Similar Documents at Surry |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing ZIRLO Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating ML18153B0061994-07-14014 July 1994 Proposed Tech Specs Changes Will Eliminate Remaining References to cycle-specific Parameters in Surry TS ML18152A1821994-06-0909 June 1994 Proposed TS Re Chemical & Vol Control Sys & Safety Injection Sys ML20065P6111994-04-19019 April 1994 Proposed Tech Specs,Modifying Control Rod Movement Surveillance Frequency ML18153A8821994-02-25025 February 1994 Proposed Tech Specs Modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys ML18153B4321993-12-27027 December 1993 Proposed Tech Specs Reflecting Revised Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML18153B4081993-12-10010 December 1993 Proposed Tech Specs,Establishing Upper Limit on Allowable COLR Mtc Values ML18153B4021993-12-10010 December 1993 Proposed Tech Specs,Modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 & NUREG-1431 ML18153B4051993-12-10010 December 1993 Proposed Tech Specs,Updating Augmented Insp Program for Sensitized Stainless Steel by Incorporating Newer Code Requirements,While Maintaining Augmented Insp Philosophy ML18153B3751993-11-15015 November 1993 Proposed Tech Specs Implementing Revised 10CFR20,revising Frequency Radiological Release Repts from Semiannual to Annual & Clarifying Site Maps ML18153B3501993-10-19019 October 1993 Proposed Tech Specs for RSHX Svc Water Outlet Radiation Monitors ML18153B3321993-09-29029 September 1993 Proposed Tech Specs Modifying Required Insp Frequency of Low Pressure Turbine Blades to Permit Blade Insp to Be Performed Concurrent W/Disk & Hub Insp ML18152A0481993-07-20020 July 1993 Proposed Tech Specs Deleting Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3921993-07-16016 July 1993 Proposed Tech Specs for Operation W/Three Degree Increase in Svc Water Temp Limit for Containment Air Partial Pressures of 9.1,9.2 & 9.35 Psia ML18152A0461993-07-16016 July 1993 Proposed Tech Specs Implementing Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from semi-annual to Annual,& Clarify Site Maps ML18152A4511993-07-0202 July 1993 Proposed Tech Specs to Include COLR Which Presents reload- Specific Limits for Key Core Operating Parameters ML18153D3811993-07-0202 July 1993 Proposed TS Table 4.2-1 Re Miscellaneous Insps & Sensitized Stainless Steel Exams ML18153D3331993-05-0606 May 1993 Proposed Tech Specs Supporting Operation of Unit 2 w/100 Psi Reduction in RCS Nominal Operating Pressure Through End of Operating Cycle 12 1999-08-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18151A6641999-08-0606 August 1999 Rev 0 to Surry Unit 2 Cycle 16 Startup Physics Tests Rept ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18151A5511999-02-10010 February 1999 To NE-1187, Surry Unit 1,Cycle 16 Startup Physics Tests Rept ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML20249B9911998-05-0606 May 1998 Analysis of Capsule X Virginia Power Surry Unit 1 Reactor Vessel Matl Surveillance Program. W/Evaluation of Surry Unit 1 Surveillance Capsule X Results & Response to NRC RAI Re GL 92-01,rev 1,suppl 1 ML18151A1931998-05-0404 May 1998 Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20199B0711998-01-0505 January 1998 Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18150A4661997-12-16016 December 1997 ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2 ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18150A4641997-10-27027 October 1997 Risk-Informed ISI (RI-ISI) Pilot Program Submittal ML18151A3911997-10-16016 October 1997 Rev 8 to VPAP-2103, Odcm ML18151A7231997-08-0707 August 1997 Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products ML20210J5031997-07-31031 July 1997 Rev 0 to NE-1132, Surry Unit 1,Cycle 15 Startup Physics Tests Rept ML18150A4441997-06-0909 June 1997 Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003 ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18151A9761996-08-13013 August 1996 Cycle 14 Startup Physics Test Rept ML20134J9861996-07-30030 July 1996 /Unit 2 Fuel Assembly Insp Program ML18152A4701996-06-13013 June 1996 Cycle 13 Control Rod Performance Test Results ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18152A0571995-12-20020 December 1995 Startup Physics Test Rept,Surry Unit 1,Cycle 14 ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18151A6421995-08-0101 August 1995 Change 3 to Rev 0 to Third Interval IST Program ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML20083C9951995-05-0808 May 1995 Rev 0 to Surry Unit 2,Cycle 13 Startup Physics Tests Rept ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing ZIRLO Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating 1999-08-06
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e ATTACHMENT 1 SUPPLEMENTAL REVISIONS TO PROPOSED TECHNICAL SPECIFICATION CHANGE Pages 6.1-1, 6.1-6, 6.4-5, and Figure 6.1-2 were previously submitted on November 2, 1984 (S.N. 577).
The attached pages supercede the corresponding pages in that submittal.
Page 6.4-2 is also attached for the first time.
8504290387 850417
~DR ADOCK 05000280 PDR
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e TS 6.1-1 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization, Safety and Operation Review Specification A.
The Station Manager shall be responsible for the overall operation of the facility.
In his absence, the Assistant Station Manager (Operations and Maintenance) shall be responsible for the safe operation of the facility.
During the absence of both, the Station Manager will delegate in writing the succession to this responsibility.
- 1.
The off-site organization for facility management and technical support shall be as* shown on TS Figure 6.1-1.
B.
The Station organization shall conform to the chart as shown on TS Figure 6.1-2.
- 1.
Each member of the facility staff shall meet or exceed the minimum qualifications of ANS 3.1 (12/79 Draft) for comparable positions, and the supplemental requirements specified in the March 28, 1980 NRC letter to all licensees, except for the Superintendent - Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
e TS 6.1-6 C.
Organization units to provide a continuing review of the opera-tional and safety aspects of the nuclear facility shall be constituted and have the authority and responsibilities outlined below:
- 1.
Station Nuclear Safety and Operating Committee (SNSOC)
- a.
Function
- b.
The SNSOC shall function to advise the Station Manager on all matters related to nuclear safety.
Composition The SNSOC shall be composed of the:
Chairman Vice Chairman Member Member Member Member Assistant Station Manager, Nuclear Safety and Licensing Assistant Station Manager, Operations and Maintenance Superintendent-Operations Superintendent-Maintenance Superintendent-Technical Svcs.
Superintendent-Health Physics
- c.
Alternates
- d.
- e.
All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; however, no more than two alternates shall partici-pate as voting members in SNSOC activities at any one time.
Meeting Frequency The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his desig-nated alternate.
Quorum A quorum of the SNSOC shall consist of the Chairman or Vice Chairman and two members including alternates.
e TS 6.4-2
- 1.
The intent of 10 CFR 20.203(c)(2)(iii) shall be implemented by satisfying the following conditions:
- a.
The entrance to each radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted.
- b.
The entrance to each radiation area in which the intensity of radiation is equal to or greater than 1000 mrem/hr shall be provided with locked barricades to prevent unauthorized entry into these areas.
Keys to these locked barricades shall be maintained under the administrative control of the Shift Supervisor on duty and/or Superintendent Health Physics.
- c.
All such accessible high radiation areas shall be surveyed by Health Physics personnel on a routine schedule, as determined by the Superintendent-Health Physics, to assure a safe and practical program.
- d.
Any individual entering a high radiation area shall have completed the indoctrination course designed to explain the hazards and safety requirements involved, or shall be escorted at all times by a person who has completed the course.
- e.
Any individual or group of individuals permitted to enter a high radiation area per 1. d above, shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
- 1.
Administrative
- 2.
Abnormal
- 3.
Annunciator
- 4.
Health Physics
- 5.
Emergency
- 6.
Maintenance
- 7.
Operating
- 8.
Periodic Test
- 9.
Start-up Test
- 10.
Special Test
- 11.
Quality Assurance
- 12.
Chemistry e
TS 6.4-5 Station Manager Superintendent - Operations Superintendent - Operations Superintendent-Health Physics Superintendent - Operations Mechanical Supervisor Electrical Supervisor Instrument Supervisor Superintendent - Operations Engineering Supervisor Engineering Supervisor Engineering Supervisor Resident Quality Control Engineer Supervisor - Chemistry Such changes will be documented as subsequently reviewed and approved by the Station Nuclear Safety and Operating Committee.
G.
In cases of emergency, operations personnel shall be authorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility.
Such changes shall be docu-mented, reviewed and approved by the Station Nuclear and Operating Committee.
MANAGER MAINTENANCE ANll PERFORMANCE SERVICES MANAGER POWER TRAINING SERVICES DIRECTOR
)
NUCLEAR TRAINING SUPERINTENDEN1 NUCLEAR TRAINING SUPERVISOR ENGINEERING (PLANNING)
L SURRY POWER STATION ORGANIZATION CHART ST~TION NUCLEAR SAFETY I OPER.
COMMITTEE VICE PRESIDENT NUCLEAR OPERATIONS STATION MANAGER EXECUTIVE MANAGER QUALITY ASSURANCE
- - -~
MANAGER QUALITY ASSURANCE I
SUPERVISOR QUALITY CONTROL Q.A. ACTIVITIES
- - -------------1-----,..------------..-----------.-------,
UPERINTENDEN OPERATIONS L
SHIFT SUPERVISOR SL ASST. SHIFT SUPERVISOR SL CONTROL RM OPERATOR OL CONTROL RM OPERATOR/
TRAINEE ASSISTANT STATION MANAGER (0 a M)
SUPERINTENDEN MAINTENANCE SUPERVISOR MECHANICAL AINTENANCE ELECTRICAL SUPERVISOR SUPERVISOR MAINTENANCE SERVICES SUPERINTENDEN TECHNICAL SERVICES SUPERVISOR CHEMISTRY INSTRUMENT SUPEVISOR SUPEVISOR ENGINEERING PERF. & TEST SUPV.-ENG.
(D/C &
PRO.ECTS)
ASSISTANT STATION MANAGER (NS a L)
SUPERINTENDENT PROJECTS SUPV.-ENO.
COORDINATOR LICENSING (SAFETY ENO.
EMERGENCY COORDINATOR STAFF)
PLANNING SHFT.
TECHNCAL ADVISORS SL -
Senior Llcenae OL -
Operator's Lice nee
---Communlcallons SUPERINTENDENT HEALTH PHYSICS DIRECTOR Nl,ICLEAR SECURITY SUPERVISOR ADMIN.
SERVICES SUPERVISOR BUSINESS RECORDS SYSTEMS MANAGEMENT SUPERVISOR SAFETY SUPERVISOR SUPERVISOR PERSONNEL SERVICES LOSS STATION PREVENTION SECURITY SUPERVISO SUPERVISOR en t,:j t-'*
OQ C
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e ATTACHMENT 2 DISCUSSION OF PROPOSED SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGES
e e
DISCUSSION OF PROPOSED SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGES The proposed Technical Specification change reflects the most recent reorganization within the Nuclear Operations Department, and supplements the previously proposed reorganization changes which were submitted to the NRC on November 2, 1984 (SN: 5 77).
The specifics of this change request deal with the addition of the position of Superintendent-Health Physics.
All previous Technical Specification references to the Supervisor-Health Physics have been changed to the Superintendent-Health Physics.
This title change is commensurate with the responsibilities associated with the Health Physics organization at Surry.
The Superintendent-Health Physics directs the activity of the Health Physics Group at the station, ensuring that all data are correctly interpreted and acted on as necessary.
He is directly responsible to the Station Manager and coordinates his efforts with the Superintendent-Operations, the Superintendent-Maintenance, and the Superintendent-Technical Services.
Because this change strengthens the existing authorities and responsibilities to enhance management controls in the Health Physics
- areas, these changes are considered administrative in nature, no unreviewed safety question is involved.
Similarly, because the proposed amendment is administrative in nature, and is similar to Example (i) of the examples specified in the Federal
- Register, 48 FR 14870, which lists examples of amendments that are considered not likely to involve significant hazards considerations, no significant hazards consideration is involved.