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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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[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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i I ! * .. ___ ._**: e TECHNICAL SPECIFICATIONS CHANGES SURRY UNITS 1 AND 2 83091.90081 830913 PDR ADDCK 05000280 P PDR ATTACHMENT 2
.. .e TS 3.2-1 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM Applicability Applies to the operational status of.the Chemical and Volume Control System. Objective To define those conditions of the Chemical and Volume Control System necessary to ensure safe reactor operation.
Specification A. When fuel is in a reactor there shall be at least one flow path to the . core for boric acid injection.
The minimum capability for boric acid injection shall be equivalent to that supplied from the refueling water storage tank. B. For one unit operation the reactor shall not be critical unless the following Chemical and Volume Control System conditions are met: 1. Two charging pumps shall be operable and one charging pump from the opposite unit shall be operable.
- 2. Two boric acid transfer pumps shall be operable.
- 3. The boric acid tanks (tank associated with the unit plus the common tank) together shall contain a minimum of 6000 gallons of at least 7.0% (but not greater than 8.5%) by weight boric acid solution at a temperature of at least 112°F. *Submitted for NRC approval on January 12, 1983 (Serial No. 740) *
- . e e TS 3.2-2 4. System piping and valves shall-be operable to the extent of establishing two flow paths to the core; one flow path from the boric acid tanks to the charging pumps and a flow path from the refueling water storage tank to the charging pumps. 5. Two channels of heat tracing shall be operable for the flow paths requiring heat tracing. 6. System piping, valves and control board indication required for the operation of the components enumerated in Specification B.l shall be operable.
C. For two unit operation the reactor shall not be critical unless the following Chemical and Volume Control System conditions are met: 1. Two charging pumps shall be operable per unit. 2. Three bori_c acid transfer pumps shall be operable.
- 3. When the common tank is in service, it shall be assigned to only one unit at a time. For that unit which has usage of the common tank, the boric acid tanks (unit's tank plus common tank) together shall contain a minimum of 6000 gallons of at least 7.0% (but not greater than 8.5%) by weight boric acid solution at a temperature of at least 112°F. For that unit which does not have usage of the common tank, the unit's own tank shall contain a minimum of 6000 gallons of at least 7.0% (but not greater than 8.5%) by weight boric acid solution at a temperature of at least 112°F. When the common tank is assigned to one unit, valves shall be positioned to establish a flow path to that unit and prevent flow to the othi:r unit. *Submitted for NRC approval on January 12, 1983 (Serial No. 740) *
This is normally accomplished by using boric acid transfer pumps which discharge to the suc.tion of each unit's charging pumps. The Chemical and Volume Control System contains four boric acid transfer pumps. Two of these pumps are normally assigned to each unit but valving and piping arrangements allow pumps to be shared such that 3 out of 4 pumps can service either unit. An alternate (not normally used) method of boration is to use the charging pumps taking suction directly from the refueling water storage tank. There are two sources of borated water available to the suction of the charging pumps through two different paths, one from the refueling water storage tank and one from the discharge of the boric acid transfer pumps. A. The boric acid transfer pumps can deliver the boric acid tank contents (7.0% solution of boric acid) to the charging pumps. B. The charging pumps can take suction from the volume control tank, the boric acid transfer pumps and the refueling water storage tank. Reference is made to Technical Specification
-3.3. The quantity of boric acid in storage from either the boric acid tanks or the refueling water storage tank is sufficient to borate the reactor coolant in order to reach cold shutdown at any time during core life. Approximately 6000 gallons of th~ 7.0% solution of boric acid are required to meet cold shutdown conditions.
Thus, a minimum of 6000 gallons in the boric acid tank is specified.
An upper concentration limit of 8.5% boric acid in L __ _ e. e TS 3.2-5 the tank is specified to maintain solution solubility at the specified low temperature limit of 112°F. For redundancy, two channels of heat tracing are installed on lines normally containing concentrated boric acid solution.
The Boric Acid Tank(s), which are located above the Boron Injection Tank(s), are supplied with level alarms, which would annunciate if a leak in the system occurred.
References FSAR Section 9.1 Chemical and Volume Control System L__ e e TS 3.3-1 3.3 SAFETY INJECTION SYSTEM Applicability Applies to the operating status of the Safety Injection System. Objective To define those limiting conditions for operation that are necessary to provide sufficient borated cooling water to remove decay heat from the core in emergency situations.
- specifications A. A reactor shall not be made critical unless the following conditions are met: 1. The refueling water storage tank contains not less than 387,100 gal of borated water. The boron concentration shall be at least 2000 ppm and not greater than 2200 ppm. 2. Each accumulator system is pressurized to at least 600 psia and contains a minimum of 975 ft 3 and a maximum of 989 ft 3 of borated water with a boron concentration of at least 1950 ppm.
.. e TS 3.3-2 3. Two channels of heat tracing shall be available for the flow paths. 4. Two charging pumps are operable.
- 5. Two low head safety injection pumps are operable.
- 6. All valves, piping, and interlocks associated with the above components which are required to operate under accident conditions are operable.
- 7. The Charging Pump Cooling Water Subsystem shall be operating as follows: a. Make-up water from the Component Cooling Water Subsystem shall be available.
- b. Two charging pump component cooling water pumps and two charging pump service water pumps shall be operable.
- c. Two charging pump intermediate seal coolers shall be operable.
- 8. During power operation the A.C. power shall be removed from the following motor operated valves with the valve in the open position:
- Unit No. 1 Unit No. 2 MOV 1890C MOV 2890C 9. During power operation the A.C. power shall be removed from the following motor operated valves with the valve in the closed position:
Unit No. 1 Unit No. 2 MOV 1869A MOV 1869B MOV 1890A MOV 1890B MOV 2869A MOV 2869B MOV 2890A MOV 2890B
.. e e TS 3.3-3 10 *. The accumulator discharge valves listed below in non-isolated loops shall be blocked open by de-energizing the valve motor operator when the reactor coolant system pressure is greater than 1000 psig. '()nit No. 1 MOV 1865A MOV 1865B MOV 1865C Unit No. 2 MOV 2865A MOV 2865B MOV 2865C 11. Power operation with less than three loops in service is prohibited.
The following loop isolation valves shall have AC power removed and be locked in open position during power operation.
Unit No. 1 Unit No. 2 MOV 1590 MOV 2590 .MOV 1591 MOV 2591 MOV 1592 MOV 2592 MOV 1593 MOV 2593 MOV 1594 MOV 2594 MOV 1595 MOV 2595 12. The total system uncollected leakage from valves, flanges, and pumps located outside containment shall not exceed the limit shown in Table 4.ll""'.l as verified.
by inspection during system testing. Individual component leakage may exceed the design value given in Table 4. ll-1 provided that the total allowable system uncollected leakage is not exceeded.
,, e e TS 3.3-5 6. One charging pump component cooling water pump or one charging pump service water pump . may be out of service
- pro~ided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 7. One charging pump intermediate seal cooler or other passive component may be out of service provided the system may still operate at 100 percent capacity and repairs are completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. 8. Power may be restored to any valve referenced in Specifications 3.3.A.9 and 3.3.A.10 for the purpose of valve testing or maintenance provided that no more than one valve has power restored and provided that testing and maintenance is completed and power removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 9. Power may be restored to any valve referenced in Specification 3.3.A.ll for the purpose of valve testing or maintenance provided that no more than* one valve has power restored and provided that testing or maintenance is completed and power removed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 10. The total uncollected system leakage for valves, flanges, and pumps I located outside containment can exceed the limit shown in Table 4 .11-1 provided immediate attention is directed to making repairs and system leakage is returned to within limits within 7 days.
.. e e TS 3.3-9 The accumulators (one for each loop) discharge into the cold leg of the reactor coolant piping when Reactor Cool_ant System pressure.decreases below accumulator pressure, thus assuring rapid core cooling for large breaks. The line from each accumulator is provided with a motorized valve to isolate the accumulator during reactor start-up and shutdown to preclude the discharge of the contents of the accumulator when not required.
These valves receive a signal to open when safety injection is initiated.
To assure .that the accumulator valves satisfy the single failure criterion, they will be blocked open by de-energizing the valve motor operators when the reactor coolant pressure exceeds 1000 psig. The operating pressure of the Reactor.Coolant System is 2235 psig and safety injection is initiated when this pressure drops to 600 psig.
ing the motor operator when the pressure exceeds 1000 psig allows sufficient time during normal startup operation to perform the actions required to de-energize the valve. This procedure will assure that there is an operable flow path from each accumulator to the Reactor Coolant System during power operation and that safety injection can be plished. The removal of power from the valves listed in the specification will assure that the systems of which they are a part satisfy the single failure criterion.
,. ,( e e TS 4.1-10 TABLE 4. l-2B MINIMUM FREQUENCIES FOR SAMPLING TESTS DESCRIPTION
- 1. 2. 3. 4. 5. 6. 7. 8.
- See Specification 4.1.D TEST Radio-chelffyal Analysis Gross Activity <2> Tritium Activity *Chemistry (Cl, F & o 2) *Boron Concentration E Determination DOSE EQUIVALENT I-131 Radio-iodine Analysis (including I-131, Il33 & I-135) Boron Concentration
- Boron Concentration NaOH Concentration
- Boron Concentration Fifteen minute g~sset4~ and q vity DOSE EQUIVALENT I-131 *I-131 and late radioactive leases Boron Concentration FREQUENCY
.. (5) Monthly
- 5 days/y 5 ,k(5) Weekly 5 days/week Twice/week 3 Semiannually~
5~ Once/2 weeks(6) Once/4 hours and (7) below Weekly Twice/week Monthly Monthly Once/72 hours Monthly ( 4)
Weekly Monthly FSAR SECTION REFERENCE 9.1 6 9.1 6 9.5 10.3 6.2 (1) A radiochemical analysis will be made to evaluate the following corrosion products:
Cr-51, Fe-59, Mn-54, Co-58, and Co-60. (2) A gross beta-gamma degassed activity analysis shall consist of the quantitative measurement of the total radioactivity of ~he pri~ary coolant in units of µCi/cc.
(. ., J;, TABLE 4. h*l (Continued)
- .. ' Channel Description Check Calibrate Test Remarks ' 10. Rod Position Bank Counters S (1, 2) N.A. N.A. 1) Each six inches of rod motion when data logger is out of service 2) With analog rod position 11. Steam Generator Level s R M e 12. Charging Flow N.A. R N.A. 13. Residual Heal Removal Pump Flow N.A. R N.A. 14. Boric Acid Tank Level *D R N.A. 15. Refueling Water Storage Tank Level s R M 16. Boron Injection Tank Level N.A. N.A. N.A. 17. Volume Control Tank Level N.A. R N.A. 18. Reactor Containment Pressure-CLS
- D R M (1) 1) Isolation Valve signal and spray signal 19. Process and Area Radiation Monitoring e System *D R M 20. Boric Acid Control N.A. R N.A. 21. Containment Pump Level N.A. R N.A. 22. Accumulator Level and Pressure s R N.A. 1--3 en 23. Containment Pressure-Vacuum Pump ,i:,. System s R N.A. . '""' I ....... 24. Steam Line Pressure s R M