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Category:Letter type:CNRO
MONTHYEARCNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process2022-05-26026 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) CNRO-2020-00015, Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)2020-06-0808 June 2020 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) CNRO-2020-00009, Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 12020-02-26026 February 2020 Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 1 CNRO-2020-00006, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 22020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 CNRO-2020-00008, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 22019-03-0707 March 2019 Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2017-00005, and Isfsl - License Amendment Request for Administrative Change to Licensee Name2017-03-29029 March 2017 and Isfsl - License Amendment Request for Administrative Change to Licensee Name CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1. CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual CNRO-2015-00011, Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 20142015-03-27027 March 2015 Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 2014 CNRO-2015-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2015-03-27027 March 2015 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2014-00009, Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations2014-07-24024 July 2014 Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2014-00004, Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/20142014-04-0303 April 2014 Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/2014 CNRO-2014-00001, Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-0962014-02-26026 February 2014 Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-096 CNRO-2013-00011, Notice Regarding Renewal of Lease2013-12-0303 December 2013 Notice Regarding Renewal of Lease CNRO-2013-00009, Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc2013-06-20020 June 2013 Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2013-00006, Decommissioning Funding Status Report - Entergy Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report - Entergy Operations, Inc CNRO-2013-00004, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2013-03-25025 March 2013 Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications CNRO-2012-00007, Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc2012-10-15015 October 2012 Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc 2022-05-26
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Entergy Operations, Inc.
Entergy 1340 Echelon Parkway Jackson. Mississippi 39213-8298 Tel 601-368-5758 F. G. Burford Acting Director Nuclear Safety & Licensing CNRO-2004-00035 May 27, 2004 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Request for Relief GGNS-PRR-E21-02 for the Low Pressure Core Spray Pump 2nd IST Ten-Year Interval
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Operations, Inc. (Entergy) hereby requests NRC approval of the following request for the 2nd ten-year interval of the Inservice Testing Program:
On a one time basis the testing frequency of the Low Pressure Core Spray Pump will be extended until Refueling Outage 14, scheduled for Fall 2005. After the outage the testing frequency will be returned to the original testing frequency.
The details of the 10 CFR 50.55a request are enclosed.
Should you have any questions regarding this request, please contact Bill Brice at (601) 368-5076.
This letter contains new commitments as identified in Attachment 2.
Very truly yours, FGB/WBB/bal Attachments: 1. Request for Alternative No. GGNS- PRR-E21-02
- 2. Licensee-identified Commitments cc: (See Next Page)
CNRO-2004-00035 Page 2 of 2 cc: Mr. W. A. Eaton (ECH)
Mr. G. A. Williams (GGNS)
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 U. S. Nuclear Regulatory Commission Attn: Mr. Bhalchandra Vaidya MS 0-7D1 Washington, DC 20555-0001 Mr. T. L. Hoeg, GGNS Senior Resident Mr. D. E. Levanway (Wise Carter)
Mr. L. J. Smith (Wise Carter)
Mr. N. S. Reynolds Mr. H. L. Thomas
ATTACHMENT 1 CNRO-2004-00035 REQUEST FOR ALTERNATIVE GGNS-PRR-E21-02
REQUEST FOR RELIEF GGNS PRR-E21-02 DATE: 5-27-2004 PAGE 1 OF 3 SYSTEM Low Pressure Core Spray i E21 Component BPV Code Type Component Function Identification Class E21C001 2 Motor Driven Low Pressure Core Spray Vertical Line Shaft (LPCS)
COMPONENT FUNCTION The LPCS pump automatically starts to provide flow to the reactor greater than or equal to 7115 gpm with 128 psid (differential) between reactor vessel and suppression pool air volume outside the Drywell. The LPCS pump automatically starts to deliver flow to the reactor when vessel pressure is below 295 psid (differential) between reactor vessel and suppression pool air volume outside the Drywell.
ASME CODE TEST REQUIREMENTS ASME/ANSI Standard OMa-1988, Part 6, ulnservice Testing of Pumps in Light-Water Reactor Power Plants"(OM-6), paragraph 5.1, requires an inservice test for each pump, nominally every 3 months except as provided for pumps in regular use, pumps in systems out of service, and pumps lacking required fluid inventory (OM-6, paragraphs 5.3, 5.4, and 5.5).
BASIS FOR RELIEF
Background
LPCS pump testing normally involves opening valve E21 F01 2, which is a single containment isolation valve located on a 14 inch return line to the suppression pool. This return line is designed to allow full flow testing of the LPCS pump without injecting water into the reactor pressure vessel by taking water from, and returning it to, the suppression pool. Valve E21 F01 2 isolates this return path to the suppression pool to ensure that the pump discharge would be directed to the vessel if needed. In addition, the valve must also be closed to allow the jockey pump to keep the system filled when the LPCS pump is in standby.
GGNS Technical Specifications, Surveillance Requirement 3.5.1.4 requires that the LPCS pump develop a flow rate of 27115 gpm at a total developed head >290 psid (this differential is more conservative than the design value of 128 psid as provided in the Component Function statement above). The Frequency for performance of the surveillance is "in accordance with the Inservice Testing Program". The GGNS Inservice Testing Program includes a quarterly flow test for the LPCS pump and is used to implement the Technical Specification requirement.
REQUEST FOR RELIEF GGNS PRR-E21-02 DATE: 5-27-2004 PAGE 2 OF 3 During the last full flow test of the LPCS pump, problems were encountered when closing valve E21 F012. Analyses have been done to determine the condition of the valve. Currently the valve is secured in the closed position and is considered to be performing its safety functions.
Valve E21 F012 information is as follows.
Component BPV Code Size OM Code Identification Class (Inches) Category E21F012 2 14 A Basis The following provide reasonable assurance that the pump is operationally ready:
- A thorough review of the LPCS pump flow test results that includes all tests from 1991 to present was conducted. All the test results indicate good pump performance. The data is consistent and results are well below the "alert" level. The last test (April 28, 2004) also indicated acceptable results.
- The LPCS pump is normally in the standby mode and is not operated routinely except for testing. The LPCS pump is not subject to the wear and the consequential degradation of a pump that is in continuous service.
- The LPCS pump is operable and capable of performing its safety function. Valve E21 F012 is not required to open in order for the system or the pump to perform its safety function. It is only required to be closed.
Compliance with the specified requirements of OM-6, paragraph 5.1 to perform the pump quarterly test would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. This is demonstrated by the following:
- The required flow test of the LPCS pump cannot be performed without the E21 F012 being open. The valve is currently closed and deactivated with the associated breaker open.
- Because the valve is a single containment isolation valve and there is no isolation capability between it and the containment, the containment would have to be breached and Technical Specification 3.6.1.1 Limiting Condition for Operation (LCO) would have to be entered in order to repair or replace the valve. This LCO only allows 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the breach. Otherwise, a plant shutdown must be completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- Certain parts required to repair the valve (i.e., valve body and stem plug assembly) are not currently available. Some of these parts have long lead times because they are custom built and forged.
PROPOSED ALTERNATIVE TESTING Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy proposes the following alternative to the testing frequency specified above. On a one time basis the testing frequency will be extended until Refueling Outage 14, scheduled for Fall 2005. After the outage, the testing frequency will be returned to the original testing frequency.
REQUEST FOR RELIEF GGNS PRR-E211-02 DATE: 5-27-2004 PAGE 3 OF 3 CONCLUSIONS 10 CFR 50.55a(a)(3) states:
Proposed alternatives to the requirements of (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i) The proposed alternatives would provide an acceptable level of quality and safety, or (ii) Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Entergy believes that there is reasonable assurance that the pump is operationally ready and that compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Entergy requests that the NRC staff authorize the proposed alternative frequency of testing as described above pursuant to 10 CFR 50.55a(a)(3)(ii).
ATTACHMENT 2 CNRO-2004-00035 LICENSEE-IDENTIFIED COMMITMENTS GGNS-PRR-E21-02 to CNRO-2004-00035 Page 1 of 1 LICENSEE-IDENTIFIED COMMITMENT The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Ch ck one) SCHEDULED COMPLETION ONE-TIME CONTINUING DATE COMMITMENT ACTION COMPLIANCE (If Required)
After Refueling Outage 14, scheduled for Fall Per IST After RF 14 2005, the testing frequency for the LPCS pump Program will be returned to the original testing frequency specified in the IST Plan, Program Section No.
CEP-IST-2. Reference Relief Request No.
GGNS-PRR-E21-02.