|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20095F5891995-12-12012 December 1995 Proposed Tech Specs Re Containment Sys ML20094D0611995-10-31031 October 1995 Proposed TS Page 6-18,deleting TS 6.9.2.d, Seismic Event Analysis ML20098C5181995-10-0202 October 1995 Proposed Tech Specs,Revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C4111995-09-29029 September 1995 Proposed TS 3/4.1.2.8 Re Reactivity Control Sys - Borated Water Sources - Shutdown TS 3/4.1.2.8 Re Reactivity Control Sys - Operating & TS 3/4.5.1 Re ECCS - Core Flooding Tanks ML20098C1121995-09-29029 September 1995 Proposed TS 3.4.3 & Associated Bases,Modifying Lift Setting of Pressurizer Code Safety Valves to Greater than or Equal to 2,575 Psig,Corresponding to Lift Setting Tolerance of +3% of Nominal Lift Pressure 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] |
Text
- _____
l
~
~
ht/ogagc 3 .
INSTRUMENTATION ,
W 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION .
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION t
3.3.2.1 The Safety Features Actuation System (SFAS) functional units shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column,of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
- a. With a SFAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the functional unit inoperable and apply the applicable ACTION requirement of Table 3.3-3, until the func-tional unit is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With a SFAS functional unit inoperable, take the action shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each SFAS functional unit shall be demonstrated OPERABLE by the perfonnance of the CFANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shewn in Table 4.3-2.
4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of functional units affected 1 by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each functional unit affected by bypass operation.
4.3.2.1.3 The SAFETY FEATURES RESPONSE TIME of each SFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one functional unit per function such 7 that all functional units are tested at least once every N times 18 .
months where N is the total number of redundant functional units in a specific SFAS function as shown in the " Total No. of Units" Column of 1 Table 3.3-3. .
DAVIS-BESSE, UNIT 1 3/4 3-9 JAN 121977 !
~~
l
-l
~
8005050179 -
TABLE 3.3-3 SAFETY FEATURES ACTUATION SYSTE'ri INSTRUMENTATION MINIMUM
[ TOTAL NO. UNITS - UNITS APPLICABLE g;
ACTION g
FUNCTIONAL UNIT OF UNIT 5 TO TRIP OPERABLE MODES g 1. INSTRUMENT STRINGS U a. Containment Radiation -
-- High 4 2 3 All MODES 9f
- b. Containment Pressure -
High 4 2 3 1,2,3 9#
- c. Containment Pressure - '#
liigh-High 4 2 3 1, 2, 3 ' 91
- d. RCS Pressure - Low 4 2 3 1, 2, 3* d 9#
- e. RCS Pressure - Low-Low 4 2 3 1, 2, 3** 9#
4 2
~
3 1,2,3 4 9#
- f. .BWST Level - Low f M
g 2. DUTPUT LOGIC g
- a. Incident Level #1:
w o
b.
Containment Isolation Incident Level #2:
NA 2
. NAl NA E-All MODES 10.
p g High Pressure Injection and Starting Diesel bh$p N Generators -
NA 1 NA I NA 2 1, 2, 3 1#
- c. Incident Level #3:
Low Pressure Injection NA b NA 8 NA z. 1, 2, 3 P-(*t10
- v10
- d. Incident Level #4:
1, 2, 3.
by Containment Spray NA h NA I NA ?. 10
- e. Incident Level #5: '
Containment Sump Recirculation NA h NA 1 NA E 1,2,3 10 Q $
- i dd M A ur s y , s g~ ym n'l O fgg %,
y rhyLw,,~~~",
i TABLE 3.3-3
$ SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM g TOTAL NO. UNITS UNITS APPLICABLE g FUNCTIONAL UNIT OF UNITS TO TRIP OPERABLE MODES -
ACTION g
~
- 3. MANUAL ACTUATION 2 SFAS(exceptContainment
- a. .
Spray and Emergency Sump 2 2 8 2 ALL MODES 11.
, Recirculation) '
- b. Containment Spray 2 2 A 2 1,2,3,4~' 11
- 4. SEQUENCE LOGIC CHANNELS 4 2*** 4 1,2,3 -
97~
i 4 O
,Q $ 4(/ hN f p cd idMif V^
^
. 3 feA an kWi W .d&
j y 1 .
f,hsh /Nb
=
.. g g y M
w -- -.
i.
I
-l TABLE 3.3-4 ,
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS' ~
en b
TRIP SETPOINT ALLOWA'BLE VALUES h
m FUNCTIONAL UNIT k
2 INSTRUMENT STRINGS ,
H a. Containment Radiation 1 25 mR/hr < 25 mR/hr
- b. Containment Pressure - High. 1.'18.4 psia , ' 1'18.4 psia .
- \ ,
- c. Containment Pressure - High-High 1 38.4 psia -
s'38.4 psia .,
.i
/ t.1600 psig t 1600 psig
- d. RCS Pressure - Low ,
- e. RCS Pressure - Low-Low ". t 400 psig' > 400 psig
$ f. BWST Level 1 36 in. H 2O >i_ 36 in. H 2O
. SEQUENCE LOGIC CilANNELS yN
- a. Undervoltage Condition 0000100 Volts 3, *o - 0000100 Volts bS
^ '
. i 5'o a de- jv dn~ dL j w///
f$ y~" lo-1' ~
- ' u3<>. N. ,ne.L., h Q4,a, ' '
jj OI !
- .. - ~9 ,
u, \,.-
,. . t. ,'
8# . 7-Fys -.
. r 52o -
.}
2 -! - ,
_........a.
a
. ..~._ 9,!R y
- nu i O,i MW WWupesuum se . - ~ + . m o ne-p
7 p7k i
. TABLE 3.3-5 (Continued)_ - i SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSETIMEINSECONDS
- n. Steam and Feedwater Isolation Valves (continued) 8
- 2. Main Feedwater Stop . NA
.3. Main-Steam Warmup NA
[MEContairinent Pressure - High
- 2. ,
- a. Fans .
. 1. Emergency-Vent Fans 1 25*
- 2. Containment Cooler Fans 1 45*
- b. HV & AC Isolation Valves
- 1. ECCS Room < 75*
- 2. Emergency Yent11ation 175*
- 3. , Containment Air Sample 1 25*
- 4. Containment Purge < NA*
- 5. Penetration Room Purge 175*
c.
d.
ControlRoomHV&dC' Units High Pressure Injection 1 10*
[c g{4* <y
- 1. High Pressure Injection Pamps < 30* ,
1
- 2. High Pressure Injection Valves i30* #
- e. Component Cooling Water g , ,
- 1. Component Cooling Water Pumps < 180*
2.
3.
Component Cooling Aux. Equip. Inlet Valves Component Cooling to Air Compressor Valves 5180* 4 1 180*
ff Ag,
- f. Service Water System
- 1. Service Water Pumps -
45*
2'. Service Water Fran Component Cooling Heat Exchanger Isolation Valves 1 NA*
. g. Containment Spray Isolation Valves 1 80*
- h. Emergency Diesel Generator 11 i!
DAVIS-BESSE UNIT 1 3/4 3-16
~
JAN 121977
TABLE 3.3-5 (Continued)
SAFETY FEATURES SYSTEM' RESPONSE TIMES INITIATINGSIGNALANDFUNCTkON RESPONSE TIME IN SECONDS
- 2. Containment Pressure - High (Continued) i
. I
- 1. Containment Isolation Valves l
- 1. Vacuum Relief < 25*
- 2. Nomal Sump ~ 25*
- 3. RCS Letdown Delay Coil Outlet 7 30*
4 RCS Letdown High Temperature 130* , ,
- 5. Pressurizer Sample '< 48*
.G. Service Water to Cooling Water 7 /
- 7. Vent Header 15*
7 15* k,1 *
- 8. Drain Tank i '
- 9. Core Flood Tank Vent 715* .
16
- 10. Core Floed Tank Fill 7 15* W
- 11. Steam Generator Sample 7 15* *
- 12. Atmospheric Vent 717*
- 13. Quench 'ank Ip
- 14. Emergency Sump < 90*
- 15. RCP Seal 'ieturn 7 30*
- 16. Air Syrkem
- 17. N Sptem 'ji*s
- 18. Q ench Tank Sample
< 35*_
- 19. Main Steam Warmup Drain Q,,),5* ) -
- 20. Makeup < 30*
- 21. RCP Seal Inlet 73*
- 2. Core Flood Tank Sample < 5*
- 23. RCP Standpipe Demin Water Supply <
- 24. Containment H Dilution Inlet < 25*
- 25. Containment 2H Dilution Outlet i25*
- j. BWST Outlet Valves 1 30*
- k. Low Pressure Injection
- 1. Decay Heat Pumps < 30*
- 2. Low Pressure Injection Valves 7 NA*
- 3. Decay Heat Pump Suction Valves 7 30*
4 Decay Heat Cooler Outlet Valves ~
1 NA*
- 5. Decay Heat Cooler Bypass Valves ,
S NA* ;
- 3. Containment Pressure--High-High
- a. Containment Spray Pump 1 80* l
- b. Component Coolfng Isolation Valves -
l
- 1. Inlet to Con +ainment < 25 * .
- 2. Outlet froo 2ntainment _725*
DAVIS-BESSE, UNIT 1 3/4 3-17 JAN 121977 l
. TABLE 3.3-5 (Continua
~
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- b. fComponent Cooling Isolation Valves (Continued)
- 3. Inle't to CRDM's < 35*
- 4. CROM Booster Pump Suction 7 35*
- 5. Component Cooling from Decay Heat Cooler -(
1 )*
- c. Steam and Feedwater Isolation Valves
< 10*
f
. 1. Main Steam Line *
- 2. Main Feedwater Stop <
- 3. Main Steam Wannup
'1 5*
- 4. RCS Pressure-Low THIS PAGE OPEN PENDING RECE:PT O INFORMATION FROM THE APPUCANT I 7 ,
- 1. Emergency Vent Fans 1 25*
- 2. Containment Cooler Fans 1 45*
- b. HV & AC Isolation Valves Y
< 75*
LL W
- l. ECCS Room 2.
3.
Emergency Ventilation Cont .inment Air Sample 7 75*
7 p
- 4. Containment Purge 11-
- 5. Penetration Room Purge '1 75*
- c. Control Room HV & AC Units 1 0*
- d. High Pressure Injection
- 1. High Pressure Injection Pumps < 30*
- 2. High Pressure Injection Valves 1,30*
- e. Component Cooling Water -
. 1. Component Cooling Water Pumps 1 180*
- 2. Component Cooling Aux. Equipment Iniet Valves < 180*
- 3. Component Cooling to Air Compressor Valves _7 180*
- f. Service Water System
- 1. Service Water Pumps 1 45*
- 2. Service Water from Cor.ponent Cooling Heat Exchanger Isolation Valves 1 NA*
- g. Containment Spray isolation Valves 1 80* 1,
- h. Emergency Diesel Generator 4 . g#'
DAVIS-BESSE, UNIT 1 3/4 3-18 t \D JAN 12
TABLE 3.3-5 (Continuedi SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS -
- 4. RCS Pressure-Low (continued)
- 1. Containment Isolation Valves
,1. Vacuum Relief 1 25* ,
- 2. Normal Sump < 25*
- 3. RCS Letdown Delay Coil Outlet 7 30*
- 4. RCS Letdown High Temperature 130* Jh._
- 5. Pressurizer Sample < 45*
- 6. Service-Water to Cooling Water -7 4 *
- 7. Vent Header < 15* f/
- 8. Drain Tank 715*
- 5. Core Flood Tank Vent 7 15*
- 10. Core Flood Tank Fill 5 15* If ky
- 11. Steam Generator Samole < 15* g 17
- 12. Atmospheric Vent
- 13. Quench Tank 7 15* N
- 14. Emergency Sump [
- 15. RCP ' Seal Return <
- 16. Air Systems < 15* .
- 17. N System 71* .
- 18. Q$ench Tank Sample
- 19. Main Steam Warmup Drain 1
- 20. Makeup < 0*
- 21. RCP Seal Inlet 7
- 22. Core Flood Tank Sample < 15*
- 23. RCP Standpipe Demin Water Supply 7 5*'
- 24. Containment H Dilution Inlet < 25*'
- 25. Containment Hf Dilution Outlet i25*
- j. BWST Outlet Valves 1 90*
- 5. RCS Pressure--Low-Low THIS PAGE OPEN NN3iNG REG!PT OF INFOR,*AATM U.A.'s T.,E APPO_NT
- a. Low Pressure Injection
- 1. Decay Heat Pumps < 30* 4
- 2. Low Pressure Injection Valves 7 NA* T# PC
- 3. D cay Heat Pump Suction Valves
- 4. Decay Heat Cooler Outlet Valves 7 7 NA* 30* M i q
- 5. Decay Heat Cooler Bypass Valves ,
[ NA* %
- b. Component Cooling Isolation Valves
- 1. Auxiliary Equipment Inlet 1 90*
l 2. Inlet to Air Compressor < 90*
l 3. Component Cooling from Decay Heat Cooler 5( )*
l DAVIS-BESSE, UNIT 1 3/4 3-19 l
l JAN 121977 l -.
\ . . . .. .. .- _.- __ ,
TABLE 3.3-5 (Continued) . d SAFETY FEATURES SYSTEM itESPONSE TIMES RESPONSE TIME IN SECONOS INITIATING SIGNAL AND FUNCTION
- 6. Containment Radiation - High
- a. Emergency Vent Fans 1 25* ;
- b. HV & AC Isolation Valves
- 1. ECCS Room < 75*
- 2. Emergency Ventilation 375* (
- 3. Containment Air Sample <
- 4. Containment Purge .
- 5. Penetration Room Purge 1 JW.
- c. Control Room HV & AC Units 1 0*
- 7. Borated Water Storage Tank-Low
- a. Containment Sump Suction Valves 1 S0*
- b. BWST Outlet Valves 1 90*
TAB'LE NOTATION
- Diesel generator starting and sequence loading delays included.
v Response time limit includes movement pump or blower discharge pressure. of valves and attainment of Ip-f*eg #
DAVIS-BESSE, UNIT 1 3/4 3-20' JAN 121977
4, TAR'.E 4.3-2 ,
i .
g SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-CilANNEL MODES'IN WHICH
!n CilANNEL . CliANNEL FUNCTIONAL SURVEILLANCE Ci FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED El '
- 1. INSTRUMENT STRINGS ,
se .
Q a. Containment Radiation - liigh S R H All M00ES
- b. Containment Pressure - liigh
/l S R M( 1, 2, ;
- c. Containment Pressure - liigh-liigh S R M( 1, 2, 3
- d. RCS Pressure - Low S M 1, 2, 3
- e. RCS Pressure - Low-Low S - M 1, 2, 3
- f. BWST Level - Low ,
S R H 1, 2, 3 i
- 2. OUTPUT LOGIC
,gs $wastfm Art ch f le- % Wmj 4
- a. Incident Level #1: Containment y b.
Isolation Incident Level #2: liigh Pressure M %*bU M/ # b5 NA d9fe b'*M Y d'Wh alt MODES ,,
I w Injection and Starting Diesel 3
w c.
Generators Incident i' vel #3: Low Pressure %5 NA M 1, 2, 3 k S d.
Injection Incident Level #4: Containment if NA M 1, 2, 3
- Spray
?)A 5 NA M 1, 2, 3
)[
- e. Incident Level #5: Containment l
Sump Recirculation y .5 NA N 1,2,3
- 3. MANUAL ACTUATION ,
- r. . SFAS (6 cent Containment Spray NA -
NA M(1) All MODES andEmergencySumpRecirculation) h
,:e
- b. Containment Spray NA NA M(1) 1, 2, 3 g
- 4. SEQUENCE LOGIC CilANNELS NA NA M 1, 2, 3 m i ljt5- }( /bue,wu.ty.'e ef #fu:- hfb Rd /day 4%*% & W h e a ,-o aca wa
INSTRUMENTATION STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.2' The Steam and Feedwater Rupture Control System (SFRCS) instrumen ,
tation channels shown in Table 3.3-11 shall be OPERABLE with their trip a setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-12 and with RESPONSE TIMES as shown in Table 3.3-13.
APPLICABILITY: MODES 1, 2 and 3. M MM h, S 2b3 ACTION:
- a. With a SFRCS instrumentation channel trip setpoint less con-servative than the value shown in the Allowable Values column of Table 3.3-12, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-11, until the channel is restored to OPERABLE status wit! t!ie trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With a SFRCS instrumentation channel inoperable, take the action shown in Table 3.3-11.
s SURVEILLANCE REQUIREMENTS 4.3.2.2.1 Each SFRCS instrumentation channel shall be demonstratid OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shown in Table 4.3-11.
4.3.2.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.
4.3.2.2.3 The STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME of each SFRCS function shall be demonstrated to be within the limit at -
least once per 18 months. Each test shall include at least one channel ~2 -
per function such that all channels are tested at least once every N
- times 18 months where N is the total number of redundant channels in a , .
specific SFRCS function as shown in the " Total No. of Channels" Column '*
of Table 3.3-11. S DAVIS-BESSE, UNIT 1 3/4 3-23 .
i JAN 121977
- z. . . - . _
l
f TABLE 3.3-11 (Continued)
STEAM AND FEEDWATER RUPTURE CONTROL SP '
'4STRUMENTATION nn a
h m TOTAL ? CilANNELS MINIMUM CHANNELS ,
c FUNCTIONAL UNIT ,
OF CilANhELS TO TRIP OPERABLE ACTION s 2
U 2. Feedwater/ Steam Generator
" Differential Pressure - liigh Instrument Channels -
- a. PDS 2685A Feedwater/ Steam Generator 2 2 1 2 13 PDS 26858 Feedwater/ Steam Generator 2 ,
- b. PDS 2685C Feedwater/ Steam Generator 2 2 1 2 13 i PDS 2685D Feedwater/ Steam Generator 2
{
$ c. PDS 2686A Feedwater/ Steam Generator 1 2 1 2 13 m PDS 2686B Feedwater/ Steam Generator 1
- d. PDS 2686C Feedwa'ter/ Steam Generator 1 2 1 2 13 PDS 2686D Feedwater/ Steam Generator 1
- 3. Steam Generator
- b. LSL SP9A3 Steam Generator 1 2 l' 2 13 LSL SP9A4 Steam Generator 1 N c. LSLSP9Al/SteamGenerator2 .2 1 2 13
] l LSL SP9A21 Steam Generator 2 , [
g lpf b "M se pp a a
+
~ TABLE 3.3-11 (Continued)
. STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION a
b
.U MINIMUM N
TOTAL N3. CilANNELS CHANNELS FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE ACTION 3 c ,
z '
M 3. Steam Generator
. Level - Low Instrument .
Channels (continued)
- d. LSL SP983 Steam Generator 2 2 1 2 13 4
- -_. LSL SP984 Steam Gener:Lui ?
- 4. Loss of RCP Channels
- a. SFRCS Channel #1 2 1 2 13
- b. SFRCS Channel #2 2 1 2 13
{
"4 5. Manual Initiation m
- a. Steam Pressure - Low 4 4 4 14
- b. Level Steam Generatar - Low 2 2 2 14
- c. Feedwater A P - liigh 2 2 2 14
- d. Loss of RCP's 2 2 2 14 h
==
a :.x3 M
i i - -. -,
_