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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20199D0391999-01-13013 January 1999 Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2801999-01-11011 January 1999 Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons ML20198L6211998-12-31031 December 1998 Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation ML20198G4001998-12-22022 December 1998 Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE ML20196H9321998-12-0404 December 1998 Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate ML20195J9021998-11-23023 November 1998 Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9551998-11-23023 November 1998 Proposed Tech Specs Re Turbine Missile Protection ML20155B8741998-10-20020 October 1998 Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal ML20154J2991998-10-0909 October 1998 Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B ML20153G7511998-09-22022 September 1998 Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6801998-09-10010 September 1998 Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6561998-09-0404 September 1998 Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances ML20236S6241998-07-22022 July 1998 Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO ML20249B4291998-06-19019 June 1998 Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels ML20216B6201998-05-11011 May 1998 Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B ML20216B4141998-05-0707 May 1998 Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8471998-04-0606 April 1998 Proposed Tech Specs Revising Containment Isolation Valves Completion Times ML20216C0051998-03-0606 March 1998 Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1 ML20199K6451998-02-0303 February 1998 Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program ML20198H8511998-01-0909 January 1998 Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train ML20198H6881998-01-0909 January 1998 Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks ML20198H7601998-01-0909 January 1998 Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time ML20198E6051998-01-0202 January 1998 Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing ML20197C7281997-12-19019 December 1997 Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability ML20199C6391997-11-14014 November 1997 Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20148R4051997-06-30030 June 1997 Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11 ML20141B4481997-06-18018 June 1997 Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions ML20198R0281997-05-30030 May 1997 Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 ML20137V2501997-04-15015 April 1997 Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing ML20134P9941997-02-21021 February 1997 Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20138L1151997-02-18018 February 1997 Proposed Tech Specs Defering Implementation of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation, for 30 Subgroup Relays Until Next Refueling Outage on Songs,Unit 3 ML20134M0831997-02-16016 February 1997 Proposed Tech Specs Re Requirements of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20134J6991997-02-0707 February 1997 Proposed Tech Specs SR 3.1.5.4, CEA Alignment ML20134G7911997-02-0606 February 1997 Proposed Tech Specs 3.1.5, CEA Alignment ML20134A9911997-01-24024 January 1997 Proposed Tech Specs Revising SR 3.8.1.9 to TS 3.8.1, AC Sources - Operating, Which More Accurately Reflects Safety Analysis Conditions ML20133G9101997-01-14014 January 1997 Proposed Tech Specs 3.8.1.14 & 3.8.1.15, AC Sources - Operating, Surveillance Requirements ML20133F7741997-01-13013 January 1997 Proposed Tech Specs Providing Followup to Request for Discretionary Enforcement from SR 3.0.3 Requirements Delaying Implementation of SR 3.8.1.14 & 3.8.1.15 of TS 3.8.1,until NRC Approves Revs ML20128P3631996-10-11011 October 1996 Proposed Tech Specs Reinstating Provisions of TS Revised as Part of Amends 127 & 116 ML20117K9931996-08-30030 August 1996 Proposed Tech Specs,Clarifying Figures 3.7.18-1 & 3.7.18-2 by Adding Line at 4.8 W/O Initial U-235 Enrichment to Explicity Show That Acceptable Zone of Operation Ends at Maximum of 4.8 W/O ML20116C6801996-07-29029 July 1996 Proposed Tech Specs,Consisting of Change Request 443, Permitting Increase in Licensed Storage Capacity of Spent Fuel Pools,By Allowing Spent Fuel to Be Consolidated After Min Required Time in SFPs ML20113C2561996-06-25025 June 1996 Proposed Tech Specs,Revising TS 3.3.11, Pami, & 5.5.2.13, Diesel Fuel Oil Testing Program ML20117L0611996-06-11011 June 1996 Revised Proposed Tech Specs Re LCO 3.3.11, Post Accident Monitoring Instrumentation (Pami) ML20112D4611996-06-0303 June 1996 Proposed Tech Specs,Reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116 ML20117J8391996-05-30030 May 1996 Proposed Tech Specs,Consisting of Change Number 164, Requesting Changes to SR 3.6.1.1,SR 3.6.2.1 & SR 3.6.3.6 Which Allows Implementation of Option B to 10CFR50,App J ML20112D0351996-05-29029 May 1996 Approved Tech Specs,Amends 127 & 116 & Proposed TS for Units 2 & 3 1999-08-09
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20199D0391999-01-13013 January 1999 Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2801999-01-11011 January 1999 Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons ML20198L6211998-12-31031 December 1998 Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation ML20198L5111998-12-23023 December 1998 Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description ML20198G4001998-12-22022 December 1998 Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE ML20196H9321998-12-0404 December 1998 Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate ML20195J9021998-11-23023 November 1998 Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9551998-11-23023 November 1998 Proposed Tech Specs Re Turbine Missile Protection ML20155B8741998-10-20020 October 1998 Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal ML20154J2991998-10-0909 October 1998 Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B ML20153G7511998-09-22022 September 1998 Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6801998-09-10010 September 1998 Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6561998-09-0404 September 1998 Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances ML20206N5381998-08-12012 August 1998 Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122 ML20236S6241998-07-22022 July 1998 Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO ML20249B4291998-06-19019 June 1998 Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels ML20216B6201998-05-11011 May 1998 Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B ML20216B4141998-05-0707 May 1998 Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8471998-04-0606 April 1998 Proposed Tech Specs Revising Containment Isolation Valves Completion Times ML20206N5231998-03-16016 March 1998 Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions ML20216C0051998-03-0606 March 1998 Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1 ML20206E6001998-02-27027 February 1998 Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm ML20199K6451998-02-0303 February 1998 Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program ML20206N5021998-01-30030 January 1998 Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64 ML20198H8511998-01-0909 January 1998 Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train ML20198H7601998-01-0909 January 1998 Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time ML20198H6881998-01-0909 January 1998 Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks ML20198E6051998-01-0202 January 1998 Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing ML20197C7281997-12-19019 December 1997 Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability ML20199C6391997-11-14014 November 1997 Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20198P4011997-10-31031 October 1997 Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan ML20217K0081997-10-16016 October 1997 Rev 1 to Evaluation of SONGS Unit 3 SG Eggcrate Support Condition-Cycle 9 ML20203E1201997-09-11011 September 1997 Rev 1 to S-PENG-DR-003, Addendum to Piping Analytical Stress Rept for SCE San Onofre Units 2 & 3. W/Memo from C Chiu to Jt Reilly Re Corrective Action for Unit 3 Pressurizer Nozzle Failure in Mar 1986 ML20203D8421997-08-28028 August 1997 Rev 1 to S-PENG-DR-002, Addendum to Pressurizer Analytical Stress Rept for SCE San Onofre Units 2 & 3 ML20203D8981997-07-0303 July 1997 Rev 0 to TR-PENG-042, Test Rept for Mnsa Hydrostatic & Thermal Cycle Tests ML20203D8761997-07-0202 July 1997 Rev 0 to TR-PENG-033, Seismic Qualification of San Onofre, Units 2 & 3 Mnsa Clamps for Pressurizer Instrument Nozzles & RTD Hot Leg Nozzles ML20148R4051997-06-30030 June 1997 Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11 ML20141B4481997-06-18018 June 1997 Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions ML20198R0281997-05-30030 May 1997 Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 ML20217P9981997-05-28028 May 1997 Rev 30 to SONGS Unit 2 & 3, Odcm ML20137V2501997-04-15015 April 1997 Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing ML20134P9941997-02-21021 February 1997 Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation 1999-08-09
[Table view] |
Text
_ __ _ _ .. . . _ -. . . _ _. ._- . . .
un
~
o 8
- TABLE 3.3-4 (Continued) 7 g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRav VALUES h,,4 ~N gul.
ALLOWABLE ;
M FUNCTIONAL UNIT TRIP VALUE VALUES DU go 9. CONTROL ROOM ISOLATION (CRIS) no N. a. Manual CRIS (Trip Buttons) Not Applicable Not Applicable
- 04 e b. Manual SIAS (Trip Buttons) Not Applicable Not Applicable
,0U ggM c. Airborne Radiation
- w g i. Particulate / Iodine 5 5.7 x 104 cpm ** 5 6.0 x 104 cpm **
' ii. Gaseous 5 3.8 x 102 cpm ** 5 4.0 x 10 .2 cpm an
- d. Autsnatic Actuation Logic Not Applicable Not Applicable
- 10. T0XIC GAS ISOLATION (TGIS) ,
- a. Manual (Trip Buttons) Not Applicable Not Applicable
- b. Chlorine - High 5 14.3 ppm 5 15.0 ppm
- c. Ammonia - High 5 97 ppm $ 100 ppm ,
- d. Butane / Propane - High $ 193 ppm 5 200 ppm h e. Automatic Actuation Logic Not Applicable Not Applicable a an .
6o 4=
5k
.g :
_ _ _ _ . _ _ . _ . . - . . . _ - ~ _ . . _
TABLE 3.3-4 (Continued) 1 TABLE NOTATION (1) Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer press.ure is reduced, provided the margin between the pressurizer and this value is maintained at less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.
Trips may be bypassed when pressurizer pressure is < 400 psia. Bypass shall be automatically removed before pressurizer pressure exceeds 500 psia (the corresponding bistable allowable alue is 5 472 psia).
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(3) % of the distance between steam generator upper and lower level ,
instrument nozzles. ,
(4) Deleted.
(5) Actuated equipment only; does not result in CIAS.
(6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur.
(7) Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 2RT-7804-1 shall be determined by the ODCH.
(8) The trip setpoint shall be set sufficiently high to prevent spurious alann/ trips yet sufficiently low to assure an alarm / trip should a fuel handling accident occur.
l l
- Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
SAN ON0FRE-UNIT 2 3/4 3-26 Amendment No. 120
" ATTACHMENT "B" EXISTING SPECIFICATIONS UNIT 3 1
l i
i
s TABLE 3.3-4 (Continued)
Y Z
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES E
a A ALLOWABLE a FUNCTIONAL UNIT TRIP VALUE VALUES 5
- 9. CONTROL ROOM ISOLATION (CRIS)
- a. Manual CRIS (Trip Buttons) Not Applicable Not Applicable
] b. Manual SIAS (Trip Buttons) Not Applicable . Not Applicable
'i
- c. Airborne Radiation
- i. Particulate / Iodine 1 5.7 x_104 cpm ** 1 6.0 x 104 cym**
ii. Gaseous 1 3.8 x 102 cpm ** $ 4.0 x 102 cpm **
w d. Automatic Actuation Logic Not Applicable Not Applicable E
- 10. T0XIC GAS ISOLATION (TGIS) i
- a. Manual (Trip Buttons) ,Not Applicable Not Applicable
- b. Chlorine - High 1 14.3 ppm i 15.0 ppm
- c. Ammonia - High 5 97 ppm 1,100 ppm '
- d. Butane / Propane - High 5 193 ppm i 200 ppe
- e. Automatic Actuation Logic Not Applicable Not Applicable D
E c_-
h
,z ,
m o e
m s -
02
. l TABLE 3.3-4 (Continued)
TABLE NOTATION (1) Value may be decreased manually to a minimum of greater than or equal to 300 psia, as pressurizer pressur,e .is reduced, provided the margin between the pressurizer and this value is maintained at less than or equal to l 400 psia;* the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trips may be bypassed when pressurizer pressure is < 400 psia. Bypass shall be automatically removed before
)ressurizer pressure exceeds 500 psia (the corresponding bistable allowa)le value is s 472 psia).
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as 4 steam generator pressure is increased until the trip setpoint is reached.
-(3) % of the distance between steam generator upper and lower level instrument nozzles.
(4) Deleted.
(5) Actuated equipment only; does not result in CIAS.
(6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur. -
(7) Prior to the completion of DCP 53N, the setpoints for Containment Airbaine Radiation Monitor 3RT-7804-1 shall be determined by the ODCH. l (8) The trip setpoint shall be set sufficiently high to prevent spurious 1 alarm / trips handling yet sufficiently accident occur. low to assure an alarm / trip should a fuel
- Variable setpoints are for use only during normal _, controlled plant heatups and cooldowns.
j
i l
SAN ONOFRE - UNIT 3 3/4 3-26 Amendment No. 45,107,109
k l
l l
" ATTACHMENT "C" )
PROPOSED SPECIFICATIONS UNIT 2
. TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES g ALLOWABLE
, q FUNCTIONAL UNIT TRIP VALUE VALUES
- 9. CONTROL ROOM ISOLATION (CRIS)
- a. Manual CRIS (Trip Buttons) Not Applicable Not Applicable
- b. Manual SIAS (Trip Buttons) Not Applicable Not Applicable
- c. Control? Room Airborne Radiation lN R i. Particulate / Iodine s 5.7 x 10' cpm ** s 6.0 x 10" cpm *'
a l *p ii. Gaseous 2 s 3.8 x 10 cpm s 4.0 x 102 cpm l g.1 gal %L l N
- d. Automatic Actuation Logic Not Applicable Not Applicable
- 10. T0XIC GAS ISOLATION (TGIS) ;
I
! a. Manual (Trip Buttons) Not Applicable Not Applicable
- b. Chlorine - High 5 14.3 ppm 5 15.0 ppm
- c. Ammonia - High 5 97 ppm s 100 ppm
- d. Butane / Propane - High 5 193 ppm 5 200 ppm k e. Automatic Actuation Logic Not Applicable Not Applicable "i
5
- TABLE 3.3-4 (Continued)
TABLE NOTATIO!!
(1) Value may be decreased manually, to a minimum of greater than or equal i to 300 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer and this value is maintained at less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.
Trips may be bypassed when pressurizer pressure is < 400 psia. Bypass shall be automatically removed before pressurizer pressure exceeds l
500 psia (the corresponding bistable allowable value is 5 472 psia).
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator, pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
1 (3) % of the distance between steam generator upper and lower level instrument nozzles.
(4) Deleted.
(5) Actuated equipment only; does not result in CIAS. ,
(6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an i inadvertent release occur. '
(7) Prior to the completion of DCP 53N, the setpcints for Containment FM Akborne Radiation Monitor 2RT 78041 shall be determined by the 00CM.
Deleted. l rn6Mp
.1 (8) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should a fuel handling accident occur.
- Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
SAN ONOFRE - UNIT 2 3/4 3-26 AMENDMENT NO.
I l
l l
ATTACHMENT "D" !
1 PROPOSED SPECIFICATIONS UNIT 3 l
l 1
l l
I
l l g TABLE 3.3-4 (Continued) g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES 2m
. ALLOWABLE c= FUNCTIONAL UNIT TRIP VALUE VALUES l
- 9. CONTROL ROOM ISOLATION (CRIS)
[
- a. Manual CRIS (Trip Buttons) Not Applicable Not Applicable
- b. Manual SIAS (Trip Buttons) Not Applicable Not Applicable
- c. Control;; Room Airborne Radiation yg W%
-I
- i. Particulate / Iodine s 5.7 x 10' cpm 5 6.0 x 10' cpm **
w 2 ii. Gaseous s 3.8 x 102 cpm 5 4.0 x 102 cpm
' Icd'JW
- d. Automatic Actuation Logic Not Applicable Not Applicable
- 10. T0XIC GAS ISOLATION (TGIS)
- a. Manual (Trip Buttons) Not Applicable Not Applicable
- b. Chlorine - High s 14.3 ppm 5 15.0 ppm
- c. Ammonia - High 5 97 ppm s 100 ppm
- d. Butane / Propane - High 5 193 ppm s 200 ppm E
g e. Automatic Actuation Logic Not Applicable Not Applicable E
9 5
1 TABLE 3.3-4 (Continued)
TABLE NOTATION (1) Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer and this value is maintained at less than or equal to 400 psia; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trips may be bypassed when pressurizer pressure is < 400 psia. Bypass shall be automatically removed before pressurizer pressure exceeds 500 psia (the corresponding bistable allowable value is 5 472 psia).
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator, pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(3) % of the distance between steam generator upper and lower level l instrument nozzles. l (4) Deleted.
(5) Actuated equipment only; does not result in CIAS.
(6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur.
(7) Prior to the completion of DCP 53N, the :ctpcint: for Containment
,m u__,, ,a o,.m.s :..-.u...,4.+_.,.
. . _.. . . n, v. .e n. a, i. u. ., n. . u_
.. -- .a_+. m.
a n .,, ...m
- u. - nn
. .c u. . f k l (8) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should a fuel handling accident occur.
- Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
SAN ONOFRE - UNIT 3 3/4 3-26 AMENDMENT NO.
ATTACHMENT "E" ,
1 POST PCN-299 (TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM) SPECIFICATIONS .
UNIT 2
CRIS 3.3.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.9.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required CRIS radiation monitor channel.
Verify CRIS high radiation setpoint is
! 5 4E2 cpm above normal background.
I i
SR 3.3.9.3 -------------------NOTE-------------------
Surveillance of Actuation Logic shall include the verification of the proper operation of each initiation relay.
4 e
a Perform a CHANNEL FUNCTIONAL TEST on 18 months required CRIS Actuation Logic channel.
l SR 3.3.9.4 Perform a CHANNEL CALIBRATION on required 18 months l
CRIS radiation monitor channel.
. SR 3.3.9.5 Perform a CHANNEL FUNCTIONAL TEST on 18 months l required CRIS Manual Trip channel.
1 j
I L
a j
i i
SAN ONOFRE--UNIT 2 3.3-41 AMENDMENT NO.
I
ATTACHMENT "F" POST PCN-299 (TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM) SPECIFICATIONS UNIT 3
'CRIS 3.3.9 ,
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SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY 1
! SR 3.3.9.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required CRIS radiation monitor channel, i
l Verify CRIS high radiation setpoint is
- 5 4E2 cpm above normal background, t
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- SR 3.3.9.3 -------------------NOTE-------------------
2 Surveillance of Actuation Logic shall include the verification of the proper
, operation of each initiation relay.
i Perform a CHANNEL FUNCTIONAL TEST on 18 months
{ required CRIS Actuation Logic channel.
1 j' SR 3.3.9.4 Perform a CHANNEL CALIBRATION on required 18 months CRIS radiation monitor channel.
i SR 3.3.9.5 Perform a CHANNEL FUNCTIONAL TEST on 18 months
! required CRIS Manual Trip channel.
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j SAN ONOFRE--UNIT 3 3.3-41 AMENDMENT NO.
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ATTACHMENT "G" PROPOSED SPECIFICATIONS Unit 2 l
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- CRIS 3.3.9
- SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY 4
SR 3.3.9.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required CRIS airborne radiation monitor l gc,g-Y73
, channel.
Verify CRIS high radiation setpoint is N 5 4E2 cpm above normal background. Sy A i
i SR 3.3.9.3 -------------------NOTE-------------------
Surveillance of Actuation Logic shall
. include the verification of the proper operation of each initiation relay.
h Perform a CHANNEL FUNCTIONAL TEST on 18 months required CRIS Actuation Logic channel.
3.3.9.4 Perform a CHANNEL CALIBRATION on required 18 months SR CRIS airborne radiation monitor channel. Ig y$P j SR 3.3.9.5 Perform a CHANNEL FUNCTIONAL TEST on 18 months required CRIS Manual Trip channel.
l SAN ON0FRE--UNIT 2 3.3-41 AMENDMENT NO.
ATTACHMENT "H" PROPOSED SPECIFICATIONS Unit 3 l
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CRIS i 3.3.9 i SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.9.2 Perform a CHANNEL FUNCTI0ilAL TEST on 92 days required CRIS airb~orne~ radiation monitor channel.
lf4byp Verify CRIS high* radiation setpoint is 5 4E2 cpm above normal background.
N
- g. i SR 3.3.9.3 -------------------NOTE-------------------
Surveillance of Actuation Logic shall include the verification of the proper operation of each initiation relay.
Perform a CHANNEL FUNCTIONAL TEST on 18 months required CRIS Actuation Logic channel.
SR 3.3.9.4 Perform a CHANNEL CALIBRATION on required 18 months CRIS ' airborne radiation monitor channel. lfggy i SR 3.3.9.5 Perform a CHANNEL FUNCTIONAL TEST on 18 months l required CRIS Manual Trip channel. l l
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l SAN ONOFRE--UNIT 3 3.3-41 AMENDMENT N0.
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