|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO.50-400/LICENSE NO.NPF-63 REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS REFUELING OPERATIONS TECHNICAL SPECIFICATION PAGES Pgp 0+2p~~o<voce~p>so---psppp~p~oc IHOEX LIMITIHG CQHOITEQNS FOR.OPERATION AHO SURVEILLANCE REQUIREMENTS 3/4.9.2 IHSTRUMKNTATION............................ | | {{#Wiki_filter:ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS REFUELING OPERATIONS TECHNICAL SPECIFICATION PAGES |
| -".......3/4.9.3 OECAY TIMKo~~~~~~~o~~~~~~~~~~~~~~o o~~~~~~~~~~~~~~~~~~~~~o 3/4.9.4 CONTAIHMEHT BUILOIHG PENETRATIONS............
| | ~~o Pgp 0+2p ~p>so-- |
| ~~~~~~~-~---3/4.9.5 COMMUNICATIONS.....
| | <voce psppp~p |
| ~.....'...
| | ~oc |
| ~----~--~-~~-"-~-~~---.--~3/4o9o6 REFUELIHG MACHINE o~~~~o~~~~~~ooo~~ooo~oo~~~~~o~~~~o~~~~~3/4.9.7 3/4.9.8 CRANE TRAVEL-FUEL HAHOLIHG BUILOING...........
| | |
| RESIOUAL HEAT REMOVAL ANO COQLQA'IRCULATION H igh Matll Leve1oo~oo~~~~~~~o~~oo~o~~~ooo~~o~~~o~o'oooo~~ow Mate1 Level~~~~~~o~~~~o~~~~~o~~~~~~~~o~~~~~~~~~~~~~~~L 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM.................
| | IHOEX LIMITIHG CQHOITEQNS FOR. OPERATION AHO SURVEILLANCE REQUIREMENTS SHCTION PAGE 3/4.8.4 ELECTRICAL E)UIPMKNT PRQTKCTIVK OEVICKS Containment Penetration Conductor Qvercurrent Protective Oevicos.................................. ~ .. 3/4 8-19 TABLE 3.8-1 CONTAINMENT PENETRATION COHOUCTOR QVERCURRBiT PROTECTIVE OEVICKS................ ~ ~ . - - " " -~ ~ ~ ~ ~ ~ ~ -~- ~ ~ ~ 3/4 8-21 Motor Operated Valves Thermal Overload Protection........ 3/4 8-.39 TABLE 3.8-2 MOTOR-OPERATED VALVES THERMAL QVERLQAO PROTECTION..... 3/4 8-40 3/4. 9 REFUELIHG OPERATIONS 3/4.9.1 BORON CONCENTRATION................................." -. 3/4 9-1 TABLE .9-1 AOMIHISTRATIVK CONTROLS TO PREVENT OILUTIQN QURIHG R EFUE LING o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 3/4 9-2 3/4.9.2 IHSTRUMKNTATION............................ - "....... 3/4 9-3 3 /4. 9. 3 OECAY TIMKo ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3/4 9-4 3/4.9. 4 CONTAIHMEHT BUILOIHG PENETRATIONS............ ~ ~ ~ ~ ~ ~ ~ -~- -- 3/4 9-5 3/4. 9.5 COMMUNICATIONS..... ~.....'... ~ -- - - -- |
| 3/4.9.10 MATER LEVEL"'-REACTOR VESSEL............. | | ~ ~ -~~- " -~- ~ ~ ---.- - ~ 3/4 9-6 3/4o9o6 REFUELIHG MACHINE o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ooo ~ ~ ooo ~ oo ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ 3/4 9-7 3/4. 9. 7 CRANE TRAVEL - FUEL HAHOLIHG BUILOING........... 3/4 9-8 3/4.9. 8 RESIOUAL HEAT REMOVAL ANO COQLQA'IRCULATION H igh Matll Leve1oo ~ oo ~ ~ ~ ~ ~ ~ ~ o ~ ~ oo ~ o ~ ~ ~ ooo ~ ~ o ~ ~ ~ o ~ |
| ~.~-~~~~~"~~~-~3/4.9.11 MATER LEVEL-HEM AHD SPENT FUEL PQOLS.....
| | o' oooo ~ ~ 3/4 9-9 Low Mate1 Level ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 9-LO 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................. 3/4 9-Ll 3/4.9.10 MATER LEVEL"'- REACTOR VESSEL............. . - ~ ~ ~ ~ ~ ~ ~ "~ - ~ ~ ~ 3/4 9-12 3/4.9.11 MATER LEVEL - HEM AHD SPENT FUEL PQOLS..... ~... ~ ~ ~ . ~ ~ - ~ ~ ~ 3/4 9 L3 3/4.9.12 FUEL HANOLIHG BUILDING EMERGENCY EXHAUST SYSTEM.......- ~ ~ 3/4 9-14 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SH UTOOMN MARGINo o o ~ ~ ~ ~ ~ ~ ~ ~ o o o ~ o o |
| ~...~~~.~~-~~~3/4.9.12 FUEL HANOLIHG BUILDING EMERGENCY EXHAUST SYSTEM.......- | | ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ |
| ~~3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 3/4.10.2 3/4.10.3 3/4.LO.4 UTOOMN MARGINo~o o~~~~~~~~~~o o~~o~~~o o~~~~~o~~~~~~~~~~~~SH GROUP HEIGHT, INSERTION, AN POMER OISTRIBUTION LIMITS...P HY5 I CS TESTS o~~~~~~~o,~o~~~o~o~~~~o o~~~~~~~~~~~~~~~~~~~~~REACTOR COO LANT LOO PS o~~o~~~~o~~~~~o~~~o~~~~~~~~~~~~~~~~~3/4.10.5 POSITION INOICATION SYFiil SHUTOOWN.................
| | ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AN POMER OISTRIBUTION LIMITS... 3/4 10-2 3/4. 10. 3 P HY5 ICS TESTS o ~ ~ ~ ~ ~ ~ ~ o, ~ o ~ ~ ~ o ~ o ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-3 3/4. LO.4 REACTOR COO LANT LOO PS o o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10 4 3/4. 10. 5 POSITION INOICATION SYFiil SHUTOOWN................. ~ ~ ~ 3/4 10-5 SHEARON HARRIS - UNIT 1 X$ |
| ~~~SHCTION 3/4.8.4 ELECTRICAL E)UIPMKNT PRQTKCTIVK OEVICKS Containment Penetration Conductor Qvercurrent Protective Oevicos.................................. | | |
| ~..TABLE 3.8-1 CONTAINMENT PENETRATION COHOUCTOR QVERCURRBiT PROTECTIVE OEVICKS................ | | 9 TABLE P' 1 ADHINISTiRATIVE CONTROLS TO PREVENT DILUTION DUR:NG R=;UELING ENSE qT-VALVE POSITION VALVE/ID DURING REFUELING LOCK DESCRIPTION 1CS-149 Closed Yes RMW to the CVCS ak'eup control (CS-0121SN) system 1CS-510 losed Yes Boric Acid tch Tank Outlet (CS-0631SN) valve. Ha be opened if he hatching nk concentration is > 20 ppm boron, and valve 1CS"50 (makeup water supply to b ch tank) is closed. |
| ~~.--"-~"~~~~~~-~-~~~Motor Operated Valves Thermal Overload Protection........ | | 1CS-503 Closed Yes to Batching Tank. Do not (CS-0251) en unless ou.let valve 1CS-510 s closed. |
| TABLE 3.8-2 MOTOR-OPERATED VALVES THERMAL QVERLQAO PROTECTION.....
| | 1CS"570 Closed No CVCS letdown to BTRS. Place (CS-0&75SN) valve in "shut" at valve con-rol switch and place BTRS , |
| 3/4.9 REFUELIHG OPERATIONS 3/4.9.1 BORON CONCENTRATION................................."-.TABLE.9-1 AOMIHISTRATIVK CONTROLS TO PREVENT OILUTIQN QURIHG R EFUE LING o~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~o~PAGE 3/4 8-19 3/4 8-21 3/4 8-.39 3/4 8-40 3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 3/4 9-6 3/4 9-7 3/4 9-8 3/4 9-9 3/4 9-LO 3/4 9-Ll 3/4 9-12 3/4 9 L3 3/4 9-14 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10 4 3/4 10-5 SHEARON HARRIS-UNIT 1 X$ | | function selector swi ch in" "off." No lock required. |
| VALVE/ID 1CS-149 (CS-0121SN) 1CS-510 (CS-0631SN) 9 TABLE P'1 ADHIN ISTiRATIVE CONTROLS TO PREVENT DILUTION DUR:NG R=;UELING ENSE qT-VALVE POSITION DURING REFUELING LOCK DESCRIPTION Yes RMW to the CVCS ak'eup control system Closed losed Yes Boric Acid tch Tank Outlet valve.Ha be opened if he hatching nk concentration is>20 ppm boron, and valve 1CS"50 (makeup water supply to b ch tank)is closed.1CS-503 (CS-0251)Closed Yes to Batching Tank.Do not en unless ou.let valve 1CS-510 s closed.1CS"570 (CS-0&75SN)
| | ICS-670 Cl os ed Yes RNM to BTRS loop. |
| Closed No CVCS letdown to BTRS.Place valve in"shut" at valve con-rol switch and place BTRS , function selector swi ch in""off." No lock required.ICS-670 (CS-0599SN)
| | (CS-0599SN) 1CS-649 Closed Yes sin sluice to BTRS (CS-019SSN) d ineralizers. |
| Cl os ed Yes RNM to BTRS loop.1CS-649 (CS-019SSN) 1CS-93 (CS-051SN) 1CS-320 (CS-0641SN) 1CS-98 (CS-074')Closed Cl ose C sed Open Yes Yes Yes.No sin sluice to BTRS d ineralizers.
| | 1CS-93 Cl ose Yes Resi sluice to CVCS (CS-051SN) demine alizers 1CS-320 C sed Yes. Recycle vaporation Feed (CS-0641SN) Pump to c r ging/safety injection p mp suction. |
| Resi sluice to CVCS demine alizers Recycle vaporation Feed Pump to c r ging/safety injection p mp suction.BTRS bypass v lve.Place valve control itch in"open" position.SHEARON HARRIS-UNIT 1 3/4 9-2 INSERT TO TABLE 3.9-1: C C CP&L VALVE NO.(Ebasco Valve No.)DESCRIPTION 1CS-149 (CS-D121SN
| | 1CS-98 Open No BTRS bypass v lve. Place (CS-074') valve control itch in "open" position. |
| )1CS-510 (CS-D631SN) | | SHEARON HARRIS - UNIT 1 3/4 9-2 |
| Reactor Makeup Water to CVCS Makeup Control System Boric Acid Batch Tank Outlet Lock closed;may be opened to permit makeup to Refueling Water Storage Tank provided valves 1CS-156 and 1CS-155 are maintained closed with their main control board control switches in"shut" position, and manual valves 1CS-274, 1CS-265 and 1CS-287 are t locked closed.Locked closed;may be opened provided the boron concentration of the boric acid batch tank is>2000 ppm and valve 1CS-503 is closed.1CS-503 (CS-D251)Reactor Makeup Water to Boric Acid Batch Tank Lock closed, may be opened provided valve 1CS-510 is closed.1CS-93 (CS-D51SN)
| | |
| Resin Sluice to CVCS Demineralizers Lock closed.1CS-320 (CS-D641SN)
| | C INSERT TO TABLE 3.9-1: C CP&L VALVE NO. |
| Boron Recycle Evaporator Feed Pump to Charging/SI Pumps Lock closed.1CS-570 (CS-D575SN)
| | (Ebasco Valve No.) DESCRIPTION 1CS-149 Reactor Makeup Water to CVCS Makeup Lock closed; may be opened to permit makeup (CS-D121SN ) Control System to Refueling Water Storage Tank provided valves 1CS-156 and 1CS-155 are maintained closed with their main control board control switches in "shut" position, and manual 1CS-510 (CS-D631SN) |
| CVCS Letdown to Boron Thermal Regeneration System Closed with main control board control switch in"shut" position, and BTRS function selector switch maintained in"off" position, no lock required.1CS-670 (CS-D599SN)
| | Boric Acid Batch Tank Outlet valves 1CS-274, 1CS-265 and 1CS-287 are locked closed. |
| Reactor Makeup Water to Boron Thermal Regeneration System Lock closed.1CS-649 (CS-D198SN)
| | Locked closed; may be opened provided the boron concentration of the boric acid batch tank is > 2000 ppm and valve 1CS-503 is t |
| Resin Sluice to BTRS Demineralizers Lock closed.1CS-98 (CS-D740SN)
| | closed. |
| Boron Thermal Regeneration System Bypass Opened with main control board control switch maintained in"open" position,'o lock required.(254CRS/cn)
| | 1CS-503 Reactor Makeup Water to Boric Acid Lock closed, may be opened provided valve (CS-D251) Batch Tank 1CS-510 is closed. |
| REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.APPLICABILI)
| | 1CS-93 Resin Sluice to CVCS Demineralizers Lock closed. |
| Y: MODE 6.ACTION: a.g~Ma.<H Mith onto ihe above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.b.With both of the above required monitors inoperable or not operating, i>~~4"">><~determine the boron concentration of the Reactor Coolant System ai least once per 12 hours.SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Fl.ux Monitor shall be demons rated OPERABLE by performance of: a.A CHANNEL CHECK at leas once per 12 hours, b.An ANALOG CHANNEL OPERATIONAL TEST within 8 hours prior to the initial start of CORE ALTERATIONS, and c.An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.SHEARON HARRIS-UNIT 1 3/4 9"3
| | (CS-D51SN) 1CS-320 Boron Recycle Evaporator Feed Pump to Lock closed. |
| \0}} | | (CS-D641SN) Charging/SI Pumps 1CS-570 CVCS Letdown to Boron Thermal Closed with main control board control switch (CS-D575SN) Regeneration System in "shut" position, and BTRS function selector switch maintained in "off" position, no lock required. |
| | 1CS-670 Reactor Makeup Water to Boron Thermal Lock closed. |
| | (CS-D599SN) Regeneration System 1CS-649 Resin Sluice to BTRS Demineralizers Lock closed. |
| | (CS-D198SN) 1CS-98 Boron Thermal Regeneration System Bypass Opened with main control board control switch (CS-D740SN) maintained in "open" position,'o lock required. |
| | (254CRS/cn) |
| | |
| | REFUELING OPERATIONS 3/4. 9. 2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room. |
| | APPLICABILI)Y: MODE 6. |
| | ACTION: |
| | g~ Ma.<H |
| | : a. Mith onto ihe above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes. |
| | : b. With both of the above required monitors inoperable or not operating, i>~~4"">> < ~determine the boron concentration of the Reactor Coolant System ai least once per 12 hours. |
| | SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Fl.ux Monitor shall be demons rated OPERABLE by performance of: |
| | : a. A CHANNEL CHECK at leas once per 12 hours, |
| | : b. An ANALOG CHANNEL OPERATIONAL TEST within 8 hours prior to the initial start of CORE ALTERATIONS, and |
| | : c. An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days. |
| | SHEARON HARRIS - UNIT 1 3/4 9"3 |
| | |
| | \ 0}} |
|
|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18017A9271999-10-21021 October 1999
Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05
ML18017A8531999-08-26026 August 1999
Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations
ML18016B0521999-08-0404 August 1999
Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits
ML18016B0451999-08-0202 August 1999
Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements
ML18016B0101999-07-0909 July 1999
Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants.
ML18016B0131999-07-0909 July 1999
Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10
ML18016A9911999-06-15015 June 1999
Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests)
ML18016A9781999-06-0202 June 1999
Proposed Tech Specs Revising TS 6.5 & TS 6.8
ML18016A8401999-02-26026 February 1999
Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.)
ML18016A7701998-12-23023 December 1998
Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.'
ML18016A7591998-12-0707 December 1998
Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks
ML18016A7561998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses
ML18016A7531998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs
ML18016A6571998-10-28028 October 1998
Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors
ML18016A6261998-10-15015 October 1998
Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases
ML18016A6051998-10-0101 October 1998
Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09
ML18016A5941998-09-23023 September 1998
Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut
ML18016A5461998-09-0101 September 1998
Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks
ML18016A5381998-08-27027 August 1998
Proposed Tech Specs,Revising Section 6.0, Administrative Controls.
ML18016A5411998-08-27027 August 1998
Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements
ML18016A5311998-08-24024 August 1998
Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE
ML18016A4301998-05-15015 May 1998
Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants
ML18016A4021998-04-24024 April 1998
Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays
ML18016A3881998-04-13013 April 1998
Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power
ML18016A3481998-03-12012 March 1998
Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months
ML18016A2591997-12-16016 December 1997
Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed
ML18016A2241997-10-29029 October 1997
Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS
ML18012A8121997-06-12012 June 1997
Proposed Tech Specs 6.0 Amending Administrative Controls.
ML18012A7991997-05-23023 May 1997
Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators
ML18012A7861997-05-16016 May 1997
Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler
ML18012A6361997-04-23023 April 1997
Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3
ML18012A5811997-03-17017 March 1997
Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances
ML18022B0041997-03-14014 March 1997
Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2
ML18022B0071997-03-10010 March 1997
Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems
ML18012A5361997-02-27027 February 1997
Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes
ML18012A5281997-02-21021 February 1997
Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability
ML18012A5351997-02-21021 February 1997
Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition
ML18012A5311997-02-18018 February 1997
Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves.
ML18012A5101997-02-13013 February 1997
Proposed Tech Specs 3.2.3 Re Rated Thermal Power
ML18012A5011997-02-0606 February 1997
Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability
ML18012A4961997-01-29029 January 1997
Proposed Tech Specs 3/4.0 Re Applicability
ML18012A4641997-01-10010 January 1997
Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements
ML18012A4531996-12-30030 December 1996
Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits
ML18012A4161996-10-31031 October 1996
Proposed Tech Specs Re Ultimate Heat Sink Level & Temp
ML18012A3981996-10-0808 October 1996
Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event
ML18012A3721996-09-18018 September 1996
Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing
ML18012A3071996-07-19019 July 1996
Proposed Tech Specs 3/4.6.2,CSS,extending Surveillance Interval for Performance of Air or Smoke Flow Test Through CS Nozzles from Once Every 5 Years to Once Every 10 Years
ML18012A2531996-05-31031 May 1996
Proposed Tech Specs,Correcting Location Described for One of Three Triaxial Peak Accelerograph Recorders
ML18012A1831996-03-20020 March 1996
Proposed Relocation of TS 3.3.3.2, Movable Incore Detectors & Associated Bases,Consistent w/NUREG-1431 & GL 95-10
ML18012A1441996-02-16016 February 1996
Proposed Tech Specs 4.3.2 Re ESFAS Instrumentation
1999-08-04
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18017A9271999-10-21021 October 1999
Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05
ML18017A8531999-08-26026 August 1999
Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations
ML18016B0521999-08-0404 August 1999
Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits
ML18016B0451999-08-0202 August 1999
Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements
ML18016B0101999-07-0909 July 1999
Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants.
ML18016B0131999-07-0909 July 1999
Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10
ML18016A9911999-06-15015 June 1999
Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests)
ML18016A9781999-06-0202 June 1999
Proposed Tech Specs Revising TS 6.5 & TS 6.8
ML18016A8401999-02-26026 February 1999
Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.)
ML18016A7701998-12-23023 December 1998
Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.'
ML18016A9341998-12-15015 December 1998
Rev 11 to ODCM, for Shnpp
ML18016A7531998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs
ML18016A7561998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses
ML18016A7591998-12-0707 December 1998
Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks
ML18016A6571998-10-28028 October 1998
Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors
ML18016A6261998-10-15015 October 1998
Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases
ML18016A6051998-10-0101 October 1998
Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09
ML18016A5941998-09-23023 September 1998
Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut
ML18016A5461998-09-0101 September 1998
Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks
ML18016A5411998-08-27027 August 1998
Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements
ML18016A5381998-08-27027 August 1998
Proposed Tech Specs,Revising Section 6.0, Administrative Controls.
ML18016A5311998-08-24024 August 1998
Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE
ML18016A4301998-05-15015 May 1998
Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants
ML18016A4021998-04-24024 April 1998
Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays
ML18016A3881998-04-13013 April 1998
Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power
ML18016A3481998-03-12012 March 1998
Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months
ML18016A3051998-01-29029 January 1998
Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval.
ML18022B0351998-01-26026 January 1998
Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval.
ML18016A4131997-12-18018 December 1997
Rev 10 to ODCM for Shearon Harris Nuclear Power Plant.
ML18016A2591997-12-16016 December 1997
Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed
ML18016A2241997-10-29029 October 1997
Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS
ML18012A8121997-06-12012 June 1997
Proposed Tech Specs 6.0 Amending Administrative Controls.
ML18012A7991997-05-23023 May 1997
Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators
ML18012A7861997-05-16016 May 1997
Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler
ML18012A6361997-04-23023 April 1997
Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3
ML18012A5811997-03-17017 March 1997
Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances
ML18022B0041997-03-14014 March 1997
Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2
ML18022B0071997-03-10010 March 1997
Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems
ML18012A5361997-02-27027 February 1997
Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes
ML18012A5351997-02-21021 February 1997
Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition
ML18012A5281997-02-21021 February 1997
Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability
ML18012A5311997-02-18018 February 1997
Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves.
ML18012A5101997-02-13013 February 1997
Proposed Tech Specs 3.2.3 Re Rated Thermal Power
ML18012A5011997-02-0606 February 1997
Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability
ML18012A4961997-01-29029 January 1997
Proposed Tech Specs 3/4.0 Re Applicability
ML18012A4641997-01-10010 January 1997
Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements
ML18012A4531996-12-30030 December 1996
Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits
ML18012A4161996-10-31031 October 1996
Proposed Tech Specs Re Ultimate Heat Sink Level & Temp
ML18012A3981996-10-0808 October 1996
Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event
ML18012A3721996-09-18018 September 1996
Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing
1999-08-04
[Table view] |
Text
ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS REFUELING OPERATIONS TECHNICAL SPECIFICATION PAGES
~~o Pgp 0+2p ~p>so--
<voce psppp~p
~oc
IHOEX LIMITIHG CQHOITEQNS FOR. OPERATION AHO SURVEILLANCE REQUIREMENTS SHCTION PAGE 3/4.8.4 ELECTRICAL E)UIPMKNT PRQTKCTIVK OEVICKS Containment Penetration Conductor Qvercurrent Protective Oevicos.................................. ~ .. 3/4 8-19 TABLE 3.8-1 CONTAINMENT PENETRATION COHOUCTOR QVERCURRBiT PROTECTIVE OEVICKS................ ~ ~ . - - " " -~ ~ ~ ~ ~ ~ ~ -~- ~ ~ ~ 3/4 8-21 Motor Operated Valves Thermal Overload Protection........ 3/4 8-.39 TABLE 3.8-2 MOTOR-OPERATED VALVES THERMAL QVERLQAO PROTECTION..... 3/4 8-40 3/4. 9 REFUELIHG OPERATIONS 3/4.9.1 BORON CONCENTRATION................................." -. 3/4 9-1 TABLE .9-1 AOMIHISTRATIVK CONTROLS TO PREVENT OILUTIQN QURIHG R EFUE LING o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 3/4 9-2 3/4.9.2 IHSTRUMKNTATION............................ - "....... 3/4 9-3 3 /4. 9. 3 OECAY TIMKo ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3/4 9-4 3/4.9. 4 CONTAIHMEHT BUILOIHG PENETRATIONS............ ~ ~ ~ ~ ~ ~ ~ -~- -- 3/4 9-5 3/4. 9.5 COMMUNICATIONS..... ~.....'... ~ -- - - --
~ ~ -~~- " -~- ~ ~ ---.- - ~ 3/4 9-6 3/4o9o6 REFUELIHG MACHINE o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ooo ~ ~ ooo ~ oo ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ 3/4 9-7 3/4. 9. 7 CRANE TRAVEL - FUEL HAHOLIHG BUILOING........... 3/4 9-8 3/4.9. 8 RESIOUAL HEAT REMOVAL ANO COQLQA'IRCULATION H igh Matll Leve1oo ~ oo ~ ~ ~ ~ ~ ~ ~ o ~ ~ oo ~ o ~ ~ ~ ooo ~ ~ o ~ ~ ~ o ~
o' oooo ~ ~ 3/4 9-9 Low Mate1 Level ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 9-LO 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................. 3/4 9-Ll 3/4.9.10 MATER LEVEL"'- REACTOR VESSEL............. . - ~ ~ ~ ~ ~ ~ ~ "~ - ~ ~ ~ 3/4 9-12 3/4.9.11 MATER LEVEL - HEM AHD SPENT FUEL PQOLS..... ~... ~ ~ ~ . ~ ~ - ~ ~ ~ 3/4 9 L3 3/4.9.12 FUEL HANOLIHG BUILDING EMERGENCY EXHAUST SYSTEM.......- ~ ~ 3/4 9-14 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SH UTOOMN MARGINo o o ~ ~ ~ ~ ~ ~ ~ ~ o o o ~ o o
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AN POMER OISTRIBUTION LIMITS... 3/4 10-2 3/4. 10. 3 P HY5 ICS TESTS o ~ ~ ~ ~ ~ ~ ~ o, ~ o ~ ~ ~ o ~ o ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-3 3/4. LO.4 REACTOR COO LANT LOO PS o o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10 4 3/4. 10. 5 POSITION INOICATION SYFiil SHUTOOWN................. ~ ~ ~ 3/4 10-5 SHEARON HARRIS - UNIT 1 X$
9 TABLE P' 1 ADHINISTiRATIVE CONTROLS TO PREVENT DILUTION DUR:NG R=;UELING ENSE qT-VALVE POSITION VALVE/ID DURING REFUELING LOCK DESCRIPTION 1CS-149 Closed Yes RMW to the CVCS ak'eup control (CS-0121SN) system 1CS-510 losed Yes Boric Acid tch Tank Outlet (CS-0631SN) valve. Ha be opened if he hatching nk concentration is > 20 ppm boron, and valve 1CS"50 (makeup water supply to b ch tank) is closed.
1CS-503 Closed Yes to Batching Tank. Do not (CS-0251) en unless ou.let valve 1CS-510 s closed.
1CS"570 Closed No CVCS letdown to BTRS. Place (CS-0&75SN) valve in "shut" at valve con-rol switch and place BTRS ,
function selector swi ch in" "off." No lock required.
ICS-670 Cl os ed Yes RNM to BTRS loop.
(CS-0599SN) 1CS-649 Closed Yes sin sluice to BTRS (CS-019SSN) d ineralizers.
1CS-93 Cl ose Yes Resi sluice to CVCS (CS-051SN) demine alizers 1CS-320 C sed Yes. Recycle vaporation Feed (CS-0641SN) Pump to c r ging/safety injection p mp suction.
1CS-98 Open No BTRS bypass v lve. Place (CS-074') valve control itch in "open" position.
SHEARON HARRIS - UNIT 1 3/4 9-2
C INSERT TO TABLE 3.9-1: C CP&L VALVE NO.
(Ebasco Valve No.) DESCRIPTION 1CS-149 Reactor Makeup Water to CVCS Makeup Lock closed; may be opened to permit makeup (CS-D121SN ) Control System to Refueling Water Storage Tank provided valves 1CS-156 and 1CS-155 are maintained closed with their main control board control switches in "shut" position, and manual 1CS-510 (CS-D631SN)
Boric Acid Batch Tank Outlet valves 1CS-274, 1CS-265 and 1CS-287 are locked closed.
Locked closed; may be opened provided the boron concentration of the boric acid batch tank is > 2000 ppm and valve 1CS-503 is t
closed.
1CS-503 Reactor Makeup Water to Boric Acid Lock closed, may be opened provided valve (CS-D251) Batch Tank 1CS-510 is closed.
1CS-93 Resin Sluice to CVCS Demineralizers Lock closed.
(CS-D51SN) 1CS-320 Boron Recycle Evaporator Feed Pump to Lock closed.
(CS-D641SN) Charging/SI Pumps 1CS-570 CVCS Letdown to Boron Thermal Closed with main control board control switch (CS-D575SN) Regeneration System in "shut" position, and BTRS function selector switch maintained in "off" position, no lock required.
1CS-670 Reactor Makeup Water to Boron Thermal Lock closed.
(CS-D599SN) Regeneration System 1CS-649 Resin Sluice to BTRS Demineralizers Lock closed.
(CS-D198SN) 1CS-98 Boron Thermal Regeneration System Bypass Opened with main control board control switch (CS-D740SN) maintained in "open" position,'o lock required.
(254CRS/cn)
REFUELING OPERATIONS 3/4. 9. 2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILI)Y: MODE 6.
ACTION:
g~ Ma.<H
- a. Mith onto ihe above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
- b. With both of the above required monitors inoperable or not operating, i>~~4"">> < ~determine the boron concentration of the Reactor Coolant System ai least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Fl.ux Monitor shall be demons rated OPERABLE by performance of:
- a. A CHANNEL CHECK at leas once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
- b. An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and
- c. An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.
SHEARON HARRIS - UNIT 1 3/4 9"3
\ 0
