GO2-14-103, Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information

Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information

ML14188B450
Person / Time
Site:	Columbia
Issue date:	06/19/2014
From:	Javorik A Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-14-103, TSTF-493, Rev 4
Download: ML14188B450 (21)

Text

Alex L. Javorik ENERGY Columbia Generating Station RP.O. Box 968, PE04 Richland, WA 99352-0968 Ph. 509.377.8555 IF. 509.377.4150 aljavodk@energy-northwest.com June 19, 2014 G02-14-103 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

Reference:

1. Letter, G02-13-138, dated October 2, 2013, A. L. Javorik (Energy Northwest) to NRC, "License Amendment Request for Adoption of TSTF-493, Revision 4, Option A"

2. Letter, dated April 30, 2014, C. F. Lyon (NRC) to ME Reddemann (Energy Northwest), "Columbia Generating Station - Request for Additional Information related to License Amendment Request to Adopt TSTF-493, Revision 4, Option A (TAC No. MF2863)"

Dear Sir or Madam:

By Reference 1, Energy Northwest requested approval of a license amendment request to revise the Technical Specifications (TS) by adding requirements to assess channel performance during testing that verifies instrument channel setting values established by the plant-specific setpoint methodologies. Attachment 1 to this letter documents a proposed change to the instrument Functions to be annotated with the TSTF-493 Surveillance Notes. The proposed change will remove the Surveillance Notes from TS Table 3.3.5.1-1 Functions 1.c, 1 .d, 2.c, and 2.d and add the Surveillance Notes to TS Table 3.3.6.2-1 Function 1. Revised pages of the TS and TS Bases markups are provided in Attachments 2 and 3, respectively. Revised pages of TS (clean pages) are provided in Attachment 4.

Via Reference 2, the Nuclear Regulatory Commission (NRC) requested additional information. Attachment 5 provides the response to the requested information.

This letter and its enclosures contain no regulatory commitments. Ifthere are any questions or if additional information is needed, please contact Ms. L. L. Williams, Licensing Supervisor, at 509-377-8148.

P 0oc P F,.

V PROPOSED REVISION TO UCENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 2 of 2 I declare under penalty of perjury that t foregoing i and correct.

Executed on A. L. Javorik Vice President, Engineering Attachments:

Attachment I - Proposed Change to the Instrument Functions to be annotated with the TSTF-493 Surveillance Notes Attachment 2 - Revision to the Technical Specification Markup Pages Proposed In G02-13-138 Attachment 3 - Revision to the Technical Specification Bases Markup Pages Proposed in G02-13-138 (for reference only)

Attachment 4 - Revision to the Revised (Clean) Technical Specification Pages Proposed In G02-13-138 Attachment 5 - Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-493, Revision 4, Option A cc: NRC RIV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C JO Luce - ESFEC RR Cowley - WDOH (email)

MA Jones - BPA1 399 (email)

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 1 of 3 PROPOSED CHANGE TO THE INSTRUMENT FUNCTIONS TO BE ANNOTATED WITH THE TSTF-493 SURVEILLANCE NOTES In Reference 1, Energy Northwest requested approval of a license amendment request to revise the Technical Specification (TS) by adding requirements to assess channel performance during testing that verifies instrument channel setting values established by the plant-specific setpoint methodologies. The proposed amendment incorporates Technical Specification Task Force (TSTF) Traveler TSTF-493-A (Reference 2) ,,

Option A. Attachment 2 to Reference I provided the plant-specific evaluation identifying the list of instrument Functions to be annotated with the TSTF-493 Surveillance Notes.

Energy Northwest proposed to add Surveillance Notes to the following functions in Columbia Generating Station (Columbia) TS table for Emergency Core Cooling System instrumentation, Table 3.3.5.1-1:

" 1.c "LPCS [Low Pressure Core Spray] Pump Start - LOCA [Loss of Coolant Accident] Time Delay Relay"

• 1.d "LPCI [Low Pressure Coolant Injection] Pump A Start - LOCA Time Delay Relay

" 2.c ULPCI Pump B Start - LOCA Time Delay Relay"

" 2.d "LPCI Pump C Start - LOCA Time Delay Relay" These Functions correspond to the following functions in NUREG-1434 Table 3.3.5.1-1:

SI.c "LPCI Pump A Start - Time Delay Relay"

• 2.c "LPCI Pump B Start - Time Delay Relay" Each LOCA time delay relay channel for TS Table 3.3.5.1-1 Functions I.c, '.d, 2.c, and 2.d consists of Drywell Pressure - High, and Reactor Vessel Water Level - Low Low, Level 2 sensors, auxiliary relay logic, and circuit breaker position switches to initiate the LOCA time delay relay when on normal off site power. The Drywell Pressure - High sensor is the same sensor that provides input to the Reactor Protection System and, In accordance with Reference 1, will have Surveillance Notes applied to TS 3.3.1.1-1 Function 6. Thus, it meets the exclusion criteria provided in TSTF-493 which states that Surveillance Notes do not have to be applied to "those permissives or interlocks that derive input from a sensor or adjustable device that is tested as part of another TS function."

However, the Reactor Vessel Water Level - Low Low, Level 2 sensor that provides input to the LOCA time delay relays did not have Surveillance Notes applied in Reference 1. In order to meet the exclusion criteria provided in TSTF-493, Energy Northwest proposes to add Surveillance Notes to the Reactor Vessel Water Level - Low Low, Level 2 sensor that provides Input to the LOCA time delay relays. These sensors are the same sensors that provide input to the Secondary Containment Isolation Instrumentation in TS Table 3.3.6.2-1 Function 1. Thus, Surveillance Notes willbe

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 2 of 3 applied to TS Table 3.3.6.2-1 Function 1, similar to the Drywell Pressure - High sensor.

The TSTF-493 criteria for excluding Surveillance Notes for the LOCA time delay relays will therefore be met. Adding the Surveillance Notes to the actual sensors clarifies which portion of the relay channel the As Found Tolerance and As Left Tolerance should be applied to. This is consistent with the application of TSTF-493 Surveillance Notes to other TS functions.

Note that TS Table 3.3.5.1-1 also contains Functions for the LOCA/LOOP time delay relays. The LOCA/LOOP time delay relay channels consist of Reactor Vessel Water Level - Low Low Low, Level 1, Drywell Pressure - High sensors, auxiliary relay logic, circuit breaker position switches and power available relays. The Reactor Vessel Water Level - Low Low Low, Level I sensors and Drywell Pressure - High sensors for these relays are the same sensors to which Surveillance Notes have been applied in TS 3.3.5.1-1 Functions 1.a, I.b, 2.a, and 2.b. The LOCA/LOOP time delay relays therefore meet the exclusion criteria provided In TSTF-493 and Surveillance Notes were not applied to these relays.

Applicabilitv of Refetrence I "EvaI.ti on of Progosed Chanes'"

Attachment I to Reference I provided an Evaluation of Proposed Changes for the original amendment request. Energy Northwest has reviewed the specific topics discussed in that attachment for applicability to the change proposed in this letter.

Energy Northwest's review determined the following.

In Reference I Attachment 1, Energy Northwest stated that it was not proposing variations or deviations from the TS changes described in TSTF-493, Revision 4 or the model SE. The discussion in Reference I Attachment I referenced Attachment 2 to that letter as providing a list of instrument Functions to be annotated with the TSTF-493 Surveillance Notes. Energy Northwest has determined that the discussion in Reference 1 Attachment I is also applicable to the changes proposed in this letter, with the following explanations:

• The changes proposed in this letter include the addition of the two TSTF-493 Surveillance Notes to SR 3.3.6.2.3 for TS Table 3.3.6.2-1, "Secondary Containment Isolation Instrumentation," Function 1, "Reactor Vessel Water Level - Low Low, Level 2. Neither TSTF-493 Attachment A, "Identification of Functions to be Annotated with the TSTF-493 Footnotes," nor the TSTF-493 Option A TS page markups include the addition of the two Surveillance Notes to the corresponding NUREG-1434 or NUREG-1433 TS. This variation or deviation from the TS changes described in TSTF-493 Is acceptable because it is consistent with the Exclusion No. 1 on page 9 In Section 4.0, "Technical Analysis" of TSTF-493, which states:

"In addition, the two Notes do not apply to those permissives and interlocks that derive Input from a sensor or adjustable device that is tested as part of another TS function."

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Attachment I Page 3 of 3 In conjunction with the addition of the two Surveillance Notes to SR 3.3.6.2.3 for TS Table 3.3.6.2-1 Function fiapplication of this,exclusiom.riteria permits deletion of the two Surveillance Notes from SR 3.3.5.1.5 for the LOCA time delay relays in TS Table 3.3.5.i.1.Functibn. tc, 1d*2.c, and t2Ad.  %*:

• Attachment 2 to Reference .lt4thf*oMAt long&r apply with respect to SR 3.3.5.1.5 for Functions i.c, 1.d, 2.c, and 2.d In TS Table 3.3.5.1-1, or SR 3.3.6.2.3 for Function I in TS Table 3.3.6.2-1.

Additionally, Energy Northwest's review has determined that all other aspects of the "Evaluation of Proposed Changes" in Reference I Attachment 1, including the sections titled "No Significant Hazards Consideration Determination," "Applicable Regulatory Requirements/Criteria" and "Environmental Considerations," remain valid and applicable to the changes proposed In this letter, References for this Attachment

1. Letter, G02-13-138, dated October 2, 2013, AL Javorik (Energy Northwest) to NRC, "License Amendment Request for Adoption of TSTF-493, Revision 4, Option A"

2. Technical Specification Task Force (TSTF) Traveler TSTF-493-A, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions"

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 1 of 1 Columbia Generatlng StMlon Revision to the Technice Speciffton Mtb*p Pages Proposed In G024.1138

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6) I Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

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

Subsystems

a. Reactor Vessel 1 2, 3, 2) B SR 3.3.5.1.1 2 -142.3 Inches Water Level - Low 4(), 5("i SR 3.3.5.1.2 Low Low, Level I SR 3.3.5.1.49 SR 3.3.5.1.6

b. Drywell Pressure - 1,2,3 2b) B SR 3.3.5.1.2 !51.88 pslg High SR 3.3.5.1.4#

SR 3.3.5.1.6

c. LPCS Pump Start- 1.2,3 1(' C SR 3.3.6.1.5 >8.53seconds LOCA Time Delay 4(, 5= SR 3.3.6.1.6 and Relay 4510.r.." f font r~oI~

d. LPCI Pump A Start - 1 2 3, 1(e) C SR 3.3.5.1.5* 17 d LOCA Time Delay 4(, 5(') SR 3.3.5.1.8 and l Relay seconds

e. LPCI Pump A Start - 1 2 3 1 C SR 3.3.5.1.2 2:3.04 seconds LOCAJLOOP Time 4?1,5(') SR 3.3.5.1.3 and Delay Relay SR 3.3.5.1.6 < 6.00 seconds

f. Reactor Vessel 1,2,3 1 per valve C SR 3.3.5.1.2 > 448 psig and Pressure - Low SR 3.3.5.1.4 < 492 psig (Injection SR 3.3.5.1.6 Permissive) 4 ),50) 1 per valve B SR 3.3.5.1.2 k448 psig and SR 3.3.5.1.4  :; 492 psig SR 3.3.5.1.6 (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to Initiate the associated diesel generator (DG).

(e) Also supports OPERABILITY of 230 kV offstte power circuit pursuant to LCO 3.8.1 and LCO 3.8.2.

(f) If the as-found channel setpolnt is outside its predefined as-found tolerance, then the Channel shall be evaluated to verify that it Is functioning as required before retu**ntj the channel to service (g) The instrument channel setpoint shall be reset to a value that i. within the as-left tnoerance around the Limiting Trip Setpolnt (LTSP) at the completion of the surveillance, otherwise, the channel shall be declared inoperable Setpoints more consvative than the LTSP are acceptable provided that the aS-I'und and as-left tolerances apply to the actual seVolnt implemented in the surveilance procedures (Nominal Trip Stpoint) to r'nfim channel performance. The LTSP and the methodologies used to determine the a-found and the as-left tolerances are specified in the Licensee Controlled Specifications Columbia Generating Station 3.3.5.1-6 Amendment No. 449,442 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 64) I Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.I REQUIREMENTS VALUE

1. LPCI and LPCS Subsystens

g. LPCS Pump 12,3 ¶ E SR 3.3.5.1.2 > 68 gpm and D*scharge Flow - 44),50(a) SR 3.3.5.1.4 r. 1067 gpm Low (Minimum Flow) SR 3.3.5.1.6

h. LPCI Pump A 1 E SR 3.3.5.1.2 > 605 gpm ard Dischare Flow - SR 3.3.5.1.4

• 984 gpm Low (Minimum Flow) SR 3.3.5.1.6 1j2,3, I. Manual Initiation 416)2() 2 C SR 3.3.5.1.6 NA

2. LPCI B and LPCI C Submystems

a. Reactor Vessel B SR 3.3.5.1.1 > -142.3 Inches Water Level - Low SR 3.3.5.1.2 Low Low, Level I SR 3.3.5.1.4% I SR 3.3.5.1.6

b. Drywell Pressure - 1,2,3 B SR 3.3.5.1.2 < 1.88 pwg High SR 3.3.5.1.4"41 SR 3.3.5.1.8 1,2 3 j(e) C SR 3.3.5.1.N, k 17.24 seconds

c. LPCI Pump B Start - 44(,')5(8')

LOCA Time Delay SR 3.3.5.1.6'", and Relay < 21.53 seconds j(@)

d. LPCI Pump C Start - 44'), '58' C SR 3.3.5.1.1 953 seconds LOCA Time Delay SR 3.3.5.1.6 Relay seconds (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to Initiate the associated DG.

(e) Also supports OPERABILITY of 230 kV offtte power drcIt pursuant to LCO 3.8.1 and LCO 3.8.2.

(0) If the as-found channel setpoirtt is outside its predefined as-found tolerance, then the channýel s-hal be evaluated to verify that it is functioning as required before returning the channel to service (g) The instrumrent channel setpoint shall be reset to a value that is witnin the as-left tolernce around the Limiting Trip SetpoWnt (LTSP) at the completion of the surveillance; otherwrse, the channel shall be declared inoperable.

Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint Implemented in the surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methcKologies used to determine the as-found and the a-left tolerances are specified in the Licensee Controlled Stpecifictkons.

Columbia Generating Station 3.3.6.1-7 Amendment No. 460,473 225

Secodary Containment Istfltlon Instutnentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE REQUIRED MODES OR CHANN4 OTHER PER' SPECIFIED TRIP SURVEILLANCE ALLOWABLE F~TI~ QPT1ONS SYSTEM R4QV , Pho" VALUE

1. Reactor Vessel Water Level X 1,2,3, (a) 2(e) SR 3.3.8.2.2 > -58 inches Low, Level 2 SR 3.3.6.2.3r"~e) I SR 3.3.6.2.4

2. Drywell Pressure - High 1,2,3 2(c) SR 3.3.6.2.2 < 1.88 pseg SR 3.3.6.2.3 SR 3.3.6.2.4

3. Reactor Building Vent Exhaust 1, 2. 3, (a) 2 SR 3.3.6.2.1 < 16.0 mR/hr Plenum Radiation - High SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4

4. Manual Initiation 1, 2,3, (a) 4 SR 3.3.6.2.4 NA (a) During operations with a potential for draining the reactor vessel.

(b) Deleted (c) Also required to Initiate the associated LOCA Time Delay Relay Function pursuant to LCO 3.3.5.1.

(d) Ifthe as-found channel setpoint is outsde its predefine ess-fnd teranc, then the channal slha b evaluated to verify that q sfunctioningasrequ fore ng thechanneltoseivlce (e) The Instrument channel se-tolt shall be reýet t' a value that is within the asFeft tor a nd tn Limitng Trip Setpot (LTSP) at the completion of the surveiance, (t , the channel shall b de inoperabl Setpoints moe conservative than the LTSP are jpcep ble provded that the a arid aseft lanc apply to the actual setpoint implemente Inthe surve lance po r (Nominal Trp Setpomnt) to c rm channel performance. The LTSP and te methdloes used to determine the as-foundad the I as4eft tolerances are spectfied in the Licensee Controlled Sqecfications Columbia Geneiratft Station Amendment No. 473,4% 225

PROPOSED REVISION TO UCENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Pagel of 1 ....

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ECCS Instruamntation 83.3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)

The Frequency Is based upon operafing expermnm that demonsora channel failure Is rare. The CHANNEL CHECK supplomfs less fomat, but more frequent, ceks of channels durng nornlW operational use of the dftpa assofate i Me dwns rqe by ft LCO.,

A CHANNEL FUNCTIONAL TEST is performd on each require channel to ensure that fte chin wIl perform thierIned fmunctlon. Any seto"t adument shall be consistent with the assumrtin of the curme plait specific etpolint methodology.

The Frequency of 92 day Isbased on the resialllty analyses of Reference 5.

SR 3.3.5. 3. SR 3.3.5.1.4. and SR 3.3.5.1.5 CHANNEL CALIBRATION Is comp check of the Instrument loop and the sensor. Thti tet verifi toe chane eponds to ft measured parameter wthin the necessry range and acurc. CHANNEL CALIBRATION leve the channel adjuslt to account for insument drft betwem success cabatn conset with the plant speclf seltpont methodolog.

The Frequencies are based upon the aseumption of a 92 day, 18 month, or 24 month caltbram Intevl, as appilloe, inthe doemination of the Idrift in the setpoln aWnysls. For SR 3.3.5.1.3 a d 3 .th'ref s a plant specific program which verifies that the 15 t functions as required by verifying the as-left and as-found setting are consistent with those estabished by the setpoln methodology.

SR 3.3.5.1.4 for designted functions is modified by two Notes as Identified in Table 3.3,5.1-1. The first Note requires evaluation of channel performance for the condition where the as-found setting for the channel setpoint is outside its as-found tolerance but conservative with respect to the Allowable Value. Evaluation of channel peormance will verify that the channel will continue to behave in accordance with safety analysis assumptions and the channel performance assumptions in the setpoint methodology. The purpose of the assessment is to ensure confidence in the channel performance prior to returning the channel to serce For channels determined to be OPERABLE but degraded, after returning the channel to service the performance of these channels will be evaluated under the plant Corrective Action Program. Entry into the Corrective Columbia Geran Stionn 8 3.3-S-1-36 Revision

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

The Reactor Water Level-Low Low Level Function is also used to initiate the LOCA Time Delay Relays of LCO 3.3.5.1. A Note (c) Is provided to Table 3.3.6.2-1 that identifies Function I channels provide one set of Since this Function isalso usid to initiate the LOCA Time Delay Relassur Lof actuatof t1 SGTF-493 footnotes havebean appleed to this Function in prieefr applying the footnotes to the LOCA Timey relay Reways themnselves.

2. LDrwell pofeta of 3..51 oTfSte - Hiah Pressure h slto nhg toerlae rw High drywetpressure can indicate a break in the reactor coolant pressure boundary (RCPB). An Isolation of the secondary containment and actuation of the SGT System are initiated Inorder to minimize the potential of an offile dose release. The Isolation on high d.well pressure supports actions to ensure that any ofmsIte relses wae within the limits calculated Inthe safety analysis. However, the Drywall Pressure - High Function associated with isolation Isnot assumed in any FSAR accidenit or transient anayss. It Isretained for the overall redundancy and diversity of the secondary containment Isolation instrumentati as required by the NRC approved licensing basis. High drywell pressure snalsn are Initiated from pressure switches that sense the pressure In the drywell. Four channels of Drywall - High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The Allowable Value was chosen to be the same as the RPS Drywell Pressure - High Function Allowable Value (LCO 3.3.1.1) since this is indicative of a loss of coolant accident.

The Drywnll Pressure - High Function is required to be OPERABLE in MODES 1,2, and 3 where considerable energy exists in the RCS; thus, there is a probability of pipe breaks resulting in significant releases of radioactive steam and gas. This Function Is notrequirIn MODES 4 and 6 because the probability and consequences of these events are low due to the RCS pressure and temperature limitatons of these MODES.

3. Reactor Suiding Vent Exaust Plenum Radit"o - Eifh High secondary containment exhaust radiation is an indication of possible gross failure of the fue cladding. The release may have originated from the primary containment due to a break Inthe RCPB or the refueling floor due to a fue handling accident. When Reactor Building Vent Exhaust Plenum Radiation - High Isdetected, secondary containment Isolation and actuation of the SGT System are Initiated to limit the release of fission products (Ref. 1).

Columbia Generating Station B 3.3.6.2-4 Revision 73

Secondary Containment Isolation Instrumentation 83.3.6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

Agreement criteria are determined by the plant staff, based on a combination of the channel Instrument uncertainties, Including indication and readability. If a channel Is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstates channel failure is rare. The CHANNEL CHECK suppleiment less formal, but more frequen checks of channels during normal operational use of the displays associated with the channel required by the LCO.

A CHANNEL FUNCTIONAL TEST Is performed on each required channel to ensure that the channel wilt perform the intended function. Any setpolnt adjustment shal be consistent wih the ssumpions of the current plant spetfc sepo methodology.

The Frequency of 92 days Is based upon the reliability analysis of References 4 and 5.

CHANNEL CALIBRATION is a compkt check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for Instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval In the determination of the magnitude of equipment drift In the setpoint analysis. There is a plant specific program which verifies that the instrument channel functions as required by veriing the as-left and as-found setting are consistent with those estabtished by the setpoint methodology.

RevIsion 73 B 3.3.6.2-9 Generating Station Columbia Generating Station 8 3.3.6.2-9 Revision 73

Secondary Containment Isolation Instrumentation B 3.&6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

=SR 3.3.6.2 3 for designated functions is modified by two Notes as Identified in Table 3.3.6.2-I1 The first Note r6quies evaluation of channel performance for the condition where the as-found setting for the channel setpolnt isoutlee its as-fouud tolerance but conservative with ."p*pct to the Allowae Value. Evaluation of channel performance will verify that the channel will continu l behai4 in accordance with safety analysis assumptions and the channel performance assumptions in the setpoint

-" methodology. The purpose of the assessment is to ensure c.nfidence in

[ the channel performance prior to returning the channel to service. For channels determined to be OPERABLE but degraded. after retuornng the channel to service the performance of these channels will be evaluated under the plant Corrective Action Program. Entry into the Corrective Action Program will ensure required review arid documentation of the condition. The second Note requires that the as-left setting for the channel be within the as-left tolerance of the LTSP. Where a setpolnt more conservative than the LTSP is used in the plant sur ance procedures (i.e., nominal trip setpoint, or NTSP), the as-left and as-found to4erances, as applicable, will be applied to the su ce prc setpoint. This will ensure that sufficient margin to the Safety Limitnd/ora Analytical Limit is maintaind. If the as-left channel setting cannot be returned to a setting within the as-left tolerance of the LTSP, then the channel shall be declared inoperable.

The second Note also requires that LTSP and the for calculating the as-teft and the as-found toierances be in the Lt-icens

,.Controllect Speiiatsn.

SIR 3.3.6,2A4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing, performed on SCIVs and the SGT System In LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 24 month Frequency.

. B 3.3.6. .. .. ... .;on.. .. Revis"iii.... 73 ColumIaIIIII Gen rai ngll Stto Columbia Generating Station 8 3.3.6.2-10 Revision 73

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 1 of 1 Columbia Generating Blation Revision to the Revised (Clean) Techlwd S11clif1ailon Pages Proposed In G02-1*l*3

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6) I Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

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

Subsystems

a. Reactor Vessel 12, 3 2() B SR 3.3.5.1.1 k -142.3 Inches Water Level - Low SR 3.3.5.1.2 I Low Low, Level 1 SR 3.3.5.104 WX)

SR 3.3.5.1.6 1.2,3 2)

b. Drywell Pressure High

- B SR 3.3.5.1.2 SR 3.3.5.1.4M SR 3.3.5.1,6

< 1.88 palg I

c. LPCS Pump Start - S12 3 C SR 3.3.5.1.5 a 8.53 seconds LOCA Time Delay 4?*), i(a3 SR 3.3.5.1.8 and Relay -<10.64 seconds

d. LPCI Pump A Start - 1. 2 3, C SR 3.3.5.1.5 > 17.24 seconds LOCA Time Delay 4W), Vl SR 3.3.5.1.6 and r.21.53 Relay seconds

e. LPCI Pump A Start - I C SR 3.3.5.1.2 > 3.04 seconds LOCAJLOOP Time 4(I,) 5(V) SR 3.3.5.1.3 and Delay Relay SR 3.3.5.1.6 < 6.00 seconds

f. Reactor Vessel .1,2,3 1 per valve C SR 3.3.5.1.2 a 448 psig and Pressure - Low SR 3.3.5.1.4 t; 492 psig (injection SR 3.3.5.1.6 Permissive) 4(m), 5(a) 1 per valve B SR 3.3.5.1.2 > 448 pslg and SR 3.3.5.1.4 :5 492 psig SR 3.3.5.1.6 (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated diesel generator (DG).

(e) Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1 and LCO 3.8.2.

(f) 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.

(g) The Instrument channel setpolnt shall be reset to a value that Is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared Inoperable.

Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint Implemented In the surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methodologies used to determine the as-found and the as-left tolerances are specified Inthe Licensee Controlled Specifications.

Columbia Generating Station 3.3.5.1-6 Amendment No. 46.,4-7 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6) I Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION AA REQUIREMENTS VALUE

1. LPCI and LPCS Subsystems

g. LPCS Pump 1,2,5~(")

4(), 3, I E SR 3.3.5.1.2 S668 gpm and Discharge Flow - SR 3.3.5.1.4 1067 gpm Low (Minimum Flow) SR 3.3.5.1.6

h. LPCl Pump A 1 2,3, I E SR 3.3.5.1.2 k 605 gpm and Discharge Flow - 4() 5a') SR 3.3.5.1.4 S6984 gpm Low (Minimum Flow) SR 3.3.5.1.6 I. Manual Initiation 1, 2, 3, 2 C SR 3.3.5.1.6 NA

2. LPCi B and LPCl C Subsystems

a. Reactor Vessel 1, 2,3, B SR 3.3.5.1.1  ? -142.3 Inches 4(8), 5(,

Water Level - Low SR 3.3.5.1.2 Low Low, Level I SR 3.3.5.1.409) I SR 3.3.5.1.6

b. Drywell Pressure - 1,2,3 B SR 3.3.5.1.2 *ý1.e88psig High SR 3.3.5.11.40) I SR 3.3.5.1.6

c. LPCI Pump B Start - 1,2, 3, C SR 3.3.5.1.5 > 17.24 seconds LOCA Time Delay 4(),5(a), SR 3.3.5.1.6 and Relay !521.53 seconds

d. LPCI Pump C Start - I(e) C SR 3.3.5.1.5 2 8.53 seconds LOCA Time Delay 4(a), 5(P)

SR 3.3.5.1.6 and Relay < 10.64 seconds (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to Initiate the associated DG.

(e) Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1 and LCO 3.8.2.

(I) Ifthe as-found channel setpoint Is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that ItIs functioning as required before returning the channel to service.

(g) The instrument channel setpolnt shall be reset to a value that Is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable.

Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpolnt implemented In the surveillance procedures (Nominal Trip SetpoInt) to confirm channel performance. The LTSP and the methodologies used to determIne the as-found and the as-left tolerances are specified in the Licensee Controlled Specifications.

Columbia Generating Station 3.3.5.1-7 Amendment No. 464,4;.2 225

Secondary Containment Isolation Instrumentation

,, . ' . , . ,.- *,., 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE `-REQUIRED .

MODES OR CHANNELS OTHER PER SPECIFIED TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE

1. ReactorVessel Water Level - Low 1, 2, 3. (a) -2(c) SR .3.3.6.2.2 >-.-

%.58"ies Low, Level 2. .... . ;SR 3 .3.6. 2 .3 (da) "

I SR 3.3.6.2.4

2. Drywall Pressure - High 1.2, 3 2(c) SR 3.3.6.2.2 < 1.88 psig SR 3.3.6.2.3 SR 3.3.6.2.4

3. Reactor Building Vent Exhaust 1,2,3,(a) 2 SR 3.3.6.2.1 *;16.0 mR/hr Plenum Radiation - High . .- -. . SR 3.3.6.2.2 SR 3.3.6.2.3-SR 3.3.6.2.4

4. Manual Initiation, 1, 2, 3. (a) 4 ,6R 3.3,6.2.4 NA (a) During operations withea potential for draining the ieactor vessel.

(b) Deleted (c) Also required to initiite the associated LOCA Time Delay Relay Functild pursuant to LCO 3.3.5.1.

(d) Ifthe as-found channel eatpoint is outside its predefined as-fouhd tolerance, then the channel shall 6e evaluated to verify that it Is functioning as required before returning the channel to service.

(a) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared Inoperable.

Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpolnt implemented in the surveillance procedures (Nominal Trip Setpolnt) to confirm channel performance. The LTSP and the methodologies used to determine.the as-found and the os-eft tolerances are specified in the Licensee Controlled Specifications.

Columbia Generating Station 3.3.6.2-3 Amendment No. 43,499 225

4 PROPOSED REVISION TO UCENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Attachment 5 Page I of 3 Response to Request for Additionai Womation Reated to Ucen Amendmetl Request to Adopt TSTF-40% Revslon 4w Option A NRCjSM 1e Please provide the Nomina Trp Setpoint and iting Tdp Setpoint (LTSP) for the functions #0t will include TSTF493, Revision 4, Surveillance Notes 1 and 2.

Also, please provide a description of the megtodology for calculating the LTSPs, As-Left Tolerance, and As-Pound Toleance based on the analytical Amits, where applicabie.

NTSP!andLTS forFucion that WINl Inodi* TSF-43 Revsio 4- %uKMlln The nominal trip setpoirt (NTSP) and LTSP for the Insfrument Functions thW will Include the TSTF-493, Revision 4, Surveillarne Notes are provided inTable 1 on the following pages. The calculations of the AFT and ALT values are still in progress.

Energy Northwest applies the AFT and ALT around the NTSP. In some cases, the values for the AFT and ALT require changes to the NTSP. For ts cases, revisions to the NTSP am sU In progress and will be processed using Enerw Northweat's setpoint change proces, These cases are marked by aTIS* in the NTSP column.

Descria 210.9.0t=ola foa Qslhifv fth LfTS As.ilt T~oleane Mn As-Energy Northwest provided =40plemental Informton regarding application of TSTF-493 Option A Surveillance noe Io TS Table 3.3.1.1-1, Funfion 7, T am Discharge Volume Water Leva - High," in letter G02-14-078, from A. L. Javorlk (Energy Northwst) to ghe Nuclear RegulaoWry Commission (NRC), dated May 8, 2014. Pages 7through 13 of the encksure tothat letter providedadescrlption of the methodology used to determine the AFT, ALT, and LTSP for a proposed change to the instrumentation that flls Function 7.b in Table 3.3.1.1-1. The basic methodology described In that enclosure exemplifies the metiodogy used for calculating the AFTs, ALTs, and LTSPs for afi the functions that vwll Inc&e TSTF-493, Revision 4, Surveillance Notes I and 2. Note that Energy Northwest utilizes the term "maximum setting*or "rnlmnm settng,' as appropat, wnonymously with aLTSPn.

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 2 of 3 Table I TS or Fun. Type Description Units Allowable Instruments LTSP NTSP Table ____ value ___ __

3.3.1.1-1 1.a RPS Intermediate Range Monitor Neutron Flux - divisions LE 122 IRM-EMSQ-601A-H 121.2 120 High 3.3.1.1-1 3 RPS Reactor Vessel Steam Dome Pressure - High psig LE 1079 MS-PS-23A-D 1063.1 TBD 3.3.1.1-1 4 RPS Reactor Vessel Water Level - Low, Level 3 inches GE 9.5 MS-LtS-24A-D 10.4 13.2 RPS-PS-2AC,D 1.72 TBD 3.3.1.1-1 6 RPS Primary Containment Pressure - High psig LE 1.88 RPS-PS-28 1.79 TBD 529' 529'7f RPS Scram Discharge Volume Water Level - High n/a LE 529' 91 CRD-LIS-601A-D 7689 3.3.1.1-1 7.a 3.3.1.1-1 9 RPS Turbine Governor Valve Fast Closure, Trip Oil Pressure - Low psig GE 1000 RPS-PS-5A-D 1171 1252 3.3.4.1.2 bb EOC- Turbine Governor Valve Fast Closure, Trip p GE 10 RPS-PS-5A-D 1171 1252 3.3.4.1_2 RPT Oil Pressure - Low _si_ GE_1000 RPS-PS-5A-D 1171 1252 3.3.5.1-1 a EGGS Reactor Vessel Water Level - Low Low LOW, inches GE -142.3 MS-LIS-37AC -139.2 -127.7 3.3.5.1-1 1 ___ECC_ Level I 3.3.5.1-1 1.b ECCS Dwell Pressure - High psig LE 1.88 MS-PS-48ftC 1.75 1.65 3.3.5.1-1 2.a ECCS Reactor Vessel Water Level - Low Low Low, inches GE -142.3 MS-LIS-37B,1D -139.2 -127.7 3.3.5.1-1 2.a _ECCS Level I psiLI1.8 S-PS-48B 1.72 1.65 ECCS Drywell Pressure - High psig LE 1.88 MS-PS-48B 1.75 1.65 3.3.5.1-1 2.b 3.3.5.1-1 3.3.5.1-1 3.3.5.1-1 3.a 3.b ECCS ECCS ECCS Reactor Vessel DRt 2.b Water Level - Low Low, Level Dryweg Pesr-Hh' wesl Pressure - High Le inches_s ' GE ic LE LE

-58 1.88__

1.88 MS-LIS-31A-D MS-PS-47A-D_

MS-PS-47A-D

-55.1 1.72__

1.72

-49.5 1.5 1.65 3.3.5.1-1 3.c ECCS Reactor Vessel Water Level - Hih, Level 8 inches LE 56 MS-LIS-IOOAB 55.1 54.3 fHPS System Flow Rate - Low (Minimum gpm GE 1200 HP Fl6 1223 1277 3...-

. GSFlow) gp LE 1512 1493 1362 3.3.5.1-1 4.a ECCS Reactor Vessel Water Level - Low Low Low, Level I inches GE -142.3 MS-LIS-37AC -139.2 -127.7 3.3.5.1-1 4.c EGOS Reactor Vessel Water Level - Low, Level 3 GE 9.5 MS-LIS-38A 10.4 13.2 3.3.6.1- 4.c (Permissive) ihes CIA-PS-21A 154 160 Accumulator Backup Compressed Gas CIA-PS-21A 154 16 3.3.5.1-1 4.f EGGS System Pressure - Low psig GE 151.4 CIA-PS-A 154 156

.CIA-PS-39A 154 160

PROPOSED REVISION TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-493, REVISION 4, OPTION A, AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 3 of 3 TS or Fun. Type Description Units TS Allowable Instruments LTSP NTSP Table ____ Value ___________

3.3.5.1-1 5.a ECCS Reactor Vessel Water Level - Low Low Low, inches GE -142.3 MS-LIS-37B,D -139.2 -127.7 Level 1 3.3.5.1-1 5.c ECCS Reactor Vessel(Permissive)

Water Level - Low, Level 3 inches GE 9.5 MS-LIS-38B 10.4 13.2 CIA-PS-218 154 160 3.3.5.1-1 5.e ECCS Accumulator Backup Crs pressed G psig GE 151.4 CIA-PS-22B 154 156 System Pressure - Low CIA-PS-39B 154 160

~Reactor Vessel Water Level - Low Low, Level 3.3.5.2-1 1 RCIC 2 inches GE -58 MS-LIS-37A-D -55.1 -49.5 3.3.5.2-1 2 RCIC Reactor Vessel Water Level - High, Level 8 inches LE 56 MS-LIS-24B,D 55.1 54.3 Reactor Vessel Water Level - Low Low, Level 3.3.62-1 1 SC 2 1 GE -58 MS-LS-300A-D -52.5 -50 ECCS = emergency core cooling system LE = less than or equal to EOC-RPT = end of cycle recirculation pump trip GE = greater than or equal to RCIC = reactor core isolation and cooling TBD = to be determined RPS = reactor protection system SCII = secondary containment isolation instrumentation