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| {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1200B EXISTING TECHNICAL SPECIFICATIONS WITH PAGES MARKED TO REFLECT PROPOSED CHANGES 950bOb0440 950525 PDR ADOCK"05000315 PDR TABLE 4.3-2 Continued gt ENCINEER D SAFETY FEATURE ACTUATION SY~r INSTRUMENTATZON SURVEILLANC REQUIRHKNTS FUNCTZONAI UNIT TRIP ACTUATING CK~'EVIC CHANNEL CHANNEL FUNCTIONAL OP~~TZONAL CIKCK CAf ZEBATEON TEST TEST MODES ZN WHICH SURVEILLANCE RE UIRED 9.Manual a.Safety Zn)ec ion (ECCS)Feedwater Isolation Reactor Trip (SZ)Containment Zsolation-Phase"A" Containment Purge and Exhaust Isolation Aux'liary Feedwater Pumps Essential Service Mater System h.Containment Spray Containment Zsolation-Phase"H" Containment Purge and Exhaust Zsolation~Containment Air Reci culatfon Pan c.Containment Zsolation-Phase"A" Containment Purge and Exhaust.Isolation d.Steam Line Zsolation N A N-A N A N.A N.A.N A N.A-N-A NA NAo N.A lp2,3,4 li2)3,4 1(2,3g4.1)2i 3 I I~K NULL PLANT-UNIT 1 3/4 3-33b u=NDmzr NO.153 TABLE 4.3-2 (Continuedl TABLE NOTATION switches shall be tes.d during shu down.All ot e.zssocia ed guards ac"ua''receive a CHAHH~~on r 31 days.g<)<~p i once per 1B months<<'i h manual szfe-7 a-1eas~~'(2)Each train or logic chzrne1 shall be tested a least:every oker 31 days.(3)The CHANNERJNCTIOHAL T"-57 snail include cxer ising the ransmi t.r by applying either a vacuum or pressure to the appropriate side o the transmitter. | | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1200B EXISTING TECHNICAL SPECIFICATIONS WITH PAGES MARKED TO REFLECT PROPOSED CHANGES 950bOb0440 950525 PDR ADOCK"05000315 PDR |
| '0.C.CQCV.-JNET~/4 3-34 g~PATTON ON>TGKBX¹D~~A~LLJ~f TBXP ACXUAZZm ABODES m CELEB DEVI&CREWEL CRANKS.FQHCXXONAL OP~~CHAL SQKVc,~~%ACE CIKXlaXI'" M1=zat-a.Stean Generator Pater Level--Lov-t,ov b.Keactor Coolant Pmp Bus Undervoltage S H.A.HM 1, 2, Hm 1,2.3 8.LOSS OP PO~a.4 hv Bus Loss of Voltage b.4 kv'us Deg aded Voltage Kf H.A.1,2,3,<l-:1,'2,'3,~I a.Safety Xag ection (iCCS)Peedmater Xsolation Reactor Trip (SX)Coacz9~ent Xsola&on.Phase"A," Coataiaaeat Purge and Exhaust Xsolatioa.Aux1liary Fee&rate Pumps EsseatiaZ.
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| Service Rater Sys ea b.Coataiane t Spray Conoid'eat Xsolation-0 B It Coataiaaeat Pu ge aad Exhaust Xsolation Coacainmeat Air Rec&culatiaa Fan Coataiaaeat Xsolation-Phase"A" Coatai eat 8 ge and Ev.?aust Isolation N.A.H.A.H.A.H-A-H.A.H.A.H.A.H.A.N.A.1,2,3,~)Stean Li e Xsolation H.A.H.A.1, 2, 3 f'ae provisions of TecL~cal Specification 4.0.8 are appl cable.COOK NUCL:-MK PZ<~i-Uhx7 2 3/4 3-32~~i.HO.8",~,~~1~9 TAMIL~4.3-2 Continued)
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| TA5L~NOThTIOH Manua tuation svitchas shall be~ease once per 18 months during shut.o y associated with nanual sa<e guards accuas a 1 AHHZL MCTIONhL TEST at least once (2)Each t ain or logic channel shall be tasted at least every other 31 days.(3)Tha CHAHNZX RNCTZONAL TEST shall include exercising
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| 'th>>t ansnittar by applying either a vacuum or pressure to the appropziata aide oi the t ansaittar.
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| COOK BUCLM PLRVi UNIT 2 3/4 3-33 Av~u~NO.gf~13~
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| ATTACHMENT 3 TO AEP'NRC:1200B REVISED TECHNICAL SPECIFICATIONS PAGES 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNlT 9.Manual TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE CHECK CALIBRATION TEST a.Safety Injection (ECCS)Feedwater Isolation Reactor Trip (SI)Containment Isolation-Phase"A Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System N.A.N.A.N.A.R 1,2,3,4 b.Containment Spray Containment Isolation-Phase"B Containment Purge and Exhaust Isolation Containment Air Recirculation Fan N.A.N.A.N.A.R-1, 2, 3, 4 c.Containment Isolation-Phase"A" Containment Purge and Exhaust Isolation d.Steam Line Isolation N.A.N.A.N.A.N.A.N.A.R 1, 2, 3, 4 1, 2, 3 COOK NUCLEAR PLAiVI'-UNIT I Page 3/4 3-33b AMENDMENT 48k 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (I)Deleted (2)Each train or logic channel shall be tested at least every other 31 days.(3)The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
| | TABLE 4. 3-2 Continued gt ENCINEER D SAFETY FEATURE ACTUATION SY~r INSTRUMENTATZON SURVEILLANC REQUIRHKNTS TRIP ACTUATING MODES ZN CK~ 'EVIC WHICH CHANNEL CHANNEL FUNCTIONAL OP~~TZONAL SURVEILLANCE FUNCTZONAI UNIT CIKCK CAf ZEBATEON TEST TEST RE UIRED 9.Manual |
| COOK NUCLEAR PLANT-UNIT I Page 3/4 3-34 AME~tbIENT BQ 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMP CHANNEL CHANNEL CHANNEL FUNCTIONAL CHECK CALIBRATION TEST TRIP ACTUATING MODES IN DEVICE WHICH OPERATIONAL SURVEILLANCE TEST~RE UIRED a.Steam Generator Water Level-Low-Low b.Reactor Coolant Pump Bus Undervoltage 8.LOSS OF POWER a.4 kv Bus Loss of Voltage b.4 kv Bus Degraded Voltage 9.MANUAL a.Safety Injection (ECCS)Fccdwater Isolation Reactor Trip (SII Containment Isolation-Phase A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System b.Containment Spray Containment Isolation-Phase"B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan c.Containment Isolation-Phase A Containment Purge and Exhaust Isolation d.Steam Line Isolation N.A.N.A.N.A.N.A.N.A.R N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.I, 2, 3 I, 2, 3 1,2,3,4 I, 2, 3, 4 1,2,3,4 I, 2, 3, 4 1,2,3,4 I, 2, 3 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-32 AIt'IENDMENT LI)&)444)4ÃEI)i49
| | : a. Safety Zn)ec ion Feedwater Isolation (ECCS) N A N.A. N A lp2,3,4 Reactor Trip (SZ) |
| | Containment Zsolation-Phase "A" Containment Purge and Exhaust Isolation Aux'liary Feedwater Pumps Essential Service Mater System |
| | : h. Containment Spray Containment Zsolation-N-A N.A- N-A li2) 3,4 Phase "H" Containment Purge and Exhaust Zsolation |
| | ~ Containment Air Reci culatfon Pan |
| | : c. Containment Zsolation- N A NA NAo 1(2,3g4 Phase "A" Containment Purge and Exhaust. Isolation |
| | : d. Steam Line Zsolation N.A N.A .1) 2i 3 I |
| | I |
| | ~K NULL PLANT - UNIT 1 3/4 3-33b u=NDmzr NO. 153 |
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| 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (1)Deleted (2)Each train or logic channel shall be tested at least every other 31 days.(3)The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter. | | TABLE 4.3-2 (Continuedl TABLE NOTATION switches shall be tes. d i once per 1B months during shu down. All ot e. zssocia ed <<'i h manual szfe-guards ac"ua'' receive a CHAHH~~ 7 a- 1eas on r 31 days. g< ) < ~p ' |
| COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-33 AAIENDib[EliT N M4 4~l~V j}} | | ~ ~ |
| | (2) Each train or logic chzrne1 shall be tested a least:every oker 31 days. |
| | (3) The CHANNERJNCTIOHAL T"-57 snail include cxer ising the ransmi t. r by applying either a vacuum or pressure to the appropriate side o the transmitter. |
| | ' |
| | : 0. C. CQCV.- JNET ~/4 3-34 |
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| | g ~PATTON TBXP ACXUAZZm ABODES m CELEB DEVI& |
| | SQKVc, ~ ~ %ACE ON > |
| | CREWEL CRANKS. |
| | CIKXlaXI'" M1= zat FQHCXXONAL OP~~CHAL TGKBX¹ D~~ A~LLJ~f |
| | : a. Stean Generator Pater S HM 1, 2, Level--Lov-t,ov |
| | : b. Keactor Coolant Pmp H.A. Hm 1,2. 3 Bus Undervoltage |
| | : 8. LOSS OP PO~ |
| | : a. 4 hv Bus H.A. 1,2,3,<l Loss of Voltage |
| | : b. 4 kv'us Kf -:1,'2,'3, ~ I Deg aded Voltage |
| | : a. Safety Xag ection (iCCS) N.A. H.A. H.A. 1,2,3,~ ) |
| | Peedmater Xsolation Reactor Trip (SX) |
| | Coacz9~ent Xsola&on . |
| | Phase "A," |
| | Coataiaaeat Purge and Exhaust Xsolatioa |
| | . Aux1liary Fee&rate Pumps EsseatiaZ. Service Rater Sys ea |
| | : b. Coataiane t Spray Conoid'eat Xsolation-H.A. H-A- H.A. |
| | 0 B It Coataiaaeat Pu ge aad Exhaust Xsolation Coacainmeat Air Rec&culatiaa Fan Coataiaaeat Xsolation- H.A. H.A. N.A. |
| | Phase "A" Coatai eat 8 ge and Ev.?aust Isolation Stean Li e Xsolation H.A. H.A. 1, 2, 3 f'ae provisions of TecL~cal Specification 4.0.8 are appl cable. |
| | COOK NUCL:-MK PZ <~i - Uhx7 2 3/4 3-32 ~~i. HO. 8", ~, |
| | 1~9 |
| | ~ ~ |
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| | TAMIL~ 4.3-2 Continued) |
| | TA5L~ NOThTIOH Manua tuation svitchas shall during shut . o be y |
| | ~ ease once per 18 months associated with nanual sa<e guards accuas a 1 AHHZL MCTIONhL TEST at least once (2) Each t ain or logic channel shall be tasted at least every other 31 days. |
| | (3) Tha CHAHNZX RNCTZONAL TEST shall include exercising 'th>> t ansnittar by applying either a vacuum or pressure to the appropziata aide oi the t ansaittar. |
| | COOK BUCLM PLRVi UNIT 2 3/4 3-33 Av~u~ NO. gf ~ 13~ |
| | |
| | ATTACHMENT 3 TO AEP'NRC:1200B REVISED TECHNICAL SPECIFICATIONS PAGES |
| | |
| | 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNlT CHECK CALIBRATION TEST |
| | : 9. Manual |
| | : a. Safety Injection (ECCS) N.A. N.A. N.A. R 1,2,3,4 Feedwater Isolation Reactor Trip (SI) |
| | Containment Isolation-Phase "A Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System |
| | : b. Containment Spray N.A. N.A. N.A. R - 1, 2, 3, 4 Containment Isolation-Phase "B Containment Purge and Exhaust Isolation Containment Air Recirculation Fan |
| | : c. Containment Isolation- N.A. N.A. N.A. R 1, 2, 3, 4 Phase "A" Containment Purge and Exhaust Isolation |
| | : d. Steam Line Isolation N.A. N.A. 1, 2, 3 COOK NUCLEAR PLAiVI'-UNITI Page 3/4 3-33b AMENDMENT48k |
| | |
| | 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (I) Deleted (2) Each train or logic channel shall be tested at least every other 31 days. |
| | (3) The CHANNELFUNCTIONALTEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter. |
| | COOK NUCLEAR PLANT-UNIT I Page 3/4 3-34 AME~tbIENT BQ |
| | |
| | 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST ~RE UIRED |
| | : 7. TURBINE DRIVEN AUXILIARYFEEDWATER PUMP |
| | : a. Steam Generator Water N.A. I, 2, 3 Level Low-Low |
| | : b. Reactor Coolant Pump N.A. N.A. I, 2, 3 Bus Undervoltage |
| | : 8. LOSS OF POWER |
| | : a. 4 kv Bus Loss of R N.A. 1,2,3,4 Voltage |
| | : b. 4 kv Bus Degraded N.A. I, 2, 3, 4 Voltage |
| | : 9. MANUAL |
| | : a. Safety Injection (ECCS) N.A. N.A. N.A. 1,2,3,4 Fccdwater Isolation Reactor Trip (SII Containment Isolation-Phase A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System |
| | : b. Containment Spray N.A. N.A. N.A. I, 2, 3, 4 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan |
| | : c. Containment Isolation- N.A. N.A. N.A. 1,2,3,4 Phase A Containment Purge and Exhaust Isolation |
| | : d. Steam Line Isolation N.A. N.A. I, 2, 3 COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-32 AIt'IENDMENTLI) &) 444) 4ÃEI) i49 |
| | |
| | 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (1) Deleted (2) Each train or logic channel shall be tested at least every other 31 days. |
| | (3) The CHANNELFUNCTIONALTEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter. |
| | COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-33 AAIENDib[EliTN M4 |
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| | 4 |
| | ~ l ~ V j}} |
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Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view] |
Text
ATTACHMENT 2 TO AEP:NRC:1200B EXISTING TECHNICAL SPECIFICATIONS WITH PAGES MARKED TO REFLECT PROPOSED CHANGES 950bOb0440 950525 PDR ADOCK"05000315 PDR
TABLE 4. 3-2 Continued gt ENCINEER D SAFETY FEATURE ACTUATION SY~r INSTRUMENTATZON SURVEILLANC REQUIRHKNTS TRIP ACTUATING MODES ZN CK~ 'EVIC WHICH CHANNEL CHANNEL FUNCTIONAL OP~~TZONAL SURVEILLANCE FUNCTZONAI UNIT CIKCK CAf ZEBATEON TEST TEST RE UIRED 9.Manual
- a. Safety Zn)ec ion Feedwater Isolation (ECCS) N A N.A. N A lp2,3,4 Reactor Trip (SZ)
Containment Zsolation-Phase "A" Containment Purge and Exhaust Isolation Aux'liary Feedwater Pumps Essential Service Mater System
- h. Containment Spray Containment Zsolation-N-A N.A- N-A li2) 3,4 Phase "H" Containment Purge and Exhaust Zsolation
~ Containment Air Reci culatfon Pan
- c. Containment Zsolation- N A NA NAo 1(2,3g4 Phase "A" Containment Purge and Exhaust. Isolation
- d. Steam Line Zsolation N.A N.A .1) 2i 3 I
I
~K NULL PLANT - UNIT 1 3/4 3-33b u=NDmzr NO. 153
TABLE 4.3-2 (Continuedl TABLE NOTATION switches shall be tes. d i once per 1B months during shu down. All ot e. zssocia ed <<'i h manual szfe-guards ac"ua receive a CHAHH~~ 7 a- 1eas on r 31 days. g< ) < ~p '
~ ~
(2) Each train or logic chzrne1 shall be tested a least:every oker 31 days.
(3) The CHANNERJNCTIOHAL T"-57 snail include cxer ising the ransmi t. r by applying either a vacuum or pressure to the appropriate side o the transmitter.
'
- 0. C. CQCV.- JNET ~/4 3-34
g ~PATTON TBXP ACXUAZZm ABODES m CELEB DEVI&
SQKVc, ~ ~ %ACE ON >
CREWEL CRANKS.
CIKXlaXI'" M1= zat FQHCXXONAL OP~~CHAL TGKBX¹ D~~ A~LLJ~f
- a. Stean Generator Pater S HM 1, 2, Level--Lov-t,ov
- b. Keactor Coolant Pmp H.A. Hm 1,2. 3 Bus Undervoltage
- 8. LOSS OP PO~
- a. 4 hv Bus H.A. 1,2,3,<l Loss of Voltage
- b. 4 kv'us Kf -:1,'2,'3, ~ I Deg aded Voltage
- a. Safety Xag ection (iCCS) N.A. H.A. H.A. 1,2,3,~ )
Peedmater Xsolation Reactor Trip (SX)
Coacz9~ent Xsola&on .
Phase "A,"
Coataiaaeat Purge and Exhaust Xsolatioa
. Aux1liary Fee&rate Pumps EsseatiaZ. Service Rater Sys ea
- b. Coataiane t Spray Conoid'eat Xsolation-H.A. H-A- H.A.
0 B It Coataiaaeat Pu ge aad Exhaust Xsolation Coacainmeat Air Rec&culatiaa Fan Coataiaaeat Xsolation- H.A. H.A. N.A.
Phase "A" Coatai eat 8 ge and Ev.?aust Isolation Stean Li e Xsolation H.A. H.A. 1, 2, 3 f'ae provisions of TecL~cal Specification 4.0.8 are appl cable.
COOK NUCL:-MK PZ <~i - Uhx7 2 3/4 3-32 ~~i. HO. 8", ~,
1~9
~ ~
TAMIL~ 4.3-2 Continued)
TA5L~ NOThTIOH Manua tuation svitchas shall during shut . o be y
~ ease once per 18 months associated with nanual sa<e guards accuas a 1 AHHZL MCTIONhL TEST at least once (2) Each t ain or logic channel shall be tasted at least every other 31 days.
(3) Tha CHAHNZX RNCTZONAL TEST shall include exercising 'th>> t ansnittar by applying either a vacuum or pressure to the appropziata aide oi the t ansaittar.
COOK BUCLM PLRVi UNIT 2 3/4 3-33 Av~u~ NO. gf ~ 13~
ATTACHMENT 3 TO AEP'NRC:1200B REVISED TECHNICAL SPECIFICATIONS PAGES
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNlT CHECK CALIBRATION TEST
- 9. Manual
- a. Safety Injection (ECCS) N.A. N.A. N.A. R 1,2,3,4 Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase "A Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
- b. Containment Spray N.A. N.A. N.A. R - 1, 2, 3, 4 Containment Isolation-Phase "B Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
- c. Containment Isolation- N.A. N.A. N.A. R 1, 2, 3, 4 Phase "A" Containment Purge and Exhaust Isolation
- d. Steam Line Isolation N.A. N.A. 1, 2, 3 COOK NUCLEAR PLAiVI'-UNITI Page 3/4 3-33b AMENDMENT48k
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (I) Deleted (2) Each train or logic channel shall be tested at least every other 31 days.
(3) The CHANNELFUNCTIONALTEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
COOK NUCLEAR PLANT-UNIT I Page 3/4 3-34 AME~tbIENT BQ
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST ~RE UIRED
- 7. TURBINE DRIVEN AUXILIARYFEEDWATER PUMP
- a. Steam Generator Water N.A. I, 2, 3 Level Low-Low
- b. Reactor Coolant Pump N.A. N.A. I, 2, 3 Bus Undervoltage
- 8. LOSS OF POWER
- a. 4 kv Bus Loss of R N.A. 1,2,3,4 Voltage
- b. 4 kv Bus Degraded N.A. I, 2, 3, 4 Voltage
- 9. MANUAL
- a. Safety Injection (ECCS) N.A. N.A. N.A. 1,2,3,4 Fccdwater Isolation Reactor Trip (SII Containment Isolation-Phase A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
- b. Containment Spray N.A. N.A. N.A. I, 2, 3, 4 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
- c. Containment Isolation- N.A. N.A. N.A. 1,2,3,4 Phase A Containment Purge and Exhaust Isolation
- d. Steam Line Isolation N.A. N.A. I, 2, 3 COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-32 AIt'IENDMENTLI) &) 444) 4ÃEI) i49
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued TABLE NOTATION (1) Deleted (2) Each train or logic channel shall be tested at least every other 31 days.
(3) The CHANNELFUNCTIONALTEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-33 AAIENDib[EliTN M4
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