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| {{#Wiki_filter:P oy+ef'W REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: IPPOLITO T ORG: DISE D P DOCD ATE: 07/17/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 07f24f7C DOCTYPE: LETTER NOTARIZED: | | {{#Wiki_filter:P oy+ef'W REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NQ COPIES RECEIVED, | | DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: IPPOLITO T ORG: DISE D P DOCD ATE: 07/17/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 07f24f7C DOCTYPE: LETTER NOTARIZED: NQ COPIES RECEIVED, |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LTR 1 ENCL 0 ADVISING DESIGN CRITERIA AND APPROPRIATE PROPOSED TECH SPECS WILL BE PROVIDED BY SEPT 1978 RE ANTICIPATED TRANSIENTS NITHOUT SCRAM PERTAINING TO RECIRCULATION PUMP TRIP.PLANT NAME: NINE MILE PT-UNIT 1 REVIENER INITIAL: X JM DISTRIBUTOR INITIAL:~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4444<<+<<+<++<++<<'", ANTICIPATED TRANSlENTS W/OUT SCRAM<ATWS)(DISTRIBUTION CODE A029)FOR ACTION: INTERNAL: EXTERNAL: BR Ol:IX F-.ORB(>B BO+%LTR ONLY(7>BEG F IL->>LTR ONLY(1>I"Y E.~~LTR ONLY<2)HANAUER++LTR ONLY (1)AD FOR ENGR 8(PROJ4+LTR ONLY<1)PLANT SYSTEMS BR++LTR ONLY(l>P SHEMANSKI~+LTR ONLY(i)D TONDI+<LTR ONLY (1>LPDR S OSWEGO>NY+<LTR ONLY<i)TERA++LTR ONLY(1)NS I C+%LTR ONLY (1)ACRS CAT B++LTR ONLY(16)NRC PDR++LTR ONLY(1>OELD4+LTR ONLY<1)AD FOR SYS 5 PROJ++LTR ONLY(i>REACTOR SAFETY BR44LTR ONLY<i)H ORNSTEIN+4LTR ONLY (1)V RQONEY+4LTR ONLY<1)DISTRIBUTIQN: | | LTR 1 ENCL 0 ADVISING DESIGN CRITERIA AND APPROPRIATE PROPOSED TECH SPECS WILL BE PROVIDED BY SEPT 1978 RE ANTICIPATED TRANSIENTS NITHOUT SCRAM PERTAINING TO RECIRCULATION PUMP TRIP. |
| LTR 40 ENCL 0 SIZE: iP CONTROL NBR: 782070019 1 4 4 P p JI I'4 0 7 HIIASABA U U MOoHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511 July 17, 1978 Director, Nuclear Reactor Regulation Operating Reactors Branch No.3 U.S.Nuclear Regulatory Commission Washington, D.C.20555 Attention: | | PLANT NAME: NINE MILE PT UNIT 1 REVIENER INITIAL: XJM DISTRIBUTOR INITIAL: |
| Mr.Thomas Ippolito RE: Nine Mile Point Un)-t 1 Docket No.50-220 DPR-63~0]Q I 44 r>>
| | ~ |
| | DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4444<<+<<+<++<++<<'", |
| | ANTICIPATED TRANSlENTS W/OUT SCRAM <ATWS) |
| | (DISTRIBUTION CODE A029) |
| | FOR ACTION: BR Ol:IX F-.ORB(>B BO+%LTR ONLY(7> |
| | INTERNAL: BEG F IL ->>LTR ONLY(1 > NRC PDR++LTR ONLY(1> |
| | I"Y E.~~LTR ONLY<2) OELD4+LTR ONLY<1) |
| | HANAUER++LTR ONLY (1 ) AD FOR SYS 5 PROJ++LTR ONLY(i> |
| | AD FOR ENGR 8( PROJ4+LTR ONLY< 1) REACTOR SAFETY BR44LTR ONLY<i) |
| | PLANT SYSTEMS BR++LTR ONLY(l> H ORNSTEIN+4LTR ONLY ( 1 ) |
| | P SHEMANSKI~+LTR ONLY(i) V RQONEY+4LTR ONLY< 1) |
| | D TONDI+<LTR ONLY (1 > |
| | EXTERNAL: LPDR S OSWEGO> NY+<LTR ONLY<i) |
| | TERA++LTR ONLY(1) |
| | I NS C+%LTR ONLY ( 1 ) |
| | ACRS CAT B++LTR ONLY(16) |
| | DISTRIBUTIQN: LTR 40 ENCL 0 CONTROL NBR: 782070019 SIZE: iP |
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| ==Dear Mr.Ippolito:== | | 1 4 |
| Our June 30, 1978 letter indicated that the design information regarding the Nine Mile Point Unit 1 recirculation pump trip would be submitted six months prior to the next refueling outage.This refueling outage is scheduled to begin in early Spring 1979.We are continuing to evaluate the criteria provided in your May 15, 1978 letter which is also described in NUREG 0460,"Anticipated Transients Without Scram for Light Water Reactors". | | 4 P p JI I' |
| However, we feel that it is inappropriate to apply these criteria unti 1 a final review and approval by the Advisory Committee on Reactor Safeguards and the Commission, and resolution by rulemaking if appropriate. | | 4 |
| Accordingly, design criteria and appropriate proposed technical specifications will be provided by September, 1978.Very truly yours, NIAGARA MOHAWK POWER CORPORATION D.P.Disc NLR/djc 782070019 (5q C}} | | |
| | 0 7 HIIASABA U U MOoHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 July 17, 1978 Director, Nuclear Reactor Regulation Operating Reactors Branch No. 3 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Q I Attention: Mr. Thomas Ippolito 44 r>> |
| | RE: Nine Mile Point Un)-t 1 |
| | ~ 0] |
| | Docket No. 50-220 DPR-63 |
| | |
| | ==Dear Mr. Ippolito:== |
| | |
| | Our June 30, 1978 letter indicated that the design information regarding the Nine Mile Point Unit 1 recirculation pump trip would be submitted six months prior to the next refueling outage. This refueling outage is scheduled to begin in early Spring 1979. |
| | We are continuing to evaluate the criteria provided in your May 15, 1978 letter which is also described in NUREG 0460, "Anticipated Transients Without Scram for Light Water Reactors". However, we feel that it is inappropriate to apply these criteria unti 1 a final review and approval by the Advisory Committee on Reactor Safeguards and the Commission, and resolution by rulemaking if appropriate. |
| | Accordingly, design criteria and appropriate proposed technical specifications will be provided by September, 1978. |
| | Very truly yours, NIAGARA MOHAWK POWER CORPORATION D. P. Disc NLR/djc 782070019 |
| | |
| | ( |
| | 5q C}} |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] |
Text
P oy+ef'W REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: IPPOLITO T ORG: DISE D P DOCD ATE: 07/17/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 07f24f7C DOCTYPE: LETTER NOTARIZED: NQ COPIES RECEIVED,
SUBJECT:
LTR 1 ENCL 0 ADVISING DESIGN CRITERIA AND APPROPRIATE PROPOSED TECH SPECS WILL BE PROVIDED BY SEPT 1978 RE ANTICIPATED TRANSIENTS NITHOUT SCRAM PERTAINING TO RECIRCULATION PUMP TRIP.
PLANT NAME: NINE MILE PT UNIT 1 REVIENER INITIAL: XJM DISTRIBUTOR INITIAL:
~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4444<<+<<+<++<++<<'",
ANTICIPATED TRANSlENTS W/OUT SCRAM <ATWS)
(DISTRIBUTION CODE A029)
FOR ACTION: BR Ol:IX F-.ORB(>B BO+%LTR ONLY(7>
INTERNAL: BEG F IL ->>LTR ONLY(1 > NRC PDR++LTR ONLY(1>
I"Y E.~~LTR ONLY<2) OELD4+LTR ONLY<1)
HANAUER++LTR ONLY (1 ) AD FOR SYS 5 PROJ++LTR ONLY(i>
AD FOR ENGR 8( PROJ4+LTR ONLY< 1) REACTOR SAFETY BR44LTR ONLY<i)
PLANT SYSTEMS BR++LTR ONLY(l> H ORNSTEIN+4LTR ONLY ( 1 )
P SHEMANSKI~+LTR ONLY(i) V RQONEY+4LTR ONLY< 1)
D TONDI+<LTR ONLY (1 >
EXTERNAL: LPDR S OSWEGO> NY+<LTR ONLY<i)
TERA++LTR ONLY(1)
I NS C+%LTR ONLY ( 1 )
ACRS CAT B++LTR ONLY(16)
DISTRIBUTIQN: LTR 40 ENCL 0 CONTROL NBR: 782070019 SIZE: iP
1 4
4 P p JI I'
4
0 7 HIIASABA U U MOoHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 July 17, 1978 Director, Nuclear Reactor Regulation Operating Reactors Branch No. 3 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Q I Attention: Mr. Thomas Ippolito 44 r>>
RE: Nine Mile Point Un)-t 1
~ 0]
Docket No. 50-220 DPR-63
Dear Mr. Ippolito:
Our June 30, 1978 letter indicated that the design information regarding the Nine Mile Point Unit 1 recirculation pump trip would be submitted six months prior to the next refueling outage. This refueling outage is scheduled to begin in early Spring 1979.
We are continuing to evaluate the criteria provided in your May 15, 1978 letter which is also described in NUREG 0460, "Anticipated Transients Without Scram for Light Water Reactors". However, we feel that it is inappropriate to apply these criteria unti 1 a final review and approval by the Advisory Committee on Reactor Safeguards and the Commission, and resolution by rulemaking if appropriate.
Accordingly, design criteria and appropriate proposed technical specifications will be provided by September, 1978.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION D. P. Disc NLR/djc 782070019
(
5q C