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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17059C7911999-09-30030 September 1999 Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS ML20211P5931999-09-10010 September 1999 Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc ML20211H2231999-08-26026 August 1999 Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20206P2661998-12-30030 December 1998 Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys ML20197K1041998-12-0404 December 1998 Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles ML20196H0671998-11-30030 November 1998 Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101 ML20196D2081998-11-24024 November 1998 Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate ML20154R1101998-10-16016 October 1998 Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open ML20217N7911998-04-24024 April 1998 Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49 ML20202G3751998-02-0505 February 1998 Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405 ML20197H3371997-12-15015 December 1997 Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation ML20211M5231997-10-0707 October 1997 Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts ML20217G9011997-07-31031 July 1997 Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation ML20148A7751997-04-30030 April 1997 Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii ML20116D8121996-07-26026 July 1996 Proposed Tech Specs Re Option B of App J to 10CFR50 ML20115H1521996-07-12012 July 1996 Proposed Tech Specs Section 6.2.2.i Re App a ML20117F9501996-05-15015 May 1996 Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation ML20101F4281996-03-20020 March 1996 Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5 ML20101D7551996-03-15015 March 1996 Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool ML20097D2391996-02-0707 February 1996 Proposed Tech Specs Re Administrative Controls ML20100C1021996-01-25025 January 1996 Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation ML20096G8401996-01-17017 January 1996 Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR ML20094B5421995-10-25025 October 1995 Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level ML20091Q9571995-08-28028 August 1995 Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity ML20081E2491995-03-0909 March 1995 Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test ML20077N1591995-01-0606 January 1995 Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks ML20077N2071995-01-0606 January 1995 Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1 ML20078Q9241994-12-13013 December 1994 Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs ML20077E1561994-12-0202 December 1994 Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid ML20078J3781994-11-14014 November 1994 Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig ML20078E0331994-10-28028 October 1994 Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position ML20078B9841994-10-21021 October 1994 Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs ML20073L8781994-10-0505 October 1994 Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation ML20072U3491994-09-0202 September 1994 Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys ML17059A4471994-09-0101 September 1994 Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases ML20072P6211994-08-26026 August 1994 Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut ML20071G2771994-07-0101 July 1994 Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2 ML20029D4001994-04-27027 April 1994 Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity ML20058N3491993-12-14014 December 1993 Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves ML20056G9391993-09-0202 September 1993 Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators ML20056G1951993-08-27027 August 1993 Proposed Tech Specs,Revising TS 4.8.1.1.2.e, AC Sources - Operating & Adding TS 4.8.1.1.2.f ML20044G6261993-05-26026 May 1993 TS Section 6.8 Re Review & Approval Process for Procedure Changes ML20044F7421993-05-21021 May 1993 Proposed Tech Specs Pages 2-3,3/4 2-2,3/4 3-60,3/4 3-62, 3/4 3-63,3/4 3-64,3/4 3-65 & 6-22 & Bases Page B3/4 2-1 ML20044F3041993-05-19019 May 1993 Proposed Tech Specs Sections 3.4.3.1 & 3.4.3.2 Re Generic Ltr 88-01,drywell Leak Detection Requirements ML17058B7751993-05-14014 May 1993 Proposed Tech Specs,Reflecting Editorial Changes, Administrative Corrections & Retyping of TS ML17056C3281993-03-29029 March 1993 Proposed TS Pages 139 & 140 Re LCO SR for Type a & Local Leak Rate Type B & C Tests ML20012G5441993-02-27027 February 1993 Proposed TS Sections 1.0, Definitions & 3/4.3.6, Control Rod Block Instrumentation. ML17056C2741993-02-18018 February 1993 Proposed TS Table 3.2.7 Re RCS Isolation Valves,Table 3.2.7.1 Re Primary Coolant Sys Pressure Isolation Valves & Table 3.3.4 Re Primary Containment Isolation Valves,Lines Entering Free Space of Containment ML17056C2571993-02-12012 February 1993 Proposed,Revised TS Pages 204,204a,207,225a & 230 to Clarify Operator Actions in Event of Loss of Two Instrument Channels ML20126H9941992-12-30030 December 1992 Proposed Tech Specs 3.4.3.1 & 3.4.3.2 Re RCS Leakage Detection Sys & Operational Leakage to Conform W/ Recommendations of Generic Ltr 88-01 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999 Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS ML20211P5931999-09-10010 September 1999 Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc ML20211H2231999-08-26026 August 1999 Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML18041A0731999-07-27027 July 1999 Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. ML20206P2661998-12-30030 December 1998 Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys ML20197K1041998-12-0404 December 1998 Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles ML20196H0671998-11-30030 November 1998 Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101 ML20196D2081998-11-24024 November 1998 Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate ML20154R1101998-10-16016 October 1998 Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open ML20217N7911998-04-24024 April 1998 Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49 ML20202G3751998-02-0505 February 1998 Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405 ML20197H3371997-12-15015 December 1997 Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation ML20211M5231997-10-0707 October 1997 Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts ML20217G9011997-07-31031 July 1997 Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation ML20148A7751997-04-30030 April 1997 Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii ML17059B2911996-09-0404 September 1996 NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20116D8121996-07-26026 July 1996 Proposed Tech Specs Re Option B of App J to 10CFR50 ML20115H1521996-07-12012 July 1996 Proposed Tech Specs Section 6.2.2.i Re App a ML20117F9501996-05-15015 May 1996 Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation ML20101F4281996-03-20020 March 1996 Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5 ML20101D7551996-03-15015 March 1996 Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool ML20097D2391996-02-0707 February 1996 Proposed Tech Specs Re Administrative Controls ML20100C1021996-01-25025 January 1996 Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation ML20096G8401996-01-17017 January 1996 Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR ML20094B5421995-10-25025 October 1995 Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level ML20091Q9571995-08-28028 August 1995 Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity ML20081E2491995-03-0909 March 1995 Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test ML17059B0221995-02-15015 February 1995 Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. ML17059B0211995-02-10010 February 1995 Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. ML17059B0201995-02-10010 February 1995 Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. ML17059A8881995-01-18018 January 1995 Rev 0 to Field Disposition Instruction 0245-90800, Shroud. ML20077N1591995-01-0606 January 1995 Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks ML20077N2071995-01-0606 January 1995 Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1 ML20078Q9241994-12-13013 December 1994 Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs ML20077E1561994-12-0202 December 1994 Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid ML20078J3781994-11-14014 November 1994 Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig ML17059A5661994-11-0909 November 1994 Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. ML20078E0331994-10-28028 October 1994 Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position ML20078B9841994-10-21021 October 1994 Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs ML20073L8781994-10-0505 October 1994 Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation ML20072U3491994-09-0202 September 1994 Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys ML17059A4471994-09-0101 September 1994 Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases ML20072P6211994-08-26026 August 1994 Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut ML17059A4241994-07-0606 July 1994 Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20071G2771994-07-0101 July 1994 Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2 ML20029D4001994-04-27027 April 1994 Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity ML18040A2941993-12-17017 December 1993 Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20058N3491993-12-14014 December 1993 Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves ML17059A0971993-10-25025 October 1993 Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20056G9391993-09-0202 September 1993 Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators 1999-09-30
[Table view] |
Text
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s ATTACHMENT A NIAGARA MOHAWK POWER CORPORATION LICENSE NO. NPF-69 DOCKET NO. 50-410 Pronosed Changen to Technical Soncifications Replace the existing page 6-2 with the attached revised page 6-2.
i L
a i
t i
l 9607220241 960712 !'
PDR ADOCK 05000410 P PDR '
6.0 ADMINISTRATIVE CONTROLS s
ORGANIZATION UNIT STAFF 6.2.2 (Continued)
- f. A Licensed Senior Operator or Licensed Senior Operator Limited to Fuel Handling shall be responsible for all movement of new and irradiated fuel within the site boundary. All core alterations shall be directly supervised by a Licensed Senior Operator or Licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. All fuel moves within the core shall be directly monitored by a member of the reactor analyst group.
- g. A Fire Brigade
- of five members shall be maintained on site at all times. The Fire Brigade shall not include the Shift Supervisor and the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
- h. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., Licensed Senior Operators, licensed operators, health physicists, auxiliary operators, and key maintenance personnel.
- i. Adequate shift coverage shall be maintained without routine heavy use of overtime. The ,
objective shall be to have operating personnel work an 8 to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, nominal 40-hour l week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major main;enance, or major unit modifications, on a temporary basis the following guidelinea sr.all be followed:
- 1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
l
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift I turnover time.
- The radiation protection qualified individual and Fire Brigade composition may be less than the mir.imum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
l i
j NINE MILE POINT - UNIT 2 6-2 Amendment No. d, M
i
'. l ATTACHMENT B NIAGARA MOHAWK POWER CORPORATION LICENSE NO. NPF-69 DOCKET NO. 50-410 Hand Marked-Uo Version of the Pronosed Chanaes The current version of the NMP2 Technical Specifications page 6-2 has been hand-marked up to reflect the proposed change.
" l 6O ADMfNIS?RATIVE CONTROLS i i
/ ORGANIZATION UNIT STAFF 1
6.2.2 (Continued) j
- f. A Licensed Senier Operator or Licensed Senior Operator Limited to Fuel l Wandling shall be responsible for all movement of new and irradiated fuel l
.itnin the site boundary. All core alterations snall be directly supervise:: l cy a Licensed Senior Operator or Licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during.this operation. All fuel moves within the core shall be directly monitored by a member of the reactor analyst group.
- g. A Fire Brigade
- of five members shall be maintained on sitt at all times.
The Fire Brigade shall not include the Shif t Supervisor and the two otner members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other. essential functions during a fire ;
emergency.
- h. Administrative procedures shall be developed and implemented to limit the working hours of Unit staff who perform safety-related functions; e.g.,
Licensed Senior Operators, licensed operators, health physicists, auxiliary a operators a_ key maintenance personnel, an 9 -to 12 houv- day i nensma.
-'-+^-Adequate 1hift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a = =;I 9 hum Joy, 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:
- 1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time. ;
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any ;
24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more J than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, l including shift turnover time.
- The radiation protection qualified individual and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
6-2 Amendment No. 9, 14 NINE MILE POINT - UNIT 2 1
9001180201 900108 PDR ADOCK 05000410 P PNU
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s ATTACHMENT C NIAGARA MOHAWK POWER CORPORATION LICENSE NO, NPF-69 DOCKET NO. 50-410 hanortina information and no Slanificant Harards Consideration Analvsis l i
INTRODUCTION Nine Mile Point Unit 2 (NMP2) Technical Specifications Section 6.2.2.1. establishes the '
normal work hours for NMP2 operating personnel as, "...a normal 8-hour day,40-hour _ l week..." The proposed change revises this section to state, "...an 8 to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, t
nominal 40-hour week...". The change is consistent with Section 5.2.2.e. of NUREG-1434, i Rev.1, " Standard Technical Specifications, General Electric Plants, BWR/6." The change is i also similar to amendment requests previously approved by the Nuclear Regulatory i Commission Staff which were submitted by Northern States Power Company (Prairie Island Nuclear Generating Plant, Units 1 and 2, approved May 4,1993), Public Service Electric & j Gas Company (Hope Creek Generating Station, approved April 22,1991), Detroit Edison !
(Fermi 2, approved August 27,1990), and Georgia Power Company (Hatch Units 1 and 2, 'i ap' proved November 24,1987). I i
EVALUATION l
~
Establishing operating personnel hours at, "an 8 to 12-hour day, nominal 40-hour week,"
improves the quality of life for operating personnel and does not adversely affect their i performance. The change also reduces the potential for shift-to-shift misinformation and l enhances overall plant operations and maintenance coherence by a potential reduction in i errors by operating personnel because interruptions in activities caused by shift turnovers are reduced. Furthermore, implementation of 12-hour shifts potentially allows completion of plant testing and other important evolutions that normally require more than 8-hours to complete, without the interruption of shift turnovers that result in a loss of continuity. This increases the productivity and effectiveness of the operating personnel and persorinel of other departments that require operations support.
Operating personnel awcreness of plant conditions is maintained. All technical specification sensor checks remain on the required technical specification frequencies. Shift checks to monitor plant conditions will continue. Since NMP2 Technical Specifications define shift frequency as "at least once par 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />," any possible reduction in the number of shift checks resulting from the proposed change (reduction from 3 checks to 2 checks per day),
would be in accordance with the NMP2 licensing bases.
While the length of operating personnel shifts is increased, the intent of this section is to j ensure excessive overtime is not utilized to complete normal or routine operations i department tasks. The proposed change meets the intent of the section in that overtime remains controlled by site administrative procedures in accordance with the NRC Policy Page 1 of 3
Statement on working hours (Generic Letter 82-12). NMP2 has been implementing 12-hour operator shifts for over one year on a trial basis. Over this period, plant productivity and the effectiveness of operations personnel have been maintained. In addition,12-hour shifts are consistent with the work schedules of other plants in the nuclear industry.
CONCLUSIONS The proposed change in operating personnel shift length is consistent with Section 5.2.2.e.
of NUREG-1434, Rev.1, " Standard Technical Specifications, General Electric Plants, BWR/6." The change meets the intent of the current NMP2 Technical Specification section in that overtime remains controlled by site administrative procedures in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12). In addition, NMP2 has sufficient operating personnel to ensure that excessive use of overtime is not required for conduct of normal plant operations. Utilization of 12-hour shifts is also consistent with the !
work schedules of other plants in the nuclear industry. NMP2 has employed 12-hour I operator shifts for over one year with no discernable decline in the performance of operating l personnel. For these reasons, this proposed change does not endanger the health and safety of the public and is consistent with common defense and security.
ANALYSIS NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS 10CFR50.91 requires that at the time a licensee requests an amendment, it must provide to the Commission its analysis, using the standards in 10CFR50.92 concerning the issue of no significant hazards consideration. Therefore, in accordance with 10CFR50.91, the following analyses have been performed with respect to the requested changes.
ENVIRONMENTAL CONSIDERATION 10CFR51.22 provides criteria for, and identification of, licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment. Niagara Mohawk has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(10). Pursuant to 10CFR51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment.
The ooeration of Nine Mile Point Unit 2. In accordance with the orooosed amendment. will not involve a sionificant increase in the orobability or consecuence of an accident oreviousiv evaluated.
Establishing operating personnel work hours at, "an 8 to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, nominal 40-hour week," allows normal plant operations to be managed more effectively and with enhanced continuity. Thare has been no noticeable increase in safety related problems during the trial period. Overtime remains controlled by site administrative procedures in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12). The probability for operating personnel error due to (1) incomplete or insufficient turnover or (2) interruption of in-plant maintenance and testing is reduced. No physical plant modifications are involved, and none of the precursors of previously evaluated accidents are affected. Therefore, this change wi!! not involve a significant increase in the probability or consequences of an accident previously evaluated.
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- l The coeration of Nine Milo Point Unit 2. In accordance with the oronosed amendment will i not create the nossibility of a new or different kind of accident from any accident oreviousIV
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evaluated.
Establishing operating personnel hours at, "an 8 to 12-hour day, nominal 40-hour week,"
improves the quality of life for operating personnel and does not adversely affect their performance. Overtime remains controlled by site administrative procedures in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12). No physical modification of the plant is involved. As such, the change does not introduce any new failure modes or conditions that may create a new or different accident. Therefore, operation in accordance with the proposed amendment will not create the possibility of a new or different kind ri accident from any previously evaluated.
The coeration of Nine Mile Point Unit 2. In accordance with the cronosed amendment will not involve a significant reduction in a margin of safetn Establishing operating personnel hours at, "an 8 to 12-hour day, nominal 40-hour week,"
improves the quality of life for operating personnel and does not adversely affect their performance. This change also decreases the risk of miscommunication between shifts and increases operations and maintenance efficiency by promoting continuity in ongoing plant activities. Overtime remains controlled by site administrative procedures in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12) and is consistent with the improved Standard Technical Specifications. The proposed change involves no physical modification of the plant, or alterations to any accident or transient analysis. There is no Basis to section 6 of the Technical Specifications, and the changes are administrative in nature. Therefore, the change does not involve any significant reduction in a margin of safety.
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