Proposed Tech Specs,Modifying Wording of Sections 3.10 & 4.1.D,Table 3.1.1 & Basis 3.1 to Allow Flexibility in Disarming Control Rods by Allowing Variety of Disarming MethodsML20198B609 |
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Millstone |
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Issue date: |
10/30/1985 |
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From: |
NORTHEAST NUCLEAR ENERGY CO. |
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Shared Package |
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ML20198B606 |
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References |
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NUDOCS 8511070097 |
Download: ML20198B609 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F ML20154A3701998-09-28028 September 1998 Proposed Tech Specs Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1, 3.6.5.1,3.7.6.1 & 3.9.15,revising Info Re Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA ML20154C0491998-09-28028 September 1998 Proposed Tech Specs Revising FSAR Separation Requirement of Six Inches Which Is Applied to Redundant Vital Cables, Internal Wiring of Redundant Vital Circuits & Associated Devices ML20151V5011998-09-0909 September 1998 Proposed Tech Spec Changing TS Definitions 1.24,1.27,1.31, 3.0.2,4.0.5,3.2.3,3.3.2.1,3.4.1.1,3.4.11 & Adding TS 3.0.6 B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified1998-08-12012 August 1998 Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified B17341, Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval1998-08-0606 August 1998 Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval ML20236Y0831998-08-0404 August 1998 Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves ML20236X2521998-07-30030 July 1998 Proposed Tech Specs Bases 3/4.9.1,3/4.1.1.3,3/4.7.1.6, 3/4.7.7,3/4.5.4 & 3/4.3.3.10,resolving Miscellaneous Condition Repts ML20236W0201998-07-30030 July 1998 Proposed Tech Specs Bases Section 3/4.6.1.1,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236T2681998-07-21021 July 1998 Proposed Tech Specs Re Reactor Protection & ESFs Trip Setpoints ML20236T5301998-07-17017 July 1998 Proposed Tech Specs Pages for TS Bases Section 3/4.4.9, Pressure/Temperature Limits ML20236T7331998-07-17017 July 1998 Proposed Tech Specs Modifying DG Testing Requirements ML20249A2811998-06-10010 June 1998 Proposed Tech Specs Re Post Accident Access to Vital Areas (Plar 3-98-6) ML20249A3121998-06-0606 June 1998 Proposed Tech Specs Re SLCRS Bypass Leakage (Plar 3-98-5) ML20249A2681998-06-0505 June 1998 Proposed Tech Specs Re Revised Steam Generator Tube Rupture Analysis (Plar 3-98-4) ML20248M2221998-06-0404 June 1998 Revised Tech Specs Pages,Changing TS Bases Section 3/4.7.1.5 to Reword Section Which Describes Limiting Temperature Case for Containment Analysis ML20247G6841998-05-14014 May 1998 Proposed Tech Specs,Modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage1998-05-0707 May 1998 Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247B9411998-05-0101 May 1998 TS Change Pages for TS Bases Section 3/4.5.4,modifying Wording Associated W/Refueling Water Storage Tank Minimum Boron Concentration ML20217D5941998-04-30030 April 1998 Proposed Tech Specs Re Change to Basis 3/4.6.4 Which Modifies Accuracy Range Associated W/Measured Std Cubic Feet Per Minute & Corrects Listed Component Number ML20217N9441998-04-29029 April 1998 Proposed Tech Specs Replacing Two low-range Pressurizer Pressure transmitters,PT-103 & PT-103-1,which Will Identify That Two low-range Pressurizer Pressure Instrument Channels Are Independent & Redundant Only 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] |
Text
r Docket No. 50-245 Attachment 1 Millstone Nuclear Power Station, Unit No.1 Proposed Revision to Technical Specifications October,1985 I
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- 5. IRM's are bypassed when made switch is placed in run. The detector for each qmrable IIN diannel shall be fully inserted until the associatd APIN channel is cperable and indicating at least 3/125 full scale.****
- 6. 'Ihe design pennits closum of any cru valve without a scran beiry initiated.
- 7. May be bypassed when necessary by closirg the manual instnment isolation valve for scran of PS-1621 A through D durity purgirg for contairment inertirg or deinertirg.
- 8. When the reactor is subcritical ard the reactor water tatperature is less than 212 F, only the follcwirg trip fmetions need to in operable:
- a. MJde Switd) in Shutdown
- b. Manual Scran
- c. High Flux IBM
- d. Scran Dischartw Volune High Level
- e. APRM Rxijoed High Flux
- 9. Not required to be cperable when primary contairnent integrity is rot required.
- 10. With the made aritch in "run positicn" an incperative trip function also requires an associated APFM "dawnscale alatm."
- 11. Trip functions are not required to be operable if all control rods are fully inserted, ard either electrically or hydraulically disanned in aJoordance with Specificaticn 4.1.D.
- A11cn: If the first ollum cantut be net for cne of tie trip systens, that trip systan shall be tripped. If tie first colurn cannot be net for toth trip systans, the apprcpriate actions listed belcw shall be taken:
A. Initiate ireerticn of cperable rods ard cotplete irsertion of all cperable rods within four hours.
B. Rdu ptwer level to IBM rarge ard place mJde switch in the StartupAlot Stanty position within eight hours.
C. FL4x:e turbire loM and close main steam lire isolatial valms within eight hours.
- An APRM will be considered incperable if there are less than two IPIN irputs per level or there are less than 50% of the nonnal cxrpliment of IPEN's to an AMN.
One inch cn the water level instrutentation is 127 above the tm of the active fuel.
1Yr errata sheet dated 10-7-70.
3/4 1-4
t LIMrrING CENDrrKN IG OPERATICN SURVEIIIAN0: MOJIREMNT 3.10 MRIELING AND SRNr FIEI. IIANILDU 4.10 IUTELING AND SMNT FUL IMNILING Applicability: Applicability:
Applies to fuel handling, com rmetivity limitations, ard A[ plies to the periodic testiro of those interlocks and spent fm1 hardling. instrunents used &rirn mfueling ard spent fuel hardlirg.
Cbjective:
Objective:
1b assure com reactivity is within capability of the control rods, to prevent criticality durity refueling, and to assure Ib verify the operability of instrunentation and safe handliry of spent fuel casks. interlocks used in refuelirn ard spent fm1 handliro.
Specification: Specificatim:
A. Defueling Interlocks A. Refuelirri Interlod:s Durity core alterations, the reactor mie switch shall be Prior to any fuel handlirg, with the head off the locked in tM IUUEL position ard the refuelirn reactor vessel, tM refuelirg interlocks shall be interlocks shall be (perable, or all control ruis shall functionally tested. 'Ihey shall also be tested at be fully insertal, and either electrically cr weekly intervals thereafter until no lonrpr hWralically dicarmed. required and follcwing any repair work associated with the interlocks.
If the refuelirg interlocks are not operable, all control rods shall be verified to be fully inserted, ard either electrically or hydraulically +
disarmed in aamrdance with Specification 4.1.D. ,
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L 3/4 10-1
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High radiation levels in the main steamlire tunnel above that (ie to' the rormal nitrogen and oxygen radioactivity is an indication of leaking fuel. A scran is initiated whenever such radiaticn level exceeds seven times ncrmal background. %e purpose of the scran is to mduce the sourm of such radiation to the extent necessary to prevent excessive release of radioactive materials. Discharge of excessive ammts of radioactivity to the site envirem is prevented by the air ejector l off-gas mcmitors which came an isolation of the min condemer offmas line provided the limit for a 15-mirute period j specified in specification 3.8 is not exceeded.**
1 he main steamline isolation valve closure scram is set to scran when the isolatim valves are 10% clmed frun full open in three out of four lines. Wis scran anticipates the pressure ard flux tramient, which would nmm when the valves close.
By scranning at this setting the resultant transient is imignificant. Ref. Secticn 11.3.7 FSAR.
A reactor node switch is prwided which actuates or bypasses tie various scran functicns appropriate to the particular plant.
cperating status. Ref. Section 7.2 FSAR.
I
! %e manual scran function is active in all podes, thus providing for a iranual neans of r@ idly inserting control rods Wrirn all nxbs of reactor cperaticn.
l The IIN ard APR4 systen ptwide protecticn against excessive pwer levels and short reactr periods in the refuel and l Starttp410t Staryby nodes. A source rarye monitor (SRM) systen is also ptwided to st(ply aliitional neutron level l information &rirg starttp but has no scram functicms. Thus the IRM ard APR4 systens are required in the refuel and l Startup/ Hot Stanty modes. In the power range the APIM provi&s tM required protections; thus,, the IBM systen is not l
required in the Run node.
1
! Ite high reactor pressure, high drywell pressure, reactor 1rw water level, and scran discharrn voltare high level scrats are i required for Starttp410t Stanty and Run rcodes of plant cperaticn. They are, therefore, required to be cperational fcr these no&s of reactor cperation.
%e requirenent to have all scran functions except those listed in Note 7 of Table 3.1.1 operable in the Refuel and shutdmn mode is to assure that shiftiry to the Refuel node durirn reactor pwer cperaticn (bes tot diminish the need far the reactor protecticn systan. As irdicated in Note 11 of Table 3.1.1, to trip ftnctions are required to te cperable if all control rods are fully inserted, ard eitMr electrically or hydraulically disarmed, since this corditicn assuras naxinun negative reactivity irserticn.
- Per errata sheet dated 10-7-70 l
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B 3/4 1-3
e m 3.10 Bases A. mfuelirn Interlocks During refwlirg cperatims, tM mactivity potential of the mre is beiry altered. It is -ry to mquim rtain interlocks and mstrict certain refueliro procedures such that there is assurance that inadvertent critality (bes not occur.
To minimize the possibility of Icadirn fuel into wil containing no artrol rui, it is required that all control rods are fully inserted when fuel is bein] loshi into tM reactor core. This requitunent assures that during refueliry the refueling interlodcs, as desig md, will prevent inadvertent criticality. The core reactivity limitation of Specification 3.2 limits the mre alteraticrs to assure that the rusultiro core loalirn can be controlled with tM reactivity (Introl systan and inteel ay tine cbring chatrhet or the fellowinJ cperating cycle.
Ailition of large mounts of reactivity to tM core is ptuvented by operating procedures, wh% are in turn backed tp ly refueling interlocks on rod witMrawal and movment of the reflatform. Men the mode switch is in the " Refuel" positicn, interlocks prevent tM refueliry platform frun heiro moved cuer the com if a control rcx3 is withdrawn and fuel is on a hoist. Likewise, if the refuelirg platform is (wer the core with the fuel on a hoist, control rod notion is blockal by tM interlocks. With the noie switd1 in tM refm1 positicn, cnly cne control rod can be witMrawn.
With all control rods fully inserted, an3 either electrically or hydraulically disarned, maxinun negative reactivity inserticn is assured, tMrefore, tM refuelinj intericxis are not ruired to be operable.
Ebr a rww core, the drqpin] of a fuel assmbly into vacant fuel locaticn adjacent to a witMrawn ortrol real (bes rot result in an excursion or a critical configuraticn, tNs, adeqtute margin is provided.
B. Dru Manitorirg The STN's are provided to umitor tM mre durity periods of station shutdcwn and to guich the operator durirg refueliro operations and station starttp. Requirity two q)erable SIM's, cru in arti one adja nt to any core quadrant where fuel or control rtris aru beirg noved assurus aiequate nmitoring of that gnirant d2rirq such alteration requirment of three neutron induced count per secxn1 prtnides assurance tMt neutrtn flux is beiry nn11tcrui.
During unlosliny, it is not necessary to naintain 3 crs because core alteratims will involve cnly reactivity runoval and will rot result in criticality.
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