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 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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
[Table view] |
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ATTACHMENT II This Attachment provides a draft of our proposed Technical Specifications as requested in the following NRC Question:
NRC Question 5: " Submit draf t proposed Technical Specifications changes to address limiting conditions for operation, testing, calibration, and surveillance requirements for the proposed undervoltage protection schemes. Also, a test is required to be included in the Technical Specifications to demonstrate the operability of .the automatic bypassing and auto-reinstatement of the undervoltage relays when the diesel generators are supplying the Class lE buses (see NRC letter dated June 3,1977)."
J l
i 8207080225 820630 PDR ADOCK 05000280 P ,
PDR -- - - - - . - - . . . - . . - , . , _ _ _ ___ ___ _ _
TABLE 3.7-2 ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS 1 2 3 4 OPERATOR ACTION IF CONDITIONS OF DEGREE COLUMN 1, OR 2 MIN. OF EXCEPT AS CONDI-OPERABLE REDUN- PERMISSIBLE BYPASS TIONED BY COLUMN 3 CHANNELS DANCY CONDITIONS CANNOT BE MET FUNCTIONAL UNIT 0 Restore inoperable
- d. Station Blackout 2 Start Motor Driven Pump channel within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in hot shutdown within next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the follow-ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1/ Pump Restore inoperable
- e. Trip of Main Feedwater 1/ Pump Pumps channel within 48 Start Motor Pumps hours or be in hot shutdown within next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the follow-ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- 4. LOSS OF POWER
- a. 4.16 KV Emergency 2/ Bus 1/ Bus Bus Undervoltage s (Loss of Voltage) [
- b. 4.16 KV Emergency 2/ Bus 1/ Bus os Bus Undervoltage (Grid Degraded Voltage)
- - . . m. . . . _ _ .
TABLE 3.7-4 .
ENGINEERED SAFETY FEATURE SYSTEM INITIATION LIMITS INSTRUMENT SETTING CHANNEL ACTION SETTING LIMIT NO. FUNCTIONAL UNIT
- 6. AUXILIARY FEEDWATER Steam Generator Water Level Low-Low Aux. Feedwater Initiation g5%narrowrange a.
S/G Blowdown Isolation
- b. RCP Undervoltage Aux. Feedwater Initiation 2t70% nominal Aux. Feedwater Initiation All S.I. setpoints
- c. Safety Injection Aux. Feedwater Initiation j;46.7% nominal
- d. Station Blackout Aux. Feedwater Initiation N.A.
- e. Main Feedwater Pump Trip
- 7. LOSS OF POWER 1
- a. 4.16 KV Emergency Bus Emergency Bus 75+g% volts with a Undervoltage Seperation and Diesel start 2+5,-0.1 second time (Loss of Voltage) delay 4.16 KV Emergency Bus Emergency Bus 90*
.0% volts with a b.
Undervoltage Seperation and Diesel start 60+3.0 second (Degraded Voltage) time delay
, (Non CLS, Non SI) i 7,+.35 second
) time delay I
(CLS or SI Conditions) vl G
t
_ . . _ _ _ _ . _ _ - . _ . _ . . _ . _ - .. . ._ _. . . _ . . _ _ . . _ .- . .m -- __ _ _ _ . ._ _ _ _ _ .__~.m ._ _ _ _ _ . . .
' TABLE 4.1-1 (Continued) .
j CHANNEL CHECK CALIBRATE TEST REMARKS DESCRIPTION i
- 35. LOSS OF POWER I a. 4.16 KV Emergency Bus N.A. R H I undervoltage I (Loss of voltage)
- b. 4.16 KV Emergency Bus N.A. R M undervoltage .
1 (Degraded voltage) 1 l
i H
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ATTACHMENT III This Attachment addresses the following NRC Questions:
NRC Question 6: "Are the following viable source connections?
(a) A single 500/230/36.5 KV autotransformitr supplying both 34.5 KV buses 5 and 6 (i.e., breal:er LT22 open and LT12 closed (or vice versa), T562 closed and both L402-5 and L402-6 open).
(b) The 230/36.5 KV transformer supplying both 34.5 buses 5 and 6 (i.e., breakers LTl2 and LT22 open, T562 closed and L402-5 closed and L402-6 open (or vice versa)).
If these are not viable connections, are there interlocks to prevent these breaker alignments?"
i NRC Question 7 "Are there interlocks to prevent closure of both the 34.5 KV low side breakers on the 230/36.5 KV transformer?"
4 l
l bec/2582/3
As discussed in our June 11, 1982 letter to you, Serial No. 317, the three arrangements discussed in Questions 6 and 7 are physically possible arrangements. There are no electrical interlocks which prevent these arrangements. An arrangement with the 230/36.5KV transfomer supplying both 34.5KV buses at the same time, through L402-5 and L402-6 with T562 open, is the most probable arrangement, since it may occur automatically. The arrangements discussed in Question 6 require manual closure of the disconnect switches on both sides of T562 prior to implementation of the arrangements.
As we originally stated in our May 20, 1982 telephone conference with Messrs.
D. Neighbors, R. Trevatte and J. Sealan, we believe the probability of two transfomer f ailures combined with an SI or CLS is extremely small. We, therefore, did not analyze these scenarios. The following scenarios do include these arrangements and are provided in response to your request.
Case I, Job Numbers 1459 and 2734, analyzes the 230/36.5KV transformer feeding both 34.5KV buses, regardless of which breaker alignment is in use.
The scenario studied is a Unit 2 CLS assuming Unit 2 station service loads transfer to the Reserve Station Service Transfomers (RSST's) at the instant the CLS occurs. Unit 1 is assumed to trip and transfer its station service loads to the RSST's 60 seconds after the Unit 2 CLS.
In Case I, the 4KV motors have adequate voltage to accelerate at T=0 seconds. The minimtsn required 480V load center voltage at bus 2H is 70.9% to start the Containment Spray Pump and 72.0% to start the Low Head Safety Injection Pump. At 480V bus 2J the voltage requirements are 73.3% and 73.5%
to start the Containment Spray and Low Head Safety Injection Pumps, re spectively. At T=0 seconds, the 2H and 2J 480V bus voltages are 70.2% and 70.5%, respectively. Since two Charging Pumps were modeled as starting when one would normally be running, these voltages are lower than actually expected for this scenario. With acceleration of the 4KV Charging Pumps and an instantaneous signal to the RSST's load tap changer (LTC) to begin correction, the voltage profile will improve to enable the starting of the 480V motors.
MOV's rated at 368V starting will receive adequata starting voltage in sufficient time to ensure their overload heaters will not operate. At T=7 seconds, the LTC taps will be advanced by another step and spurious separation will not occur (the degraded voltage setpoint during accident conditions is 90% voltage at 7 seconds). Analysis at T=59 seconds is equivalent to a steady state condition for single unit loading to the RSST's. The voltages at this time are acceptable. Analysis of the steady state voltages at T= infinity, which represents the effects of two unit loading on the RSST's, indicates unacceptably im voltages on 480V buses lH1, IJ1, 2H, 2H1, 2J and 2J1.
Case II, uob Numbers 1609 and 3589, analyzes a 500/230/36.5KV autotransfomer feeding both 34.5KV buses, irregardless of which breaker alignment is in use. The scenario analyzed is the same as in Case. I. The resultant voltages are approximately 1% - 2.5% lower than those in Case I during motor starting and 2.5% - 3% lower at steady state. These are unacceptable results.
b "C /2 g]/M.
With reference to Technical Specification Section 3.16, each 500/230/36.5KV autotransformer and the 230/36.5KV transformer is considered to be a primary source which can supply offsite power to a 34.5KV bus. The intent of item B.2 is to maintain separate offsite supplies to each 34.5KV bus. With only one of the above mentioned transformers supplying both 34.5KV buses, both units may be operated for seven days, provided the dependable alternate source can be operable within eight hours. This restriction sufficiently controls operation with a single transformer supplying both 34.5KV buses. In view of the low probability of these events, modifications are not required to prevent this operating arrangement.
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