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| {{#Wiki_filter:ENERGY NORTHWEST MAY 15 2015 G02-15-075 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 W. Grover Hettel Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509.377.8311 I F. 509.377.4150 wghettel@energy-northwest.com 10 CFR 50.90 10 CFR 50.91 | | {{#Wiki_filter:W. Grover Hettel ENERGY Columbia Generating Station P.O. Box 968, PE23 NORTHWEST Richland, WA 99352-0968 Ph. 509.377.8311 I F. 509.377.4150 wghettel@energy-northwest.com MAY 15 2015 G02-15-075 10 CFR 50.90 10 CFR 50.91 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
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| ==Subject:== | | ==Subject:== |
| COLUMBIA GENERATING STATION, DOCKET NO. 50-397 EXIGENT LICENSE AMENDMENT REQUEST -EXTENSION OF IMPLEMENTATION PERIOD FOR AMENDMENT 232 CHANGING TECHNICAL SPECIFICATION TABLE 3.3.1.1-1FUNCTION7 "SCRAM DISCHARGE VOLUME WATER LEVEL -HIGH" | | COLUMBIA GENERATING STATION, DOCKET NO. 50-397 EXIGENT LICENSE AMENDMENT REQUEST - EXTENSION OF IMPLEMENTATION PERIOD FOR AMENDMENT 232 CHANGING TECHNICAL SPECIFICATION TABLE 3.3.1.1-1FUNCTION7 "SCRAM DISCHARGE VOLUME WATER LEVEL - HIGH" |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| Pursuant to 1 O CFR 50.90, "Application for amendment of license or construction permit," and 10 CFR 50.91 (a)(6) (exigent requests) | | |
| Energy Northwest is requesting exigent approval for a license amendment to extend the implementation period for License Amendment No. 232 to Renewed Facility Operating License No. NPF-21 for Columbia Generating Station (Columbia). | | Pursuant to 1O CFR 50.90, "Application for amendment of license or construction permit," and 10 CFR 50.91 (a)(6) (exigent requests) Energy Northwest is requesting exigent approval for a license amendment to extend the implementation period for License Amendment No. 232 to Renewed Facility Operating License No. NPF-21 for Columbia Generating Station (Columbia). License Amendment No. 232 was issued on March 27, 2015. |
| License Amendment No. 232 was issued on March 27, 2015. The need for the proposed change is based on unforeseen equipment test qualification delays associated with the replacement AMETEK trip units. As discussed with Nuclear Regulatory Commission (NRG) staff on May 8 and 11, 2015, an exigent license amendment request is needed to ensure compliance with operating license requirements. | | The need for the proposed change is based on unforeseen equipment test qualification delays associated with the replacement AMETEK trip units. As discussed with Nuclear Regulatory Commission (NRG) staff on May 8 and 11, 2015, an exigent license amendment request is needed to ensure compliance with operating license requirements. This request is purely administrative in nature, in that it will defer the implementation date of License Amendment No. 232 from the current refueling outage (R-22) to the following refueling outage (R-23), scheduled for spring 2017. contains an evaluation of the proposed changes. |
| This request is purely administrative in nature, in that it will defer the implementation date of License Amendment No. 232 from the current refueling outage (R-22) to the following refueling outage (R-23), scheduled for spring 2017. Attachment 1 contains an evaluation of the proposed changes. Energy Northwest requests approval of the proposed amendment by June 13, 2015, to support the scheduled end date of the current refueling outage. This letter and its enclosures contain no regulatory commitments. | | Energy Northwest requests approval of the proposed amendment by June 13, 2015, to support the scheduled end date of the current refueling outage. |
| Using the standards in 1 O CFR 50.92, "Issuance of amendment," Energy Northwest has concluded that the proposed change does not constitute a significant hazards consideration as described in the enclosed analysis performed in accordance with 1 O CFR 50.91 (a)(1 ). | | This letter and its enclosures contain no regulatory commitments. |
| G02-15-075 Page 2 of 2 In accordance with 1 O CFR 50.91, "Notice for public comment; State consultation," Energy Northwest is notifying the State of Washington of this amendment request by transmitting a copy of this letter and its attachment to the designated state official. | | Using the standards in 1O CFR 50.92, "Issuance of amendment," Energy Northwest has concluded that the proposed change does not constitute a significant hazards consideration as described in the enclosed analysis performed in accordance with 1O CFR 50.91 (a)(1 ). |
| If there are any questions or if additional information is needed, please contact Ms. L. L. Williams, Licensing Supervisor, at 509-377-8148. | | |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on {"('\ A'f l C::.J d.D l 5. Respectfully, W. G. Hettel Vice President, Operations | | G02-15-075 Page 2 of 2 In accordance with 1O CFR 50.91, "Notice for public comment; State consultation," |
| | Energy Northwest is notifying the State of Washington of this amendment request by transmitting a copy of this letter and its attachment to the designated state official. |
| | If there are any questions or if additional information is needed, please contact Ms. L. L. |
| | Williams, Licensing Supervisor, at 509-377-8148. |
| | I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on {"('\ A'f lC::.J d.D l 5. |
| | Respectfully, W. G. Hettel Vice President, Operations |
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| ==Attachment:== | | ==Attachment:== |
| | As stated cc: NRC RIV Regional Administrator NRC NRA Project Manager NRC Senior Resident lnspector/988C CD Sonoda - BPA/1399 (email) |
| | JO Luce - ESFEC (email) |
| | RR Cowley - WDOH (email) |
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| As stated cc: NRC RIV Regional Administrator NRC NRA Project Manager NRC Senior Resident lnspector/988C CD Sonoda -BP A/1399 (email) JO Luce -ESFEC (email) RR Cowley -WDOH (email)
| | GO2-15-075 Page 1 of 8 Evaluation of Proposed Change 1.0 |
| GO2-15-075 Page 1 of 8 Evaluation of Proposed Change | |
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| ==SUMMARY== | | ==SUMMARY== |
| DESCRIPTION | | DESCRIPTION This evaluation supports an exigent license amendment request to extend the implementation period for License Amendment No. 232, Changing Technical Specification (TS) Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level - |
| | | High, (Reference 1) to ensure compliance with Renewed Facility Operating License No. NPF-22 for Columbia Generating Station (Columbia). |
| This evaluation supports an exigent license amendment request to extend the implementation period for License Amendment No. 232, Changing Technical Specification (TS) Table 3.3.1.1-1 Function 7 "Scram Discharge Volume Water Level - High," (Reference 1) to ensure compliance with Renewed Facility Operating License No. NPF-22 for Columbia Generating Station (Columbia). | | Energy Northwest proposes to extend the implementation period associated with License Amendment No. 232 from the currently approved prior to restarting from refueling outage R-22, scheduled for spring 2015 to prior to restarting from refueling outage R-23, scheduled for spring 2017. |
| Energy Northwest proposes to extend the implementation period associated with License Amendment No. 232 from the currently approved "prior to restarting from refueling outage R-22, scheduled for spring 2015" to "prior to restarting from refueling outage R-23, scheduled for spring 2017." | | By letter dated March 27, 2015, the NRC issued License Amendment No. 232 for Columbia. The amendment revised TS Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 7.b to change the term Float Switch to Transmitter/Level Switch and add footnotes (d) and (e) to SR 3.3.1.1.10 for the new scram discharge volume instrumentation scheduled to be installed during the upcoming refueling outage. |
| By letter dated March 27, 2015, the NRC issued License Amendment No. 232 for Columbia. The amendment revised TS Table 3.3.1.1-1, "Reactor Protection System Instrumentation," Function 7.b to change the term "Float Switch" to "Transmitter/Level Switch" and add footnotes (d) and (e) to SR 3.3.1.1.10 for the new scram discharge volume instrumentation scheduled to be installed during the upcoming refueling outage. The amendment also approved administrative changes to Function 7.a to change the term "Transmitter/Trip Unit" to "Transmitter/Level Indicating Switch" and add Surveillance Requirement (SR) 3.3.1.1.1 to require performance of a channel check every 12 hours. This amendment was requested by Energy Northwest letter to NRC dated March 24, 2014 (Reference 2). | | The amendment also approved administrative changes to Function 7.a to change the term Transmitter/Trip Unit to Transmitter/Level Indicating Switch and add Surveillance Requirement (SR) 3.3.1.1.1 to require performance of a channel check every 12 hours. This amendment was requested by Energy Northwest letter to NRC dated March 24, 2014 (Reference 2). |
| The amendment was effective as of the date of issuance and is required to be implemented prior to restarting from refueling outage R-22. | | The amendment was effective as of the date of issuance and is required to be implemented prior to restarting from refueling outage R-22. |
| Energy Northwest has encountered unexpected difficulty and delays in qualifying the new scram discharge volume instrumentation electronic level switches (also referred to as trip units) to satisfy electromagnetic interference (EMI) and radio frequency interference (RFI) test requirements as part of the design change. This creates a potential challenge to nuclear safety as these interferences could affect the trip units - either causing or preventing a reactor scram. The design change is now to be implemented during the subsequent refueling outage (R-23), scheduled to begin during May 2017. As such, Energy Northwest requests to delay implementation of the amendment for one refueling outage. | | Energy Northwest has encountered unexpected difficulty and delays in qualifying the new scram discharge volume instrumentation electronic level switches (also referred to as trip units) to satisfy electromagnetic interference (EMI) and radio frequency interference (RFI) test requirements as part of the design change. This creates a potential challenge to nuclear safety as these interferences could affect the trip units - |
| The functional objective of the design change is to address issues with the existing scram discharge instrument volumes, level instruments and associated small bore, socket welded piping and valves, which are inherent crud traps that have resulted in elevated general area radiation levels and increased personnel dose exposure. Operation for an additional cycle with the existing instrumentation will have no impact on nuclear safety. Administrative controls will continue to be utilized to minimize radiation GO2-15-075 Page 2 of 8 dose to personnel. As such, Energy Northwest requests an extension for implementation of License Amendment No. 232 to prior to startup from the Columbia spring 2017 refueling outage R-23. | | either causing or preventing a reactor scram. The design change is now to be implemented during the subsequent refueling outage (R-23), scheduled to begin during May 2017. As such, Energy Northwest requests to delay implementation of the amendment for one refueling outage. |
| Exigent Circumstances:
| | The functional objective of the design change is to address issues with the existing scram discharge instrument volumes, level instruments and associated small bore, socket welded piping and valves, which are inherent crud traps that have resulted in elevated general area radiation levels and increased personnel dose exposure. |
| | Operation for an additional cycle with the existing instrumentation will have no impact on nuclear safety. Administrative controls will continue to be utilized to minimize radiation |
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| The Commission's regulations, 10 CFR 50.91, contain provisions for issuance of amendments when the usual 30-day public notice period cannot be met. One type of special exception is an exigency. An exigency is a case where the staff and licensee need to act promptly. In this case, Energy Northwest cannot implement an amendment within the implementation date agreed upon, and therefore a new date must be agreed upon to avoid delaying startup from refueling outage R-22. Pursuant to 10 CFR 50.91(a)(6), Energy Northwest is requesting the proposed amendment on an exigent basis. Under such circumstances, the Commission notifies the public in one of two ways: | | GO2-15-075 Page 2 of 8 dose to personnel. As such, Energy Northwest requests an extension for implementation of License Amendment No. 232 to prior to startup from the Columbia spring 2017 refueling outage R-23. |
| (A) Issue a Federal Register notice providing notice of an opportunity for hearing and allowing at least two weeks from the date of the notice for prior public comment; or (B) Use local media to provide reasonable notice to the public in the area surrounding a licensee's facility, consulting with the licensee on the proposed media release and on the geographical area of its coverage; 2.0 DETAILED DESCRIPTION In Reference 2, Energy Northwest requested revision of the specified function description and SRs in Table 3.3.1.1-1, "Reactor Protection System Instrumentation," Function 7, "Scram Discharge Volume Water Level - High." The proposed changes support a planned upgrade to Columbia's Reactor Protection System (RPS) Scram Discharge Volume (SDV) Water Level - High instrumentation. The instrument replacements are part of a larger plant modification to replace the two scram discharge instrument volume tanks with new stainless steel tanks and fittings that will reduce future crud accumulation and recurring radiation dose exposure to plant personnel. | | Exigent Circumstances: |
| | The Commission's regulations, 10 CFR 50.91, contain provisions for issuance of amendments when the usual 30-day public notice period cannot be met. One type of special exception is an exigency. An exigency is a case where the staff and licensee need to act promptly. In this case, Energy Northwest cannot implement an amendment within the implementation date agreed upon, and therefore a new date must be agreed upon to avoid delaying startup from refueling outage R-22. Pursuant to 10 CFR 50.91(a)(6), Energy Northwest is requesting the proposed amendment on an exigent basis. |
| | Under such circumstances, the Commission notifies the public in one of two ways: |
| | (A) Issue a Federal Register notice providing notice of an opportunity for hearing and allowing at least two weeks from the date of the notice for prior public comment; or (B) Use local media to provide reasonable notice to the public in the area surrounding a licensee's facility, consulting with the licensee on the proposed media release and on the geographical area of its coverage; 2.0 DETAILED DESCRIPTION In Reference 2, Energy Northwest requested revision of the specified function description and SRs in Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 7, Scram Discharge Volume Water Level - High. The proposed changes support a planned upgrade to Columbias Reactor Protection System (RPS) Scram Discharge Volume (SDV) Water Level - High instrumentation. The instrument replacements are part of a larger plant modification to replace the two scram discharge instrument volume tanks with new stainless steel tanks and fittings that will reduce future crud accumulation and recurring radiation dose exposure to plant personnel. |
| The existing instrumentation for TS Table 3.3.1.1-1 Function 7.b are Magnetrol level switches. These switches are mechanical float-type switches. They will be replaced by Rosemount 3152N Level Transmitters and the AMETEK ET-1200 series non-indicating trip units. | | The existing instrumentation for TS Table 3.3.1.1-1 Function 7.b are Magnetrol level switches. These switches are mechanical float-type switches. They will be replaced by Rosemount 3152N Level Transmitters and the AMETEK ET-1200 series non-indicating trip units. |
| Energy Northwest has encountered difficulties and delays in qualifying the AMETEK trip units to satisfy EMI/RFI test requirements. The trip units required commercial grade dedication by a qualified vendor in order to qualify the parts for safety related applications. Receipt of the parts from the vendor was significantly delayed, and did not GO2-15-075 Page 3 of 8 occur until early March 2015. As part of the dedication process, EMI/RFI testing (meeting Regulatory Guide 1.180) was performed. When qualification testing was completed, Energy Northwest was notified that modifications to the trip units had been made in order to obtain acceptable test results, requiring Energy Northwest to re-evaluate the suitability of the new instruments in our application including updating the design control documents to reflect the modified instruments. | | Energy Northwest has encountered difficulties and delays in qualifying the AMETEK trip units to satisfy EMI/RFI test requirements. The trip units required commercial grade dedication by a qualified vendor in order to qualify the parts for safety related applications. Receipt of the parts from the vendor was significantly delayed, and did not |
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| | GO2-15-075 Page 3 of 8 occur until early March 2015. As part of the dedication process, EMI/RFI testing (meeting Regulatory Guide 1.180) was performed. When qualification testing was completed, Energy Northwest was notified that modifications to the trip units had been made in order to obtain acceptable test results, requiring Energy Northwest to re-evaluate the suitability of the new instruments in our application including updating the design control documents to reflect the modified instruments. |
| In early April 2015, Energy Northwest completed mock-up testing onsite and determined that the modification and external wiring requirements for the trip units received from the vendor were incompatible with our application and thus would require requalification to match plant configuration. Removal of modifications and requalification of the trip units with wiring that represents the actual plant signals was required, and limited EMI/RFI testing by the vendor was conducted in late April and early May. This testing revealed that additional modifications were required in order to show acceptable resistance to EMI/RFI in configurations that match plant installation. | | In early April 2015, Energy Northwest completed mock-up testing onsite and determined that the modification and external wiring requirements for the trip units received from the vendor were incompatible with our application and thus would require requalification to match plant configuration. Removal of modifications and requalification of the trip units with wiring that represents the actual plant signals was required, and limited EMI/RFI testing by the vendor was conducted in late April and early May. This testing revealed that additional modifications were required in order to show acceptable resistance to EMI/RFI in configurations that match plant installation. |
| As a result, the trip units must be returned to the vendor for reconfiguration, dedication and requalification. Discussions with the vendor indicate that five weeks is required to complete these tasks on an expedited schedule; this will be followed by on-site acceptance testing by Energy Northwest resulting in an overall extension of the current outage duration of 14 days. | | As a result, the trip units must be returned to the vendor for reconfiguration, dedication and requalification. Discussions with the vendor indicate that five weeks is required to complete these tasks on an expedited schedule; this will be followed by on-site acceptance testing by Energy Northwest resulting in an overall extension of the current outage duration of 14 days. |
| Based on the difficulties and delays with dedication and qualification experienced to date, Energy Northwest has elected to delay implementation of the proposed design change to the next refueling outage. Operation for an additional cycle with the existing configuration will have no impact on nuclear safety since existing instrument volumes and instrumentation maintain the required redundancy, diversity and capacity to ensure there is sufficient volume available to accommodate a reactor scram. | | Based on the difficulties and delays with dedication and qualification experienced to date, Energy Northwest has elected to delay implementation of the proposed design change to the next refueling outage. Operation for an additional cycle with the existing configuration will have no impact on nuclear safety since existing instrument volumes and instrumentation maintain the required redundancy, diversity and capacity to ensure there is sufficient volume available to accommodate a reactor scram. |
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| ==3.0 TECHNICAL EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
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| The request for extending the implementation period is not a technical or safety issue. The proposed change is purely an administrative change. In issuing an amendment to an operating license, the NRC staff states when the amendment is effective and when the amendment must be implemented. These dates are given in Enclosure 1 of the amendment and are part of the operating license. As such, a change to the implementation date is a change to the operating license for the plant. Although there are no regulatory requirements on the implementation date specified in an amendment, the licensee is required by the operating license to fully implement the amendment by the date specified (i.e., by a date no later than that specified). | | The request for extending the implementation period is not a technical or safety issue. |
| In addition, an evaluation of the impact of the delay on each change to TS Table 3.3.1.1-1 approved in Reference 1 is provided below: | | The proposed change is purely an administrative change. In issuing an amendment to an operating license, the NRC staff states when the amendment is effective and when the amendment must be implemented. These dates are given in Enclosure 1 of the amendment and are part of the operating license. As such, a change to the implementation date is a change to the operating license for the plant. Although there are no regulatory requirements on the implementation date specified in an amendment, the licensee is required by the operating license to fully implement the amendment by the date specified (i.e., by a date no later than that specified). |
| | In addition, an evaluation of the impact of the delay on each change to TS Table 3.3.1.1-1 approved in Reference 1 is provided below: |
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| GO2-15-075 Page 4 of 8 | | GO2-15-075 Page 4 of 8 |
| * Revise the title of the Function 7.a instruments from "Transmitter/Trip Unit" to "Transmitter/Level Indicating Switch." | | * Revise the title of the Function 7.a instruments from Transmitter/Trip Unit to Transmitter/Level Indicating Switch. |
| Evaluation: The change in title is purely administrative. The proposed term more accurately describes the capability of the existing instrumentation to provide level indication. Since this is an administrative change, there is no impact by delaying implementation of License Amendment No. 232. | | Evaluation: The change in title is purely administrative. The proposed term more accurately describes the capability of the existing instrumentation to provide level indication. Since this is an administrative change, there is no impact by delaying implementation of License Amendment No. 232. |
| * Revise the title of the Function 7.b instruments from "Float Switch" to "Transmitter/Level Switch." | | * Revise the title of the Function 7.b instruments from Float Switch to Transmitter/Level Switch. |
| Evaluation: The design change to physically replace the existing float switches is deferred to the next refueling outage. As such, the existing instruments will remain installed for an additional cycle. The existing float switches have acceptable performance; therefore, there is no impact by delaying implementation of License Amendment No. 232. | | Evaluation: The design change to physically replace the existing float switches is deferred to the next refueling outage. As such, the existing instruments will remain installed for an additional cycle. The existing float switches have acceptable performance; therefore, there is no impact by delaying implementation of License Amendment No. 232. |
| * Add SR 3.3.1.1.1 to Function 7.a to require performance of a channel check every 12 hours. | | * Add SR 3.3.1.1.1 to Function 7.a to require performance of a channel check every 12 hours. |
| Evaluation: As stated in Reference 2, Energy Northwest's procedures currently require performance of a channel check every 12 hours and require declaring the Limiting Condition for Operation (LCO) not met for a failure of the channel check. The lack of a SR for performing channel checks on the Function 7.a instruments is a legacy issue which is being managed in accordance with NRC guidance in Administrative Letter 98-10. Upon discovery of this condition, procedures were revised to require performance of the channel check and a corrective action was opened to add the requirement to the TS. Since the required channel checks are currently being performed and are controlled by procedure, there is no impact by delaying implementation of License Amendment No. 232. | | Evaluation: As stated in Reference 2, Energy Northwests procedures currently require performance of a channel check every 12 hours and require declaring the Limiting Condition for Operation (LCO) not met for a failure of the channel check. |
| * Add footnotes (d) and (e) to SR 3.3.1.1.10 for Function 7.b to reflect the requirements of TSTF-493, Revision 4, Option A. | | The lack of a SR for performing channel checks on the Function 7.a instruments is a legacy issue which is being managed in accordance with NRC guidance in Administrative Letter 98-10. Upon discovery of this condition, procedures were revised to require performance of the channel check and a corrective action was opened to add the requirement to the TS. Since the required channel checks are currently being performed and are controlled by procedure, there is no impact by delaying implementation of License Amendment No. 232. |
| | | * Add footnotes (d) and (e) to SR 3.3.1.1.10 for Function 7.b to reflect the requirements of TSTF-493, Revision 4, Option A. |
| Evaluation: This change was a result of the change in instrumentation proposed for Function 7.b. The existing float switches are excluded from the scope of TSTF-493 since they are mechanical devices. The existing instruments will remain installed for an additional cycle and there is no impact by delaying implementation of License Amendment No. 232. | | Evaluation: This change was a result of the change in instrumentation proposed for Function 7.b. The existing float switches are excluded from the scope of TSTF-493 since they are mechanical devices. The existing instruments will remain installed for an additional cycle and there is no impact by delaying implementation of License Amendment No. 232. |
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| ==4.0 REGULATORY EVALUATION==
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| 4.1 Applicable Regulatory Requirements
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| The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Energy Northwest has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the license. The following applicable regulations and regulatory requirements were reviewed in making this determination: 10 CFR 50.90, 10 CFR 50.91, and 10 CFR 50.92. The existing plant design continues to comply with all regulatory requirements.
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| 4.2 Precedent
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| Three similarly related license amendments involving extensions to license amendment implementation due dates were approved and are summarized below:
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| : 1. Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment Re: Revision to the Implementation Date for Cooldown Rates for Pressure-Temperature Limits (TAC NOS. MC2183 AND MC2184), dated April 4, 2004. The license amendment extended the implementation date of new cooldown rates for pressure-temperature (P-T) limits that were established for Amendment Nos. 261 and 238 for Calvert Cliffs, Unit Nos. 1 and 2, respectively, to July 1, 2004. Although the existing reactor pressure vessel P-T limit cooldown rates were non-conservative over the life of the units, they remained valid through the end of 2004 and there was no technical issue with implementing the Amendment Nos. 261 and 238 changes until after the 2004 outage. The NRC staff found the proposed delay of implementation acceptable. (ML040640795)
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| : 2. Joseph M. Farley Nuclear Plant - Issuance of Amendment Regarding Change of Implementation Date for Amendment No. 176 for Unit 2 (TAC NO. ME3445), dated May 10, 2010. The license amendment extended the implementation date for deletion of the reactor coolant pump breaker position reactor trip function from the TS one additional cycle due to unforeseen difficulties encountered with respect to delays in the receipt of design input from the original equipment manufacturer and the resulting impact on the schedule for implementing the modification during the originally scheduled refueling outage. The NRC staff did not identify a safety-related issue concerning the modification date extension. The NRC staff found that the primary and secondary features of the reactor protection system providing protection from partial or complete loss of flow that are relied upon in the safety analyses, remained in effect and the delay in implementation date acceptable. (ML101100668)
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| : 3. Limerick Generating Station, Unit 2 - Issuance of Exigent Amendment Re: Extend Implementation Period for Amendment No. 174 - Leak Detection System GO2-15-075 Page 6 of 8 Setpoint and Allowable Value Changes (TAC NO. MF5695) dated February 25, 2015. The license amendment extended the implementation date for changes to instrument setpoints and allowable values associated with the leak detection system due to unforeseen difficulties associated with calibration of a temperature indicating switch. The NRC staff found that the proposed extension of the implementation period was purely administrative in nature and that operation of the plant with the currently calibrated setpoints (i.e., setpoints prior to approval of Amendment No. 174) did not raise any safety concerns and was acceptable. (ML15049A084) 5.0 SIGNIFICANT HAZARDS CONSIDERATION
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| Energy Northwest has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
| | ==4.0 REGULATORY EVALUATION== |
| : 1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
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| Response: No.
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| The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The amendment implementation schedule extension does not increase the probability or consequences of an accident previously evaluated in the Final Safety Analysis Report. The change in the implementation schedule of the scram discharge volume instrumentation float switches and Technical Specification changes will have no impact on the initiation or the consequences of any accidents previously evaluated. Technical Specification requirements that govern operability or routine testing of plant instruments are not assumed to be initiators of any analyzed event. The change in implementation schedule will not increase the consequences of an accident since the existing scram discharge volume instrumentation is in accordance with the plant's design and licensing bases. All acceptance criteria continue to be met. Therefore there is no significant increase in the probability or consequences of an accident previously evaluated. | | 4.1 Applicable Regulatory Requirements The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Energy Northwest has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the license. The following applicable regulations and regulatory requirements were reviewed in making this determination: 10 CFR 50.90, 10 CFR 50.91, and 10 CFR 50.92. The existing plant design continues to comply with all regulatory requirements. |
| : 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously analyzed? | | 4.2 Precedent Three similarly related license amendments involving extensions to license amendment implementation due dates were approved and are summarized below: |
| Response: No.
| | : 1. Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment Re: Revision to the Implementation Date for Cooldown Rates for Pressure-Temperature Limits (TAC NOS. MC2183 AND MC2184), dated April 4, 2004. The license amendment extended the implementation date of new cooldown rates for pressure-temperature (P-T) limits that were established for Amendment Nos. 261 and 238 for Calvert Cliffs, Unit Nos. 1 and 2, respectively, to July 1, 2004. |
| | Although the existing reactor pressure vessel P-T limit cooldown rates were non-conservative over the life of the units, they remained valid through the end of 2004 and there was no technical issue with implementing the Amendment Nos. |
| | 261 and 238 changes until after the 2004 outage. The NRC staff found the proposed delay of implementation acceptable. (ML040640795) |
| | : 2. Joseph M. Farley Nuclear Plant - Issuance of Amendment Regarding Change of Implementation Date for Amendment No. 176 for Unit 2 (TAC NO. ME3445), |
| | dated May 10, 2010. The license amendment extended the implementation date for deletion of the reactor coolant pump breaker position reactor trip function from the TS one additional cycle due to unforeseen difficulties encountered with respect to delays in the receipt of design input from the original equipment manufacturer and the resulting impact on the schedule for implementing the modification during the originally scheduled refueling outage. The NRC staff did not identify a safety-related issue concerning the modification date extension. |
| | The NRC staff found that the primary and secondary features of the reactor protection system providing protection from partial or complete loss of flow that are relied upon in the safety analyses, remained in effect and the delay in implementation date acceptable. (ML101100668) |
| | : 3. Limerick Generating Station, Unit 2 - Issuance of Exigent Amendment Re: |
| | Extend Implementation Period for Amendment No. 174 - Leak Detection System |
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| There are no postulated hazards, new or different, contained in this amendment. The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any GO2-15-075 Page 7 of 8 plant systems or components, or entail changes in plant operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
| | GO2-15-075 Page 6 of 8 Setpoint and Allowable Value Changes (TAC NO. MF5695) dated February 25, 2015. The license amendment extended the implementation date for changes to instrument setpoints and allowable values associated with the leak detection system due to unforeseen difficulties associated with calibration of a temperature indicating switch. The NRC staff found that the proposed extension of the implementation period was purely administrative in nature and that operation of the plant with the currently calibrated setpoints (i.e., setpoints prior to approval of Amendment No. 174) did not raise any safety concerns and was acceptable. |
| : 3) Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. | | (ML15049A084) 5.0 SIGNIFICANT HAZARDS CONSIDERATION Energy Northwest has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: |
| | : 1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? |
| | Response: No. |
| | The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The amendment implementation schedule extension does not increase the probability or consequences of an accident previously evaluated in the Final Safety Analysis Report. The change in the implementation schedule of the scram discharge volume instrumentation float switches and Technical Specification changes will have no impact on the initiation or the consequences of any accidents previously evaluated. Technical Specification requirements that govern operability or routine testing of plant instruments are not assumed to be initiators of any analyzed event. |
| | The change in implementation schedule will not increase the consequences of an accident since the existing scram discharge volume instrumentation is in accordance with the plants design and licensing bases. All acceptance criteria continue to be met. Therefore there is no significant increase in the probability or consequences of an accident previously evaluated. |
| | : 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously analyzed? |
| | Response: No. |
| | There are no postulated hazards, new or different, contained in this amendment. |
| | The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any |
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| | GO2-15-075 Page 7 of 8 plant systems or components, or entail changes in plant operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | : 3) Does the proposed amendment involve a significant reduction in a margin of safety? |
| | Response: No. |
| The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The existing scram discharge volume instrumentation maintains the required redundancy, diversity and capability to ensure there is sufficient volume available to accommodate a reactor scram. Therefore, the proposed change does not involve a significant reduction in the margin of safety. | | The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The existing scram discharge volume instrumentation maintains the required redundancy, diversity and capability to ensure there is sufficient volume available to accommodate a reactor scram. Therefore, the proposed change does not involve a significant reduction in the margin of safety. |
| Based on the above, Energy Northwest concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified. | | Based on the above, Energy Northwest concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified. |
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| ==6.0 CONCLUSION== | | ==6.0 CONCLUSION== |
| S Based on the considerations discussed above: (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 applicable regulations as identified herein, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. | | S Based on the considerations discussed above: (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 applicable regulations as identified herein, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
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| ==7.0 ENVIRONMENTAL CONSIDERATION== | | ==7.0 ENVIRONMENTAL CONSIDERATION== |
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| Energy Northwest has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within Columbia's restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, Energy Northwest has evaluated the proposed change and has determined that the change does not involve, (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion in accordance with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment. | | Energy Northwest has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within Columbia's restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, Energy Northwest has evaluated the proposed change and has determined that the change does not involve, (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion in accordance with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment. |
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| GO2-15-075 Page 8 of 8 | | GO2-15-075 Page 8 of 8 |
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| ==8.0 REFERENCES== | | ==8.0 REFERENCES== |
| : 1. Columbia Generating Station - Issuance Of Amendment Re: License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, "Scram Discharge Volume Water Level - High" (TAC NO. MF3673) dated March 27, 2015 (ML15063A010) | | : 1. Columbia Generating Station - Issuance Of Amendment Re: License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, "Scram Discharge Volume Water Level - High" (TAC NO. MF3673) dated March 27, 2015 (ML15063A010) |
| : 2. Letter GO2-14-043 dated March 24, 2014, AL Javorik (Energy Northwest) to NRC, "License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, 'Scram Discharge Volume Water Level - High'" (ML14098A400)}} | | : 2. Letter GO2-14-043 dated March 24, 2014, AL Javorik (Energy Northwest) to NRC, License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High (ML14098A400)}} |
Letter Sequence Request |
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TAC:MF6234, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARGO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. Project stage: Request GO2-15-081, Supplement to Exigent License Amendment Request - Extension of Implementation Period for Amendment 2322015-05-19019 May 2015 Supplement to Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Project stage: Supplement ML15141A2762015-05-28028 May 2015 Public Notice of Application for Amendment, Extension of Implementation Period for Amendment 232 Revision of Technical Specification Table 3.3.1.1-1, Function 7, Scram Discharge Volume Water Level - High Project stage: Acceptance Review ML15141A2722015-05-28028 May 2015 Letter, Public Notice of Application for Amendment, Extension of Implementation Period for Amendment 232 Revision of Technical Specification Table 3.3.1.1-1, Function 7, Scram Discharge Volume Water Level - High Project stage: Acceptance Review ML15154A8002015-06-11011 June 2015 Issuance of Amendment No. 235, Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1, Function 7, Scram Discharge Volume Water Level - High (Exigent Circumstances) Project stage: Approval 2015-05-19
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Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-21-133, License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-11-0909 November 2021 License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GO2-21-016, License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits2021-10-13013 October 2021 License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits GO2-21-042, License Amendment Request to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement2021-05-0808 May 2021 License Amendment Request to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement GO2-20-104, On-Site Cooling System Sediment Disposal2020-12-21021 December 2020 On-Site Cooling System Sediment Disposal GO2-20-108, License Amendment Request to Adopt TSTF-439, Elinate Second Completion Times Limitng Time from Discovery of Failure to Meet an LCO2020-12-0202 December 2020 License Amendment Request to Adopt TSTF-439, Elinate Second Completion Times Limitng Time from Discovery of Failure to Meet an LCO GO2-20-095, Application to Revise Technical Specifications to Adopt TSTF-582, 'Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, 'Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements GO2-20-063, Exigent License Amendment Request for Extension of Implementation Period for Amendment 255 Change to Control Room Air Conditioning System2020-04-15015 April 2020 Exigent License Amendment Request for Extension of Implementation Period for Amendment 255 Change to Control Room Air Conditioning System GO2-20-052, Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems2020-04-15015 April 2020 Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems GO2-20-004, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-01-27027 January 2020 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR GO2-20-008, License Amendment Request to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-01-27027 January 2020 License Amendment Request to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process GO2-19-090, License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-08-15015 August 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program GO2-19-053, License Amendment Request to Remove Operating License Condition 2.C.(11) and Attachment 32019-03-27027 March 2019 License Amendment Request to Remove Operating License Condition 2.C.(11) and Attachment 3 GO2-19-027, License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System2019-02-25025 February 2019 License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System GO2-17-137, License Amendment Request to Update Appendix B to the Renewed Facility Operating License to Incorporate 2017 Biological Opinion2017-12-18018 December 2017 License Amendment Request to Update Appendix B to the Renewed Facility Operating License to Incorporate 2017 Biological Opinion GO2-17-181, License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-12-12012 December 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements GO2-17-038, License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-10-23023 October 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. GO2-17-028, License Amendment Request for Change to Technical Specification 3.5.1, ECCS-Operating.2017-07-25025 July 2017 License Amendment Request for Change to Technical Specification 3.5.1, ECCS-Operating. GO2-17-009, License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies2017-03-27027 March 2017 License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies GO2-17-062, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 22017-03-27027 March 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2 GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A2016-11-0808 November 2016 License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A ML16243A5152016-08-30030 August 2016 License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System ML16244A8332016-08-30030 August 2016 License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System - Drawing M523-1-3, Revision 10, Flow Diagram Reactor Water Clean-up System Radwaste Bldg. ML16210A5282016-07-28028 July 2016 Request for Amendment to Emergency Plan GO2-16-087, License Amendment Request for Changes to Technical Specification 2.1.1, Reactor Core SLs2016-07-12012 July 2016 License Amendment Request for Changes to Technical Specification 2.1.1, Reactor Core SLs GO2-16-096, License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate2016-06-28028 June 2016 License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate GO2-16-079, Erratum for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance2016-05-18018 May 2016 Erratum for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance GO2-16-046, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance2016-05-10010 May 2016 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance GO2-16-047, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 02016-03-0303 March 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0 GO2-15-070, Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2015-09-0202 September 2015 Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process GO2-16-112, License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System - Drawing M523-3, Revision 10, Flow Diagram Reactor Water Clean-up System Radwaste Bldg.2015-06-17017 June 2015 License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System - Drawing M523-3, Revision 10, Flow Diagram Reactor Water Clean-up System Radwaste Bldg. GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. GO2-15-007, License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 32015-03-17017 March 2015 License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 3 ML14336A0062014-11-17017 November 2014 License Amendment Request for Technical Specification Change to Safety Limit Minimum Critical Power Ratio ML14268A2332014-09-0404 September 2014 Erratum for License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-14-126, License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink2014-08-22022 August 2014 License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink ML14234A4572014-08-12012 August 2014 License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-14-103, Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information2014-06-19019 June 2014 Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information ML14086A3892014-03-18018 March 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-535, Revision 0 ML13316A0092013-10-31031 October 2013 License Amendment Request for Change to Emergency Core Cooling Systems Surveillance Requirements GO2-13-138, License Amendment Request for Adoption of TSTF-493, Revision 4, Option a2013-10-0202 October 2013 License Amendment Request for Adoption of TSTF-493, Revision 4, Option a ML13247A6592013-07-25025 July 2013 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF 477, Revision 3 GO2-13-002, License Amendment Request to Implement Prnm/Arts/Mellla - Revised Reports2013-01-0707 January 2013 License Amendment Request to Implement Prnm/Arts/Mellla - Revised Reports GO2-12-003, License Amendment Request to Make Administrative and Editorial Changes to Technical Specifications and the Operating License2012-01-0909 January 2012 License Amendment Request to Make Administrative and Editorial Changes to Technical Specifications and the Operating License 2024-01-30
[Table view] Category:Technical Specification
MONTHYEARGO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-21-016, License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits2021-10-13013 October 2021 License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits GO2-20-004, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-01-27027 January 2020 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR ML19343C0352019-12-0505 December 2019 Rev. 111 to Licensee Controlled Specifications Manual - Part 2 of 2 GO2-19-098, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2019-09-12012 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules GO2-19-123, Supplemental Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems-Operating2019-08-19019 August 2019 Supplemental Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems-Operating GO2-19-119, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-15015 August 2019 Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating ML17355A6562017-12-21021 December 2017 Technical Specification Bases GO2-17-181, License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-12-12012 December 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements GO2-17-194, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-11-15015 November 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control GO2-17-022, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 02017-01-19019 January 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 0 GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A2016-11-0808 November 2016 License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 32016-07-14014 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 GO2-16-096, License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate2016-06-28028 June 2016 License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML15355A4812015-12-21021 December 2015 Revision 87 to Technical Specification Bases GO2-15-070, Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2015-09-0202 September 2015 Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process2015-08-11011 August 2015 Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. GO2-15-007, License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 32015-03-17017 March 2015 License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 3 GO2-14-139, Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 232014-10-31031 October 2014 Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 23 GO2-14-126, License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink2014-08-22022 August 2014 License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink ML14010A0302014-02-11011 February 2014 Issuance of Amendment No. 227, Request to Adopt Technical Specification Task Force (TSTF)-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystem ML14010A2902013-12-30030 December 2013 Columbia, 10 CFR 50.71 Maintenance of Records Licensing Basis Document Update ML13247A6592013-07-25025 July 2013 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF 477, Revision 3 GO2-13-043, Request for Technical Specification Interpretation Regarding the Offsite Power Supplies to the Onsite Class 1E AC Power Distribution System2013-03-13013 March 2013 Request for Technical Specification Interpretation Regarding the Offsite Power Supplies to the Onsite Class 1E AC Power Distribution System ML12011A1492011-12-14014 December 2011 Columbia, Technical Specification (TS) Basis, Rev. 69, Licensee Controlled Specifications (LCS) Rev. 67 and Operational Quality Assurance Program Description (Oqapd), Rev. 44 ML1013903692010-05-11011 May 2010 Columbia Generating Station, License Amendment Request to Change Technical Specifications in Support of Prnm/Arts/Mella Implementation GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-4752009-01-14014 January 2009 License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475 ML0826100562008-09-30030 September 2008 Tech Spec Pages for Amendment No. 210 Revised TS 3.3.5.2 RCIC System Instrumentation, and TS 3.5.2 ECCS-Shotdown to Increase Storage Tank Level GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 12008-09-0909 September 2008 License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1 ML0822506802008-07-16016 July 2008 Columbia - License Amendment Request for Changes to Technical Specifications Involving Core Operating Limits Report and Scram Time Testing GO2-08-071, License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities2008-05-0707 May 2008 License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities GO2-07-123, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-08-0808 August 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)2007-07-30030 July 2007 Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP) GO2-07-112, License Amendment Request for Proposed Changes to Technical Specifications: Miscellaneous Administrative Changes Including Adoption of Approved TSTF Travelers 284, 479, and 4852007-07-30030 July 2007 License Amendment Request for Proposed Changes to Technical Specifications: Miscellaneous Administrative Changes Including Adoption of Approved TSTF Travelers 284, 479, and 485 GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves2007-07-30030 July 2007 License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-07-26026 July 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level ML0709204712007-05-0101 May 2007 Technical Specification Pages - Issuance of Amendment No. 204 AC and DC Electrical Power ML0706400652007-03-23023 March 2007 Technical Specification, AC Sources - Operating 3.8.1 GO2-07-024, GO2-07-024 - Columbia Generating Station - Exigent License Amendment Request - Amend Operating License to Revise TS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers2007-02-0202 February 2007 GO2-07-024 - Columbia Generating Station - Exigent License Amendment Request - Amend Operating License to Revise TS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test2006-04-18018 April 2006 Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test GO2-06-042, Revised Technical Specification Bases Change (for Information) and Summary of Commitments Associated with the License Amendment Requests for Extension of Diesel Generator Completion Time2006-03-20020 March 2006 Revised Technical Specification Bases Change (for Information) and Summary of Commitments Associated with the License Amendment Requests for Extension of Diesel Generator Completion Time GO2-05-184, Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.12005-11-15015 November 2005 Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.1 ML0507000912005-03-0909 March 2005 Technical Specification Pages (Amd. 190) Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval2004-08-0505 August 2004 Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval ML0415405452004-05-19019 May 2004 Application for Amendment of Facility Operating for Extension of Diesel Generator Completion Time GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal2002-11-27027 November 2002 Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal 2023-05-01
[Table view] Category:Amendment
MONTHYEARGO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-20-004, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-01-27027 January 2020 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR GO2-19-098, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2019-09-12012 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules GO2-19-119, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-15015 August 2019 Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-17-181, License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-12-12012 December 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements GO2-17-194, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-11-15015 November 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control GO2-17-022, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 02017-01-19019 January 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 0 GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A2016-11-0808 November 2016 License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process2015-08-11011 August 2015 Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. ML14010A0302014-02-11011 February 2014 Issuance of Amendment No. 227, Request to Adopt Technical Specification Task Force (TSTF)-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystem ML13247A6592013-07-25025 July 2013 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF 477, Revision 3 GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-4752009-01-14014 January 2009 License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475 ML0826100562008-09-30030 September 2008 Tech Spec Pages for Amendment No. 210 Revised TS 3.3.5.2 RCIC System Instrumentation, and TS 3.5.2 ECCS-Shotdown to Increase Storage Tank Level GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 12008-09-0909 September 2008 License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1 ML0822506802008-07-16016 July 2008 Columbia - License Amendment Request for Changes to Technical Specifications Involving Core Operating Limits Report and Scram Time Testing GO2-08-071, License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities2008-05-0707 May 2008 License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities GO2-07-123, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-08-0808 August 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves2007-07-30030 July 2007 License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)2007-07-30030 July 2007 Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP) GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-07-26026 July 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level ML0709204712007-05-0101 May 2007 Technical Specification Pages - Issuance of Amendment No. 204 AC and DC Electrical Power ML0706400652007-03-23023 March 2007 Technical Specification, AC Sources - Operating 3.8.1 GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test2006-04-18018 April 2006 Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test GO2-05-184, Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.12005-11-15015 November 2005 Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.1 ML0507000912005-03-0909 March 2005 Technical Specification Pages (Amd. 190) Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval2004-08-0505 August 2004 Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval ML0415405452004-05-19019 May 2004 Application for Amendment of Facility Operating for Extension of Diesel Generator Completion Time GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal2002-11-27027 November 2002 Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal GO2-02-111, Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.12002-07-16016 July 2002 Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.1 2023-05-01
[Table view] |
Text
W. Grover Hettel ENERGY Columbia Generating Station P.O. Box 968, PE23 NORTHWEST Richland, WA 99352-0968 Ph. 509.377.8311 I F. 509.377.4150 wghettel@energy-northwest.com MAY 15 2015 G02-15-075 10 CFR 50.90 10 CFR 50.91 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 EXIGENT LICENSE AMENDMENT REQUEST - EXTENSION OF IMPLEMENTATION PERIOD FOR AMENDMENT 232 CHANGING TECHNICAL SPECIFICATION TABLE 3.3.1.1-1FUNCTION7 "SCRAM DISCHARGE VOLUME WATER LEVEL - HIGH"
Dear Sir or Madam:
Pursuant to 1O CFR 50.90, "Application for amendment of license or construction permit," and 10 CFR 50.91 (a)(6) (exigent requests) Energy Northwest is requesting exigent approval for a license amendment to extend the implementation period for License Amendment No. 232 to Renewed Facility Operating License No. NPF-21 for Columbia Generating Station (Columbia). License Amendment No. 232 was issued on March 27, 2015.
The need for the proposed change is based on unforeseen equipment test qualification delays associated with the replacement AMETEK trip units. As discussed with Nuclear Regulatory Commission (NRG) staff on May 8 and 11, 2015, an exigent license amendment request is needed to ensure compliance with operating license requirements. This request is purely administrative in nature, in that it will defer the implementation date of License Amendment No. 232 from the current refueling outage (R-22) to the following refueling outage (R-23), scheduled for spring 2017. contains an evaluation of the proposed changes.
Energy Northwest requests approval of the proposed amendment by June 13, 2015, to support the scheduled end date of the current refueling outage.
This letter and its enclosures contain no regulatory commitments.
Using the standards in 1O CFR 50.92, "Issuance of amendment," Energy Northwest has concluded that the proposed change does not constitute a significant hazards consideration as described in the enclosed analysis performed in accordance with 1O CFR 50.91 (a)(1 ).
G02-15-075 Page 2 of 2 In accordance with 1O CFR 50.91, "Notice for public comment; State consultation,"
Energy Northwest is notifying the State of Washington of this amendment request by transmitting a copy of this letter and its attachment to the designated state official.
If there are any questions or if additional information is needed, please contact Ms. L. L.
Williams, Licensing Supervisor, at 509-377-8148.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on {"('\ A'f lC::.J d.D l 5.
Respectfully, W. G. Hettel Vice President, Operations
Attachment:
As stated cc: NRC RIV Regional Administrator NRC NRA Project Manager NRC Senior Resident lnspector/988C CD Sonoda - BPA/1399 (email)
JO Luce - ESFEC (email)
RR Cowley - WDOH (email)
GO2-15-075 Page 1 of 8 Evaluation of Proposed Change 1.0
SUMMARY
DESCRIPTION This evaluation supports an exigent license amendment request to extend the implementation period for License Amendment No. 232, Changing Technical Specification (TS) Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level -
High, (Reference 1) to ensure compliance with Renewed Facility Operating License No. NPF-22 for Columbia Generating Station (Columbia).
Energy Northwest proposes to extend the implementation period associated with License Amendment No. 232 from the currently approved prior to restarting from refueling outage R-22, scheduled for spring 2015 to prior to restarting from refueling outage R-23, scheduled for spring 2017.
By letter dated March 27, 2015, the NRC issued License Amendment No. 232 for Columbia. The amendment revised TS Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 7.b to change the term Float Switch to Transmitter/Level Switch and add footnotes (d) and (e) to SR 3.3.1.1.10 for the new scram discharge volume instrumentation scheduled to be installed during the upcoming refueling outage.
The amendment also approved administrative changes to Function 7.a to change the term Transmitter/Trip Unit to Transmitter/Level Indicating Switch and add Surveillance Requirement (SR) 3.3.1.1.1 to require 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 />. This amendment was requested by Energy Northwest letter to NRC dated March 24, 2014 (Reference 2).
The amendment was effective as of the date of issuance and is required to be implemented prior to restarting from refueling outage R-22.
Energy Northwest has encountered unexpected difficulty and delays in qualifying the new scram discharge volume instrumentation electronic level switches (also referred to as trip units) to satisfy electromagnetic interference (EMI) and radio frequency interference (RFI) test requirements as part of the design change. This creates a potential challenge to nuclear safety as these interferences could affect the trip units -
either causing or preventing a reactor scram. The design change is now to be implemented during the subsequent refueling outage (R-23), scheduled to begin during May 2017. As such, Energy Northwest requests to delay implementation of the amendment for one refueling outage.
The functional objective of the design change is to address issues with the existing scram discharge instrument volumes, level instruments and associated small bore, socket welded piping and valves, which are inherent crud traps that have resulted in elevated general area radiation levels and increased personnel dose exposure.
Operation for an additional cycle with the existing instrumentation will have no impact on nuclear safety. Administrative controls will continue to be utilized to minimize radiation
GO2-15-075 Page 2 of 8 dose to personnel. As such, Energy Northwest requests an extension for implementation of License Amendment No. 232 to prior to startup from the Columbia spring 2017 refueling outage R-23.
Exigent Circumstances:
The Commission's regulations, 10 CFR 50.91, contain provisions for issuance of amendments when the usual 30-day public notice period cannot be met. One type of special exception is an exigency. An exigency is a case where the staff and licensee need to act promptly. In this case, Energy Northwest cannot implement an amendment within the implementation date agreed upon, and therefore a new date must be agreed upon to avoid delaying startup from refueling outage R-22. Pursuant to 10 CFR 50.91(a)(6), Energy Northwest is requesting the proposed amendment on an exigent basis.
Under such circumstances, the Commission notifies the public in one of two ways:
(A) Issue a Federal Register notice providing notice of an opportunity for hearing and allowing at least two weeks from the date of the notice for prior public comment; or (B) Use local media to provide reasonable notice to the public in the area surrounding a licensee's facility, consulting with the licensee on the proposed media release and on the geographical area of its coverage; 2.0 DETAILED DESCRIPTION In Reference 2, Energy Northwest requested revision of the specified function description and SRs in Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 7, Scram Discharge Volume Water Level - High. The proposed changes support a planned upgrade to Columbias Reactor Protection System (RPS) Scram Discharge Volume (SDV) Water Level - High instrumentation. The instrument replacements are part of a larger plant modification to replace the two scram discharge instrument volume tanks with new stainless steel tanks and fittings that will reduce future crud accumulation and recurring radiation dose exposure to plant personnel.
The existing instrumentation for TS Table 3.3.1.1-1 Function 7.b are Magnetrol level switches. These switches are mechanical float-type switches. They will be replaced by Rosemount 3152N Level Transmitters and the AMETEK ET-1200 series non-indicating trip units.
Energy Northwest has encountered difficulties and delays in qualifying the AMETEK trip units to satisfy EMI/RFI test requirements. The trip units required commercial grade dedication by a qualified vendor in order to qualify the parts for safety related applications. Receipt of the parts from the vendor was significantly delayed, and did not
GO2-15-075 Page 3 of 8 occur until early March 2015. As part of the dedication process, EMI/RFI testing (meeting Regulatory Guide 1.180) was performed. When qualification testing was completed, Energy Northwest was notified that modifications to the trip units had been made in order to obtain acceptable test results, requiring Energy Northwest to re-evaluate the suitability of the new instruments in our application including updating the design control documents to reflect the modified instruments.
In early April 2015, Energy Northwest completed mock-up testing onsite and determined that the modification and external wiring requirements for the trip units received from the vendor were incompatible with our application and thus would require requalification to match plant configuration. Removal of modifications and requalification of the trip units with wiring that represents the actual plant signals was required, and limited EMI/RFI testing by the vendor was conducted in late April and early May. This testing revealed that additional modifications were required in order to show acceptable resistance to EMI/RFI in configurations that match plant installation.
As a result, the trip units must be returned to the vendor for reconfiguration, dedication and requalification. Discussions with the vendor indicate that five weeks is required to complete these tasks on an expedited schedule; this will be followed by on-site acceptance testing by Energy Northwest resulting in an overall extension of the current outage duration of 14 days.
Based on the difficulties and delays with dedication and qualification experienced to date, Energy Northwest has elected to delay implementation of the proposed design change to the next refueling outage. Operation for an additional cycle with the existing configuration will have no impact on nuclear safety since existing instrument volumes and instrumentation maintain the required redundancy, diversity and capacity to ensure there is sufficient volume available to accommodate a reactor scram.
3.0 TECHNICAL EVALUATION
The request for extending the implementation period is not a technical or safety issue.
The proposed change is purely an administrative change. In issuing an amendment to an operating license, the NRC staff states when the amendment is effective and when the amendment must be implemented. These dates are given in Enclosure 1 of the amendment and are part of the operating license. As such, a change to the implementation date is a change to the operating license for the plant. Although there are no regulatory requirements on the implementation date specified in an amendment, the licensee is required by the operating license to fully implement the amendment by the date specified (i.e., by a date no later than that specified).
In addition, an evaluation of the impact of the delay on each change to TS Table 3.3.1.1-1 approved in Reference 1 is provided below:
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- Revise the title of the Function 7.a instruments from Transmitter/Trip Unit to Transmitter/Level Indicating Switch.
Evaluation: The change in title is purely administrative. The proposed term more accurately describes the capability of the existing instrumentation to provide level indication. Since this is an administrative change, there is no impact by delaying implementation of License Amendment No. 232.
- Revise the title of the Function 7.b instruments from Float Switch to Transmitter/Level Switch.
Evaluation: The design change to physically replace the existing float switches is deferred to the next refueling outage. As such, the existing instruments will remain installed for an additional cycle. The existing float switches have acceptable performance; therefore, there is no impact by delaying implementation of License Amendment No. 232.
- Add SR 3.3.1.1.1 to Function 7.a to require 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 />.
Evaluation: As stated in Reference 2, Energy Northwests procedures currently require 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 /> and require declaring the Limiting Condition for Operation (LCO) not met for a failure of the channel check.
The lack of a SR for performing channel checks on the Function 7.a instruments is a legacy issue which is being managed in accordance with NRC guidance in Administrative Letter 98-10. Upon discovery of this condition, procedures were revised to require performance of the channel check and a corrective action was opened to add the requirement to the TS. Since the required channel checks are currently being performed and are controlled by procedure, there is no impact by delaying implementation of License Amendment No. 232.
- Add footnotes (d) and (e) to SR 3.3.1.1.10 for Function 7.b to reflect the requirements of TSTF-493, Revision 4, Option A.
Evaluation: This change was a result of the change in instrumentation proposed for Function 7.b. The existing float switches are excluded from the scope of TSTF-493 since they are mechanical devices. The existing instruments will remain installed for an additional cycle and there is no impact by delaying implementation of License Amendment No. 232.
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4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Energy Northwest has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the license. The following applicable regulations and regulatory requirements were reviewed in making this determination: 10 CFR 50.90, 10 CFR 50.91, and 10 CFR 50.92. The existing plant design continues to comply with all regulatory requirements.
4.2 Precedent Three similarly related license amendments involving extensions to license amendment implementation due dates were approved and are summarized below:
- 1. Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment Re: Revision to the Implementation Date for Cooldown Rates for Pressure-Temperature Limits (TAC NOS. MC2183 AND MC2184), dated April 4, 2004. The license amendment extended the implementation date of new cooldown rates for pressure-temperature (P-T) limits that were established for Amendment Nos. 261 and 238 for Calvert Cliffs, Unit Nos. 1 and 2, respectively, to July 1, 2004.
Although the existing reactor pressure vessel P-T limit cooldown rates were non-conservative over the life of the units, they remained valid through the end of 2004 and there was no technical issue with implementing the Amendment Nos.
261 and 238 changes until after the 2004 outage. The NRC staff found the proposed delay of implementation acceptable. (ML040640795)
- 2. Joseph M. Farley Nuclear Plant - Issuance of Amendment Regarding Change of Implementation Date for Amendment No. 176 for Unit 2 (TAC NO. ME3445),
dated May 10, 2010. The license amendment extended the implementation date for deletion of the reactor coolant pump breaker position reactor trip function from the TS one additional cycle due to unforeseen difficulties encountered with respect to delays in the receipt of design input from the original equipment manufacturer and the resulting impact on the schedule for implementing the modification during the originally scheduled refueling outage. The NRC staff did not identify a safety-related issue concerning the modification date extension.
The NRC staff found that the primary and secondary features of the reactor protection system providing protection from partial or complete loss of flow that are relied upon in the safety analyses, remained in effect and the delay in implementation date acceptable. (ML101100668)
- 3. Limerick Generating Station, Unit 2 - Issuance of Exigent Amendment Re:
Extend Implementation Period for Amendment No. 174 - Leak Detection System
GO2-15-075 Page 6 of 8 Setpoint and Allowable Value Changes (TAC NO. MF5695) dated February 25, 2015. The license amendment extended the implementation date for changes to instrument setpoints and allowable values associated with the leak detection system due to unforeseen difficulties associated with calibration of a temperature indicating switch. The NRC staff found that the proposed extension of the implementation period was purely administrative in nature and that operation of the plant with the currently calibrated setpoints (i.e., setpoints prior to approval of Amendment No. 174) did not raise any safety concerns and was acceptable.
(ML15049A084) 5.0 SIGNIFICANT HAZARDS CONSIDERATION Energy Northwest has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The amendment implementation schedule extension does not increase the probability or consequences of an accident previously evaluated in the Final Safety Analysis Report. The change in the implementation schedule of the scram discharge volume instrumentation float switches and Technical Specification changes will have no impact on the initiation or the consequences of any accidents previously evaluated. Technical Specification requirements that govern operability or routine testing of plant instruments are not assumed to be initiators of any analyzed event.
The change in implementation schedule will not increase the consequences of an accident since the existing scram discharge volume instrumentation is in accordance with the plants design and licensing bases. All acceptance criteria continue to be met. Therefore there is no significant increase in the probability or consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously analyzed?
Response: No.
There are no postulated hazards, new or different, contained in this amendment.
The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any
GO2-15-075 Page 7 of 8 plant systems or components, or entail changes in plant operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed amendment implementation schedule extension is administrative in nature and does not require any physical plant modifications, physically affect any plant systems or components, or entail changes in plant operation. The existing scram discharge volume instrumentation maintains the required redundancy, diversity and capability to ensure there is sufficient volume available to accommodate a reactor scram. Therefore, the proposed change does not involve a significant reduction in the margin of safety.
Based on the above, Energy Northwest concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.
6.0 CONCLUSION
S Based on the considerations discussed above: (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 applicable regulations as identified herein, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 ENVIRONMENTAL CONSIDERATION
Energy Northwest has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within Columbia's restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, Energy Northwest has evaluated the proposed change and has determined that the change does not involve, (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion in accordance with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
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8.0 REFERENCES
- 1. Columbia Generating Station - Issuance Of Amendment Re: License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, "Scram Discharge Volume Water Level - High" (TAC NO. MF3673) dated March 27, 2015 (ML15063A010)
- 2. Letter GO2-14-043 dated March 24, 2014, AL Javorik (Energy Northwest) to NRC, License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High (ML14098A400)