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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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e Attachment 2 Technical Specifications Change Surry Power Station 9410140256 941011 PDR ADOCK 05000280 P PDR
I I
TABLE 4.1-2A (CONTINUED)
MINIMUM FREQUENCY FOR EQUIPMENT TESTS UFSAR SECTION DESCRIPTION FREQUENCY REFERENCE
- 18. Primary Coolant System Functional 1. Periodic leakage testing(a)(b) on each valve listed in Specification 3.1.C.7a shall.be accomplished prior to entering POWER OPERATION after every time the plant is placed in COLD SHUTDOWN for refueling, after each time the plant is placed in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is e
performed.
- 19. ,Containment Purge MOV Leakage Functional Semi-Annual (Unit at power or shutdown) if purge valves are operated during interva1(c)
- 20. Containment Hydrogen Analyzers a. CHANNEL FUNCTIONAL TEST Once per 92 days
- b. CHANNEL CALIBRATION Once per 18 months
- 1. Sample gas used:
One volume percent
(+/-0.25%) hydrogen, balance nitrogen Four volume percent
(+/-0.25%) hydrogen, balance nitrogen
- 2. CHANNEL CALIBRATION will include startup and operation of the Heat Tracing System e
- 21. RCS Flow Flow ~ 273,000 gpm Once per refueling cycle 14
- 22. RWST Parameters a. Temperature~ 45°F Once per shift
- b. Volume ~ 387,100 gallons Once per shift
-I
(/)
(a)
To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve
......
~
I compliance with the leakage criteria. I.C (b) a.
Minimum differential test pressure shall not be below 150 psid.
(c) Refer to Section 4.4 for acceptance criteria.
See Specification 4.1.D.
e Attachment 3 Significant Hazards Consideration Determination Surry Power Station
e e Significant Hazards Considerations As documented in NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements," dated December 13, 1992, the NRC has completed a comprehensive examination of surveillance requirements in technical specifications that require testing at power. The NRC staff found that while the majority of testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by reducing the amount of testing that is required by technical specifications at power. Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993, provides guidance for preparing license amendments to implement the recommendations of NUREG-1366. Consistent with GL 93-05, we are proposing changes to the surveillance frequencies of the containment hydrogen analyzers for Surry.
NUREG-0737 required continuous indication of containment hydrogen concentration in the control room within 30 minutes of the initiation of safety injection. This indication is only used to monitor hydrogen concentration in containment following a loss-of-coolant-accident (LOCA) and to alert the plant operator to take planned manual actions to activate the hydrogen recombiners. Hydrogen recombiners are not immediately required following accident initiation. For the design basis accident (i.e., large break LOCA) they are not needed for a period of several days.
Surry has the capability to provide continuous indication in the control room of the hydrogen concentration in the containment atmosphere within 30 minutes of the initiation of safety injection. During normal plant operations, Surry maintains the analyzers in a standby mode and only fully energizes the equipment to perform the Technical Specification routine surveillance requirements. Both a monthly functional test and a quarterly calibration are performed on the hydrogen analyzers. The surveillance test history at Surry has shown that the hydrogen analyzers to be very reliable and a change in test frequency is not expected to adversely affect that experience.
Virginia Electric and Power Company has reviewed the proposed changes against the criteria of 1O CFR 50.92 and has concluded that the changes as proposed do not pose a significant hazards consideration. The proposed changes to the surveillance requirements for the hydrogen analyzers at Surry are consistent with the intent of Page 1 of 3
' . e
- Ge,neric Letter 93-05, dated September 27, 1993, which was promulgated to improve safety, decrease equipment degradation, and reduce unnecessary burden on personnel resources by reducing testing requirements that are marginal to safety. Specifically, operation of Surry Power Station in accordance with the proposed Technical Specifications changes will not:
- 1. Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
The proposed changes to the surveillance requirements for the hydrogen analyzers have no impact on the probability of any accident occurrence. The hydrogen analyzers are maintained in a standby mode during normal operation and are made fully operable within thirty minutes after a safety injection signal to provide indication of the hydrogen concentration in containment after a loss-of-coolant accident. This instrumentation is used solely post-accident to monitor containment conditions. Reduced testing of a post-accident monitor does not contribute to the probability of any previously analyzed accident. These monitors have no automatic safety function. Furthermore, the hydrogen analyzers will be operated in the same manner, and the operability requirements are not being altered. In addition, the Post-Accident Sampling System serves as a diverse means to confirm post-accident hydrogen concentration in containment.
Therefore, the consequences of a Design Basis Accident are not being increased by the proposed change in surveillance test frequency of the hydrogen analyzers.
Reducing the frequency of surveillance testing could however decrease the timeliness in identifying an inoperable hydrogen analyzer. However, our surveillance test experience has shown that the analyzers have been very stable with repeatable results, and we conclude that the change in test frequency should not affect the reliability or operability of the analyzers. Likewise, the NRC has determined in Generic Letter 93-05 that a reduced frequency of surveillance testing during power is acceptable to determine hydrogen analyzer operability.
Page 2 of 3
,2. Create the possibility of a new or different kind of accident from any accident previously evaluated.
There are no plant modifications or changes in methods of plant operation introduced by this change in hydrogen analyzer surveillance frequencies. The hydrogen analyzers are maintained in a standby mode during normal operation and are fully operable within thirty minutes after a safety injection signal to provide indication of the hydrogen concentration in containment after a loss-of-coolant accident. Therefore, the possibility of a new or different kind of accident than previously evaluated is not created by the proposed changes in surveillance frequency of the control rods.
- 3. Involve a significant reduction in a margin of safety.
The hydrogen analyzer surveillance requirements do not affect the margin of safety in that the operability requirements for the safety systems and containment remain unchanged. The hydrogen analyzers only provide indication and do not perform any direct function to mitigate the consequences of any previously analyzed accidents. Furthermore, the change in surveillance frequency is associated with a post-accident monitor with no automatic safety functions and a diverse means of confirming the parameter by the Post-Accident Sampling System. Therefore, the margin of safety is not altered by this proposed change in the surveillance frequencies of the hydrogen analyzers.
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