System Design and System Description, Including Design Limits) CTS Table 3.3-1, "Reactor Trip System Instrumentation," includes three columns stating various requirements for the Source Range Neutron Flux Shutdown Function. These columns are labeled "TOTAL NO. OF CHANNELS," "CHANNELS TO TRIP," and "MINIMUM CHANNELS OPERABLE." For CTS Table 3.3.1 Functional Unit 6.B, the "CHANNELS TO TRIP COLUMN" is "0" (i.e., the Function is required to provide an indication only function and is not required to have a trip function). ITS 3.3.9 does not include the "TOTAL NO. OF CHANNELS" and "CHANNELS TO TRIP" columns. This changes the CTS by moving the information of the "TOTAL NO. OF CHANNELS" and "CHANNELS TO TRIP" columns to the Bases.

The removal of these details, which are related to system design, from the Technical Specifications, is acceptable because this type of information is not necessary to be included in the Technical Specifications to provide adequate protection of public health and safety. The ITS still retains the requirement for the number of required channels and the appropriate Condition to enter if a

required channel becomes inoperable. Also, this change is acceptable because the removed information will be adequately controlled in the ITS Bases.

Changes to the Bases are controlled by the Technical Specification Bases Control Program in Chapter 5. This program provides for the evaluation of changes to ensure the Bases are properly controlled. This change is designated as a less restrictive removal of detail change because information relating to system design is being removed from the Technical Specifications.

LA02 (Type 5 - Removal of SR Frequency to the Surveillance Frequency Control Program) CTS 4.3.1.1.1 requires that each reactor trip system instrumentation channel be demonstrated OPERABLE by performance of a CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST for the MODES and Frequencies shown in Table 4.3-1. CTS Table 4.3-1 Functional Unit 6 requires performance of a CHANNEL CHECK every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL CALIBRATION every refueling outage, and a CHANNEL FUNCTIONAL TEST every month for the source range neutron flux monitors during MODES 3, 4, and

5. ITS SR 3.3.9.1, SR 3.3.9.2, and SR 3.3.9.3 require similar Surveillances and specify the periodic Frequency as, "In accordance with the Surveillance Frequency Control Program." (See DOC M01 for the discussion on changing the , Volume 8, Rev. 0, Pa g e 1097 of 1148 , Volume 8, Rev. 0, Pa g e 1097 of 1148 DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 5 of 6 L02 (Category 7 - Relaxation of Surveillance Frequency)

CTS Table 4.3-1 Functional Unit 6 requires a CHANNEL FUNCTIONAL TEST of the Source Range Neutron Flux at startup if not performed within the previous 31 days. The ITS does not require the "during startup if not performed within the previous 31 days" test. This changes the CTS by deleting the requirement to perform the startup Surveillance on the Source Range Neutron Flux.

The purpose of a CHANNEL FUNCTIONAL TEST is to ensure the instrumentation is functioning properly. This change is acceptable because the normal periodic CHANNEL FUNCTIONAL TEST (See DOC M01 for discussion on changing the channel FUNCTIONAL TEST to a COT) Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. This change deletes the requirement to perform the startup Surveillance on the Source Range Neutron Flux channels. ITS SR 3.0.4 requires the periodic Surveillances to be performed and be current prior to entry

into the applicability. Once the applicable conditions are entered, the normal, periodic Surveillance Frequency provides adequate assurance of OPERABILITY.

Therefore, the removal of this Frequency is considered acceptable. This change

is designated as less restrictive because Surveillances will be performed less frequently under ITS than under the CTS.

L03 (Category 9 - Allowed Outage Time, Surveillance Frequency, and Bypass Time Extensions Based on Generic Topical Reports) CTS Table 4.3-1 requires a CHANNEL FUNCTIONAL TEST on a monthly bases (M) for Functional Unit 6 (Source Range Neutron Flux). ITS SR 3.3.9.2 requires performance of a COT every 184 days. (See DOC LA02 for discussion on relocating the Surveillance

Frequency to the Surveillance Frequency Control Program.) This changes the CTS by changing the frequency of the Surveillances from monthly to 184 days.

The purpose of the CHANNEL FUNCTIONAL TEST/COT is to ensure that the instrumentation is functioning properly. These changes are acceptable and are the result of WCAP-10271, Revision 0 ("Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System"), dated May 1996, and supplements, WCAP-14333, Revision 1 ("Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times"), dated October 1998, or WCAP-15376, Revision 1 ("Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and

Completion Times"), dated March 2003 (or a combination of the WCAPs). TVA has performed evaluations of the applicable changes associated with the three WCAPs to justify the above changes. The evaluations supporting these changes are provided in Enclosure 4 of this submittal. This change is designated as less restrictive because less stringent Frequencies are being applied in the ITS than

were applied in the CTS.

L04 (Category 7 - Relaxation Of Surveillance Frequency)

CTS Table 4.3-1, in part, requires a FUNCTIONAL TEST for Functional Unit 6.B (Source Range, Neutron Flux, Shutdown) in MODES 2, 3, 4, 5, and with the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. When in the required MODES, the FUNCTIONAL TEST is required to be performed on a monthly basis (M) and prior to startup (S/U) if not performed in the previous 31 days (Note (1)). ITS SR 3.3.9.2 requires a CHANNEL OPERATIONAL TEST , Volume 8, Rev. 0, Pa g e 1099 of 1148 , Volume 8, Rev. 0, Pa g e 1099 of 1148 DISCUSSION OF CHANGES ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 6 of 6 (COT) for the required Boron Dilution Monitoring Instrumentation (Source Range Neutron Flux Monitoring Channel) in MODE 3, 4, and 5. ITS SR 3.3.9.2 is

modified by a note stating, "Not required to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3." This changes the CTS by allowing for a delay in performance of the surveillance.

The purpose of the CTS FUNCTIONAL TEST for the Source Range Neutron Flux Function is to ensure the channel will perform the intended Function. This change is acceptable because the delay in surveillance performance is similar to

that allowed under SR 3.0.3 when it is determined a surveillance has been missed. The function of the Source Range Neutron flux monitoring channel is to provide the operators indication of a dilution accident with sufficient time for operator action to mitigate the accident (i.e., greater than 15 minutes). The addition of the Note allows a normal shutdown to proceed without a delay for testing in MODE 2 and for a short time in MODE 3 and prevents entry into Required Actions, which are probably unnecessary, should an unplanned reactor trip occur. ITS SR 3.3.9.3 requires a channel calibration of these instrument every 18 months. ITS SR 3.3.9.2 requires a COT performed on the required

channel every 184 days when in MODES 3, 4, or 5. ITS SR 3.3.9.1 requires a

CHANNEL CHECK be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODES 3, 4, or 5.

Before exiting MODE 6 and entering MODE 5 the required channel's testing must be current and maintained current until MODE 3 is exited and MODE 2 entered. Once in MODE 2 and then MODE 1, the instruments are no longer in their MODE of Applicability and in accordance with ITS SR 3.0.1 the surveillance requirements are not required to be meet. Entry into MODE 3 from MODE 2 without performance of SR 3.3.9.2 is similar to discovery of a Surveillance not being performed within its specified Frequency. Similarly, ITS SR 3.3.1.7 Note and ITS SR 3.0.3, under the condition of a missed surveillance, allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform surveillance requirements. In addition, the operators will be monitoring the source range nuclear instruments during the plant shutdown performing a qualitative assessment of the channel's behavior where any unusual behavior will be identified and evaluated. This change is designated as less restrictive because a Surveillance will be performed less frequently under the ITS than under the CTS. , Volume 8, Rev. 0, Pa g e 1100 of 1148 , Volume 8, Rev. 0, Pa g e 1100 of 1148 BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-1 Rev. 4.0 MICTS SEQUOYAH UNIT 1 Amendment XXX 5 13.3 INSTRUMENTATION 3.3.9 A Boron Dilution Protection System (BD PS) (Without Setpoint Control Program)

LCO 3.3.9 A Two t rains of the BDPS shall be OPERABLE.APPLICABILITY: MODES

[2,] 3, 4, and 5.---------------------------------------------NOTE--------------------------------------------

The boron dilution flux doubling signal may be blocked in MODE S 2 and 3 during reactor startup.



ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train inoperable. A.1 Restore train to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Two t rains inoperable.

OR Required Action and associated Completion Time of Condition A not met. B.1 --------------NOTE-------------- Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM. ------------------------------------- Suspend operations involving positive reactivity additions.

AND B.2.1 Restore one t rain to OPERABLE status. OR Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> One source range neutron flux monitoring channel MI3.3.1.1, Table 3.3-1 Function 6.B Applicability, Table 3.3-1 Function 6.B DOC M02 A One required channel Table 3.3-1 ACTION 5 DOC M02 Monitoring Instrumentation required channel 1 2 3 4 2 2 A A DOC M02 2high flux at shutdown alarm DOC L01 Enclosure 2, Volume 8, Rev. 0, Pa g e 1102 of 1148 , Volume 8, Rev. 0, Pa g e 1102 of 1148 DOC M02 DOC M02 Table 3.3-1 ACTION 5 DOC M02 9--------------NOTE--------------Plant temperature changes pg are allowed provided the p temperature change is pgaccounted for in the calculated SDM.


Suspend operations pp involving positive reactivity gp additions.

Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ANDrequired channel A 2 OR.2.1 Restore OPERABLE status.

to BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-2 Rev. 4.0 MICTS SEQUOYAH UNIT 1 Amendment XXX 5 1ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.2.2.1 Close unborated water source isolation valves. AND B.2.2.2 Perform SR 3.1.1.1.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK.

[ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance

Frequency Control Program

] SR 3.3.9.2 Perform COT.

[ [184] days OR In accordance with the Surveillance

Frequency

Control Program

] DOC M02 Table 3.3-1 ACTION 5 Table 4.3-1 Function 6 6 6 6 6 Table 4.3-1 Function 6, DOC M01, DOC L01 A A 2 2one combination of ------------------------------NOTE------------------------------- Not required to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 --------------------------------------------------------------------

DOC L04 7Initiate action to Immediately 4 Enclosure 2, Volume 8, Rev. 0, Pa g e 1103 of 1148 , Volume 8, Rev. 0, Pa g e 1103 of 1148 9 DOC M02Initiate action to A A AND Immediately 2 4.2.2.1 Close unborated water source isolation valves.

.2.2.2 ------------------------------NOTE-------------------------------Not required to be performed prior to entering MODE 3 qppgfrom MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 y--------------------------------------------------------------------

7 DOC L04 one combination of 2

BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-1 Rev. 4.0 MICTS SEQUOYAH UNIT 2 Amendment XXX 5 13.3 INSTRUMENTATION 3.3.9 A Boron Dilution Protection System (BD PS) (Without Setpoint Control Program)

LCO 3.3.9 A Two t rains of the BDPS shall be OPERABLE.APPLICABILITY: MODES

[2,] 3, 4, and 5.---------------------------------------------NOTE--------------------------------------------

The boron dilution flux doubling signal may be blocked in MODE S 2 and 3 during reactor startup.



ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train inoperable. A.1 Restore train to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Two t rains inoperable.

OR Required Action and associated Completion Time of Condition A not met. B.1 --------------NOTE-------------- Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM. ------------------------------------- Suspend operations involving positive reactivity additions.

AND B.2.1 Restore one t rain to OPERABLE status. OR Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> One source range neutron flux monitoring channel MI3.3.1.1, Table 3.3-1 Function 6.B Applicability, Table 3.3-1 Function 6.B DOC M02 A One required channel Table 3.3-1 ACTION 5 DOC M02 Monitoring Instrumentation required channel 1 2 3 4 2 2 A A DOC M02 2high flux at shutdown alarm DOC L01 Enclosure 2, Volume 8, Rev. 0, Pa g e 1105 of 1148 , Volume 8, Rev. 0, Pa g e 1105 of 1148 Table 3.3-1 ACTION 5 DOC M02 DOC M02 DOC M02--------------NOTE--------------Plant temperature changes pg are allowed provided the p temperature change is pgaccounted for in the calculated SDM.


Suspend operations pp involving positive reactivity gp additions.

Immediately 2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR A .2.1 AND OPERABLE status.

Restore to required channel 9

BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-2 Rev. 4.0 MICTS SEQUOYAH UNIT 2 Amendment XXX 5 1ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.2.2.1 Close unborated water source isolation valves. AND B.2.2.2 Perform SR 3.1.1.1.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK.

[ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance

Frequency Control Program

] SR 3.3.9.2 Perform COT.

[ [184] days OR In accordance with the Surveillance

Frequency

Control Program

] DOC M02 Table 3.3-1 ACTION 5 Table 4.3-1 Function 6 6 6 6 6 Table 4.3-1 Function 6, DOC M01, DOC L01 A A 2 2one combination of ------------------------------NOTE------------------------------- Not required to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 --------------------------------------------------------------------

DOC L04 7Initiate action to Immediately 4 Enclosure 2, Volume 8, Rev. 0, Pa g e 1106 of 1148 , Volume 8, Rev. 0, Pa g e 1106 of 1148 DOC M02Initiate action toone combination of Immediately 2 4 2.2.2.1 Close unborated water source isolation valves.

A A .2.2.2 AND 9 DOC L04 ------------------------------NOTE-------------------------------Not required to be performed prior to entering MODE 3 qppgfrom MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 y--------------------------------------------------------------------

7 JUSTIFICATION FOR DEVIATIONS ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION (BDMI) Sequoyah Unit 1 and Unit 2 Page 1 of 2 1. The type of Setpoint Control Program (Without Setpoint Control Program) and the Specification designator "A" are deleted since they are unnecessary. This information is provided in NUREG 1431, Rev. 4.0 to assist in identifying the appropriate Specification to be used as a model for the plant specific ITS conversion, but serves no purpose in the plant specific implementation. In addition, ISTS 3.3.9B (with Setpoint Control Program Specification) is not used and is not shown. Additionally, the title of the Specification has been changed from "Boron Dilution Protection System (BDPS)" to "Boron Dilution Monitoring Instrumentation (BDMI)"

since an actual "Protection System" does not exist at SQN.

2. ISTS 3.3.9A is not applicable to the SQN design or licensing bases. The BDPS as described in the ISTS is a two train system that provides automatic protection against boron dilution accidents by switching the charging pump suction to the RWST upon a specified high flux signal. Such a system is not part of the SQN plant

design. The SQN units rely on detection of the event and operator action to mitigate the accident in MODES 3, 4, and 5.

CTS 3.3.1.1, Reactor Trip System Instrumentation requires a single channel of source range instrumentation OPERABLE in MODES 3, 4, and 5. This requirement

provides the only TS required means to monitor core reactivity under the specified plant condition. The requirement includes MODE 3 where the monitoring function

serves as the only "required" means to detect a boron dilution event in progress. Although the source range channel does not actuate a system designed to mitigate a boron dilution event, it does provide the only TS required means of directly indicating neutron flux in the specified MODES. Therefore, the CTS Table 3.3-4 Functional Unit 6.B requirement for a single OPERABLE source range indication channel in MODES 3, 4, and 5 is being retained in ITS 3.3.9. The proposed LCO and ACTIONS have been changed to reflect the current requirement of one source range monitoring instrument channel to identify a possible boron dilution event.

3. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis.
4. ISTS 3.3.9A contains an Applicability Note which states that the boron dilution flux doubling signal may be blocked in MODES 2 and 3 during reactor startup. ITS 3.3.9

Applicability does not include MODE 2 and SQN does not have a boron dilution flux doubling signal but a High Flux at Shutdown alarm. Therefore, this information was changed to reflect the SQN design.

5. Changes are made (additions, deletions, and/or changes) to the ISTS that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description.
6. ISTS SR 3.3.9.1, SR 3.3.9.2 and SR 3.3.9.3 (ITS SR 3.3.9.1, SR 3.3.9.2 and SR 3.3.9.3) provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program.
7. A Note has been added to ISTS SR 3.3.9.2 similar to the Note included in ITS 3.3.1.7 to delay performance of the surveillance when entering MODE 3 from , Volume 8, Rev. 0, Pa g e 1108 of 1148 , Volume 8, Rev. 0, Pa g e 1108 of 1148 JUSTIFICATION FOR DEVIATIONS ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION (BDMI) Sequoyah Unit 1 and Unit 2 Page 2 of 2 MODE 2 allowing time for performed without entering the Required Actions for an inoperable required channel.
8. CTS Table 3.3.1 ACTION 5 is associated with Functional Unit 6.B (Source Range, Neutron Flux - Shutdown) and requires that with the number of Source Range channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. TVA proposes to add a requirement, under this condition, to

initiate action to one combination of unborated water source isolation valves immediately. This changes the ISTS requirements on closing the unborated water source isolation valve within one hour to initiating action to close one combination of unborated water source isolation valves immediately. This change from ISTS is justified because the CTS requirements are being retained and completion of the

closure of the required isolation valves is being performed in a reasonable time.

Requiring one hour for isolation of numerous isolation valves during a plant shutdown with shutdown margin confirmed and monitored is considered unnecessary. , Volume 8, Rev. 0, Pa g e 1109 of 1148 , Volume 8, Rev. 0, Pa g e 1109 of 1148 9.ISTS Required Actions B.1, B.2.1, and B.2.2.1 have been deleted. CTS does not require suspending operations involving positive reactivity, restoring one train to OPERABLE status, or closing unborated water source isolation valves when the

required source range neutron flux monitoring channel is inoperable. However, CTS

Table 3.3-1, ACTION 5 does require verifying compliance with SHUTDOWN MARGIN (SDM) requirements within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter when the

required source range neutron flux monitoring channel is inoperable. Therefore, ISTS

Required Action B.2.2.2 is retained as ITS Required Action A.1, which requires

performance of ITS SR 3.1.1.1 (Verify SDM to be within limits specified in the COLR)

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

BD PS (Without Setpoint Control Program)

B 3.3.9 A Westinghouse STS B 3.3.9 A-3 Rev. 4.0 MISEQUOYAH UNIT 1 Revision XXX 1 2 BASES ACTIONS (continued)

B.1, B.2.1, B.2.2.1, and B.2.2.2 With two t rains inoperable, or the Required Action and associated Completion Time of Condition A not met, the initial action (Required Action B.1) is to suspend all operations involving positive reactivity additions immediately. This includes withdrawal of control or shutdown rods and intentional boron dilution. A Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is provided to restore one train to OPERABLE status.

As an alternate to restoring one train to OPERABLE status (Required Action B.2.1), Required Action B.2.2.1 requires valves listed in LCO 3.9.2 (Required Action A.2) to be secured to prevent the flow of unborated water into the RCS. Once it is recognized that two t rains of the BD PS are inoperable, the operators will be aware of the possibility of a boron dilution, and the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Com pletion Time is adequate to complete the requirements of LCO 3.9.2.

Required Action B.2.2.2 accompanies Required Action B.2.2.1 to verify the SDM according to SR 3.1.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This backup action is intended to confirm that no unintended boron dilution has occurred while the BD PS was inoperable, and that the required SDM has been maintained. The specified Completion Time takes into consideration sufficient time for the initial determination of SDM and other information available in the control room related to SDM.

Required Action B.1 is modified by a Note which permits plant temperature changes provided the temperature change is accounted for in the calculated SDM. Introduction of temperature changes, including temperature increases when a positive MTC exists, must be evaluated to ensure they do not result in a loss of required SDM. SURVEILLANCE SR 3.3.9.1 REQUIREMENTS The BDPS trains are subject to a COT and a CHANNEL CALIBRATION.

Performance of the CHANNEL CHECK ensures that gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL

CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION. the required channelMI is MI 2 2 1 1 2 5 A A A A A 4 4 4 4 4the required channel the required channel 2 2in one of the required valve combinations A are required to immediately take action , Volume 8, Rev. 0, Pa g e 1116 of 1148 , Volume 8, Rev. 0, Pa g e 1116 of 1148requirestheverificationof B.2.2.2.2.2.1, and B221and B.2.1, B 21 B 1, B With the required channel inoperable, inoperablethe initial action (Required p Action B A .1) is to suspend all operations involving positive reactivity (q)ppgpyadditions immediately. This includes withdrawal of control or shutdown yrods and intentional boron dilution. A Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is provided to restorethe required channelto OPERABLE status.

pin one of the required valve combinations As an alternate to restoring to OPERABLE status (Required A B.2.2.1 requires valves listed in LCO 3.9.2 (q B.2.1), Required Action B21)RequiredAction g Action B (Required Action A.2) to be secured to prevent the flow of unborated q),q (q)pwater into the RCS. Once it is recognized that two t rains of the BD PS are ginoperable, the operators will be aware of the possibility of a boron pppydilution, and the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Com pletion Time is adequate to complete the requirements of LCO 3.9.2. the required channelMI is are required to immediately take action 2 2 4 2 1 Required Action B.1 is modified by a Note which permits plant qypptemperature changes provided the temperature change is accounted for pgppgin the calculated SDM. Introduction of temperature changes, includingpg,gtemperature increases when a positive MTC exists, must be evaluated to ppensure they do not result in a loss of required SDM.

A Required Action B.2.2.2 accompanies A B.2.2.to verify the q gbackup 4 5 4 2 BD PS (Without Setpoint Control Program)

B 3.3.9 A Westinghouse STS B 3.3.9 A-3 Rev. 4.0 MISEQUOYAH UNIT 2 Revision XXX 1 2 BASES ACTIONS (continued)

B.1, B.2.1, B.2.2.1, and B.2.2.2 With two t rains inoperable, or the Required Action and associated Completion Time of Condition A not met, the initial action (Required Action B.1) is to suspend all operations involving positive reactivity additions immediately. This includes withdrawal of control or shutdown rods and intentional boron dilution. A Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is provided to restore one train to OPERABLE status.

As an alternate to restoring one train to OPERABLE status (Required Action B.2.1), Required Action B.2.2.1 requires valves listed in LCO 3.9.2 (Required Action A.2) to be secured to prevent the flow of unborated water into the RCS. Once it is recognized that two t rains of the BD PS are inoperable, the operators will be aware of the possibility of a boron dilution, and the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is adequate to complete the requirements of LCO 3.9.2.

Required Action B.2.2.2 accompanies Required Action B.2.2.1 to verify the SDM according to SR 3.1.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This backup action is intended to confirm that no unintended boron dilution has occurred while the BD PS was inoperable, and that the required SDM has been maintained. The specified Completion Time takes into consideration sufficient time for the initial determination of SDM and other information available in the control room related to SDM.

Required Action B.1 is modified by a Note which permits plant temperature changes provided the temperature change is accounted for in the calculated SDM. Introduction of temperature changes, including temperature increases when a positive MTC exists, must be evaluated to ensure they do not result in a loss of required SDM. SURVEILLANCE SR 3.3.9.1 REQUIREMENTS The BDPS trains are subject to a COT and a CHANNEL CALIBRATION.

Performance of the CHANNEL CHECK ensures that gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL

CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION. the required channelMI is MI 2 2 1 1 2 5 A A A A A 4 4 4 4 4the required channel the required channel 2 2in one of the required valve combinations A are required to immediately take action , Volume 8, Rev. 0, Pa g e 1125 of 1148 , Volume 8, Rev. 0, Pa g e 1125 of 1148requirestheverificationof

.2.2.2.2.2.1, and B B.2.1, With the required channel inoperable, o inoperable o , the initial action (Required p (q Action B.1) is to suspend all operations involving positive reactivity)ppgpyadditions immediately. This includes withdrawal of control or shutdown yrods and intentional boron dilution. A Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is provided to restoreto OPERABLE status.

pthe required channel A in one of the required valve combinations 4 2 2 2 4 1 2 As an alternate to restoring to OPERABLE status (Required (q Action B.2.1), Required Action B.2.2.1 requires valves listed in LCO 3.9.2 B21)RequiredAction B g),q q (Required Action A.2) to be secured to prevent the flow of unborated (q)pwater into the RCS. Once it is recognized that two t rains of the BD PS are ginoperable, the operators will be aware of the possibility of a boron pppydilution, and the 1hour Completion Time is adequate to complete the requirements of LCO 3.9.2.

A MI is the required channelare required to immediately take action Required Action B.2.2.2 accompanies A .2.2.1 to verify gbackup a Required Action B.1 is modified by a Note which permits plant qypptemperature changes provided the temperature change is accounted for pgppgin the calculated SDM. Introduction of temperature changes, includingpg,gtemperature increases when a positive MTC exists, must be evaluated to ppensure they do not result in a loss of required SDM.

A 5 4 JUSTIFICATION FOR DEVIATIONS ITS 3.3.9 BASES, BORON DILUTION MONITORING INSTRUMENTATION (BDMI) Sequoyah Unit 1 and Unit 2 Page 1 of 1 1. The type of Setpoint Control Program (Without Setpoint Control Program) and the Specification designator "A" are deleted since they are unnecessary. This information is provided in NUREG 1431, Rev. 4.0 to assist in identifying the appropriate Bases to be used as a model for the plant specific ITS conversion, but

serves no purpose in the plant specific implementation. In addition, ISTS B 3.3.9B (with Setpoint Control Program Specification) is not used and is not shown. Additionally, the title of the Bases has been changed from "Boron Dilution Protection System (BDPS)" to "Boron Dilution Monitoring Instrumentation (BDMI)" since an actual "Protection System" does not exist at SQN.

2. Changes are made (additions, deletions, and/or changes) to the ISTS Bases that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description.
3. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis.
4. Changes have been made to be consistent with changes made to the Specification.
5. The paragraph has been moved to after the discussion on Required Action B.1 since the Note is associated with Required Action B.1.
6. Typographical/grammatical error corrected.
7. ISTS SR 3.3.9.1, SR 3.3.9.2 and SR 3.3.9.3 Bases provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program. Additionally, the Frequency description which is being removed will be included in the Surveillance Frequency Control Program.
8. The Reviewer's Note has been deleted. This information is for the NRC reviewer to be keyed into what is needed to meet this requirement. This Note is not meant to be retained in the final version of the plant specific submittal. , Volume 8, Rev. 0, Pa g e 1129 of 1148 , Volume 8, Rev. 0, Pa g e 1129 of 1148 Licensee Response/NRC Response/NRC Question Closure Id334NRC Question Number KAB049Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 9/15/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 9/15/2014 10:29 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 9/17/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 89 NRC Question Number KAB050Category EditorialITS Section 3.3ITS Number 3.3.9DOC Number JFD Number 2JFD Bases Number Page Number(s) 1108 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested N NRC Question On page 1108 of Enclosure 2, Volume 8, JFD 2 discusses on ly Sequoyah Unit 1 CTS 3.3.1.1 and states, "Therefore, the CTS Table 3.

3-4 Functional Unit 6.B requirement for a single OPERABLE source range indication channel in MODES 3, 4, and 5 is being retained in ITS 3.3.9.However, JFD 2 is used in the Sequoyah Unit 2 ITS 3.3.9 mark up.In addition, CTS Table 3.3-4 is ESFAS instrumentation setpoints and functional unit 6.

b is the Auxiliary Feedwater automatic actuation logic.Please provide a correction to JFD 2 so that it is accurate, or explain the discrepancies.Attach File 1 Attach File 2 Issue Date 5/23/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 2:51 PMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew Hon Lynn Mynatt Ray Schiele Roger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 105NRC Question Number KAB050Select Application Licensee Response Attachment 1 3.3.9 revised JFD 2.pdf (13KB)Attachment 2 Response Statement In response to KAB050, ju stification for deviation (JFD) 2, on page 1108 of Enclosure 2, Volume 8, will be revised.Specifically, additional text will be added to the CTS 3.3.1.1 reference to read, "CTS 3.3.1.1 (Unit 1) and CTS 3.1.1 (Unit 2)."Additionally, the reference to CT S Table 3.3-4 will be revised to reference CTS Table 3.3-1.

See Attachment 1 for a draft revised JFD 2.Response Date/Time 6/6/2014 6:50 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanDate Added 6/6/2014 5:50 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/26/201 4htt p s://members.excelservices.com/rai/index.

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JUSTIFICATION FOR DEVIATIONS ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION (BDMI)

Sequoyah Unit 1 and Unit 2 Page 1 of 2 1. The type of Setpoint Control Program (Without Setpoint Control Program) and the Specification designator "A" are deleted since they are unnecessary. This information is provided in NUREG 1431, Rev. 4.0 to assist in identifying the appropriate Specification to be used as a model for the plant specific ITS conversion, but serves no purpose in the plant specific implementation. In addition, ISTS 3.3.9B (with Setpoint Control Program Specification) is not used and is not shown. Additionally, the title of the Specification has been changed from "Boron Dilution Protection System (BDPS)" to "Boron Dilu tion Monitoring Instrumentation (BDMI)"

since an actual "Protection System" does not exist at SQN.

2. ISTS 3.3.9A is not applicable to the SQN design or licensing bases. The BDPS as described in the ISTS is a two train system that provides automatic protection against boron dilution accidents by switching the charging pump suction to the RWST upon a specified high flux signal. Such a system is not part of the SQN plant design. The SQN units rely on detection of the event and operator action to mitigate the accident in MODES 3, 4, and 5.

CTS 3.3.1.1, Reactor Trip System Instrumentation requires a single channel of source range instrumentation OPERABLE in MODES 3, 4, and 5. This requirement provides the only TS required means to monitor core reactivity under the specified plant condition. The requirement includes MODE 3 where the monitoring function serves as the only "required" means to detect a boron dilution event in progress. Although the source range channel does not actuate a system designed to mitigate a boron dilution event, it does provide the only TS required means of directly indicating neutron flux in the specified MODES. Therefore, the CTS Table 3.3-4 Functional Unit 6.B requirement for a single OPERABLE source range indication channel in MODES 3, 4, and 5 is being retained in ITS 3.3.9. The proposed LCO and ACTIONS have been changed to reflect the current requirement of one source range monitoring instrument channel to identify a possible boron dilution event.

3. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis.
4. ISTS 3.3.9A contains an Applicability Note which states that the boron dilution flux doubling signal may be blocked in MODES 2 and 3 during reactor startup. ITS 3.3.9 Applicability does not include MODE 2 and SQN does not have a boron dilution flux doubling signal but a High Flux at Shutdown alarm. Therefore, this information was changed to reflect the SQN design.
5. Changes are made (additions, deletions, and/or changes) to the ISTS that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description.
6. ISTS SR 3.3.9.1, SR 3.3.9.2 and SR 3.3.9.3 (ITS SR 3.3.9.1, SR 3.3.9.2 and SR 3.3.9.3) provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program.
7. A Note has been added to ISTS SR 3.3.9.2 similar to the Note included in ITS 3.3.1.7 to delay performance of the surveillance when entering MODE 3 from Licensee Response/NRC Response/NRC Question Closure Id118NRC Question Number KAB050Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:03 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=118 ITS NRC Questions Id 90NRC Question Number KAB051 Category EditorialITS Section 3.3ITS Number 3.3.9DOC Number JFD Number JFD Bases Number 8Page Number(s) 1109NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 1109 of Enclosure 2, Volume 8, JFD 8 discusses the changes to ITS 3.3.9 required action A.2.2.1 wording. However, JFD 8 is not referenced in the ITS 3.3.9 mark ups for Sequoyah unit 1 or 2.

Please explain this discrepancy.

Attach File 1 Attach File 2 Issue Date 5/23/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 2:52 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=90 Licensee Response/NRC Response/NRC Question Closure Id109 NRC Question Number KAB051Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.9 revised ISTS markups.pdf (39KB)Attachment 2 Response Statement In response to KAB051, the ISTS markups for SQN, Units 1 and 2, on pages 1103 and 1106 of Enclosure 2, Volume 8, will be revised.S pecifically, the justification for deviation (JFD) indicator in the righ t hand margin will be revised to reference JFD 8 vice JFD 4.JFD 4 is associated with the deviation to the ISTS Applicability Note and is not the correct reference for a deviation associated wi th ISTS Required Action B.2.2.1 (ITS Required Action A.2.2.1).This was a typographical error.

During review of JFD 8, the following issue was identified.The sentence, "TVA proposes to add a requirement, under this condition, to initiate action to one combinat ion of unborated water source isolation valves immediately."should be revised to read, "TVA proposes to add a requirement, under this condition, to initiate action to close one combination of unborated water sour ce isolation valv es immediately."See Attachment 1 for the draft revised ISTS markups for Units 1 and 2 and JFD 8.Response Date/Time 6/6/2014 11:25 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/6/2014 10:21 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-2 Rev. 4.0 MICTS SEQUOYAH UNIT 1 Amendment XXX 5 1ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.2.1 Close unborated water source isolation valves.

AND B.2.2.2 Perform SR 3.1.1.1.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK.

[ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.9.2 Perform COT.

[ [184] days OR In accordance with the Surveillance

Frequency

Control Program

] DOC M02 Table 3.3-1 ACTION 5 Table 4.3-1 Function 6 6 6 6 6 Table 4.3-1 Function 6, DOC M01, DOC L01 A A 2 2one combination of ------------------------------NOTE------------------------------- Not required to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 --------------------------------------------------------------------

DOC L04 7Initiate action to Immediately 4

BD PS (Without Setpoint Control Program) 3.3.9 A Westinghouse STS 3.3.9 A-2 Rev. 4.0 MICTS SEQUOYAH UNIT 2 Amendment XXX 5 1ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.2.1 Close unborated water source isolation valves.

AND B.2.2.2 Perform SR 3.1.1.1.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK.

[ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance

with the Surveillance

Frequency Control Program

] SR 3.3.9.2 Perform COT.

[ [184] days OR In accordance with the Surveillance

Frequency

Control Program

] DOC M02 Table 3.3-1 ACTION 5 Table 4.3-1 Function 6 6 6 6 6 Table 4.3-1 Function 6, DOC M01, DOC L01 A A 2 2one combination of ------------------------------NOTE------------------------------- Not required to be performed prior to entering MODE 3 from MODE 2 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into MODE 3 --------------------------------------------------------------------

DOC L04 7Initiate action to Immediately 4

JUSTIFICATION FOR DEVIATIONS ITS 3.3.9, BORON DILUTION MONITORING INSTRUMENTATION (BDMI)

Sequoyah Unit 1 and Unit 2 Page 2 of 2 MODE 2 allowing time for performed without entering the Required Actions for an inoperable required channel.

8. CTS Table 3.3.1 ACTION 5 is associated with Functional Unit 6.B (Source Range, Neutron Flux - Shutdown) and requires that with the number of Source Range channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. TVA proposes to add a requirement, under this condition, to initiate action to one combination of unborated water source isolation valves immediately. This changes the ISTS requirements on closing the unborated water source isolation valve within one hour to initiating action to close one combination of unborated water source isolation valves immediately. This change from ISTS is justified because the CTS requirements are being retained and completion of the closure of the required isolation valves is being performed in a reasonable time.

Requiring one hour for isolation of numerous isolation valves during a plant shutdown with shutdown margin confirmed and monitored is considered unnecessary.

Licensee Response/NRC Response/NRC Question Closure Id120NRC Question Number KAB051Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:33 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=120 ITS NRC Questions Id 91NRC Question Number KAB052 Category TechnicalITS Section 3.3 ITS Number 3.3.9DOC Number JFD Number 8JFD Bases Number Page Number(s) 1109NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On page 1109 of Enclosure 2, Volume 8, JFD 8 discusses the changes to ITS 3.3.9 required action A.2.2.1 wording.JFD 8 states, "Requiring one hour for isol ation of numerous isolation valves during a plant shutdo wn with shutdown margin confirmed and monitored is considered unnecessary."ITS Condition B is entered when al l source range channels are inoperable.Please explain how shutdown margin is

monitored when both source range channels are inoperable.Attach File 1 Attach File 2 Issue Date 5/23/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/23/2014 2:54 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=91 Licensee Response/NRC Response/NRC Question Closure Id 110NRC Question Number KAB052 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement ITS 3.3.9, "Boron Dilution Monitoring Instrumentation (BDMI),"requires that one Source Range Monitor shall be OPERABLE in Modes 3, 4, and 5. If two source range neutron flux monitors are inoperable, ITS Required Action A.2.2.2 requires performanc e of SR 3.1.1.1 within one hour and e very twelve hours thereafter.ITS SR 3.1.1.1 is satisfied by the performance of Surveillance Instruction, 0-SI-NUC-000-038.0, Shutdown Margin.

0-SI-NUC-000-038.0 provides detailed steps to verify and/or calculate sufficient Shutdown Margin (SDM) during unit operat ion in Modes 1 through 6. SDM is monitored by performance of 0-SI-NUC-000-038.0 until at least one source range neutron flux moni tor is returned to operable status.

Boron, xenon, inverse boron worth, core bur n up, temperature, and RHR flow are some of the factors used to ensure that SDM remains within technical specification limits. The fact ors utilized in the SDM calculation depend on reactor conditions at the time of the calculations. 0-SI-NUC-000-038.0 includes calculations for the different core conditions present at the time the calculation is performed.Response Date/Time 6/6/2014 11:25 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott BowmanDate Added 6/6/2014 10:24 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=110 Licensee Response/NRC Response/NRC Question Closure Id121NRC Question Number KAB052Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:39 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=121 ITS NRC Questions Id 92NRC Question Number KAB053 Category TechnicalITS Section 3.3ITS Number 3.3.1DOC Number JFD Number JFD Bases Number Page Number(s) 127, 159NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On pages 127 and 159 of En closure 2, Volume 8, ITS Table 3.3.1-1 Note 2 states, " 4 [*] sec"and " 5 [*] sec."However, CTS Table 2.2-1 Note 2 states, " 4 , 5 = as defined in Note 1,"and Note 1 states, " 4 , 5 = Time constants utilized in the lead-lag controller for T, 4 5 secs, 5 3 secs."Please explain this discrepancy.

Attach File 1 Attach File 2 Issue Date 5/27/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/27/2014 1:00 PMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id195NRC Question Number KAB053 Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.1 Note 2 KAB053.pdf (92KB)Attachment 2 Response Statement In response to KAB053, the ISTS Markups for Note 2: Overpower T time constants 4 and 5 on pages 127 and 159 of Enclosure 2, Volume 8, are incorrect and will be revised.Speci fically, ITS Table 3.3.1-1 Note 2:

Overpower T will be changed to reflect CTS such that the ISTS markup will show 4 [*] sec and 5 [*] sec.See Attachment 1 for draft revised ISTS markups for Units 1 and 2.Response Date/Time 7/21/2014 8:00 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay Schiele Added By Scott BowmanDate Added 7/21/2014 6:54 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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RTS Instrumentation (Without Setpoint Control Program) 3.3.1 A Westinghouse STS 3.3.1 A-24 Rev. 4.0 CTS Amendment XXXSequoyah Unit 1 1 1 2Table 3.3.1-1 (page 8 of 8) Reactor Trip System Instrumentation

Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following

[Nominal Trip Setpoint

] by more than

[3]% of T span.

++++++)(1 1 1 1 1 1 1)1()1(2 6 6 6 7 754 3 2 1IfTSTTKTSTSTSTKKTSTSTST T Q Where: T is measured RCS T,°F. T Q is the indicated T at RTP,°F. s is the Laplace transform operator, sec

-1. T is the measured RCS average temperature,°F.

T" is the nominal Tavg at RTP, [*]°F. K 4 [*] K 5 [*]/°F for increasing Tavg K 6 [*]/°F when T > T

"

[*]/°F for decreasing Tavg [*]/°F when T T" T 1 [*] sec T 2 [*] sec T 3 [*] sec T 6 [*] sec T 7 [*] sec f 2 (I) = [*] *These values denoted with

[*] are specified in the COLR.

Table 2.2-1 1.7 INSERT 8 INSERT 9 INSERT 11Note 2 Note 4 Note 5 3 2 2 2 2 INSERT 10 * (including QPNL, QPPL, QPNS, and QPPS) 3 3 RTS Instrumentation (Without Setpoint Control Program) 3.3.1 A Westinghouse STS 3.3.1 A-24 Rev. 4.0 CTS Amendment XXXSequoyah Unit 2 1 1 2Table 3.3.1-1 (page 8 of 8) Reactor Trip System Instrumentation

Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following

[Nominal Trip Setpoint

] by more than

[3]% of T span.

++++++)(1 1 1 1 1 1 1)1()1(2 6 6 6 7 754 3 2 1IfTSTTKTSTSTSTKKTSTSTST T Q Where: T is measured RCS T,°F. T Q is the indicated T at RTP,°F. s is the Laplace transform operator, sec

-1. T is the measured RCS average temperature,°F.

T" is the nominal Tavg at RTP, [*]°F. K 4 [*] K 5 [*]/°F for increasing Tavg K 6 [*]/°F when T > T

"

[*]/°F for decreasing Tavg [*]/°F when T T" T 1 [*] sec T 2 [*] sec T 3 [*] sec T 6 [*] sec T 7 [*] sec f 2 (I) = [*] *These values denoted with

[*] are specified in the COLR.

Table 2.2-1 1.7 INSERT 8 INSERT 9 INSERT 11Note 2 Note 4 Note 5 3 2 2 2 2 INSERT 10 * (including QPNL, QPPL, QPNS, and QPPS) 3 3 Licensee Response/NRC Response/NRC Question Closure Id203NRC Question Number KAB053Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/22/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/22/2014 7:52 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 109NRC Question Number KAB054Category EditorialITS Section 3.3ITS Number 3.3.1DOC Number JFD Number JFD Bases Number 9Page Number(s) 321 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On page 321 of Enclosure 2, Volume 8, JFD 9 discusses the surveillance frequency control program.However, JFD 9 states:

ISTS SR 3.3.1.1 through ISTS 3.3.16 (ITS SR 3.3.1.1 through ITS 3.1.14) -Therefore, the Frequency for ITS

SR 3.3.1.1 through ITS 3.3.1.14 is "I n accordance with the Surveillance Frequency Control Program."However, ISTS does not contain a LCO 3.3.16, nor does ITS have a LCO 3.1.14. ISTS 3.3.1 does have a surveillance requirement 3.3.1.16 and ITS has a surveillance requirement 3.3.1.14. Please correct JFD 9 to reference ISTS SR 3.3.1.16 and ITS SR 3.3.1.14 or explain why ISTS 3.3.16 and ITS 3.1.14 ar e the correct references.Attach File 1 Attach File 2 Issue Date 5/30/2014Added By Kristy BucholtzDate Modified Modified By Date Added 5/30/2014 8:33 AMNotification Scott BowmanMichelle Conner Khadijah Hemphill Andrew Hon Lynn Mynatt Ray Schiele Roger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id126 NRC Question Number KAB054Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.1 revised JFD 9.pdf (897KB)Attachment 2 Response Statement In response to KAB054, justification for deviation (JFD) 9, on page 321 of Enclosure 2, Volume 8, will be revised.Additionally, duri ng review it was identified that ISTS SR 3.3.1.15 a nd ITS SR 3.3.1.13 do not provide an option for controlling the Frequency "In accordance with the Surveillance Frequency Control Program."Therefore, JFD 9 will be revised to read, "ISTS SR 3.3.1.1 through ISTS SR 3.

3.1.14 and ISTS SR 3.3.1.16 (ITS SR 3.3.1.1 through ITS SR 3.

3.1.12 and ITS SR 3.3.1.14) provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program. Therefore, the Fre quency for ITS SR 3.3.1.1 through ITS SR 3.3.1.12 and ITS SR 3.3.1.14 is 'In accordance with the Surveillance Frequency Control Program.'"See Attachment 1 for a draft revised JFD 9.Response Date/Time 6/17/2014 1:30 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/17/2014 12:26 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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JUSTIFICATION FOR DEVIATIONS ITS 3.3.1 BASES, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 1 1. NUREG 1431, Standard Technical Specificat ions - Westinghouse Plants, Revision 4.0 provides two sets of specification for Section 3.3.1; one for adoption "Without a Setpoint Control Program," (3.3.1.A) the other for adoption "With a Setpoint Control Program," (3.3.1.B). This information is provided in NUREG-1431, Rev. 4.0, to assist in identifying the appropriate Specification to be used as a model for the plant specific ITS conversion, but serves no purpose in a plant specific implementation and is removed. 2. Changes are made (additions, deletions, and/or changes) to the ISTS Bases that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description. Where a deletion has occurred, subsequent alpha-numeric designators have been changed for any applicable affected ACTIONS, SURVEILLANCE REQUIREMENTS, FUNCTIONS, and Footnotes. 3. The Reviewer's Note has been deleted. This information is for the NRC reviewer to be keyed into what is needed to meet this requirement. This Note is not meant to be retained in the final version of the plant specific submittal. 4. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis. 5. Editorial changes made for enhanced clarity. 6. Proposed changes to the CTS removed details of system design and system description, including design limits stating that the removed detail will be located in the bases for the specification. These changes are made to be consistent with changes made to the Specification. 7. Changes are made to be consistent with changes made to the Specification. 8. SQN source could not be found to support this statement, therefore it is removed.

9. ISTS SR 3.3.1.1 through ISTS 3.3.16 (ITS SR 3.3.1.1 through ITS 3.1.14) provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program. Therefore, the Frequency for ITS SR 3.3.1.1 through ITS 3.3.1.14 is "In accordance with the Surv eillance Frequency Control Program."

Licensee Response/NRC Response/NRC Question Closure Id128NRC Question Number KAB054Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/18/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/18/2014 1:05 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=128 ITS NRC Questions Id 110NRC Question Number KAB055 Category TechnicalITS Section 3.3 ITS Number 3.3.1DOC Number JFD Number JFD Bases Number 9Page Number(s) 188, 266NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 188 and 266 of Enclosure 2, Volume 8, a reference is made to JFD 9 for deletion of a sentence in the pressurize r water level high discussion. JFD 9 discusses the surveillance frequency cont rol program. Please explain why JFD 9 applies since this change was not part of TSTF-425. Attach File 1 Attach File 2 Issue Date 5/30/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 5/30/2014 8:35 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=110 Licensee Response/NRC Response/NRC Question Closure Id190 NRC Question Number KAB055Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.1 Bases JFD 8.pdf (26KB)Attachment 2 Response Statement In response to KAB055, the ISTS 3.3.1 Bases for Units 1 and 2, on pages 188 and 266 of Enclosure 2, Volume 8, where reference is made to justification for deviation (JFD) 9 fo r the deletion of a sentence in the pressurizer water level hi gh discussion, will be revised.Specifically, ITS JFD 9 will be changed to JFD 8.JFD 8 states, "SQN sour ce could not be found to support this statemen t, therefore it is removed."

JFD 9 discusses the option for contro lling Surveillance Frequencies under the Surveillance Frequency Control Program and is not applicable to this deletion of information from the ISTS Bases.See Attachment 1 for draft revised ISTS Bases markups for Units 1 and 2.Response Date/Time 7/17/2014 5:15 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 7/17/2014 4:13 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=190 RTS Instrumentation (Without Setpoint Control Program)

B 3.3.1 A Westinghouse STS B 3.3.1 A-19 Rev. 4.0 SEQUOYAH UNIT 1 Revision XXX 1 2 1BASES

APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

The Pressurizer Pressure - High LSSS is selected to be below the pressurizer safety valve actuation pressure and above the power operated relief valve (PORV) setting. This setting minimizes challenges to safety valves while avoiding unnecessary reactor trip for those pressure increases that can be controlled by the PORVs.

In MODE 1 or 2, the Pressurizer Pressure - High trip must be OPERABLE to help prevent RCS overpressurization and minimize challenges to the relief and safety valves. In MODE 3, 4, 5, or 6, the Pressurizer Pressure - High trip Function does not have to be OPERABLE because transients that could cause an overpressure condition will be slow to occur. Therefore, the

operator will have sufficient time to evaluate unit conditions and take corrective actions. Additionally, low temperature overpressure protection systems provide overpressure protection when below MODE 4.

9. Pressurizer Water Level - High The Pressurizer Water Level - High trip Function provides a backup signal for the Pressurizer Pressure - High trip and also provides protection against water relief through the pressurizer safety valves. These valves are designed to pass steam in order to achieve their design energy removal rate. A reactor trip is actuated prior to the pressurizer becoming water solid. The LCO requires three channels

of Pressurizer Water Level - High to be OPERABLE. The pressurizer level channels are used as input to the Pressurizer Level Control System. A fourth channel is not required to address control/protection interaction concerns. The level channels do not actuate the safety valves, and the high pressure reactor trip is set below the safety valve setting. Therefore, with the slow rate of charging available, pressure overshoot due to level channel failure cannot cause the safety valve to lift before reactor high pressure trip.

In MODE 1, when there is a potential for overfilling the pressurizer, the Pressurizer Water Level - High trip must be OPERABLE. This trip Function is automatically enabled on increasing power by the P-7 interlock. On decreasing power, this trip Function is automatically blocked below P-7.

Below the P

-7 setpoint, transients that could raise the pressurizer water level will be slow and the operator will have sufficient time to evaluate unit conditions and take corrective actions. There are three Pressurizer Level - High channels arranged in a two-out-of-three logic.

6 9 RTS Instrumentation (Without Setpoint Control Program)

B 3.3.1 A Westinghouse STS B 3.3.1 A-19 Rev. 4.0 SEQUOYAH UNIT 2 Revision XXX 1 2 1BASES

APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

The Pressurizer Pressure - High LSSS is selected to be below the pressurizer safety valve actuation pressure and above the power operated relief valve (PORV) setting. This setting minimizes challenges to safety valves while avoiding unnecessary reactor trip for those pressure increases that can be controlled by the PORVs.

In MODE 1 or 2, the Pressurizer Pressure - High trip must be OPERABLE to help prevent RCS overpressurization and minimize challenges to the relief and safety valves. In MODE 3, 4, 5, or 6, the Pressurizer Pressure - High trip Function does not have to be OPERABLE because transients that could cause an overpressure condition will be slow to occur. Therefore, the

operator will have sufficient time to evaluate unit conditions and take corrective actions. Additionally, low temperature overpressure protection systems provide overpressure protection when below MODE 4.

9. Pressurizer Water Level - High The Pressurizer Water Level - High trip Function provides a backup signal for the Pressurizer Pressure - High trip and also provides protection against water relief through the pressurizer safety valves. These valves are designed to pass steam in order to achieve their design energy removal rate. A reactor trip is actuated prior to the pressurizer becoming water solid. The LCO requires three channels

of Pressurizer Water Level - High to be OPERABLE. The pressurizer level channels are used as input to the Pressurizer Level Control System. A fourth channel is not required to address control/protection interaction concerns. The level channels do not actuate the safety valves, and the high pressure reactor trip is set below the safety valve setting. Therefore, with the slow rate of charging available, pressure overshoot due to level channel failure cannot cause the safety valve to lift before reactor high pressure trip.

In MODE 1, when there is a potential for overfilling the pressurizer, the Pressurizer Water Level - High trip must be OPERABLE. This trip Function is automatically enabled on increasing power by the P-7 interlock. On decreasing power, this trip Function is automatically blocked below P-7.

Below the P

-7 setpoint, transients that could raise the pressurizer water level will be slow and the operator will have sufficient time to evaluate unit conditions and take corrective actions. There are three Pressurizer Level - High channels arranged in a two-out-of-three logic.

6 9 Licensee Response/NRC Response/NRC Question Closure Id193NRC Question Number KAB055Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/17/2014 7:21 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id129 NRC Question Number KAB056 Category EditorialITS Section 3.3ITS Number 3.3.2DOC Number JFD Number JFD Bases Number 8Page Number(s) 675 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested N NRC Question On page 675 of Enclosure 2, Volume 8, JFD 8 discusses the surveillance frequency control program.However, JFD 8 states:

ISTS SR 3.3.2.1 through ISTS 3.3.2.11 (ITS SR 3.3.2.1 through ITS 3.3.2.10) -Therefore, the Frequency for ITS SR 3.3.

2.1 through ITS 3.3.2.10 is "In accordance with the Surveillance Frequency Control Program."However, ISTS does not contain a LCO 3.3.2.11, nor does ITS have a LCO 3.3.2.10. ISTS 3.3.2 does have a surveillance requirement 3.3.2.11 and ITS has a surveillance requirement 3.3.2.10. Please correct JFD 8 to reference ISTS SR 3.3.2.11 and ITS SR 3.3.2.10 or explain why ISTS 3.3.2.11 and ITS 3.3.2.10 are the correct references.

Attach File 1 Attach File 2 Issue Date 6/3/2014Added By Kristy BucholtzDate Modified Modified By Date Added 6/3/2014 9:17 AMNotification Scott BowmanPage 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Michelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id127 NRC Question Number KAB056 Select Application Licensee Response Attachment 1 Attachment 1 3.3.2 revised Bases JFD.pdf (28KB)Attachment 2 Response Statement In response to KAB056, justification fo r deviation (JFD) 8, on page 675 of Enclosure 2, Volume 8, will be revised.Additionally, during review it was identified that ISTS SR 3.3.2.11 and ITS SR 3.3.2.10 do not provide an option for controlling the Frequency "In accordance with the Surveillance Frequency Control Program."Therefore, the sentence, "ISTS SR 3.3.2.1 through ISTS 3.3.2.11 (ITS SR 3.3.2.

1 through ITS 3.3.

2.10) provide two options for controlling th e Frequencies of Surveillance Requirements."will be revised to read, "IST S SR 3.3.2.1 through ISTS SR 3.3.2.10 (ITS SR 3.3.2.1 through ITS SR 3.

3.2.9) provide two opti ons for controlling the Frequencies of Surveillance Requirements."Based on the issue identified during revi ew, the final senten ce of JFD 8 will be revised to read, "Therefore, the Frequency for ITS SR 3.3.2.1 through ITS SR 3.3.2.9 is "In accordance with the Surveillance Frequency Control Program.""See Attachment 1 for a draft revised JFD 8.Response Date/Time 6/17/2014 1:30 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 6/17/2014 12:29 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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JUSTIFICATION FOR DEVIATIONS ITS 3.3.2 BASES, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 1 of 1 1. NUREG 1431, Standard Technical Specificat ions - Westinghouse Plants, Revision 4.0 provides two sets of specification for Section 3.3.2; one for adoption "Without a Setpoint Control Program," (3.3.2.A) the other for adoption "With a Setpoint Control Program," (3.3.2.B). This information is provided in NUREG-1431, Rev. 4.0, to assist in identifying the appropriate Specification to be used as a model for the plant specific ITS conversion, but serves no purpose in a plant specific implementation and is removed. 2. Changes are made (additions, deletions, and/or changes) to the ISTS Bases that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description. Where a deletion has occurred, subsequent alpha-numeric designators have been changed for any applicable affected ACTIONS, SURVEILLANCE REQUIREMENTS, FUNCTIONS, and Footnotes. 3. The Reviewer's Note has been deleted. This information is for the NRC reviewer to be keyed into what is needed to meet this requirement. This Note is not meant to be retained in the final version of the plant specific submittal. 4. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis. 5. Changes are made to be consistent with changes made to the Specification. 6. Editorial changes are made for clarity.

7. Changes made to explain the basis for the Note added to the Required Actions consistent with NRC approval contained in SQN License Amendment 319/312, reference ADAMS Accession Nos. ML082401385 and ML082401446. 8. ISTS SR 3.3.2.1 through ISTS 3.3.2.11 (ITS SR 3.3.2.1 through ITS 3.3.2.10) provide two options for controlling the Frequencies of Surveillance Requirements. SQN is proposing to control the Surveillance Frequencies under the Surveillance Frequency Control Program. Therefore, the Frequency for ITS SR 3.3.2.1 through ITS 3.3.2.10 is "In accordance with the Surveillance Frequency Control Program."

Licensee Response/NRC Response/NRC Question Closure Id129NRC Question Number KAB056Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/18/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/18/2014 1:05 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 130NRC Question Number KAB057Category TechnicalITS Section 3.3 ITS Number 3.3.2DOC Number JFD Number JFD Bases Number Page Number(s) 474, 508, 591, 669NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 474, 508, 591 and 669 of Enclosure 2, Volume 8, footnotes (b) and (c) have been deleted from ISTS SR 3.3.2.8 (ITS SR 3.3.2.7) and a paragraph that discusses the TSTF-493 notes (b) and (c) has been deleted from SR 3.3.2.8 bases. ISTS SR 3.3.2.8 (ITS SR 3.3.2.7) is a trip actuating devi ce operational test as applied to the trip of all main feedwater pumps. Please remove the proposed changes or explain why the TSTF-493 footnotes are not applicab le to the trip of all main feedwater pumps, and include a discussion of the TSTF-493 exclusion criteria if it is applicable.Attach File 1 Attach File 2 Issue Date 6/3/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 6/3/2014 9:19 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=130 Licensee Response/NRC Response/NRC Question Closure Id 205NRC Question Number KAB057 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement ITS SR 3.3.2.7 (ISTS SR 3.3.2.8) requires performa nce of a Trip Actuating Device Operational Test (TADOT).ITS SR 3.3.2.7 is applicable to ITS Table 3.3.2-1 Functions 1.a (Saf ety Injection - Manual Init iation), 2.a (Containment Spray - Manual Initiation), 3.a.(1) (Containment Isolation, Phase A Isolation -

Manual Initiation), 3.b.(1) (Containment Isolation, Phase B Isolation - Manual Initiation), 4.a (Steam Line Isolation - Manual Initiation), and 6.e (Auxiliary Feedwater - Trip of all Main Feedwater Pumps).None of these Functions have an Allowable Value or a Nominal Trip Se tpoint listed, but rather list these values as NA.The Allo wable Value and Nominal Trip Setpoint for ITS Function 6.e (Auxiliary Feedwater - Trip of all Main Feedwater Pumps) is "NA." This is consistent with CTS Functional Unit 6.f (Auxiliary Feedwater -Trip of Main Feedwater Pumps).Therefore, no Functions associated with ITS SR 3.3.2.7 have an associated Allowable Value or Nominal Trip Setpoint, to which Footno tes (b) and (c) relate.ITS Table 3.3.2-1 Footnotes (b) and (c) describe actions to take when the as-found channel setpoint is outside it s predefined as-found tolerance or cannot be reset to within the as-left tolerance around the Nominal Trip Setpoint.Because ITS Function 6.e's (Auxiliary Feedwater - Trip of all Main Feedwater Pumps) Allowable Value and Nominal Trip Se tpoint values are listed as "NA," Footnotes (b) and (c) do not apply as with no listed value there is no as-found or as-left tolerance.In addition, because there are no Functions associated with ITS SR 3.3.2.7 where F ootnote (b) or (c) are applied, the information associated with these footnotes in the Bases was deleted.In addition, TSTF-493-A, Rev.4, states that all Func tions in the affected specifications were included unless one or more of the following exclusions apply, then lists three exclusions.Of these three exclusions, the first exclusion applies.The discussion for the first exclusion states that the two Notes are not applied to Functions which utilize mechanical components to sense the trip setpoint, or to manual initiation circuits (the latter are not explicitly modeled in the accident analysis) because current functional Surveillance Requirements, which have no setpoint verifications, adequately demonstrate the OPERABILITY of these functions.As stated above for this function, current functional Surveillance Requirements, which have no setpoint, ad equately demonstrate th e OPERABILITY of this Page 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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function.The TSTF-493 exclusion discussion also states that while it may be possible to verify a limit switch functi ons at a point of travel (similar to the pressure switch in this instance) a change in the surveillance results probably indicates that the switch has moved, not that the input/output relationship has changed.In this instance verifying the state of the mechanical device (i.e., open or closed pressure switch) when the pump is running and when the pum p is tripped, adequate ly demonstrates the OPERABILITY of the function.Response Date/Time 7/22/2014 11:45 PM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 7/22/2014 10:41 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id210NRC Question Number KAB057Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/23/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/23/2014 11:45 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=210 ITS NRC Questions Id 131NRC Question Number KAB058 Category Technical ITS Section 3.3 ITS Number 3.3.3 DOC Number JFD Number JFD Bases Number Page Number(s) 736, 737, 760, 761NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 736, 737, 760 and 761 of Enclosure 2, Volume 8, the bases for TS 3.3.3 states that the reactor coolant T h and T cold , containment pressure wide range, and containment pressure narrow range channe ls provide indication over a range of 0° F to 700°F, -5 to 60 psig, and -1 to 15psig respectively.

However, Sequoyah's UFSAR states that the minimum range for reactor coolant T h and T cold is from 50, the range for containment pressure wide rang e is -4.7 to 48 psig, and the range for containment pressure narrow range is -1 to 13 psig. Please explain why the bases do not match the UFSAR.Attach File 1 Attach File 2 Issue Date 6/3/2014Added By Kristy BucholtzDate Modified Modified By Date Added 6/3/2014 2:09 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=131 Licensee Response/NRC Response/NRC Question Closure Id 163NRC Question Number KAB058 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement In response to KAB058, the following information is provided to explain why the ITS 3.3.3 Bases and the SQN UFSAR do not match for the reactor coolant Thot and Tcold, containment pressure wide range, and containment pressure narrow rang e channels range.

SQN UFSAR Section 7.5, Safety-Related Display In strumentation for Post Accident Monitoring (PAM), includes Table 7.5-2, which lists the process information required at the initiation of an accident, during the course of an accident, and until the unit is in cold shutdown following an accident.UFSAR Section 7.5.2.3.1, Display Requirements, states that PAM parameters have associated required accident ranges and that the minimum required ranges are given in Table7.5-2.SQN UFSAR Table 7.5-2, Table of Variables for Post Accident Monitoring, lists the necessary PAM variable and provides columns stating the variable's Type/Category, Minimum Range From, Minimum Rang e To, Redundancy Required, and Notes.SQN UFSAR Table 7.5-2, Sheet 8 lists the "RCS Co ld Leg Water Temp" and the "RCS Hot Leg Water Temp" vari ables as requiring a "Minimum Range From" of 50 with a "Minimum Range To" of 700 Deg F.SQN ITS Bases associated with the RCS Hot and Cold Leg Water Temperature variables lists the actual range of the instruments from 0 to 700°F.The range of RCS Cold and Hot Leg Temperature instru ments provides an indication range equal to or greater than that listed in UFSAR Table 7.5-2.

SQN UFSAR Table 7.5-2, Sheet 3 lists the "Containment Pressure (WR)" variable as requiring a "Minimum Range From" of -4.7 PSIG with a "Minimum Range To" of 48 PSIG.SQN ITS Bases associated with the Containment Pressure (Wide Range) variable lists the actual range of the instruments from -5 to 60 psig.The range of the Containment Pressure (Wide Range) instruments provides an indication range equa l to or greater than that listed in UFSAR Table 7.5-2.

SQN UFSAR Table 7.5-2, Sheet 3 lists the "Containment Pressure (NR)" variable as requiring a "Minimum Ra nge From" of -1 with a "Minimum Range To" of 13 PSIG.SQN ITS Bases associated with the Containment Page 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Pressure (Narrow Range) variable lists the actual range of the instruments from -1 to 15 psig.The range of the Containment Pressure (Narrow Range) instruments provides an indication range equal to or greater than that listed in UFSAR Table 7.5-2.

Therefore, the ITS Bases do not match the SQN UFSAR because the UFSAR lists the "Minimum Range From" and "Minimum Range To" values, whereas, the Bases lists the instruments actual range.Response Date/Time 6/30/2014 1:20 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonCarl SchultenAdded By Scott BowmanDate Added 6/30/2014 12:19 PMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id170NRC Question Number KAB058Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/2/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/2/2014 3:16 PMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=170 ITS NRC Questions Id 132NRC Question Number KAB059Category TechnicalITS Section 3.3 ITS Number 3.3.3DOC Number JFD Number JFD Bases Number Page Number(s) 739, 763NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 739 and 763 of Enclosure 2, Volume 8, the bases for TS 3.3.3 states that the auxiliary feedwater flow channels pr ovide indication over a range of 0 to 440 gpm. However, Sequoyah's UFSAR states that the range for auxiliary feedwater flow 0 to 242 gpm. Please explain why the bases do not match the UFSAR.Attach File 1 Attach File 2 Issue Date 6/3/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 6/3/2014 2:10 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 206NRC Question Number KAB059 Select Application Licensee ResponseAttachment 1 Attachment 2 Response Statement In response to KAB059, the following information is provided to explain why the ITS 3.3.3 Bases do not match the SQN UFSAR for the auxiliary feedwater (AFW) flow channels'range.

SQN UFSAR Section 7.5, Safety-Related Display In strumentation for Post Accident Monitoring (PAM), includes Table 7.5-2, which lists the process information required at the initiation of an accident, during the course of an accident, and until the unit is in cold shutdown following an accident.UFSAR Section 7.5.2.3.1, Display Requirements, states that PAM parameters have associated required accident ranges and that the minimum required ranges are given in Table7.5-2.SQN UFSAR Table 7.5-2, Table of Variables for Post Accident Monitoring, lists the necessary PAM variable and provides columns stating the variable's Type/Category, Minimum Range From, Minimum Rang e To, Redundancy Required, and Notes.SQN UFSAR Table 7.5-2, Sheet 1 lists the "AFW Flow" variable as requiring a "Minimum Range From" as 0 with a "Minimum Range To" as 242 GPM.SQN ITS Bases associated with the AFW Flow variable lists the actual range of the instruments from 0 to 440 gpm.This range of AFW Flow provides indication range equal to or greater than that listed in UFSAR Table 7.5-2.

Therefore, the ITS Bases do not match the UFSAR because the UFSAR lists the "Minimum Range From" and "Minimum Range To" values, whereas, the Bases lists the instruments actual range.Response Date/Time 7/22/2014 11:45 PMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillPage 1of 2 Sequoyah ITS Conversion Databas e 8/26/201 4htt p s://members.excelservices.com/rai/index.

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Andrew HonRay SchieleAdded By Scott BowmanDate Added 7/22/2014 10:44 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/26/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id211NRC Question Number KAB059Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/23/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/23/2014 11:46 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=211 ITS NRC Questions Id 133NRC Question Number KAB060Category Technical ITS Section 3.3 ITS Number 3.3.3DOC Number JFD Number JFD Bases Number Page Number(s) 741, 765NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 741 and 765 of Enclosure 2, Volume 8, the bases for TS 3.3.3 states that the neutron flux channels provide indication over a range of 1 to 10 6 cps source range and 10

-8 to 200% RTP intermediate range. However, Sequoyah's UFSAR states that the range for neutron flux is 1E-6 % to 100 %. Please explain why the bases do not match the UFSAR.Attach File 1 Attach File 2 Issue Date 6/3/2014Added By Kristy BucholtzDate Modified Modified By Date Added 6/3/2014 2:11 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id207 NRC Question Number KAB060Select Application Licensee Response Attachment 1 Attachment 2 Response Statement In response to KAB060, the following information is provided to explain why the ITS 3.3.3 Bases do not match the SQN UFSAR for the neutron flux channels'range.SQN UFSAR Section 7.5, Safety-Related Display Instrumentation for Post Accident Monitoring (PA M), includes Table 7.5-2, which lists the process information required at the initiation of an accident, during the course of an accident, and until the unit is in cold shutdown following an accident.

UFSAR Section 7.5.2.3.1, Display Requirements, states that PAM parameters have associated required accident ranges and that the minimum required ranges are given in Table7.5-2.UFSAR also states that where two or more instruments are needed to cove r a particular range, overlapping of instrument spans have been provided to ensure one of the two instruments will be on scale at all times.SQN UFSAR Table 7.5-2, Table of Variables for Po st Accident Monitoring, list the necessary PAM variable and provides columns stati ng the variable's Type/Category, Minimum Range From, Minimum Range To, Redundancy Required, and Notes.SQN UFSAR Table 7.5-2, Sheet 5 lists the "Neu tron Flux Monitoring" variable as requiring a "Min imum Range From" of 1E

-6% with a "Minimum Range To" of 100% (Full PWR).SQN ITS Bases associated with the Neutron Flux variable lists the actua l range of the instruments with the Source Range as 1 to 10 6 CPS and the Intermediate Range 10

-8 to 200% RTP.This range of neutron flux monitoring channels provides an indication range equal to or greater th an that listed in UFSAR Table 7.5-2.

Therefore, the ITS Bases do not match the SQN UFSAR because the UFSAR lists the "Minimum Range From" and "Minimum Range To" values, whereas, the Bases lists the instruments actual range.Response Date/Time 7/22/2014 11:50 PMClosure Statement Question Closure Page 1of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 7/22/2014 10:47 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id212NRC Question Number KAB060Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 7/23/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 7/23/2014 11:47 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id135NRC Question Number KAB061 Category TechnicalITS Section 3.3 ITS Number 3.3.7 DOC Number JFD Number JFD Bases Number Page Number(s) 1012, 1024NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add Name Conf Call Requested NNRC Question On pages 1012 and 1024 of Enclosure 2, Vo lume 8, the reference to WCAP 15376, Rev. 0, October 2000, has been deleted. WCAP-15376 and TSTF-411 added ISTS

SR 3.3.7.5 and SR 3.3.7.6. ITS proposes to delete ISTS SR 3.3.7.3 and SR 3.3.7.4 and proposes utilize ISTS SR 3.3.7.5 and SR 3.3.7.6. Since ITS is utilizing ISTS SR 3.3.7.5 and SR 3.3.7.6, which is provide by WCAP

-15376, it is appropriate to list WCAP-15376 as a reference. Add WCAP-15376 as a reference to TS 3.3.7 bases or remove ISTS SR 3.3.7.5 and SR 3.3.7.6 from ITS and add ISTS SR 3.3.7.3 and SR 3.3.7.4 to ITS.Attach File 1 Attach File 2 Issue Date 6/4/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 6/4/2014 6:40 AMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id111NRC Question Number KAB061 Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.7 revised ISTS Bases pages.pdf (23KB)Attachment 2 Response Statement In response to KAB061, the ISTS Bases, Reference Section markup, on pages 1012 and 1024 of En closure 2, Volume 8, will be revised.Specifically, ITS will re tain the Reference, WCAP

-15376, Rev.0, October 2000, for ITS Bases 3.3.7.

See Attachment 1 for draft revised ISTS Bases markups for Units 1 and 2.Response Date/Time 6/6/2014 11:30 AMClosure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay Schiele Added By Scott Bowman Date Added 6/6/2014 10:27 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/26/201 4htt p s://members.excelservices.com/rai/index.

p h p?re q uestT yp e=areaItemPrint&itemId=111 CRE FS Actuation Instrumentation (Without Setpoint Control Program)

B 3.3.7 A Westinghouse STS B 3.3.7 A-12 Rev. 4.0 1 V Revision XXXSEQUOYAH UNIT 1 BASES

SURVEILLANCE REQUIREMENTS (continued)


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

REFERENCES

1. WCAP-15376, Rev. 0, October 2000.

7 5 None CRE FS Actuation Instrumentation (Without Setpoint Control Program)

B 3.3.7 A Westinghouse STS B 3.3.7 A-12 Rev. 4.0 1 V Revision XXXSEQUOYAH UNIT 2 BASES

SURVEILLANCE REQUIREMENTS (continued)


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

REFERENCES

1. WCAP-15376, Rev. 0, October 2000.

7 5 None Licensee Response/NRC Response/NRC Question Closure Id122NRC Question Number KAB061Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:42 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id 136NRC Question Number KAB062 Category EditorialITS Section 3.3ITS Number 3.3.8DOC Number JFD Number JFD Bases Number Page Number(s) 1063, 1074NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question On pages 1063 and 1074 of Enclosure 2, Volume 8, under the discussion of Condition B a change is made to add the words, "one reqired."However, required is misspelled.Plea se provide a correction. Attach File 1 Attach File 2 Issue Date 6/4/2014Added By Kristy BucholtzDate Modified Modified By Date Added 6/4/2014 1:00 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 112NRC Question Number KAB062Select Application Licensee Response Attachment 1 3.3.8 revised ISTS Bases.pdf (29KB)Attachment 2 Response Statement In response to KAB062, the ISTS Bases ACTIONS mark up, on pages 1063 and 1074 of Enclosure 2, Volume 8, will be revised.Specifically, the insert, "one reqired,"in ISTS ACTION B.1.1, B.1.2, B.2 (ITS ACTION B.1 and B.2) description will be revised to read, "one required."

See Attachment 1 for the draft revised ISTS Bases pages for Units 1 and 2.Response Date/Time 6/6/2014 11:30 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle Conner Khadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/6/2014 10:29 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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FBACS Actuation Instrumentation (Without Setpoint Control Program)

B 3.3.8 A Westinghouse STS B 3.3.8 A-4 Rev. 4.0 1ABGTS Revision XXX SEQUOYAH UNIT 1 4 1BASES ACTIONS (continued) A second Note has been added to the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.8-1 in the accompanying LCO. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

A.1 Condition A applies to the actuation logic train function of the Solid State Protection System (SSPS

), the radiation monitor functions, and the manual function. Condition A applies to the failure of a single actuation logic train, radiation monitor channel, or manual channel. If one channel or train is inoperable, a period of 7 days is allowed to restore it to OPERABLE status. If the train cannot be restored to OPERABLE status, one FBACS train must be placed in operation. This accomplishes the actuation instrumentation function and places the unit in a conservative mode of operation. The 7 day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this time is the same as that provided in LCO 3.7.

13. B.1.1 , B.1.2 , B.2 Condition B applies to the failure of two FBACS actuation logic trains, two radiation monitor s , or two manual channels. The Required Action is to place one FBACS train in operation immediately. This accomplishes the actuation instrumentation function that may have been lost and places the unit in a conservative mode of operation. The applicable Conditions and

Required Actions of LCO 3.7.

13 must also be entered for the FBACS train made inoperable by the inoperable actuation instrumentation. This ensures appropriate limits are placed on train inoperability as discussed in the Bases for LCO 3.7.

13. Alternatively, both trains may be placed in the emergency [radiation protection] mode. This ensures the FBACS Function is performed even in the presence of a single failure.

ABGTS 12 ABGTS ABGTS 12 12 1 3 5 1 1 3 3 5 and 5 5channel one reqired FBACS Actuation Instrumentation (Without Setpoint Control Program)

B 3.3.8 A Westinghouse STS B 3.3.8 A-4 Rev. 4.0 1ABGTS Revision XXX SEQUOYAH UNIT 2 4 1BASES

ACTIONS (continued)

A second Note has been added to the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.8-1 in the accompanying LCO. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

A.1 Condition A applies to the actuation logic train function of the Solid State Protection System (SSPS

), the radiation monitor functions, and the manual function. Condition A applies to the failure of a single actuation logic train, radiation monitor channel, or manual channel. If one channel or train is inoperable, a period of 7 days is allowed to restore it to OPERABLE status. If the train cannot be restored to OPERABLE status, one FBACS train must be placed in operation. This accomplishes the actuation instrumentation function and places the unit in a conservative mode of operation. The 7 day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this time is the same as that provided in LCO 3.7.

13.

B.1.1 , B.1.2 , B.2 Condition B applies to the failure of two FBACS actuation logic trains, two radiation monitor s , or two manual channels. The Required Action is to place one FBACS train in operation immediately. This accomplishes the actuation instrumentation function that may have been lost and places the unit in a conservative mode of operation. The applicable Conditions and

Required Actions of LCO 3.7.

13 must also be entered for the FBACS train made inoperable by the inoperable actuation instrumentation. This ensures appropriate limits are placed on train inoperability as discussed in the Bases for LCO 3.7.

13.

Alternatively, both trains may be placed in the emergency [radiation protection] mode. This ensures the FBACS Function is performed even in the presence of a single failure.

ABGTS 12 ABGTS ABGTS 12 12 1 3 5 1 1 3 3 5 and 5 5channel one reqired Licensee Response/NRC Response/NRC Question Closure Id123NRC Question Number KAB062Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:44 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id137 NRC Question Number KAB063 Category TechnicalITS Section 3.3ITS Number 3.3.9DOC Number JFD Number JFD Bases Number Page Number(s) 1118, 1127 NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested N NRC Question On pages 1118 and 1127 of Enclosure 2, Volume 8, the reference to WCAP 15376, Rev. 0, October 2000, has been deleted.WCAP-15376 and TSTF-411 changed the surveillance frequency for ISTS SR 3.3.9.2 to 184 days.ITS proposes to utilize ISTS SR 3.3.9.2.Since ITS is utilizing IS TS SR 3.3.9.2 with the frequency of 184 days, which is provide by WCAP-15376, it is appropriate to list WCAP-15376 as a reference.Add WCAP-15376 as a referenc e to TS 3.3.9 bases or remove the surveillance frequency changes pr ovided by WCAP-15376 from ITS SR 3.3.9.

Attach File 1 Attach File 2 Issue Date 6/4/2014Added By Kristy BucholtzDate Modified Modified By Date Added 6/4/2014 1:01 PMNotification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 115NRC Question Number KAB063 Select Application Licensee ResponseAttachment 1 Attachment 1 3.3.9 revised ISTS Bases pages.pdf (38KB)Attachment 2 Response Statement In response to KAB063, the ISTS Bases, Reference Se ction markup, on pages 1118 and 1127 of En closure 2, Volume 8, will be revised.Specifically, ITS will retain the Reference, WCAP

-15376, Rev.0, October 2000.See Attachment 1 for draft revised IS TS Bases markups for Units 1 and 2.Response Date/Time 6/12/2014 4:55 AM Closure Statement Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonRay SchieleAdded By Scott Bowman Date Added 6/12/2014 3:52 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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BD PS (Without Setpoint Control Program)

B 3.3.9 A Westinghouse STS B 3.3.9 A-5 Rev. 4.0 MIRevision XXX 1 2BASES

SURVEILLANCE REQUIREMENTS (continued)

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

SR 3.3.9.3 SR 3.3.9.3 is the performance of a CHANNEL CALIBRATION.

CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor except the neutron detector of the SRM circuit. There is a plant specific program which verifies that the instrument channel functions as required by verifying and as-left and as-found setting are consistent with those established by the setpoint methodology. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

For the BDPS, the CHANNEL CALIBRATION shall include verification that on a simulated or actual boron dilution flux doubling signal the centrifugal charging pump suction valves from the RWST open, and the normal CVCS volume control tank discharge valves close in the required closure time of 20 seconds. [ The Frequency of 18 months is based on operating experience and consistency with the typical industry refueling cycle.

OR The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

REFERENCES 1. FSAR, Chapter [15]. 2. WCAP-15376, Revision 0, October 2000.

U Section 2.4 8 2 7 8 2 2 3 2 INSERT 6SEQUOYAH UNIT 1 Revision XXX BD PS (Without Setpoint Control Program)

B 3.3.9 A Westinghouse STS B 3.3.9 A-5 Rev. 4.0 MIRevision XXX 1 2BASES

SURVEILLANCE REQUIREMENTS (continued)

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

SR 3.3.9.3 SR 3.3.9.3 is the performance of a CHANNEL CALIBRATION.

CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor except the neutron detector of the SRM circuit. There is a plant specific program which verifies that the instrument channel functions as required by verifying and as-left and as-found setting are consistent with those established by the setpoint methodology. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

For the BDPS, the CHANNEL CALIBRATION shall include verification that on a simulated or actual boron dilution flux doubling signal the centrifugal charging pump suction valves from the RWST open, and the normal CVCS volume control tank discharge valves close in the required closure time of 20 seconds. [ The Frequency of 18 months is based on operating experience and consistency with the typical industry refueling cycle.

OR The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.


REVIEWER'S NOTE-----------------------------------

Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.


]

REFERENCES 1. FSAR, Chapter [15]. 2. WCAP-15376, Revision 0, October 2000.

U Section 2.4 8 2 7 8 2 2 3 2 INSERT 6SEQUOYAH UNIT 2 Revision XXX Licensee Response/NRC Response/NRC Question Closure Id124NRC Question Number KAB063Select Application NRC Question ClosureAttachment 1 Attachment 2 Response Statement Response Date/Time Closure Statement This question is closed and no further information is required at this time to draft the Safety Evaluation.Question Closure Date 6/17/2014Notification Scott BowmanMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay SchieleRoger ScottAdded By Kristy Bucholtz Date Added 6/17/2014 9:50 AMDate Modified Modified By Page 1of 1 Sequoyah ITS Conversion Databas e 8/21/201 4htt p s://members.excelservices.com/rai/index.

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ITS NRC Questions Id167NRC Question Number KAB064 Category TechnicalITS Section 3.3ITS Number DOC Number JFD Number JFD Bases Number Page Number(s) NRC Reviewer Supervisor Rob ElliottTechnical Branch POC Add NameConf Call Requested NNRC Question For Sequoyah's CTS that are converting to ITS Section 3.3, explain if Administrative Letter 98-10 is currently being applied to any of these CTS. For each application of Administrative Letter 98-10 provide a technical evaluation for the NRC staff to review and explain how it is being corrected in the ITS.

Attach File 1 Attach File 2 Issue Date 6/19/2014 Added By Kristy BucholtzDate Modified Modified By Date Added 6/19/2014 7:16 AMNotification Scott BowmanMichelle Conner Khadijah HemphillAndrew Hon Lynn MynattRay SchieleRoger ScottPage 1of 1 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Licensee Response/NRC Response/NRC Question Closure Id 362NRC Question Number KAB064 Select Application Licensee ResponseAttachment 1 Attachment 1 for KAB064.pdf (137KB)Attachment 2 Attachment 2 for KAB064 from EDMS.pdf (15MB)Response Statement SQN is currently contro lling the reactor coolan t pump (RCP) undervoltage trip allowable value (AV) and the RC P underfrequency setpoint and AV under administrative controls, as described in Administrative Letter 98-10, to ensure adequate performance of the reactor protection system.

Changes to the RCP underfrequency and underv oltage values were previously proposed in SQN license amendment request (LAR) TVA-SQN-TS-02-01, Revision 1 (M L042430467), but later withdrawn in TVA-SQN-TS-02-01, Revision 2 (ML061990303) pending resolu tion of issues with Technical Specification Task Force (TSTF)-493, which at the time was under NRC review.

The original ITS submit tal contains the change s required for the RCP underfrequency setpoint and AV, and a technical evaluati on was previously submitted.NRC questions associated with the technical evaluation for this change are being addr essed in RAI KAB065.

Regarding the RCP unde rvoltage AV, ITS Tabl e 3.3.1-1, Function 11 (Undervoltage RCPs), on pages 119 and 151 of Enclosure 2, Volume 8, will be revised to indicate an AV of 4952 V.Additionally, the following changes will be necessary:1.The CTS markups for CT S Table 2.2-1, Functional Unit 15 (Undervoltage-Reactor Coolant Pumps) will be revised to re flect the revised AV.(pages 22 and 46)2.A new Discussion of Change (DOC) M25 will be a dded, as well as, DOC M25 indicators, to justif y the more restrictive change to CTS.(pages 22, 46, and 76)

See Attachment 1 for th e draft revised CTS and ISTS markups and new DOC M25.See Attachment 2 for the technical evaluation associated with the change to the RCP undervoltage AV.Response Date/Time 9/30/2014 8:50 AMClosure Statement Page 1of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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Question Closure Date Notification Scott BowmanKristy BucholtzMichelle ConnerKhadijah HemphillAndrew HonLynn MynattRay Schiele Added By Scott BowmanDate Added 9/30/2014 7:45 AMDate Modified Modified By Page 2of 2 Sequoyah ITS Conversion Databas e 1/13/201 5htt p s://members.excelservices.com/rai/index.

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ITS A01 ITS 3.3.1 TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRU MENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

14. Deleted
15. Undervoltage-Reactor 5022 volts-each bus 4739 volts-each bus Coolant Pumps
16. Underfrequency-Reactor 56.0 Hz - each bus 55.9 Hz - each bus Coolant Pumps
17. Turbine Trip A. Low Trip System 45 psig 39.5 psig Pressure B. Turbine Stop Valve 1% open 1% open Closure
18. Safety Injection Input from ESF Not Applicable Not Applicable 19. Intermediate Range Neutron 1 x 10

-4% of RATED THERMAL 6 x 10-5% of RATED Flux - (P-6) Enable Block Source Range Reactor Trip POWER THERMAL POWER 20. Power Range Neutron Flux 10% of RATED THERMAL 12.4% of RATED (not P-10) Input to Low Power Reactor Trips Block P

-7 POWER THERMAL POWER

September 20, 2007 SEQUOYAH - UNIT 1 2-6a Amendment No. 16, 85, 136, 141, 307, 310, 316 11 12 14 15 16.a 16.e Page 18 of 47Table 3.3.1-1 LA07 A21 57.056.3 M24 ITS A01 ITS 3.3.1 TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRU MENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

b. RCS Loop T Equivalent to Power > 50% RTP Coincident with Steam Generator Water 15.0% of narrow range 14.4% of narrow range Level -- Low-Low (Adverse) instrument span instrument span and Containment Pressure (EAM) 0.5 psig 0.6 psig or Steam Generator Water 10.7% of narrow range 10.1% of narrow range Level -- Low-Low (EAM) instrument span instrument 14. Deleted
15. Undervoltage-Reactor 5022 volts-each bus 4739 volts - each bus Coolant Pumps
16. Underfrequency-Reactor 56.0 Hz - each bus 55.9 Hz - each bus Coolant Pumps
17. Turbine Trip A. Low Trip System 45 psig 39.5 psig Pressure B. Turbine Stop Valve 1% open > 1% open Closure 18. Safety Injection Input from Not Applicable Not Applicable ESF

September 20, 2007 SEQUOYAH - UNIT 2 2-7 Amendment Nos. 7, 76, 132, 296, 299, 306 Page 42 of 47 11 12 14 14.a 14.b 15 Table 3.3.1-1 57.056.3 M24 DISCUSSION OF CHANGES ITS 3.3.1, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION Sequoyah Unit 1 and Unit 2 Page 25 of 45 requirements to ensure that the automatic protective action will correct the abnormal situation before a safety limit is exceeded. This change is consistent with TSTF-493 Option A. This change is considered a more restrictive change because additional requirements have been added to Surveillance Requirements.

M24 CTS Table 2.2-1 for Functional Unit 16 (Underfrequency-Reactor Coolant Pumps) lists the Nominal Trip Setpoint as 56.0 Hz - each bus, and the Allowable Value as 55.9 Hz - each bus. ITS Table 3.3.1-1 for Function 12 (Underfrequency RCPs) lists the Nominal Trip Setpoint as 57.0 Hz and the

Allowable Value as 56.3 Hz. This changes the CTS by increasing the Nominal Trip Setpoint and the Allowable Value for the Underfrequency RCP reactor trip.

The purpose of the Underfrequency RCP reactor trip is to ensure that protection is provided against violating the DNBR limit due to a loss of flow in two or more RCS loops from a major network frequency disturbance. TVA has determined that to provide adequate protection changes to the Underfrequency RCP Nominal Trip Setpoint and the Allowable Value are needed. This change was previously proposed in SQN license amendment request TVA-SQN-TS-02-01, Revision 1 (ADAMS Accession No. 042430467) but later withdrawn in TVA-SQN-TS-02-01, Revision 2 (ADAMS Accession No. ML061990303) pending resolution of issues with TSTF-493. In Revision 2 TVA stated that a new TS amendment request would be submitted to the NRC once TSTF-493 receives NRC approval. As TSTF-493 has been approved by the NRC and is being adopted under this conversion, TVA is proposing to change the setpoints to those proposed in the previous submittal. This change is acceptable because the revised Allowable Value and Nominal Trip Setpoint continue to provide assurance that the safety limit for the underfrequency reactor trip function is not impacted. In addition, this change ensures instrument uncertainties have been included in the as-found tolerance calculations in a manner that is acceptable and the surveillance Note requirements also ensure that there will be a reasonable expectation that these instruments will perform their safety function if required. This change is designated as more restrictive because more stringent acceptance requirements are being applied in the ITS than were applied in the CTS.

RELOCATED SPECIFICATIONS None

REMOVED DETAIL CHANGES

LA01 (Type 5 - Removal of SR Frequency to the Surveillance Frequency Control Program) The proposed change removes all designated periodic Surveillance Frequencies from CTS 4.3.1.1.1, as addressed in CTS Table 4.3-1, CTS 4.3.1.1.2, and CTS 4.3.1.1.3, and places the Frequencies under licensee control in accordance with a new program, the Surveillance Frequency Control Program.

ITS 3.3.1 Surveillance Requirements require similar Surveillances and, except for special or conditional frequencies stated in the individual surveillance, specifies the periodic Frequency as, "In accordance with the Surveillance Frequency M25 CTS Table 2.2-1 for Functional Unit 15 (Undervoltage-Reactor Coolant Pumps) lists the Allowable Value as 4739 volts - each bus. ITS Table 3.3.1-1 for Function 11 (Undervoltage RCPs) lists the Allowable Value as 4952 volts. This changes the CTS by increasing the Allowable Value for the Undervoltage RCP reactor trip.

The purpose of the Undervoltage RCP reactor trip is to ensure that protection is provided against violating the DNBR limit due to a loss of flow in two or more RCS loops. TVA has determined that to provide adequate protection, a change to the Undervoltage Allowable Value is needed. This change was previously proposed in SQN license amendment request TVA-SQN-TS-02-01, Revision 1 (ADAMS Accession No. ML042430467) but later withdrawn in TVA-SQN-TS- 02-01, Revision 2 (ADAMS Accession No. ML061990303)

pending resolution of issues with TSTF-493. In Revision 2, TVA stated that a new license amendment request would be submitted to the NRC once TSTF-493 received NRC approval. TSTF-493 has since been approved by the NRC and is being adopted under this conversion. Therefore, TVA is proposing to change the Undervoltage RCPs Allowable Value to those proposed in the previous submittal. This change is acceptable because the revised Allowable Value continues to provide assurance that the safety limit for the undervoltage reactor trip function is not impacted. In addition, this change ensures instrument uncertainties have been included in the as-found tolerance calculations in a manner that is acceptable and the surveillance Note requirements also ensure that there will be a reasonable expectation that these instruments will perform their safety function if required. This change is designated as more restrictive because more stringent acceptance requirements are being applied in the ITS than were applied in

the CTS.

RTS Instrumentation (Without Setpoint Control Program) 3.3.1 A Westinghouse STS 3.3.1 A-19 Rev. 4.0 CTS Amendment XXXSequoyah Unit 1 1 1 2Table 3.3.1-1 (page 3 of 8) Reactor Trip System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 8. Pressurizer Pressure

a. Low 1 (h) [4] K SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [1886] psig [1900] psig
b. High 1,2 [4] E SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [2396] psig [2385] psig
9. Pressurizer Water Level - High 1 (g) 3 K SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR3.3.1.10(b)(c) [93.8]% [92]% 10. Reactor Coolant Flow - Low 1 (g) 3 per loopK SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [89.2]% [90]%
11. Reactor Coolant Pump (RCP) Breaker Position
a. Single Loop 1 (h) 1 per RCP L SR 3.3.1.14 NA NA
b. Two Loops 1 (i) 1 per RCP M SR 3.3.1.14 NA NA 12. Undervoltage RCPs 1 (g) [3] per busK SR 3.3.1.9 SR 3.3.1.10(b)(c)SR 3.3.1.16 [4760] V [4830] V (b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than t he NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveilla nce procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference]. (g) Above the P-7 (Low Power Reactor Trips Block) interlock.

(h) Above the P

-8 (Power Range Neutron Flux) interlock.

(i) Above the P

-7 (Low Power Reactor Trips Block) interlock and below the P

-8 (Power Range Neutron Flux) interlock.


---REVIEWER'S NOTE--------------------------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit.


11 Table 3.3-1 Table 4.3-1 Table 2.2-1 (unless otherwise noted)

DOC L02 DOC M23 DOC M22 9 10 11 12 13 (g) 1964.8 1970 2390.292.7 4739 5022 1 16 Table 2.2-1 Function 15 89.6 14 14 14 14UFSAR Section 7.1.2 4 10 3 3 3 3 3 3 3 2 13 9 9 9 9 2 2 RTS Instrumentation (Without Setpoint Control Program) 3.3.1 A Westinghouse STS 3.3.1 A-19 Rev. 4.0 CTS Amendment XXXSequoyah Unit 2 1 1 2Table 3.3.1-1 (page 3 of 8) Reactor Trip System Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE [NOMINAL (l) TRIP SETPOINT] 8. Pressurizer Pressure

a. Low 1 (h) [4] K SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [1886] psig [1900] psig
b. High 1,2 [4] E SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [2396] psig [2385] psig
9. Pressurizer Water Level - High 1 (g) 3 K SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR3.3.1.10(b)(c) [93.8]% [92]% 10. Reactor Coolant Flow - Low 1 (g) 3 per loopK SR 3.3.1.1 SR 3.3.1.7 (b)(c) SR 3.3.1.10(b)(c)SR3.3.1.16 [89.2]% [90]%
11. Reactor Coolant Pump (RCP) Breaker Position
a. Single Loop 1 (h) 1 per RCP L SR 3.3.1.14 NA NA
b. Two Loops 1 (i) 1 per RCP M SR 3.3.1.14 NA NA 12. Undervoltage RCPs 1 (g) [3] per busK SR 3.3.1.9 SR 3.3.1.10(b)(c)SR 3.3.1.16 [4760] V [4830] V (b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than t he NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveilla nce procedures (field setting) to confirm channel performance. The NTS P and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference]. (g) Above the P-7 (Low Power Reactor Trips Block) interlock.

(h) Above the P

-8 (Power Range Neutron Flux) interlock.

(i) Above the P

-7 (Low Power Reactor Trips Block) interlock and below the P

-8 (Power Range Neutron Flux) interlock.


---REVIEWER'S NOTE--------------------------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit.


11 Table 3.3-1 Table 4.3-1 Table 2.2-1 (unless otherwise noted)

DOC L02 DOC M23 DOC M22 9 10 11 12 13 (g) 1964.8 1970 2390.292.7 4739 5022 1 16 Table 2.2-1 Function 15 89.6 14 14 14 14UFSAR Section 7.1.2 4 10 3 3 3 3 3 3 3 2 13 9 9 9 9 2 2