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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] |
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l ATTACIIMENT A I NIAGARA MOIIAWK POWER CORPORATION LICENSE NO. NPF-69 ' ,
DOCKET NO. 50-410 PROPOSED CIIANGES TO THE TECHNICAL SPECIFICATIONS Replace existing page 6-16 with the attached revised page. This page has been retyped in its entirety with marginal markings to indicate changes to the text. :
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b 9306040024 930526 0 PDR ADOCK 0500 P
AO'MINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS
{ PROCEDURES
. 6.8.1 (Continued)
- d. Surveillance and test activities of safety-related equipment
- e. Security Plan implementation
- f. Emergency Plan implementation
- g. Fire Protection Program implementation
- h. PROCESS CONTROL PROGRAM implementation
- i. OFFSITE DOSE CALCULATION MANUAL implementation and l
- j. Quality Assurance for effluent and environmental monitoring.
REVIEW AND APPROVAL 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed in accordance with Spacification 6.5.2 and approved prior to implementation by the branch manager for the functional area of the procedure or higher levels of management as governed l by administrative procedures. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
l l TEMPORARY CHANGES 6.8.3 Temporary changes to pt: a. ;ures of Specification 6.8.1 may be made provided:
- a. The intent of the original procedure is not altered;
- b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and
- c. The change is documented, reviewed in accordance with Specification 6.5.2 and l approved within 14 days of implementation by the branch manager for the functional area I of the procedure or higher levels of management as governed by administrative procedures.
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NINE MILE POINT - UNIT 2 6-16 Amendment No.)fI
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l ATTACIIMENT B Page 1 of 6 NIAGARA MOIIAWK ' POWER CORPORATION LICENSE NO. NPF-69 DOCKET NO. 50-410 SUPPORTING INFORMATION AND NO SIGNIFICANT IIAZARDS !
CONSIDERATION ANALYSIS-INTRODUCTION The proposed changes to Niagara Mohawk Power Corporation's Nine Mile Point Unit 2 Technical Specifications contained herein represent revisions to Section 6.8, " Procedures and Programs." The proposed amendment would modify the approval requirements for procedures important to nuclear safety to allow the branch manager for the functional area of the procedure to approve changes to procedures. This will alleviate undue burden on the
! Plant Manager and place the responsibility with the appropriate branch manager.for the functional area of the procedure. Currently, the Plant Manager is required to review and approve each procedure prior to its implementation.
In addition, an editorial change has been proposed to correct the spelling of "DOES" to
" DOSE" in Technical Specification section 6.8.1.i. This change will correct a spelling error in amendment 25 of the Technical Specifications for Nine Mile Point Unit 2. :
The proposed changes to delete the footnote on page 6-16 and to replace the reference to SORC in Specifications 6.8.2 and 6.8.3.c with a reference to Specification 6.5.2 are being requested for clarification purposes and do not change what is currently allowed by the Nine Mile Point Unit 2 Technical Specifications.
DESCRIFFION OF PROPOSED TECIINICAL SPECIFICATION CIIANGES Niagara Mohawk Power Corporation (NMPC) proposes the following changes:
- 1) Technical Specification (TS) Section 6.8.2, " Review and Approval", currently states:
"Each procedure of Specification 6.8.1 and changes thereto, shall be approved by the Plant Manager based on the recommendations of SORC* before implementation and reviewed periodically as set forth in administrative procedures."
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i Page 2 of 6 NMPC proposes to modify the above TS Section to state:
"Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed in -
accordance with Specification 6.5.2 and approved prior to implementation by the branch manager for the functional area of the procedure or higher levels of management as governed by administrative procedures. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures."
- 2) TS Section 6.8.3.c, which addresses temporary changes to procedures, currently states:
"The change is documented, approved by the Plant Manager based on the recommendations of the SORC within 14 days ofimplementation."
NMPC proposes to modify the above TS section to state:
"The change is documented, reviewed in accordance with Specification 6.5.2 and approved within 14 days of implementation by the branch manager for the functional area of the procedure or higher levels of management as governed by administrative procedures."
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- 3) The footnote on Technical Specification page 6-16 currently statcs:
"*SORC recommendations to the Plant Manager are to be based on SORC responsibilities as identified in Specification 6.5.1.7.a."
1 NMPC proposes to delete this footnote.
- 4) TS Section 6.8.1.i currently states:
"OFFSITE DOES CALCULATION MANUAL implementation and" l
NMPC proposes the following editorial change:
"OFFSITE DOSE CALCULATION MANUAL implementation and" EVALUATION The proposed amendment consists of administrative changes which shift the approval of procedures important to nuclear safety from the Plant Manager to the branch manager for the functional area of the procedure. These changes will allow the approval of a procedure by l
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Page 3 of 6 the branch manager in the area of expertise for the procedure, thereby providing the Plant j Manager with more time for other responsibilities. In addition, an editorial change has been '
proposed to correct the spelling of "DOES" to " DOSE" in TS section 6.8.1.i. This change will correct a spelling error in Amendent 25 of the Technical Specifications for Nine Mile Point Unit 2. ,
The logical basis for requiring the Plant Manager to approve all procedures prior to implementation is to ensure that overall plant impact is considered from an adequate management and power plant experience base as well as for effectiveness in achieving its purpose. Niagara Mohawk concludes that the proposed changes do not reduce the effectiveness of the Specification and will relieve the Plant Manager of administrative duties which the branch managers are fully capable and qualified to perform.
The quality of plant procedures will be preserved since approval will rest with the branch managers in the area of expertise for the procedure. Niagara Mohawk believes that it is prudent to have plant procedures approved by the appropriate branch manager. This allows the person most familiar with the procedure the opportunity to approve it. Any safety concerns regarding a procedure change can be elevated to higher levels of management. The proposed changes are intended to enhance the overall management capability and performance of Nine Mile Point Unit 2 by freeing the Plant Manager for other duties involving plant safety.
Niagara Mohawk's current procedure program requires that:
- Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure.
- Procedures shall be approved as designated by the owner organization before initial use. Rules shall be established which clearly delineate the review of l procedures by knowledgeable personnel other than the originator and the l approval of procedures and procedure changes by authorized individuals.
- Changes to documents shall be reviewed by the same organization that performed the original review unless the owner organization designates another i
qualified organization.
i The footnote on page 6-16 is proposed for deletion to clarify the Station Operations Review
- Comn.ittee (SORC) functions with respect to procedures and changes thereto. It is also i l
proposed to replace the reference to SORC in Specifications 6.8.2 and 6.8.3.c with a reference to Specification 6.5.2. These changes are being made to more accurately depict the process currently in place for review of procedures and procedure changes.
Page 4 of 6 l
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The review and control of procedures and procedure changes is required per Specification l 6.5.2, " Technical Review and Control Activities." This section requires an independent review by technically qualified personnel and, if necessary, additional cross-disciplinary !
review. The proposed changes to remove the footnote on page 6-16 and to replace the l reference to SORC in Specifications 6.8.2 and 6.8.3.c with a reference to Specification 6.5.2 )
will not alter the process that is currently in effect at Nine Mile Point Unit 2. These !
proposed changes will state more succinctly what is currently allowed by the Nine Mile Point i Unit 2 Technical Specifications. Furthermore, these changes are in agreement with Section l 5.0 of NUREG-1433, " Improved Standard Technical Specifications", for BWR/4.
CONCLUSION The proposed amendment incorporates an editorial change and administrative changes and does not affect assumptions contained in any safety analyses. There are no physical changes to the facility or any changes to operating procedures. Limiting Conditions for Operation (LCO's), limiting safety system settings, and safety limits specified in the Technical Specifications will also remain ur. changed as a result of the proposed amendment. Since there are no changes in the way the plant is operated and plant equipment and physical features are not affected, the potential for an unanalyzed accident is not created.
Furthermore, the quality of plant procedures will be preserved since approval will rest with the branch managers in the area of expertise for the procedure. For these reasons, there is reasonable assurance that the changes that would be authorized by the proposed amendment can be implemented without endangering the health and safety of the public and are consistent with common defense and security.
NO SIGNIFICANT HAZARDS CONSIDERATION 10CFR 6 50.91 requires that at the time a licensee requests an amendment, it must provide to the Commission its analysis using the standards in 10 CFR 6 50.92 concerning the issue of no significant hazards consideration. Therefore, in accordance with 10 CFR f 50.92, the following analysis has been performed:
The operation of Nine Mile Point Unit 2 in accordance with the nronosed amendment will not involve a significant increase in the nrobability or consecuences of an accident j oreviousiv evaluated. l The proposed amendment incorporates administrative and editorial changes and does not affect assumptions contained in any safety analyses nor do the changes affect Technical l Specifications that preserve safety analyses assumptions. Additionally, these proposed !
changes do not modify the physical design or operation of the plant. Furthermore, the quality of plant procedures will be preserved since approval will rest with the branch i
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\
. Page 5 of 6 j managers in the area of expertise for the procedure. Niagara Mohawk believes that it is prudent to have plant procedures approved by the appropriate branch manager. This allows the person most familiar with the procedure the ability to approve it. Any safety concerns t regarding a procedure change can be elevated to higher levels of management. The proposed :
l changes are intended to enhance the overall management capability and performance of Nine Mile Point Unit 2 by freeing the Plant Manager for other duties involving plant safety. The !
proposed changes to delete the footnote on page 6-16 and to replace the reference to SORC in Specifications 6.8.2 and 6.8.3.c with a reference to Specification 6.5.2 are being requested
! for clarification purposes and do not change what is currently allowed by the Nine Mile Point ,
Unit 2 Technical Specifications. In addition, an editorial change has been proposed to
, correct the spelling of "DOES" to " DOSE" in Section 6.8.1.i. Therefore, the proposed l amendment will not increase the probability or consequences of an accident previously evaluated.
The operation of Nine Mile Point Unit 2 in accordance with the oronosed amendment will not create the nossibility of a new or different kind of accident from any accident . ,
previousiv evaluated. i l
Sir.ce there are no changes in the way the plant is operated and plant equipment and physical l features are not affected, the potential for an unanalyzed accident is not created. The ,
l proposed changes are administrative and editorial in nature and do not affect any accident l initiators for Nine Mile Point Unit 2. Therefore, no new failure modes are introduced.
Furthermore, the quality of station procedures will be preserved since approval will rest with the branch managers in the area of expertise for the procedure. Niagara Mohawk believes that it is prudent to have plant procedures reviewed by the appropriate branch manager. 'This allows the person most familiar with the procedure the ability to approve it. Any safety ,
concerns regarding a procedure change can be elevated to higher levels of management. The proposed changes are intended to enhance the overall management capability and performance of Nine Mile Point Unit 2 by freeing the Plant Manager for other duties ,
l involvi.ng plant safety. The proposed changes to delete the footnote on page 6-16 and to -
l replace the reference to SORC in Specifications 6.8.2 and 6.8.3.c with a reference to l Specification 6.5.2 are being requested for clarification purposes and do not change what is ,
currently allowed by the Nine Mile Point Unit 2 Technical Specifications. In addition, an '
l editorial change has been proposed to correct the spelling of "DOES" to " DOSE" in Section l 6.8.1.i. The proposed amendment will, therefore, not create the possibility of a new or different kind of accident from any accident previously evaluated.
The operation of Nine Mile Point Unit 2 in accordance with the proposed amendment will not involve a significant reduction in aJmLrein of safety.
Plant safety margins are established through LCO's, limiting safety system settings, and safety limits specified in the Technical Specifications. As a result of the proposed ,
amendment, there will be no changes to eiti.er the physical design of the plant or to any of i
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. Page 6 of 6 these settings and limits. No margin of safety is affected by this change. The initial conditions utilized in the conduct of the accident analysis are unchanged. The methodologies used for the analyses are unchanged. The analyses results are not impacted. Sufficient controls are included in the procedure review methodology to ensure that the plant conditions and equipment availability required to support the integrity of the analyses, and hence the margin of safety, will continue to be maintained.
The proposed amendment does not involve a significant reduction in a margin of safety because Niagara Mohawk, through its Quality Assurance programs and other required controls, maintains ANSI standard or Regulatory Guide 1.8, as appropriate, qualified personnel in positions of responsibility. This assures that procedures and procedure changes are approved at a high level of competence.
The proposed changes are administrative and editorial in nature and do not affect the safe operation of the plant. Therefore, there will be no changes to any of the margins of safety.
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