Letter Sequence Supplement |
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MONTHYEARJAFP-21-0028, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-04-16016 April 2021
Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
Project stage: Request
ML21144A1072021-05-17017 May 2021
Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582
Project stage: Acceptance Review
JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021
Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
Project stage: Supplement
ML21300A3552021-11-16016 November 2021
Issuance of Amendment No. 345 Adoption of TSTF-582
Project stage: Approval
2021-04-16
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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023
License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications
JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023
and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023
Emergency Plan Document Revision
JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023
Registration of Spent Fuel Cask Use
JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023
Registration of Spent Fuel Cask Use
JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023
Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023
Physical Security Plan, Revision 24
JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023
License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023
10 CFR 50.46 Annual Report
JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023
License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance
JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023
License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation
JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
2022 Annual Radiological Environmental Operating Report
JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report
JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023
2022 REIRS Transmittal of NRC Form 5
JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023
Supplement to Inservice Inspection Summary Report Cycle 25
JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022
Inservice Inspection Summary Report Cycle 25
JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022
Core Operating Limits Report Cycle 26
JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022
10 CFR 50.46 Annual Report
JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022
Core Operating Limits Report Mid-Cycle 25
JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022
Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..
JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022
Oswego County and New York State Participation in the Emergency Plan
JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022
2021 Annual Radioactive Effluent Release Report
JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022
2021 REIRS Transmittal of NRC Form 5
JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022
Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed
JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022
Amendments to Indemnity Agreements
JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022
Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022
Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments
JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022
Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary
JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021
Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021
Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021
Notification of Readiness for NRC 95001 Inspection
JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021
Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021
Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs
JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021
Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.
JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021
Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b
JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021
10 CFR 50.46 Annual Report
JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021
Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021
Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021
Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021
Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021
Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021
Reply to a Notice of Violation; EA-20-138
JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021
Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021
Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
2023-08-31
[Table view] |
Text
200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 JAFP-21-0081 September 3, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
SUBJECT:
Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
References:
- 1. Letter from Dave T. Gudger (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, License Amendment Request -
Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC)
Enhancements dated April 16, 2021.
- 2. E-mail from Justin Poole (Nuclear Regulatory Commission Project Manager for the James A. FitzPatrick Nuclear Power Plant) to Christian Williams (Exelon Nuclear Principal Licensing Engineer) titled Items the staff noticed while reviewing TSTF-582 LAR dated August 11, 2021.
By letter dated April 16, 2021, Exelon Generation Company, LLC (Exelon) submitted a license amendment request to revise Technical Specifications (TS) to Adopt TSTF-582 Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements.
By electronic mail dated August 11, 2021 (Reference 2), the NRC identified areas where corrections to the submitted TS Markup pages were necessary to complete the review. These corrections were discussed with the NRC Staff in a clarification call held on August 12, 2021. It was agreed that corrected TS Markup pages would be submitted in the form of this supplement. to this letter contains the superseded TS Markup pages followed by the corrected TS Markup pages which will replace the corresponding TS Markup pages provided in the original submittal.
Supplement to Application to Adopt TSTF-582, Revision 0 September 3, 2021 Page 2 Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The information attached to this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore, the information attached to this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no commitments contained in this response.
If you should have any questions regarding this submittal, please contact Christian Williams at 610-765-5729.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 3rd day of September 2021.
Respectfully, David T. Gudger Senior Manager, Licensing Exelon Generation Company, LLC Attachments: 1. Superseded and Corrected Technical Specification Markup pages cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector - JAF NRC Project Manager, NRR - JAF A. L. Peterson, NYSERDA
ATTACHMENT 1 Superseded and Corrected Technical Specification Markup pages TS Markup Pages Superseded 3.3.5.2.1 Corrected 3.3.5.2-1 Superseded 3.5.1-1 Corrected 3.5.1-1 Superseded 3.8.2-4 Corrected 3.8.2-4
RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The Reactor Pressure Vessel (RPV) Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.5.2-1.
immediately ACTIONS DED
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME inoperable.
PE A. One or more channels A.1 Enter the Condition referenced in Immediately A.1 Initiate action to place R
Table 3.3.5.2-1 for the channel. channel in trip OR Action A.1 and referenced in Table 3.3.5.2-1.
SE B. As required by Required B.1 A.2.1 Declare associated penetration flow path(s) incapable of automatic isolation.
Immediately A. One or more channels AND A.2.2 SU inoperable.
C. As required by Required B.2 C.1 Calculate DRAIN TIME.
Initiate action to c Place channel in trip.
Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced in Table 3.3.5.2-1.
D. As required by Required D.1 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action A.1 and OPERABLE status.
referenced in Table 3.3.5.2-1.
JAFNPP 3.3.5.2-1 Amendment 321
RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The Reactor Pressure Vessel (RPV) Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.5.2-1.
Immediately ACTIONS
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in A.1 Initiate action to Table 3.3.5.2-1 for the place channel in trip.
channel.
OR B. As required by Required B.1 Declare associated Immediately Action A.1 and penetration flow path(s) referenced in incapable of automatic Table 3.3.5.2-1. isolation.
A.2.1 A. One or more channels AND A.2.2 inoperable.
B.2 Calculate DRAIN TIME. Immediately Initiate action to calculate C. As required by Required C.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced in Table 3.3.5.2-1.
D. As required by Required D.1 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action A.1 and OPERABLE status.
referenced in Table 3.3.5.2-1.
JAFNPP 3.3.5.2-1 Amendment 321
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
- - - - - - - - - - - - - - - -- - - - - - - - - -NOTE - - - - - - - - -- - - - - - -- - - - - - -
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with APPLICABILITY: MODE 1, D
reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being ED manually realigned and not otherwise inoperable.
MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS PE High Pressure Core Spray (HPCI)
NOTE-------------------------------------------------------------
LCO 3.0.4.b is not applicable to HPCI.
R CONDITION SE REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem(s) to OPERABLE status.
SU OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in Mode 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
JAFNPP 3.5.1-1 Amendment 321
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
- - - - - - - - - - - - - - - -- - - - - - - - - -NOTE - - - - - - - - -- - - - - - -- - - - - - -
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
high pressure ACTIONS coolant injection
NOTE-------------------------------------------------------------
(HPCI)
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem(s) to OR OPERABLE status.
One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in Mode 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
JAFNPP 3.5.1-1 Amendment 321
AC Sources Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY and SR 3.8.2.1 ---------------------------NOTES---------------------
- 1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.
- 2. SR 3.8.1.10 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control."
DED For AC sources required to be OPERABLE the In accordance SRs of Specification 3.8.1, except with applicable SR 3.8.1.7, are applicable. SRs PE R
The following SRs are applicable for AC sources to be OPERABLE:
SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.3, SR 3.8.1.4, SR 3.8.1.5, SR SE 3.8.1.6, SR 3.8.1.8, and SR 3.8.1.11.
SU JAFNPP 3.8.2-4 Amendment 321
AC Sources Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY and SR 3.8.2.1 ---------------------------NOTES---------------------
- 1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.
- 2. SR 3.8.1.10 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control."
For AC sources required to be OPERABLE the In accordance SRs of Specification 3.8.1, except with applicable SR 3.8.1.7, are applicable. SRs The following SRs are applicable for AC sources required to be OPERABLE: SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.3, SR 3.8.1.4, SR 3.8.1.5, SR 3.8.1.6, SR 3.8.1.8, and SR 3.8.1.11.
JAFNPP 3.8.2-4 Amendment 321
