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| {{#Wiki_filter:* * * 'ATO* fllE COPY consumers . Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 | | {{#Wiki_filter:'ATO* fllE COPY consumers |
| * Area Code 517 788-0550 July 7, 1978 Director, Nuclear Reactor Regulation Att: :M.r Dennis L Ziemann, Chief' Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCK.ET 50-255 -LICENSE DPR-20 -PALISADES PI..ANT -DIESEL GENEFATORS CONTROL CIRCUITRY AND ALARMS CJ cl: ---\ ....... t:':'l _,,.-. | | * .Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 |
| :P--o_ .... :;;c:z;,v f'T1 ::::0 < 0 fTl (J? ...... ., -.J co c_ c: r-..,:..:..
| | * Area Code 517 788-0550 |
| .... '* 0 i\) OJ r.--J :: /) | | -*~ |
| ..-.::: t:J C"'..'l \::J rr: --* c.:::.:.:J
| | July 7, 1978 CJ -.J co -:-~I cl: r.--J |
| :r:o:; =ic -f CJ ..... In the NRC review of previous Consumers Power submittals, dated May 16, 1977 and July 12, 1977 related to diesel generators control circuitry at the Palisades Plant additional information was requested. | | ---\ c_ :: /) :_:_~ |
| The information requested and responses are as follows: Item 1 11 determine if the diesel generators are provided with a manual shutdown lockout relay .** " Response A manual shutdown relay does not exist in the Palisades Plant diesel generator control circuitry Item 2 "verify that an alarm is -provided. | | ....... c: |
| which clearly indicates when the diesel ge11erator control switch is not in the automatic position ..* " Resuonse The diesel generator control switch is always in the automatic position, except during testing. An indicator light on the control panel indicates when the switch is in the automatic position | | t:':'l r- ~~~:~~ |
| * Item 3 11 verify that all shared. ar!nunc1ar,ors for disabling c*Jnd.iticns cannot be until all condi ti ens a:re correete:i. " clearecL .. | | ..-.::: t:J |
| | ~~::~ ..,:..:...... '* C"'..'l \::J |
| | :P--o_.... rr: --* |
| | :;;c:z;,v 0)~ |
| | ~r.r>o c.:::.:.:J f'T1 |
| | ::::0 |
| | ~ :r:o:; |
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| | 0 -f CJ Director, Nuclear Reactor Regulation fTl (J? i\) ..... |
| | Att: :M.r Dennis L Ziemann, Chief' OJ Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCK.ET 50-255 - LICENSE DPR PALISADES PI..ANT - DIESEL GENEFATORS CONTROL CIRCUITRY AND ALARMS In the NRC review of previous Consumers Power submittals, dated May 16, 1977 and July 12, 1977 related to diesel generators control circuitry at the Palisades Plant additional information was requested. The information requested and responses are as follows: |
| | Item 1 11 determine if the diesel generators are provided with a manual shutdown lockout relay .** " |
| | |
| | ===Response=== |
| | A manual shutdown relay does not exist in the Palisades Plant diesel generator control circuitry Item 2 "verify that an alarm is -provided. which clearly indicates when the diesel ge11erator control switch is not in the automatic position ..* " |
| | Resuonse The diesel generator control switch is always in the automatic position, except during testing. An indicator light on the control panel indicates when the switch is in the automatic position * |
| | * Item 3 11 verify that all shared. ar!nunc1ar,ors for disabling c*Jnd.iticns cannot be clearecL .. |
| | until all abno:;,~mal condi ti ens a:re correete:i. " |
| | |
| 2 | | 2 |
| * Response * | | * Response Shared annunciators cannot be cleared until all abnormal conditions are cleared. |
| * Shared annunciators cannot be cleared until all abnormal conditions are cleared. To assist NRC staff in completing their review of this subject all previous responses are attached for clarity. Also, reference Consumers Power responses dated January 20, 1978 and February 2, 1978 (Diesel Generator Questionnaire) for additional information.
| | To assist NRC staff in completing their review of this subject all previous responses are attached for clarity. Also, reference Consumers Power responses dated January 20, 1978 and February 2, 1978 (Diesel Generator Questionnaire) for additional information. |
| Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC | | ~::~~ |
| * *
| | Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC |
| * ATTACHMENT Diesel Generators Control Circuitry and Alarms The following information is provided in response to your March 29, 1977 letter relating to alarm and diesel generator control circuitry for the Palisades Plant diesel generators. | | * ATTACHMENT Diesel Generators Control Circuitry and Alarms The following information is provided in response to your March 29, 1977 letter relating to alarm and diesel generator control circuitry for the Palisades Plant diesel generators. |
| Item (a) "All conditions that render the diesel generator incapable of responding to an automatic emergency start signal **** " Response (a) The following condition relays operate the shutdown relay which renders incapable of automatic start: 1. Generator differential relay. 2. Overcrank relay | | Item (a) |
| * 3. Jacket water temperature relay. 4. Overspeed relay. 5. Oil pressure relay 6. Loss of direct current control relay. Item (b) 11 The wording on the annuhciator window in the cont:::-ol room that is alarmed for each of the conditions identified in (a).11 Resnonse (b L The control room annunciator windows and the condition in (a) above which operates them: 1. Diesel Generator Breaker Trip 2. 3. Generator differential relay. Diesel Generator Fail To Start Overcrank relay . Diesel Generator Trouble a. Jacket water temperature relay. 1::. Ov-erspeed relay. c. Oil pressure relay. d. .Loss of d-c control power.
| | "All conditions that render the diesel generator incapable of responding to an automatic emergency start signal **** " |
| * *
| | Response (a) |
| * I* \l
| | The following condition relays operate the shutdown relay which renders the:~un:ilt incapable of automatic start: |
| * Item (c) "Any other alarm signals that also cause the same annunciator to alarm. '1 Response (c) Other alarm signals which share the annunciators listed in'(b) above: 1. Diesel Generator Breaker Trip Breaker contact position switch. 2. Diesel Generator Fail To Start None. 3. Diesel Generator Trouble a. High lube oil differential pressure. | | : 1. Generator differential relay. |
| | : 2. Overcrank relay * |
| | : 3. Jacket water temperature relay. |
| | : 4. Overspeed relay. |
| | : 5. Oil pressure relay |
| | : 6. Loss of direct current control relay. |
| | Item (b) 11 The wording on the annuhciator window in the cont:::-ol room that is alarmed for each of the conditions identified in (a). 11 Resnonse (b L The control room annunciator windows and the condition in (a) above which operates them: |
| | : 1. Diesel Generator Breaker Trip Generator differential relay. |
| | : 2. Diesel Generator Fail To Start |
| | * 3. |
| | Overcrank relay . |
| | Diesel Generator Trouble a. |
| | 1::. |
| | Jacket water temperature relay. |
| | Ov-erspeed relay. |
| | : c. Oil pressure relay. |
| | : d. .Loss of d-c control power. |
| | |
| | I* |
| | \l |
| | * Item (c) |
| | "Any other alarm signals that also cause the same annunciator to alarm. '1 Response (c) |
| | Other alarm signals which share the annunciators listed in'(b) above: |
| | : 1. Diesel Generator Breaker Trip Breaker contact position switch. |
| | : 2. Diesel Generator Fail To Start None. |
| | : 3. Diesel Generator Trouble |
| | : a. High lube oil differential pressure. |
| : b. Low lube oil temperature. | | : b. Low lube oil temperature. |
| : c. High lube oil temperature. | | : c. High lube oil temperature. |
| : d. Air supply tanks low pressure. | | : d. Air supply tanks low pressure. |
| : e. Jacket water level low. f. Low lube oil level g. Raw water pressure low | | : e. Jacket water level low. |
| * h. Prelube pressure low. Item (d) "Any condition that renders the diesel generator incapable of responding to an automatic emergency start signal which is not alarmed in the control room." Item (d) Resnonse Jacket water pressure low will not prevent auto start. This is the dition when the engine is not running. A high jacket water pressure will prevent the engine from starting. (The cranking relay will be isolated.)
| | : f. Low lube oil level |
| The reason for this is that a high jacket waterpressureindicates that the engine is running. This is the signal that turns off the starting motor after an engine start signal. Jacket water pressure is supplied only by the engine-driven water circulating pump. Item (e) "Any pr9posed modifications resulting from this evaluation." Item (e) Response The jacket water pressure will not be alarmed. A low pressure is normal while the engine is shut down. A high pressure is normal while the engine is running | | : g. Raw water pressure low * |
| * A high jacket water pressure is an impossible condition if the engine is not running for the following reasons: 1. Jacket water pressure is supplied only by the engine-driven water pump. 2. The cooling system is vented to at the cooling expansion tank.}} | | : h. Prelube pressure low. |
| | Item (d) |
| | "Any condition that renders the diesel generator incapable of responding to an automatic emergency start signal which is not alarmed in the control room." |
| | Item (d) Resnonse Jacket water pressure low will not prevent auto start. This is the nor~al con-dition when the engine is not running. A high jacket water pressure will prevent the engine from starting. (The cranking relay will be isolated.) The reason for this is that a high jacket waterpressureindicates that the engine is running. |
| | This is the signal that turns off the starting motor after an engine start signal. |
| | Jacket water pressure is supplied only by the engine-driven water circulating pump. |
| | Item (e) |
| | "Any pr9posed modifications resulting from this evaluation." |
| | Item (e) Response The jacket water pressure will not be alarmed. A low pressure is normal while the engine is shut down. A high pressure is normal while the engine is running |
| | * A high jacket water pressure is an impossible condition if the engine is not running for the following reasons: |
| | : 1. Jacket water pressure is supplied only by the engine-driven water pump. |
| | : 2. The cooling system is vented to at~osphere at the cooling wate~ expansion tank.}} |
|
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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARPNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-012, Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition2022-04-21021 April 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition 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 ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, 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 PNP 2019-034, Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification...2019-08-23023 August 2019 Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification... ML19149A3042019-05-28028 May 2019 Enclosure Attachment 1 (Continued) to Pnp 2019-028: Operating License Page Change Instructions and Retyped Renewed Facility Operating License Pages ML19149A3022019-05-28028 May 2019 Enclosure to Pnp 2019-028: Response to Request for Additional Information - License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications ML19149A3032019-05-28028 May 2019 Enclosure Attachment 1 to Pnp 2019-028: Renewed Facility Operating License Page Markups PNP 2019-003, Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement2019-02-0707 February 2019 Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement PNP 2018-059, Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations2018-12-0303 December 2018 Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations PNP 2018-023, Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-04-30030 April 2018 Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2018-018, Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel2018-04-16016 April 2018 Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel PNP 2018-014, Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-03-27027 March 2018 Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2017-075, Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition2017-12-19019 December 2017 Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition PNP 2017-020, Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval2017-04-0505 April 2017 Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval PNP 2016-055, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools.2016-10-25025 October 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools. PNP 2016-053, Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance2016-09-0808 September 2016 Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance PNP 2016-047, Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations2016-07-26026 July 2016 Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations PNP 2016-037, Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF74352016-06-0707 June 2016 Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF7435 ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) PNP 2016-016, Reply to Request for Information EA-16-0112016-03-0303 March 2016 Reply to Request for Information EA-16-011 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 PNP 2015-069, Response to Request for Additional Information Regarding Relief Request No. RR 5-22015-09-0909 September 2015 Response to Request for Additional Information Regarding Relief Request No. RR 5-2 PNP 2015-063, Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a2015-08-14014 August 2015 Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a PNP 2015-059, Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-07-31031 July 2015 Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML18344A4421993-11-30030 November 1993 Reply to NRC Request for Information Regarding the Pressurizer Safe End Crack Critical Flaw Size and Margin to Failure Analysis. Response to Items 10 and 11 of the Nrc'S October 8, 1993 Information Request ML18346A2931993-09-22022 September 1993 CPC Letter of 7/6/1993, Responding to Inspection Report 93010 & Subsequent Conference Call of 7/22/1993, Letter Submit Supplemental Information to Inspection Report within 60 Days ML18344A2651993-08-16016 August 1993 Response to Request for Additional Information Recent Fuel Failure Event ML18354A6531990-05-30030 May 1990 Information Required by the November 9, 1989 Technical Evaluation Report - NUREG 0737, Item Ii.D.L, Performance Testing of Relief and Safety Valves, Palisades Plant to Close Items Not Fully Resolved ML18354A6151988-01-15015 January 1988 Updated Response to IE Bulletin 87-03 Dated 11/15/1985, Entitled, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings ML18348A8881979-05-15015 May 1979 Rapid Response to Additional Information Request on Three Mile Island ML18348A3721978-07-0707 July 1978 Provide Additional Information Related to Diesel Generators Control Circulatory, as Requested ML18348A3741978-07-0606 July 1978 Provide Requested Information of Additional Analysis Specific to Determine Consequences of Potential Boron Dilution Incidents ML18348A7441978-05-23023 May 1978 Response to Request for Additional Information Reactor Vessel Material Surveillance ML18346A1121978-01-24024 January 1978 Response to Request for Additional Information Relating to Water Hammer in Feed-Water Lines and Feed-Water Spargers ML18353B1571977-12-22022 December 1977 Response to Request for Specific Information Re Potential Problem of Post-LOCA Ph Control of Containment Sump Water of IE Bulletin 77-04 ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A3961977-07-29029 July 1977 Response to Request for Specific Information Concerning Reactor Vessel Materials & Associated Surveillance Programs ML18348A4151977-07-12012 July 1977 Response to Request for Additional Information Re IE Bulletin 77-01, Relating to Use of Pneumatic Time Delay Relays in Safety-Related Systems ML18348A6911977-05-16016 May 1977 Response to Request for Additional Information Alarm and Diesel Generator Control Circuitry ML18348A6921977-05-12012 May 1977 Response to Request for Additional Information Proposed Emergency Dose Assessment System ML18348A8521977-05-0404 May 1977 Advising Exxon Concluded Three of Six Documents Do Not Contain Proprietary Information, Which Was Identified by AEC Letter of 3/1/1977, & Forwarding Affidavit as Additional Information Re Proprietary Documents ML18348A7051977-03-23023 March 1977 Response to Request for Additional Information Environmental Qualification of Electrical Equipment and the Effects of Its Submergence ML18348A8681977-03-0808 March 1977 Letter Reactor Vessel Overpressurization ML18348A8631977-03-0808 March 1977 Response to Request for Additional Information Reactor Vessel Overpressurization ML18348A7121977-02-15015 February 1977 Response to Request for Additional Information Power Defect Value Stated in Report No. XN-76-52 2023-03-01
[Table view] |
Text
'ATO* fllE COPY consumers
- .Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
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Att: :M.r Dennis L Ziemann, Chief' OJ Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCK.ET 50-255 - LICENSE DPR PALISADES PI..ANT - DIESEL GENEFATORS CONTROL CIRCUITRY AND ALARMS In the NRC review of previous Consumers Power submittals, dated May 16, 1977 and July 12, 1977 related to diesel generators control circuitry at the Palisades Plant additional information was requested. The information requested and responses are as follows:
Item 1 11 determine if the diesel generators are provided with a manual shutdown lockout relay .** "
Response
A manual shutdown relay does not exist in the Palisades Plant diesel generator control circuitry Item 2 "verify that an alarm is -provided. which clearly indicates when the diesel ge11erator control switch is not in the automatic position ..* "
Resuonse The diesel generator control switch is always in the automatic position, except during testing. An indicator light on the control panel indicates when the switch is in the automatic position *
- Item 3 11 verify that all shared. ar!nunc1ar,ors for disabling c*Jnd.iticns cannot be clearecL ..
until all abno:;,~mal condi ti ens a:re correete:i. "
2
- Response Shared annunciators cannot be cleared until all abnormal conditions are cleared.
To assist NRC staff in completing their review of this subject all previous responses are attached for clarity. Also, reference Consumers Power responses dated January 20, 1978 and February 2, 1978 (Diesel Generator Questionnaire) for additional information.
~::~~
Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC
- ATTACHMENT Diesel Generators Control Circuitry and Alarms The following information is provided in response to your March 29, 1977 letter relating to alarm and diesel generator control circuitry for the Palisades Plant diesel generators.
Item (a)
"All conditions that render the diesel generator incapable of responding to an automatic emergency start signal **** "
Response (a)
The following condition relays operate the shutdown relay which renders the:~un:ilt incapable of automatic start:
- 1. Generator differential relay.
- 2. Overcrank relay *
- 3. Jacket water temperature relay.
- 4. Overspeed relay.
- 5. Oil pressure relay
- 6. Loss of direct current control relay.
Item (b) 11 The wording on the annuhciator window in the cont:::-ol room that is alarmed for each of the conditions identified in (a). 11 Resnonse (b L The control room annunciator windows and the condition in (a) above which operates them:
- 1. Diesel Generator Breaker Trip Generator differential relay.
- 2. Diesel Generator Fail To Start
Overcrank relay .
Diesel Generator Trouble a.
1::.
Jacket water temperature relay.
Ov-erspeed relay.
- c. Oil pressure relay.
- d. .Loss of d-c control power.
I*
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"Any other alarm signals that also cause the same annunciator to alarm. '1 Response (c)
Other alarm signals which share the annunciators listed in'(b) above:
- 1. Diesel Generator Breaker Trip Breaker contact position switch.
- 2. Diesel Generator Fail To Start None.
- 3. Diesel Generator Trouble
- a. High lube oil differential pressure.
- b. Low lube oil temperature.
- c. High lube oil temperature.
- d. Air supply tanks low pressure.
- e. Jacket water level low.
- f. Low lube oil level
- g. Raw water pressure low *
- h. Prelube pressure low.
Item (d)
"Any condition that renders the diesel generator incapable of responding to an automatic emergency start signal which is not alarmed in the control room."
Item (d) Resnonse Jacket water pressure low will not prevent auto start. This is the nor~al con-dition when the engine is not running. A high jacket water pressure will prevent the engine from starting. (The cranking relay will be isolated.) The reason for this is that a high jacket waterpressureindicates that the engine is running.
This is the signal that turns off the starting motor after an engine start signal.
Jacket water pressure is supplied only by the engine-driven water circulating pump.
Item (e)
"Any pr9posed modifications resulting from this evaluation."
Item (e) Response The jacket water pressure will not be alarmed. A low pressure is normal while the engine is shut down. A high pressure is normal while the engine is running
- A high jacket water pressure is an impossible condition if the engine is not running for the following reasons:
- 1. Jacket water pressure is supplied only by the engine-driven water pump.
- 2. The cooling system is vented to at~osphere at the cooling wate~ expansion tank.