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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20078L5561994-11-23023 November 1994 Proposed Tech Specs Re Independent Technical Reviews ML20076G4701994-10-0707 October 1994 Proposed Tech Specs Re Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20072G0371994-08-15015 August 1994 Proposed Bases of TS 3/4.1.1.3, Moderator Temp Coefficient & 3/4.3.3.2, Incore Detector Sys ML20059H6381994-01-14014 January 1994 Proposed Tech Specs,Changing Administrative Controls in Section 6.0 to Redefine Composition of Sorc,Create Station Qualified Reviewer Program,Delete Requirement to Perform Periodic Procedure Reviews & Revise TS 6.4.2.9 ML20058C3161993-11-23023 November 1993 Proposed Tech Specs,Allowing Operation of Core within Axial Flux Difference Band Expanded from Current Band in TSs & Improved Fuel Cycle Mgt Through Implementation of Core Design Enhancements ML20059C5441993-10-28028 October 1993 Proposed Tech Specs Implementing Thirteen Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20056F7671993-08-26026 August 1993 Proposed Tech Specs Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045C5571993-06-18018 June 1993 Proposed Tech Spec 6.2.3 Reflecting Title Change to Independent Technical Reviews & Deletion of Requirement to Maintain Five Person Organization,Iseg ML20045D5841993-06-18018 June 1993 Proposed Tech Specs Reducing Frequency of Surveillances, Required to Verify Integrity of CST Enclosure ML20127F8101993-01-13013 January 1993 Proposed TS 6.8.1.4 Re Submittal Frequency of Semiannual Radioactive Effluent Release Rept ML20117A8041992-11-25025 November 1992 Proposed Tech Specs for Incore Detector Sys ML20106E4181992-11-0303 November 1992 Proposed TS Section 6.2.2.f Deleting Requirement That Operations Manager Hold or Have Held Senior Reactor Operator License Prior to Assuming Operations Manager Position 1999-07-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210R8051999-08-10010 August 1999 Startup Test Rept for Cycle 7 ML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217Q1111998-02-25025 February 1998 Rev 18 to Odcm ML20211F4401997-09-26026 September 1997 Cycle 6 Startup Test Rept for Seabrook Station,Unit 1 ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20195J1451997-07-23023 July 1997 Rev 15 to Seabrook Station Operating Experience Manual (Ssoe) ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20148K1251997-05-0707 May 1997 Rev 6 to Part I, Seabrook Station Pump & Valve IST Program Plan ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20138J3351996-12-19019 December 1996 Rev 16 to Offsite Dose Calculation Manual ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20115J7481996-03-26026 March 1996 Procedure for Ultrasonic Examination of Centrifugally Cast Stainless Steel Piping Using Low Frequency SAFT-UT System ML20138J3621996-03-21021 March 1996 Process Control Program ML20100G8351996-02-16016 February 1996 Startup Test Rept,Cycle 5. W/ ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20083K7351995-04-19019 April 1995 Rev 74 to Emergency Response Manual (Sser) ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20081J6021995-03-22022 March 1995 Revised Table A.3-1, Radioactive Liquid Waste Sampling & Analysis Program, to ODCM ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20079B2491994-12-27027 December 1994 Proposed Changes to Part a of ODCM 1999-08-10
[Table view] |
Text
'
e ENCLOSURE 1 TO NYN-88096 PROPOSED TECHNICAL SPECIFICATION CHANGES 8807220200 DR 890714 ADOCK {
- 6. 0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall station opera-tion and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Superintendent (or during his absence from the control room, a designated individual) shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President, Nuclear Projuction shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION nere,ve qw.ss2 r p S . 2.1 'h: :ff:it: Org:ni:stier for :tation men:g;;:nt and-technicel suppurt.
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STATION STAFF 6.2.2 -Tt.0-:t: tier Org:ri:: tier :h:l' be :: cheur '- Figur: 5.2-2 and;
- a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1;
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;
- c. A Health Physics Technician
- shall be on site when fuel is in the reactor;
- d. All CORE AmTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; and
- e. Administrative procedures shall be developed and implemented to limit the working hours of statioa staf f who perform safety-related func-tions, e.g., licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance personnel. The amount of overtime worked by station staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
h.dsf.2 7 D
- The Health Physics Technician 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 e *er to accommodate unexpected l absence, provided immediate actior: is take .o fill the required positions.
l l SEABROOK - UNIT 1 6-1
INSERT A 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Oncite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels thcough intermediate levels to and including all operating organi ation positions. These relationships shall be documented and updatad, as appropriate, in the form of organization charts, functional it: scrip-tions for departmental responsibilities and relationships, i.nd job descriptions for key personnel positions, or in equivalent farms of documentation. These requirements shall be documenced in the FSAR and updated in accordance with the requirements of 10CFR50.71.
- b. The Station Manager shall be responsible for overall unit safe i operation and shall have control over those onsite activiti;1 necessary for safe operation and maintenance of the plant.
- c. The Vice President - Nuclear Production shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out hecith physics and quality assurance functions may report to the appropriate onsite manager; howevor, they shall have sufficient vrganizational freedom to ensure their independence f rom owrating pressures.
INSERT B
- f. The Operations Manager and Assistant Operations Manager shall hold a senior reactor operator license.
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& CHIEF EXECUTTYE OFFiC01 P44 YAWEE PREStKNT k CEO SENII7t YlCE [r PRESIDENT
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VICE PRESIDENT NUCLEAR YlCE PESIDENT APO DIRECTOR OF PRODUCTLON QUAL!TY PROGRAMS STATION MANAGER i ram
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SEABROOK - UNIT 1 6-3
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ADMINISTRATIVE CONTROLS
! 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) i FUNCTION ,
1 6.2.3.1 .The ISEG shall function to examine station operating characteristics, l NRC issuances, industry advisories, Licensee Event Reports, and other sources of station design and operating experience information, including units of similar design, which may indicate areas for improving station safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving station safety to the Executive A::f:t:nt te the Serf er !!!::
ore:!d:nt. Vice President of Engineering, Licensing and Quality Programs.
-COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on si.e. Each shall have a bachelor's degree in engineering or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field.
l l RESPONSIBILITIES l
6.2.3.3 The ISEG sha: 1 be responsible for maintaining surveillance of station activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be preparsd, main-I tained, and forwarded each calendar month to the Executive A: ictent to the Scri r "ic: "re:id:nt. Vice President of Engineering, Licensing 6.23 SHIFT TECHNICAL ADVISOR f.2.4.1 1he Shift Technical Adsisor shall provide advisory technical support to the Shift Superintendent in the areas of thermal hydraulics, reactor engi-neering, and plant analysis with regard to the safe operation of the station.
6.3 TRAINING 6.3.1 A reteaining and replacement licensed training progra for'the,s*ation staff shall og_ maintained under the direction of the Trainin C:nt:r fanager and shall et- r ex eed the requirements and recommendations C Sect i c a 5. 5 of ANSI N1.1-197/ an Appendix A of 10 CFR Part 55 and the supplemental requiremen spec ed in Sections A and C of Enclosure 1 of the NRC letter dated March , 1980 to all licensees, and shall include familiarization with relevant industry operational experience.
"Not responsib'e for sign-off function.
SEABROOK - UN!T 1 6-5
ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.4.1.7 (Continued) and the Station Manager however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS 6.4.1.8 The 50RC shall maintain written minutes of each 50RC meeting that, at a 'nimum, document the results of all 50RC activities performed under the respv .,bility provisions of these Technical Specifications. Copies sh311 be provided to the Vice President-Nuclear Production and the N5 ARC.
6.4.2 NUCLEAR SACETY AUDIT REVIEW COMMITTEE (NSARC)
FUNCTION 6.4.2.1 The NSARC shall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear power plant operations,
- b. Nuclear engineering,
- c. Chemistry and radiochemistry,
- d. Metallurgy,
- e. Instrumentatior,and control,
- f. Radiological safety,
- g. Mechanical and electrical engineering, and
- h. QJality assurance practices.
A/U TheNSARCshallreporttoandadvisethe5:ri:r"!:[Presidentonthoseareas of responsibility specified in Specifications 6.4.2.7 and 6.4.2.8.
COMPOSITION 6.4.2.2 The NSARC shall be composed of at least five (5) individuals. The Chairman, Vice Chairman and members, including designated alternates, shall A'#// be appointed in writing by the fir!:r "ice President. Collectively, the individuals appointed to the NSARC should be competent to conduct reviews identified by Specification 6.4.2.1. Each member shall meet the qualifica-tions of ANSI 3.1-1978, Section 4.7.
ALTERNATES 6.d.2.3 All alternate members shall be appointed in writing by the Senter A49/V+ee President to serve on a temporary basis; however, no more than a minority shall participate as voting rambers in NSARC activities at any one time.
CONSULTANTS 6.4.2.4 Consultants shall be .tilized as determined by the NSARC to provide expert advice to the NSARC.
SEABROOK - UNIT 1 6-8
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.' l ADMINISTRATIVE CONTROLS AUDITS 6.4.2.8 (Continued) provided the combined time interval for si.y three consecutive intervals shall not exceed 3.25 times the specified interval. These audits shall encompass:
- a. The conformance of station operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months;
- b. The perf ormance, training, and qualifications of the entire station staff at least once per 12 months;
- c. The results of actions taken to correct deficiencies occurring in station equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months;
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months;
- e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel;
- f. The fire frotection equipment ano program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protectien engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year;
- g. The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months;
- n. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months;
- i. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months;
- j. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months;
- k. The Emergency Plan and implementing procedures at least once per 12 months;
- 1. The Security Plan and implementing procedures at least once per 12 months; and
- m. Any other area of station operation considered appropriate by the NSARC or the Scrf:r '!!:c President.
NNY SEABROOK - UNIT 1 6-10
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ADMINISTRATIVE CONTROLS RECORDS 6.4.2.9 Records of NSARC activities shall be prepared and distributed as indicated below:
- a. Minutes of each NSARC meeting shall be prepared and forwarded to the N#7 kri:r "!:: President within 44-days following each meeting; 30
- b. Reports of reviews encompassed by Specification 6.4.2.7 shall be included in the minutes where applicable or forwarded under sepa-rate cover to the b rie- "ic: President within 14 days following completion of the review; and b h/
- c. Audit reports encompassed by Specification 6.4.2.8 shall be forwarded gpy To tRY Seri:r "ice President and to the management positions respons-ible for the areas audited within 30 days after completion of the audit by the auditing organization.
6.5 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commissior, shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and D. Each REPORTABLE EVENT shall be reviewed by the 50RC and the results of this review shall be submitted to the NSARC and the Vice President-Nuclear Production.
6.6 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
- a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President-Nuclear Production and the NSARC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;
- b. A Safety Limit Violation Report shall be prepared. The report shall be reviend by the 50RC. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence;
- c. The Safety Limit Violation Report shall be submitted to the Commission, the NSARC, and the Vice President-Nuclear Production within 14 days of the violation; and
- d. Operation of the station shall not be resumed until authorized by the Commission.
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! SEABROOK - UNIT 1 6-11