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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20138M5091997-02-13013 February 1997 Proposed Tech Specs Section 15.3.3. Re Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray ML20134L9791997-02-12012 February 1997 Proposed Tech Specs Re Relocation of Turbine Overspeed Protection ML20134A3661997-01-24024 January 1997 Proposed Tech Specs 15.5.4 Re Fuel Storage ML20134A3121997-01-21021 January 1997 Proposed Tech Specs 15.6.11, Radiation Protection Program ML20133N4021997-01-16016 January 1997 Proposed Tech Specs 15.3.2 Re Chemical & Volume Control Sys, 15.3.3 Re Emergency Core Cooling Sys,Auxiliary Cooling Systems,Air Recirculation Fan Coolers & Containment Spray & 15.3.8 Re Refueling ML20133N6321997-01-16016 January 1997 Proposed Tech Specs 15.1-6,15.2.2 Re Safety Limit,Reactor Coolant Sys Pressure,Ts 15.3.1-9,TS 15.3-10,TS 15.3.4-2 & TS 15.3.4-3 ML20133L1071997-01-13013 January 1997 Proposed Tech Specs 15.3.15 Re Overpressure Mitigating Sys & 15.3.1 Re Reactor Coolant Sys ML20133E5531997-01-0606 January 1997 Proposed Tech Specs 15.4.1, Operational Safety Review, Changing Ref Note 20 from TS 15.3.10.B to TS 15.3.10.E to Match TS Section Previously Containing Hot Channel Factor Limit ML20132F3471996-12-19019 December 1996 Proposed Tech Specs Improving Sections TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20132C3741996-12-12012 December 1996 Proposed Tech Specs Section 15.3.3 Re Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers & Containment Spray ML20135A8921996-12-0202 December 1996 Proposed Tech Specs 15.3.14 & 15.4.15 Re Fire Protection Sys ML20135A8431996-12-0202 December 1996 Proposed Tech Specs 15.3.10 Re Control Rod & Power Distribution Limits & 15.4.1 ML20129F2101996-09-30030 September 1996 Proposed Tech Specs Modify TS Section 15.3.3, Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers, & Containment Spray,To Incorporate Allowed Outage Times ML20129C0771996-09-19019 September 1996 Proposed Tech Specs Revising Section 15.3.15, Overpressure Mitigating Sys & Section 15.3.1, Rcs ML20117D2651996-08-22022 August 1996 Proposed Tech Specs Re Licensed Power Level for Plant ML20116N1341996-08-15015 August 1996 Proposed Tech Specs,Consisting of Suppl to Change Request 170,modifying TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20116G4891996-08-0505 August 1996 Proposed Tech Specs Modifying 15.2.3 & 15.5.3 of Change Request 188 & 15.2.1,15.2.3 & 15.3.1.G of Change Request 189 Supporting SEs ML20116D7471996-07-29029 July 1996 Proposed Tech Specs Re Health Physics Manager Qualifications for Plant ML20112F7341996-06-0404 June 1996 Proposed Tech Specs 15.2.3, Limiting Safety Sys Settings & Protective Instrumentation & 15.5.3, Design Features - Reactor ML20117K1991996-06-0404 June 1996 Proposed Tech Specs 15.2.1, Safety Limit,Reactor Core, 15.2.3, Limiting Safety Sys Settings,Protective Instrumentation & 15.3.1.G, Operational Limitations to Maintain Safety Margin for Unit 2 W/Replacement SGs ML20112E2441996-05-29029 May 1996 Proposed Tech Specs 15.1 Re definitions,15.3.6 Re Containment sys,15.4.4 Re Containment Tests & 15.6 Re Administrative Controls ML20108D1531996-04-29029 April 1996 Proposed Tech Specs Re Removal of Fire Protection Requirements ML20108A0011996-04-24024 April 1996 Proposed Tech Specs Section 15.7 RETS Re Removing Items Identified in GLs 89-01 & 95-10 as Being Procedural Details & Relocating Items to Appropriate Documents ML20149D9691996-03-20020 March 1996 Proposed Tech Specs,Providing Corrected Page to Bases for TS 15.3.1 ML20100L3891996-02-27027 February 1996 Proposed Tech Specs,Consisting of Change Request 186, Modifying TS Section 15.4.4, Containment Tests, Spec I.C.1 to State That Type a Tests Shall Be Conducted Per 10CFR50, App J Modified by Approved Exemptions 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] |
Text
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950511@233 950502 rr a =
TABLE 15.4.1-1 '
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTS OF INSTRUMENT CHANNELS -
PLANT CONDITIONS N_L CHANNEL DESCRIPTION CHECK CALIBRATE IESI WHEN REQUIRED
- 1. Nuclear Power Range -
R .
ALL
-Heat Balance S(1) D(1,4918)
~
ALL
-Signal to delta T; bistable - -
Q(1,2) ALL actions (rod stops, trips)
-Compare results of the incore M(4,5,2019)
~
PWR detector measurements to NIS axial flux difference
- 2. Nuclear Intermediate Range -
R -
ALL
-when not blocked S(1) - -
ALL
-logarithR level; bistable action - -
P ALL (rod sh,p, trips)
- 3. Nuclear Source Range -
R -
ALL
-when not blocked S - -
ALL
-Bistable action (alarm and - -
P ALL trips)
- 4. Reactor Coolant Temperature S R -
PWR, HOT S/D, COLD S/D
-0vertemperature delta T - -
Q(1,2) ALL
-0verpower delta T - -
Q(1,2) ALL
- 5. Reactor Coolant Flow S(1) R -
ALL
-Analog and single loop loss- - -
Q(1,2) ALL of-flow logic testing
-Logic channel testing for - -
R ALL reactor trip on loss of reactor coolant flow in both loops
- 6. Pressurizer Water Level S(1) R Q(1,2) ALL
- 7. Pressurizer Pressure S(1) R Q(1,2) ALL
- 8. Steam Generator Level S(l) R Q(1,4Q4) ALL Unit 1 - Amendment No. Page 1 of 6 Unit 2 - Amendment No.
_ _ , ,z.
v
.i -
TABLE 15.4.1-1 (continued) ,
' PLANT CONDITIONS
& CHANNEL DESCRIPTION CHECK CALIBRATE IE11 WHEN REQUIRED
- 9. Steam. Generator Flow Mismatch S(MH) R Q(1) ALL
- 10. Steam Generator Pressure S(M]$) R Q(1) ALL-
- 11. 4KV Bus Undervoltage (A01 & A02)
-AFW pump actuation -
R M(1) ALL
-Reactor Protection actuation -
R M(1,2) ALL
- 12. 4KV Bus Underfrequency (A01 & A02)
-to Reactor Coolant Pump trip -
.R -
ALL
- 13. Safeguards Bus Voltage
-Loss of 4KV S R M(1) ALL
-Degraded 4KV S R M(1) ALL
-Loss of 480V S R M(1) ALL
- 14. 120 Vac Instrument Buses W(6) - -
.ALL
- 15. Reactor Trip Signal From Turbine
-Turbine Autostop - -
M(1) ALL
-Turbine Stop Valve - -
M(1) ALL
- 16. Reactor Trip Signal From SI - -
M(1) .ALL
- 17. Feedwater Isolation on SI
-MFP Trip on Safety Injection - -
R ALL
-MFRV Shutting on Safety Injection - -
'R ALL
- 18. Accumulator Level and Pressure S R -
ALL
- 19. Analog Rod Position S(8,MH) R M(1) .ALL
-with step counters S(Mt()~ - -
ALL
-Monitoring by On-Line Computer (48R)' - -
PWR, HOT S/D' Unit 1 - Amendment No. Page'2 of 6 Unit 2 - Amendment No.
- a. _ _ _ _ . . _ . _ _ . ~ . . _ _ _ . . - - _ - . _ _ . . .. _ .. .. _ ___.____ _ _ _ _ _ . _...u_ _._. . . _ . . . _ _ _ _ _ _ _ . _ _ -
TABLE 15.4.1-1 (continued) - .,
PLANT CONDITIONS ML. CHANNEL DESCRIPTION CHECK CALIBRATE IESI WHEN REQUIRED
- 20. Auxiliary Feedwater Flowrate (M) R -
ALL
- 21. Boric Acid Control System -
R -
ALL
- 22. Boric Acid Tank Level D R -
ALL
- 23. Charging Flow -
R -
ALL
- 24. Condensate Storage Tank Level S(l) R -
ALL
- 25. Containment High Range Radiation S(l) R(M13) MQ(1) ALL
- 26. Containment Hydrogen Monitor D - -
ALL
-Gas Calibration -
Q(M)}) -
ALL
-Electronic Calibration -
R -
ALL
- 27. Containment Pressure S R Q(1,3,98,) ALL
- 28. Containment Water level M R -
ALL
- 29. Emergency Plan Radiation Survey Instruments Q R Q ALL
- 30. Environmental Monitors M - -
ALL
- 31. In-Core Thermocouples M R(Mf3) -
ALL
- 32. Overpressure Mitigating System S(Ml}) R (Mj) ALL
- 33. PORY Block Valve Position Indicator Q R -
ALL
- 34. PORV Operability -
R Q(R}0) ALL
- 35. PORV Position Indicator S(M[0) R R ALL l
l Unit 1 - Amendment No. Page 3 of 6 i Unit 2 - Amendment No.
l
TABLE 15.4.1-1 (continued) ,
& CHANNEL DESCRIPTION CHECK CALIBRATE IESI WHEN REOUIRED
- 36. P.:dicti:n Megtering Syst;c-M[n]}$sii 9t7t[(1J R(7}3) Mf7}QJ}} ALL LTrEIRid1Ti6on
- 37. RisdhfVessel Fluid Level System M R -
ALL
- 38. Refueling Water Storage Tank Level -
R -
ALL
- 39. Residual Heat Removal Pump Flow -
R -
ALL
- 40. Safety Valve Position Indicator M R -
ALL
- 41. Subcooling Margin Monitor M R -
ALL
- 42. Turbine First Stage Pressure S(1) R M(1) ALL
'43. Turbine Overspeed Trips
-Independent Overspeed Protection System -
R M(1) ALL
-0verspeed Block trip -
R M(1) ALL
- 44. Volume Control Tank Level -
R -
ALL
- 45. Reactor Protection System and - -
M(1,4312)
~
ALL Emergency Safety Feature Actuation System logic
- 46. Reactor Trip System Interlocks . . . . . .
-Intermediate Range Neutron Flux, P R(4423) R ALL
-Power Range Neutron Flux, P-8 -
R(2423) R ALL
-Power Range Neutron Flux, P-9 -
R(2423) R ALL
-Power Range Neutron Flux, P-10 -
R(2423) R ALL
-1st Stage Turbine Impulse Pressure -
R(4423,) R ALL' Unit 1 - Amendment No. Page 4 of 6 Unit 2 - Amendment No.
. . ~ . - , ..... . . . . . - < - . - - . ....,---.-,m ,, . . . , ,. ...~ .m_ . . . _w
- 1. -.
NOTATION USED IN TABLE 15.4.1-1 ,
S- Each shift D- Daily W- W;ekly Q- Quarterly M- Monthly P- Prior to reactor criticality if not performed during the previous week.
R- Each refueling interval (but not to exceed 18 months)
PWR- Power and Low Power Operation, as defined in Specifications 15.1.h. and 15.1.n.
HOT S/D- Hot Shutdown, as defined in Specification 15.1.g.1.
COLD S/D- Cold Shutdown, as defined in Specification 15.1.g.2.
REF S/D- Refueling Shutdown, as defined in Specification 15.1.g.3.
ALL- All conditions of operation, as defined in Specifications 15.1.g, h and n.
NOTES USED IN TABLE 15.4.1-1 (1) Not required during periods of refueling shutdown, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period.
(2) Tests of the low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to reactor criticality if not done in the previous surveillance interval.
(3) Perform test of the isolation valve signal.
(4) Perform by means of the moveable incore detector system.
(5) Recalibrate if the absolute difference is 23 percent.
(6) Verification of proper breaker alignment and that the 120 Vac instrument buses are energized.
(7) Radic::tive Effluent Monitoring In:trun:nt: tion Surv;ill:ne: Requir:::nt: r: :p :!fied in S :ti:n 15.7.4.
(8Z) Verify that the associated rod insertion limit is not being violated at least once per 4 hours whenever.the rod insertion limit alarm for a control bank is inoperable.
(98) Test of Narrow Range Pressure, 3.0 psig, -3.0 psig excluded.
Unit 1 - Amendment No. Page 5 of 6 Unit 2 - Amendment No.
v.s NOTES USED IN TABLE 15.4.1-1 (continued) ,
(Mg) When used for the Overpressure Mitigating System, each PORV shall be demonstrated operable by: . .
- a. Perfomance of a channel functional test on_ the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required operable and at least once per 31' days i thereafter when the PORV is required operable.
(Hjj) Performance of a channel functional test is required, excluding valve operation.
(MM)Shiftly check is required when the reactor coolant system is not open to the atmosphere and the reactor coolant system temperature is less than the minimum temperature for the in-service pressure test as specified in.TS Figure 15.3.1-1.-
(M}2)An AFW flow path to each steam generator shall be demonstrated operable, following each cold shutdown of greater than 30 days, prior to entering power operation by verifying AFW flow to each steam generator.
- (M)))Calibrationistobeaverificationofresponsetoasource.
- (HQ) Sample gas for calibration at 2% and 6%.
l (M}})A check of one pressure channel per steam generator is required whenever the steam generator could be pressurized.
(Wi() Includes test of logic for reactor trip on low-low level, automatic actuation logic for auxiliary feedwater pumps, and test of logic for feedwater isolation on high steam generator level.
(481?) Rod positions must be logged at least once per hour, after a load change >10% or after >30 inches of control' rod motion-if the on-line computer is inoperable.
(491))The daily heat halance is a gain adjustment performed to match Nuclear Instrumentation System indicated power level with reactor thermal output.
(2019)To confirm that hot channel factor limits are being satisfied, the requirements of TS 15.3.10.B must be mat.
(M20) Check required only when the overpressure mitigation system is in operation.
(M21)Not required during period of cold and refueling shutdowns, but must be performed prior to reactor criticality if it
~ has not been performed during the previous surveillance period.
(M)$)Each train tested at least every 62 days on a staggered basis.
(Mi3) Neutron detectors excluded from calibration.
Unit 1 - Amendment No. Page 6 of 6 Unit 2 - Amendment No.
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