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| {{#Wiki_filter:REGUL 1 t'NFORMATION DISTRIt3UT YSTEM (RIDS)ACCESSION NBR: 8509100061-DOC~DATE: 85/09/04 NOTARIZED:= | | {{#Wiki_filter:REGUL 1 t'NFORMATION DISTRIt3UT YSTEM (RIDS) |
| NO DOCKET''ACIL'.50. | | ACCESSION NBR: 8509100061- DOC DATE: 85/09/04 |
| 410 Nine Mile Point Nuclear"Stationi Unit 2E: Niagar a Moha 05000410 AUTHI,NAME AUTHOR AFFILIATION MANGANECO-Vs= | | ~ NOTARIZED:= NO 410 Nine Mile Point Nuclear "Stationi Unit 2E: Niagar a Moha 05000410 DOCKET''ACIL'.50. |
| Niagara Mohawks,Power Corp'.RECIPONAMEt RECIPIENT: | | AUTHI,NAME AUTHOR AFFILIATION MANGANECO-Vs= Niagara Mohawks,Power Corp'. |
| AFFILIATION BUTLER'S'j1t
| | RECIPONAMEt BUTLER'S'j1t ~ 'icensing. RECIPIENT: AFFILIATION Branch 2" SUBJECT! Forwards FSAR changes requested by Singh Changes. provided to close out SER Open I.teip" 12'.re'lternate) shutdown capability.. |
| ~'icensing. | | Futuret amend of FSAR will incorpot'ate changes; DISTRIBUTION CODE: S001D Licensing Submittal0'SAR/FSAR Amdts COPIES RECEIVEDILiTR 8, |
| Branch 2" SUBJECT!Forwards FSAR changes requested by Singh Changes.provided to close out SER Open I.teip" 12'.re'lternate) shutdown capability.. | | J'NCL Related JCo>re'spondence |
| Futuret amend of FSAR will incorpot'ate changes;DISTRIBUTION CODE: S001D COPIES RECEIVEDILiTR J'NCL J.01ZE:l"'p'ITLE".Licensing Submittal0'SAR/FSAR Amdts 8, Related Co>re'spondence NOTES: RECIPIENT ID CODE/NAtlEl NRR/OL/ADL NRR" LB2'A COPIES RECIPIENT LTTR ENCLi.ID CODE/NAME' 0 NRR LB2 BC 1 0 HAUGHEYiM 01 COPIES LT'TR ENCL" 1 0 1 l~INTERNAL: ACRS 41 ELO/HDS3>>IE/DEPER/EPB 36'RR ROE'AL'RR/DE/CEB 11'RR/OE/EQB 131 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40. | | .01ZE:l "' |
| NRR/DHFS/PSRB NRR/OSI"/AEB | | p'ITLE". |
| '26 NRR/OSI/CPB 10 NRR/DSI/ICSB 16 NRR/DS I'/PSB 19 NRR/DSI/RSB 23>>RGN1 EXTERNAL:?4X DMB/OSS (AMOTS).NRC PDR 02!PNLi GRUEL'ER 6 6 1 0 1~1" 1 1 2 2" 1 1 1 1<<1 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1.1 1 1 1 1 1 ADA/LFMB IE".F ILE'E/DQAVT/QAB21 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32" NRR/DL/SSPB NRR/DSI/ASB NRR/DSI/CSB 09'RR/DSI/METB 12" NRR'AB 22'4 RM/ODAMI/MI B BNL(AMOTS ONLY)LPOR'03~NSIC 05 0" 1.1~1 1 1 0 1 1 21 1 1 1 1 1 1 1 0 1'1 1 1 1 1 1 1 1 0 1 1 1 1 1"1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL' I ivp Ik r<<k(4~<<'l-4'("'I rgvr" 4 4'"Il I"<<'(v," iY t l r 4&4<<<<444 vI (f 4 I rk<<4~4 g~I'f)Vf<<4<<vl Y, f 4 V 4 F 4 k ,~HT V v Ij LI T NIIINRA A V MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE.N,Y.13202/TELEPHONE (315)474-1511 September 4, 1985 (NMP2L 0486)Mr.Walter Butler, Chief Licensing Branch No.2 U.S.Nuclear Regulatory Commission Washington, OC 20555
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAtlEl LTTR ENCLi . ID CODE/NAME' LT'TR ENCL" NRR/OL/ADL 0 NRR LB2 BC 1 0 NRR" LB2'A 1 0 HAUGHEYiM 01 1 l~ |
| | INTERNAL: ACRS 41 6 6 ADA/LFMB 0" ELO/HDS3>> 1 0 IE".F 1. 1 ~ |
| | IE/DEPER/EPB 36'RR 1 ~ 1" ILE'E/DQAVT/QAB21 1 1 1 1 NRR/DE/AEAB 1 0 ROE'AL'RR/DE/CEB 11 NRR/DE/EHEB 1 1 131 'RR/OE/EQB 2 2" NRR/DE/GB 28 21 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 NRR/DE/SGEB 25 NRR/DHFS/HFEB40. |
| | NRR/DHFS/PSRB 1<<1 1 1 NRR/DHFS/LQB NRR/DL/SSPB 32" 1 |
| | 1 1 0 1 |
| | 1 1 1 NRR/OSI"/AEB '26 1 1 NRR/DSI/ASB 1' NRR/OSI/CPB 10 1 1 NRR/DSI/CSB 1 NRR/DSI/ICSB 16 1 1 12" 09'RR/DSI/METB 1 1 NRR/DS I'/PSB 19 1 1 NRR 'AB 22'4 1 1 NRR/DSI/RSB 23>> 1 1 1 1 RGN1 3 RM/ODAMI/MIB 1 0 EXTERNAL: ?4X 1 1 BNL(AMOTS ONLY) 1 1 DMB/OSS (AMOTS). .1 1 LPOR' 03~ 1 1 NRC PDR 02! 1 1 NSIC 05 1 "1 PNLi GRUEL'ER 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL' |
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| ==Dear Mr.Butler:==
| | I ivp Ik r |
| Re: Nine Mile Point Unit 2 Docket No.50-410 Enclosed are changes requested by Mr.Singh of your staff.The changes are provided to close out Safety Evaluation Report Open Item 12.These changes will be incorporated into a future amendment of the Final Safety Analysis Report.Very truly yours, C.V.Mangan Senior Vice President BB/rla Enclosure 0925G xc: R.A.Gramm, NRC Resident Inspector Project File (2)8509i'00061 850904'PDR ADOCK 050004i0 E'.PDR'
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| Nine Mile Point Un'AR 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4.1 Description This section discusses the instrumentation and controls of the following systems which can be used for safe plant shutdown: 1.Reactor core isolation cooling system (RCIC).2.Standby liquid control system{SLCS).3.RHR shutdown cooling mode (RSCM).4.Remote shutdown system{RSS).The sources that supply power to the safe shutdown systems originate from onsite ac/dc safety-related buses.Refer to Chapter 8 for a complete discussion of the safety-related power sources.7.4.1.1 Reactor Core Isolation Cooling System S stem Function The RCIC system is designed to assure that sufficient reactor water inventory is maintained in the reactor vessel thus assuring continuity of core cooling.Reactor vessel water is maintained or supplemented by RCIC system during the following conditions:
| | LI T NIIINRA A V MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N,Y. 13202/TELEPHONE (315) 474-1511 September 4, 1985 (NMP2L 0486) |
| 1.When the reactor vessel is isolated and maintained in the hot standby condition.
| | Mr. Walter Butler, Chief Licensing Branch No. 2 U.S. Nuclear Regulatory Commission Washington, OC 20555 |
| When the reactor vessel is isolated and accompanied by a loss of normal coolant flow from the reactor feedwater system.When a complete plant shutdown under conditions of loss of normal feedwater system is started before the reactor is depressurized to a level where the reactor shutdown cooling mode of the RHR system can be placed into operation.
| |
| S stem 0 eration Schematic arrangements of system mechanical equipment and instrumentation and a description of system design and operation are provided in Section S.4.6.The instrumentation specifications are listed in Table 7.4-1'.The control logic is shown on Figure 7.4-1.7.4-1
| |
| ~0 4 k Res on As shown on FSAR Figure 9B.4-2, the approach used for NMP2 is similar to that described above.The reactor is either manually or automatically scramed.Then one of four trains are used to provide makeup water and decay heat removal.Either HPCS or RCIC is used for high pressure makeup.If a blowdown were to occur either through the ADS or relief valves, makeup would be provided using the lowpressure systems (LPCS or LPCI);Additionally, decay heat removal is provided by the RHR system.In the event of a fire in the control room or relay room which forces evacuation of the control room, sufficient equipment to enable hot and cold shutdown is provided at the remote shutdown panels (FSAR Section 7.4)and through the use of local control.Viability of these circuits is assured by the use of transfer switches whicn electrically isolate the control room and transfer control to the local panels and the remote shutdown panels.Redundant and isolated fuses are provided (in the emer gency switchgear rooms)to maintain the power source to these circuits.12.The description of the systems or portions ther eof used to provide the shutdown capability and modifications required to achieve alternate shutdown capability if required.~Res ense Appendix 98 and Section 7.4 of the FSAR provide descriptions of the shutdown systems and modifications and alternate shutdown capability from the remote shutdown room.
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| ATTACHMENT le 0 Hi h/Low Pressure Interfaces S tern Boundaries OER-Reactor Building Equipment Drain 2OER~V128 MSS-Main Steam 2MSS*MOV112 2MSS+HYV6A,B,C,D 2HSS+HYV7A,B,C,D RHS-Residual Heat Removal 2RHS*MOV22A, B 2RHSAOV80A, B 2RHS*MOV113 2RHS*MOV67A,B 2RHS*MOV32A,B WCS-Reactor Water Cleanup 2WCS-MOV106 2WCS-MOV107 2WCS-AOV26A,B,C,O 2WCS-AOV28A,B,C,O 2WCS-AOV29A,B,C,O 2WCS-AOV30A,B,C,O 2WCS-AOV44A,B,C,D 2WCS-AOV51A,B,C,O 2WCS-AOV52A,B,C$ | | ==Dear Mr. Butler:== |
| 0 2WCS-AOV53A,B,C,O 2WCS-AOV54A,B,C,O 2WCS-AOV61A,B,C,O Notes: Descri tion WCS Drain Valve Main Steam Drain Main Steam Isolation Hain Steam Isolation Steam Supply to RHS*El Steam Supply to RHS*El Shutdown Cooling Suction Shutdown Cooling Return RHS*El Return to ICS Drain to Liquid Waste Drain to Main Condenser Demineralizer Vent/Drain Oemineralizer Vent/Drain Demineralizer Vent/Drain Oemineralizer Vent/Drain Demineralizer Vent/Drain Oemineralizer Vent/Drain Oemineralizer Vent/Drain Demineralizer Vent/Drain Oemineralizer Vent/Drain Oemineralizer Vent/Drain Resolution Note 1 Note 1 Note 3 Note 3 Note 1 Note 1 Note 1 Note 1 Note 1 Note 1 Note 1 Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 1)2)3)At least one valve is de-energized and disconnected from power source (breaker open)during normal plant operation. | | |
| No single fire could cause sufficient spurious operations to violate the high/low pr essure interface in this flow path since these valves are controlled from local panels which are located in a separate fire area from the control room.These valves are normally open.In the event of a control room fire, as defined by the Appendix R criteria, they are closed by the operator and subsequently disconnected from their.power source to ensure no spurious operation. | | Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are changes requested by Mr. Singh of your staff. The changes are provided to close out Safety Evaluation Report Open Item 12 . |
| @II'l~}} | | These changes will be incorporated into a future amendment of the Final Safety Analysis Report. |
| | Very truly yours, C. V. Mangan Senior Vice President BB/rla Enclosure 0925G xc: R. A. Gramm, NRC Resident Inspector Project File (2) 8509i'00061 850904' PDR E |
| | ADOCK 050004i0 PDR' |
| | |
| | Nine Mile Point Un'AR 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4. 1 Description This section discusses the instrumentation and controls of the following systems which can be used for safe plant shutdown: |
| | : 1. Reactor core isolation cooling system (RCIC). |
| | : 2. Standby liquid control system {SLCS). |
| | : 3. RHR shutdown cooling mode (RSCM). |
| | : 4. Remote shutdown system {RSS) . |
| | The sources that supply power to the safe shutdown systems originate from onsite ac/dc safety-related buses. Refer to Chapter 8 for a complete discussion of the safety-related power sources. |
| | 7.4.1.1 Reactor Core Isolation Cooling System S stem Function The RCIC system is designed to assure that sufficient reactor water inventory is maintained in the reactor vessel thus assuring continuity of core cooling. |
| | Reactor vessel water is maintained or supplemented by RCIC system during the following conditions: |
| | : 1. When the reactor vessel is isolated and maintained in the hot standby condition. |
| | When the reactor vessel is isolated and accompanied by a loss of normal coolant flow from the reactor feedwater system. |
| | When a complete plant shutdown under conditions of loss of normal feedwater system is started before the reactor is depressurized to a level where the reactor shutdown cooling mode of the RHR system can be placed into operation. |
| | S stem 0 eration Schematic arrangements of system mechanical equipment and instrumentation and a description of system design and operation are provided in Section S.4.6. The instrumentation specifications are listed in Table 7.4-1'. |
| | The control logic is shown on Figure 7.4-1. |
| | 7.4-1 |
| | |
| | ~0 k |
| | 4 Res on As shown on FSAR Figure 9B.4-2, the approach used for NMP2 is similar to that described above. The reactor is either manually or automatically scramed. Then one of four trains are used to provide makeup water and decay heat removal. Either HPCS or RCIC is used for high pressure makeup. If a blowdown were to occur either through the ADS or relief valves, makeup would be provided using the lowpressure systems (LPCS or LPCI); Additionally, decay heat removal is provided by the RHR system. |
| | In the event of a fire in the control room or relay room which forces evacuation of the control room, sufficient equipment to enable hot and cold shutdown is provided at the remote shutdown panels (FSAR Section 7.4) and through the use of local control. Viability of these circuits is assured by the use of transfer switches whicn electrically isolate the control room and transfer control to the local panels and the remote shutdown panels. Redundant and isolated fuses are provided (in the emer gency switchgear rooms) to maintain the power source to these circuits. |
| | : 12. The description of the systems or portions ther eof used to provide the shutdown capability and modifications required to achieve alternate shutdown capability if required. |
| | ~Res ense Appendix 98 and Section 7.4 of the FSAR provide descriptions of the shutdown systems and modifications and alternate shutdown capability from the remote shutdown room. |
| | |
| | ATTACHMENT le 0 Hi h/Low Pressure Interfaces S tern Boundaries Descri tion Resolution OER-Reactor Building Equipment Drain 2OER~V128 WCS Drain Valve Note 1 MSS - Main Steam 2MSS*MOV112 Main Steam Drain Note 1 2MSS+HYV6A,B,C,D Main Steam Isolation Note 3 2HSS+HYV7A,B,C,D Hain Steam Isolation Note 3 RHS - Residual Heat Removal 2RHS*MOV22A, B Steam Supply to RHS*El Note 1 2RHSAOV80A, B Steam Supply to RHS*El Note 1 2RHS*MOV113 Shutdown Cooling Suction Note 1 2RHS*MOV67A,B Shutdown Cooling Return Note 1 2RHS*MOV32A,B RHS*El Return to ICS Note 1 WCS - Reactor Water Cleanup 2WCS-MOV106 Drain to Liquid Waste Note 1 2WCS-MOV107 Drain to Main Condenser Note 1 2WCS-AOV26A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV28A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV29A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV30A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV44A,B,C,D Demineralizer Vent/Drain Note 2 2WCS-AOV51A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV52A,B,C$ 0 Oemineralizer Vent/Drain Note 2 2WCS-AOV53A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV54A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV61A,B,C,O Oemineralizer Vent/Drain Note 2 Notes: |
| | : 1) At least one valve is de-energized and disconnected from power source (breaker open) during normal plant operation. |
| | : 2) No single fire could cause sufficient spurious operations to violate the high/low pr essure interface in this flow path since these valves are controlled from local panels which are located in a separate fire area from the control room. |
| | : 3) These valves are normally open. In the event of a control room fire, as defined by the Appendix R criteria, they are closed by the operator and subsequently disconnected from their. power source to ensure no spurious operation. |
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| | @II' l ~}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies
ML20217G1291999-10-15015 October 1999
Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend
ML20217K2831999-10-14014 October 1999
Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001
ML20217H3211999-10-0808 October 1999
Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls
ML20212K8601999-10-0606 October 1999
Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2
ML20216J9311999-09-30030 September 1999
Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
ML20212J4651999-09-30030 September 1999
Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl
ML18040A3701999-09-30030 September 1999
Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs
ML20212K8641999-09-30030 September 1999
Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam
ML20212J8831999-09-30030 September 1999
Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant
ML20212E9801999-09-23023 September 1999
Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03
ML20216F7101999-09-17017 September 1999
Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed
ML20212B2821999-09-14014 September 1999
Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable
ML20212D8981999-09-14014 September 1999
Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl
ML20212B2581999-09-10010 September 1999
Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List
ML20211P5771999-09-10010 September 1999
Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld
ML20212A1341999-09-0707 September 1999
Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f
ML20211K8141999-09-0101 September 1999
Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met
ML20211L9221999-09-0101 September 1999
Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC
ML20211J6461999-08-30030 August 1999
Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity
ML20211K3001999-08-30030 August 1999
Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1
ML20211K5031999-08-30030 August 1999
Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999
ML20211H1921999-08-26026 August 1999
Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML20211P5161999-08-26026 August 1999
Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied
ML20211G4921999-08-26026 August 1999
Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
ML20211B9371999-08-18018 August 1999
Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based
ML18040A3691999-08-16016 August 1999
Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys.
ML20210Q0031999-08-11011 August 1999
Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr
ML20210R6661999-08-10010 August 1999
Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2
ML20210R8101999-08-10010 August 1999
Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b)
ML20210L5321999-08-0606 August 1999
Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue
ML18041A0711999-07-30030 July 1999
Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed
ML20210J9351999-07-29029 July 1999
Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage
ML20216E1491999-07-26026 July 1999
Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206
ML20210E9151999-07-23023 July 1999
Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied
ML20209G7911999-07-12012 July 1999
Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions
ML20209G3711999-07-12012 July 1999
Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1
ML20209G2001999-07-0909 July 1999
Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01)
ML20209F8561999-07-0606 July 1999
Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4
ML20211K5071999-07-0606 July 1999
Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857
ML20196J6421999-06-30030 June 1999
Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110
ML20209B7071999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl
ML20211P5271999-06-29029 June 1999
Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted
ML20196K6461999-06-29029 June 1999
Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV
ML20209B3501999-06-25025 June 1999
Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs
ML20212J4431999-06-25025 June 1999
Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity
ML20209B3531999-06-25025 June 1999
Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment
ML20196F5721999-06-23023 June 1999
Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl
ML20196G1461999-06-23023 June 1999
Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed
1999-09-07
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999
Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001
ML20217H3211999-10-0808 October 1999
Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls
ML18040A3701999-09-30030 September 1999
Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs
ML20216J9311999-09-30030 September 1999
Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
ML20212E9801999-09-23023 September 1999
Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03
ML20216F7101999-09-17017 September 1999
Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed
ML20212D8981999-09-14014 September 1999
Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl
ML20212B2581999-09-10010 September 1999
Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List
ML20211P5771999-09-10010 September 1999
Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld
ML20212A1341999-09-0707 September 1999
Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f
ML20211K8141999-09-0101 September 1999
Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met
ML20211L9221999-09-0101 September 1999
Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC
ML20211K3001999-08-30030 August 1999
Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1
ML20211J6461999-08-30030 August 1999
Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity
ML20211H1921999-08-26026 August 1999
Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
ML20211B9371999-08-18018 August 1999
Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based
ML18040A3691999-08-16016 August 1999
Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys.
ML20210R6661999-08-10010 August 1999
Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2
ML20210R8101999-08-10010 August 1999
Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b)
ML18041A0711999-07-30030 July 1999
Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed
ML20210J9351999-07-29029 July 1999
Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage
ML20209G3711999-07-12012 July 1999
Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1
ML20209G7911999-07-12012 July 1999
Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions
ML20209G2001999-07-0909 July 1999
Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01)
ML20209F8561999-07-0606 July 1999
Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4
ML20211K5071999-07-0606 July 1999
Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857
ML20209B7071999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl
ML20211P5271999-06-29029 June 1999
Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted
ML20209B3501999-06-25025 June 1999
Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs
ML20209B3531999-06-25025 June 1999
Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment
ML20196G1461999-06-23023 June 1999
Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed
ML20196F5721999-06-23023 June 1999
Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl
ML20209B2951999-06-22022 June 1999
Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226
ML20196E9231999-06-21021 June 1999
Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor
ML18040A3651999-06-0707 June 1999
Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission
ML18040A3661999-06-0404 June 1999
Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr
ML20195C9751999-06-0101 June 1999
Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods
ML20195C9601999-05-28028 May 1999
Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr
ML20207F1811999-05-24024 May 1999
Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns
ML20195B1861999-05-21021 May 1999
Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl
ML20207D1541999-05-21021 May 1999
Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld
ML20207D5331999-05-21021 May 1999
Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790
ML20206S2621999-05-16016 May 1999
Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date
ML20195D5911999-05-13013 May 1999
Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411
ML20206P1981999-05-11011 May 1999
Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2
ML20206R6941999-05-10010 May 1999
Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate
ML20206N0291999-05-0707 May 1999
Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28
ML20206G8121999-04-30030 April 1999
Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083
ML20206F7731999-04-22022 April 1999
Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2
1999-09-07
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17056A9771990-08-30030 August 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm.
ML18038A3231990-08-30030 August 1990
Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM
ML18038A3221990-08-24024 August 1990
Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation
ML18038A3201990-08-21021 August 1990
Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components
ML18038A3251990-08-20020 August 1990
Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed
ML20058Q1151990-08-15015 August 1990
Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21)
ML20055G5261990-07-18018 July 1990
Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl
ML17058A5841990-06-27027 June 1990
Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2
ML18038A3051990-06-26026 June 1990
Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl
ML20042E3741990-04-11011 April 1990
Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request
ML20012F6131990-03-30030 March 1990
Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d))
ML17056A6721990-03-0202 March 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.
ML18038A7071990-02-0505 February 1990
Forwards Rev 5 to NMPC-QATR-1, QA Topical Rept for Nine Mile Point Nuclear Station Operations.
ML18038A7061990-01-10010 January 1990
Forwards Rev 21 to Emergency Plan,Revised Emergency Action Procedures,Including Rev 7 to S-EAP-1,Rev 11 to S-EAP-2,Rev 8 to S-EAP-3 & Epips,Including Rev 13 to S-EPP-4 & Rev 13 to S-EPP-20
ML20042D1981989-12-28028 December 1989
Informs of Delay in Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Until BWR Owner Group Generic Program Completed & NRC Appraisal of Program Reviewed by Util
ML18038A7021989-11-28028 November 1989
Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Usi A-5,A-6 & A-7 Inapplicable to Facility
ML18038A7711989-11-28028 November 1989
Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Requirements for NUREG-0612 Re Control of Heavy Loads Near Spent Fuel Completed.Usi A-40 Re Seismic Design Criteria Being Resolved as Part of USI A-46
ML18038A7701989-10-25025 October 1989
Forwards Rev 1 to Updated SAR for Nine Mile Point Unit 2. All Errata Items Identified in Attachment 1 to Previous Updated SAR Transmittal Ltr of 890428 Resolved.Programs to Resolve Setpoint Issues Will Be Established by 891130
ML18038A7611989-09-29029 September 1989
Forwards Addl Info Re Simulator Certification for Facility, Per 890803 Request.Schedule Extension Verbally Granted Until 890930
ML18038A6641989-09-0808 September 1989
Forwards Restart Readiness Rept. Rept Submitted in Fulfillment of Util Third Action Required by Confirmatory Action Ltr CAL-88-17,dtd 880724
ML17056A2701989-08-30030 August 1989
Forwards Nine Mile Point Nuclear Station - Unit 2 Semiannual Radioactive Effluent Release Rept Jan-June 1989 & Rev 1 to Administrative Procedure AP-3.7.1 Process Control Program.
ML20245E8451989-08-0707 August 1989
Forwards Rev 6 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21 & 10CFR2.790(d))
ML20247M2771989-07-25025 July 1989
Forwards Issue 2,Rev 0 to Physical Security Plan.Specific Changes Set Forth in Attachment A.Supporting Info Set Forth in Attachment B.Master Acronym & Abbreviation List Also Encl.Encls Withheld (Ref 10CFR73.21)
ML20246N9041989-07-13013 July 1989
Forwards Vital Area Evaluation for Plant Screenhouse.Encl Withheld (Ref 10CFR73.21(b))
ML18038A6611989-07-11011 July 1989
Provides Response to Generic Ltr 89-06, Task Action Plan Item I.D.2 - Spds. Certification Stating Plant Unit 1 SPDS Sys Meets Requirements of NUREG-0737,Suppl 1 & Plant Unit 2 SPDS Sys Will Be Modified to Meet NUREG-0737,Suppl 1 Encl
ML18038A6591989-06-23023 June 1989
Forwards Util Response to 890522 Salp.Util Agrees W/Need to Improve Surveillance Testing Data & Upgrading Design Basis for Core Spray & HPCI Sys
ML20244E3631989-06-15015 June 1989
Forwards Revised Application for Amend to License DPR-63, Incorporating Request to Limit Reactor Power Level at Which Blocking Valve in Feedwater May Be Closed
ML18038A4731989-05-31031 May 1989
Forwards Emergency Preparedness Exercise/Drill Scenario 12 1989 Annual Exercise, Vols 1 & 2
ML18038A4581989-04-28028 April 1989
Forwards Rev 0 to Updated SAR for Nine Mile Point Unit 2. Emergency Plan,Formerly Included in Fsar,Not Included in Updated Sar.Portions of Util Responses to NRC FSAR Questions Incorporated Into Body of Initial Updated SAR
ML20246Q0071989-04-28028 April 1989
Forwards Proprietary Section 6A of Updated FSAR for Nine Mile Point Unit 2.Section 6A Withheld (Ref 10CFR2.790)
ML20246B5451989-04-28028 April 1989
Advises That Util Will Submit Rev to Restart Action Plan After Receipt of Repts from NRC Special Team Insp & INPO Reassessment of Facility
ML18038A4561989-03-23023 March 1989
Forwards Addl Info Supporting Application to Use Alternative to 10CFR50.55a Requirements.W/Two Oversize Drawings
ML18038A4551989-03-21021 March 1989
Provides Util Plans for Future Exam & Evaluation of Four Feedwater Nozzles Per NUREG-0619.Indications Conservatively Evaluated as Cracks Not Scratch Marks.During 1993 Refueling Outage,Sparger from Nozzle a Will Be Removed
05000410/LER-1989-003, Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected1989-03-21021 March 1989
Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected
ML18038A4521989-03-0202 March 1989
Forwards Responses to NRC Questions Re Licensee Restart Action Plan & Nuclear Improvement Program.Replacement Pages for Action Plan Encl
ML20245J5521989-03-0202 March 1989
Forwards Rept of Physical Security Event,Reported Via Emergency Notification Sys on 890203
ML18038A4511989-02-22022 February 1989
Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified
ML18038A4501989-02-14014 February 1989
Forwards Rev 1 to TR-6801-2, Mark I Torus Shell & Vent Sys Thickness Requirements Nine Mile Point Unit 1 Nuclear Station. Requests Approval to Use Certified Matl Test Repts for Most of Torus Matls
ML18038A4341989-01-18018 January 1989
Forwards Revised,Second 10-yr Interval Inservice Testing Program Plan for Plant & Supporting Documentation,Per 881220 Commitment.Interim Approval of Program as Submitted to Spent Fuel Loading Scheduled for Apr 1989 Requested
ML18038A4201988-09-29029 September 1988
Advises That No Unresolved Safety Issues Re Flow Fluctuations & Neutron Flux Noise Exist,Per NRC 880527 Ltr Requesting Summary of Plans to Mitigate Oscillations in APRM Signals & Total Core Flow
ML20154C4221988-09-0909 September 1988
Informs That Contracted Vendor to Present Courses Will Not Be Able to Commence Training Until Later in Month of Oct or Early Nov 1988.Schedule Revised to Have Instrumentation & Control Initial Training Implemented by Nov 1988
ML20154B4301988-09-0808 September 1988
Forwards Security & Safeguards Contingency Plan.Definition of Security Force Member Discussed.Plan Withheld
ML17055E2471988-08-30030 August 1988
Forwards Semiannual Radioactive Effluent Release Rept, Jan-Jun 1988, & Revs 4 & 6 to Offsite Dose Calculation Manual.
ML18038A4121988-07-28028 July 1988
Forwards Info Re Implementation of NUREG-0131,Rev 2, Technical Rept on Matl Selection & Process Guidelines for BWR Coolant Pressure Boundary Piping.
ML18038A4101988-07-28028 July 1988
Forwards Comments,Clarifications & Agreements Re Implementation Re 880506 SER Concerning 10CFR50,App J.Info Submitted Per Commitment Resulting from 880609 Meeting W/ NRC.W/15 Oversize Drawings
ML18038A4111988-07-28028 July 1988
Forwards Licensee Response to Generic Ltr 88-01 Re Austenitic Stainless Steel Piping at Facility.Application for Amend to Incorporate Requirements of Generic Ltr Will Be Submitted Later
ML20151A2971988-07-15015 July 1988
Forwards Changes to Physical Security Plan.Supporting Info Also Encl.Encls Withheld (Ref 10CFR73.21)
ML20151A2751988-07-15015 July 1988
Forwards Changes to Security Training & Qualification Plan. Changes Withheld (Ref 10CFR2.790)
ML18038A4081988-07-0707 July 1988
Submits Listed Changes to Util 880609 Comments on SALP, Including Advisal That Review of Nonradiological Chemistry Program Revised to More Accurately Describe How Review Performed
ML18038A4061988-07-0606 July 1988
Responds to Request for Addl Info on ATWS Review Re Alternate Rod Injection & Recirculation Pump Trip Sys.W/ Seven Oversize Drawings
1990-08-30
[Table view] |
Text
REGUL 1 t'NFORMATION DISTRIt3UT YSTEM (RIDS)
ACCESSION NBR: 8509100061- DOC DATE: 85/09/04
~ NOTARIZED:= NO 410 Nine Mile Point Nuclear "Stationi Unit 2E: Niagar a Moha 05000410 DOCKETACIL'.50.
AUTHI,NAME AUTHOR AFFILIATION MANGANECO-Vs= Niagara Mohawks,Power Corp'.
RECIPONAMEt BUTLER'S'j1t ~ 'icensing. RECIPIENT: AFFILIATION Branch 2" SUBJECT! Forwards FSAR changes requested by Singh Changes. provided to close out SER Open I.teip" 12'.re'lternate) shutdown capability..
Futuret amend of FSAR will incorpot'ate changes; DISTRIBUTION CODE: S001D Licensing Submittal0'SAR/FSAR Amdts COPIES RECEIVEDILiTR 8,
J'NCL Related JCo>re'spondence
.01ZE:l "'
p'ITLE".
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAtlEl LTTR ENCLi . ID CODE/NAME' LT'TR ENCL" NRR/OL/ADL 0 NRR LB2 BC 1 0 NRR" LB2'A 1 0 HAUGHEYiM 01 1 l~
INTERNAL: ACRS 41 6 6 ADA/LFMB 0" ELO/HDS3>> 1 0 IE".F 1. 1 ~
IE/DEPER/EPB 36'RR 1 ~ 1" ILE'E/DQAVT/QAB21 1 1 1 1 NRR/DE/AEAB 1 0 ROE'AL'RR/DE/CEB 11 NRR/DE/EHEB 1 1 131 'RR/OE/EQB 2 2" NRR/DE/GB 28 21 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 NRR/DE/SGEB 25 NRR/DHFS/HFEB40.
NRR/DHFS/PSRB 1<<1 1 1 NRR/DHFS/LQB NRR/DL/SSPB 32" 1
1 1 0 1
1 1 1 NRR/OSI"/AEB '26 1 1 NRR/DSI/ASB 1' NRR/OSI/CPB 10 1 1 NRR/DSI/CSB 1 NRR/DSI/ICSB 16 1 1 12" 09'RR/DSI/METB 1 1 NRR/DS I'/PSB 19 1 1 NRR 'AB 22'4 1 1 NRR/DSI/RSB 23>> 1 1 1 1 RGN1 3 RM/ODAMI/MIB 1 0 EXTERNAL: ?4X 1 1 BNL(AMOTS ONLY) 1 1 DMB/OSS (AMOTS). .1 1 LPOR' 03~ 1 1 NRC PDR 02! 1 1 NSIC 05 1 "1 PNLi GRUEL'ER 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL'
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LI T NIIINRA A V MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N,Y. 13202/TELEPHONE (315) 474-1511 September 4, 1985 (NMP2L 0486)
Mr. Walter Butler, Chief Licensing Branch No. 2 U.S. Nuclear Regulatory Commission Washington, OC 20555
Dear Mr. Butler:
Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are changes requested by Mr. Singh of your staff. The changes are provided to close out Safety Evaluation Report Open Item 12 .
These changes will be incorporated into a future amendment of the Final Safety Analysis Report.
Very truly yours, C. V. Mangan Senior Vice President BB/rla Enclosure 0925G xc: R. A. Gramm, NRC Resident Inspector Project File (2) 8509i'00061 850904' PDR E
ADOCK 050004i0 PDR'
Nine Mile Point Un'AR 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4. 1 Description This section discusses the instrumentation and controls of the following systems which can be used for safe plant shutdown:
- 1. Reactor core isolation cooling system (RCIC).
- 2. Standby liquid control system {SLCS).
- 3. RHR shutdown cooling mode (RSCM).
- 4. Remote shutdown system {RSS) .
The sources that supply power to the safe shutdown systems originate from onsite ac/dc safety-related buses. Refer to Chapter 8 for a complete discussion of the safety-related power sources.
7.4.1.1 Reactor Core Isolation Cooling System S stem Function The RCIC system is designed to assure that sufficient reactor water inventory is maintained in the reactor vessel thus assuring continuity of core cooling.
Reactor vessel water is maintained or supplemented by RCIC system during the following conditions:
- 1. When the reactor vessel is isolated and maintained in the hot standby condition.
When the reactor vessel is isolated and accompanied by a loss of normal coolant flow from the reactor feedwater system.
When a complete plant shutdown under conditions of loss of normal feedwater system is started before the reactor is depressurized to a level where the reactor shutdown cooling mode of the RHR system can be placed into operation.
S stem 0 eration Schematic arrangements of system mechanical equipment and instrumentation and a description of system design and operation are provided in Section S.4.6. The instrumentation specifications are listed in Table 7.4-1'.
The control logic is shown on Figure 7.4-1.
7.4-1
~0 k
4 Res on As shown on FSAR Figure 9B.4-2, the approach used for NMP2 is similar to that described above. The reactor is either manually or automatically scramed. Then one of four trains are used to provide makeup water and decay heat removal. Either HPCS or RCIC is used for high pressure makeup. If a blowdown were to occur either through the ADS or relief valves, makeup would be provided using the lowpressure systems (LPCS or LPCI); Additionally, decay heat removal is provided by the RHR system.
In the event of a fire in the control room or relay room which forces evacuation of the control room, sufficient equipment to enable hot and cold shutdown is provided at the remote shutdown panels (FSAR Section 7.4) and through the use of local control. Viability of these circuits is assured by the use of transfer switches whicn electrically isolate the control room and transfer control to the local panels and the remote shutdown panels. Redundant and isolated fuses are provided (in the emer gency switchgear rooms) to maintain the power source to these circuits.
- 12. The description of the systems or portions ther eof used to provide the shutdown capability and modifications required to achieve alternate shutdown capability if required.
~Res ense Appendix 98 and Section 7.4 of the FSAR provide descriptions of the shutdown systems and modifications and alternate shutdown capability from the remote shutdown room.
ATTACHMENT le 0 Hi h/Low Pressure Interfaces S tern Boundaries Descri tion Resolution OER-Reactor Building Equipment Drain 2OER~V128 WCS Drain Valve Note 1 MSS - Main Steam 2MSS*MOV112 Main Steam Drain Note 1 2MSS+HYV6A,B,C,D Main Steam Isolation Note 3 2HSS+HYV7A,B,C,D Hain Steam Isolation Note 3 RHS - Residual Heat Removal 2RHS*MOV22A, B Steam Supply to RHS*El Note 1 2RHSAOV80A, B Steam Supply to RHS*El Note 1 2RHS*MOV113 Shutdown Cooling Suction Note 1 2RHS*MOV67A,B Shutdown Cooling Return Note 1 2RHS*MOV32A,B RHS*El Return to ICS Note 1 WCS - Reactor Water Cleanup 2WCS-MOV106 Drain to Liquid Waste Note 1 2WCS-MOV107 Drain to Main Condenser Note 1 2WCS-AOV26A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV28A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV29A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV30A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV44A,B,C,D Demineralizer Vent/Drain Note 2 2WCS-AOV51A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV52A,B,C$ 0 Oemineralizer Vent/Drain Note 2 2WCS-AOV53A,B,C,O Demineralizer Vent/Drain Note 2 2WCS-AOV54A,B,C,O Oemineralizer Vent/Drain Note 2 2WCS-AOV61A,B,C,O Oemineralizer Vent/Drain Note 2 Notes:
- 1) At least one valve is de-energized and disconnected from power source (breaker open) during normal plant operation.
- 2) No single fire could cause sufficient spurious operations to violate the high/low pr essure interface in this flow path since these valves are controlled from local panels which are located in a separate fire area from the control room.
- 3) These valves are normally open. In the event of a control room fire, as defined by the Appendix R criteria, they are closed by the operator and subsequently disconnected from their. power source to ensure no spurious operation.
@II' l ~
