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. W/960830 Ltr 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. W/960111 Ltr 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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ATTACHMENT 1 SURRY POWER STATION PROPOSED TECHNICAL SPECIFICATION CHANGE RADWASTE FACILITY GASEOUS EFFLUENT
?104010385 910327 PDR ADOCK o~noc*1?0(1 p . ----~5~-
I1 Inch = Approximately 1,000 Feet I STATION .'
A. Gaseous Release
- 1. Process Vent - 131 Ft. - Mixed Mode JAMES 2. Vent-Vent Stacks.
RIVER Ground Level B. Liquid Leaves Site RADWASTE FACILITY C. Gaseous Release Ground Level
- Security Fence -Area Outside is Unrestricted for
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Gaseous Effluents
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~i~ _!3~~ndary Land Maximum Individual Occupancy Within Site I I Boundary:
I I I 1. Canal Bank Fishing = 160 HrNr
- - - _ I Liquid Maximum Individual Occupancy Within Site Boundary:
- 1. Boat Fishing Discharge Canal = 800 HrNr
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I JAMES
RIVER Site Boundary' ' , - - - - -----------------,!
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FIGURE 5.1-1 (t) 01 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE ......
GASEOUS AND LIQUID EFFLUENTS
ATTACHMENT 2 SURRY POWER STATION PROPOSED TECHNICAL SPECIFICATION CHANGE RADWASTE FACILITY GASEOUS EFFLUENT SIGNIFICANT HAZARDS CONSIDERATION
e BACKGROUND The Radwaste Facility is being constructed to supplement the radwaste systems at Surry Power Station. The purposes of the installation are to treat liquid and solid waste, to provide a decontamination facility, and to store packaged processed radwaste prior to shipment. A safety evaluation has been developed with the results being that there is no increase in the radiological effluents or the risk of an accident.
Therefore, the construction of the Radwaste Facility is being accomplished under the provisions of 10 CFR 50.59.
The Radwaste Facility is located east of the station just outside the protected area fence in the construction area. The Radwaste Facility has a radiation monitoring system to ensure the radiological protection of the facility personnel and members of the general public, as well as monitor, record, and control the release of radioactive materials.
The overall design approach in the construction of the Radwaste Facility was to ensure that quantity of radioactive effluents generated would be less than or equal to the amount presently generated. Our evaluation concludes that lower total station releases of radioactive materials in liquid effluents is achievable. Although the thyroid component of calculated dose from routine liquid radwaste increases slightly, the overall calculated Appendix I exposure would decrease with the use of the radwaste facility. The GI-LU remains the most limiting organ with respect to dose. The liquid effluent discharge point_ for the Radwaste Facility is the same as the existing plant discharge point. In addition, the total gaseous release of radioactive material from the station will not increase as a result of the Radwaste Facility.
DISCUSSION OF CHANGE Construction of a Radwaste Facility at Surry Power Station is being performed under the provisions of 10 CFR 50.59. Formal reporting of these station modifications will be made in accordance with Technical Specification 6.9 and by inclusion into the UFSAR after the facility becomes operational.
The proposed Technical Specification change incorporates the location of the gaseous effluent release point associated with the Radwaste Facility into the site map
e Figure 5.1-1 in the Design Features section of the Technical Specifications. The purpose of that figure in Technical Specifications is to define the unrestricted areas with respect to the plant effluent release points. The proposed change is administrative in nature in that it simply identifies the gaseous release point for the Radwaste Facility. There are no limiting conditions for operation, action statements, or surveillance requirements associated with this section of the Technical Specifications.
Since the liquid effluent discharge point for the site remains unchanged, no similar changes of Figure 5.1-1 are needed for the liquid effluents from the Radwaste Facility.
Additionally, the Station's Process Vent at 131 feet is being identifed as a mixed mode release point. The vent has been treated as a mixed mode release point but never identified as such in the Technical Specifications.
SIGNIFICANT HAZARDS CONSIDERATION Virginia Electric and Power Company has reviewed the proposed changes against the criteria of 10 CFR 50.92 and has concluded that the changes as proposed do not pose a significant hazards consideration. Specifically, the proposed change is administrative in nature, in that it merely adds the Radwaste Facility gaseous release point to the Design Features section (Section 5) of the Technical Specifications. Thus, operation of the Surry Power Station in accordance with the proposed administrative changes will not:
- 1. Involve a significant increase in the probability of occurrence or consequences of any accident or malfunction of equipment which is important to safety and which has been evaluated in the UFSAR. The Radwaste Facility has been designed as a facility enhancement to improve the existing radwaste processing capabilities of the plant with the intent of reducing the overall quantity of radioactive effluents discharged from the plant. As part of off-gasing during liquid radwaste processing, a small portion of normal plant gaseous effluents will be discharged by way of the Radwaste Facility vent. This effluent would otherwise be discharged by way of the vent-vent stack. Processing radwaste in the Radwaste Facility rather than using the existing station's processes involves no significant increase in the probability or consequences of any accident previously evaluated in the UFSAR and is bounded by the Chapter 14 analyses. As for the specific proposed change to Technical
e Specifications to incorporate the gaseous release point into Figure 5.1-1, it is administrative in nature and has no effect on analyzed accident probabilities or consequences.
- 2. Create the possibility of a new or different type of accident from those previously evaluated in the safety analysis report. As noted above, the Radwaste Facility is designed to improve upon existing radwaste processing capabilities. An evaporation process as well as a demineralization process will be used *to process liquid radwaste. The original evaporation process has not been in use at Surry for several years, but a radioactive release due to failure of the evaporator had been previously considered in the original design basis. The calculated release is negligible with respect to the rupture of a waste gas decay tank. Within the scope of radwaste processing, the Radwaste Facility does not introduce any new or different type of accident. As for the specific proposed change, it is administrative in nature and has no effect on creating a new or different type of accident.
- 3. Involve a significant reduction in the margin of safety. Safety system operations are not being changed nor are any of the accident analysis assumptions being modified or exceeded by this change. As stated above, the Radwaste Facility has been designed to reduce the overall quantity of radwaste generated for discharge and its operation is bounded by the existing UFSAR analyses. As for the specific proposed change, it is administrative in nature and involves no overall change to safety system operations. The margin _of safety is not changed by the administrative identification of the location of the Radwaste Facility gaseous release point in Figure 5.1-1.