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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20202E1611997-12-0101 December 1997 IST Program Third Ten Yr Interval Submittal. W/32 Oversize Drawings ML20211Q1221997-10-14014 October 1997 Rev 22,change 2 to OP-1903.011, Emergency Response Notifications ML20198J8081997-10-14014 October 1997 Rev 28,Permanent Change 2 to Procedure/Work Plan 1903.061, Communications Equipment Tests ML20217K3001997-08-0808 August 1997 Change PC-03,Rev 21 to Work Plan 1903.030, Evacuation ML20151K2241997-07-29029 July 1997 Change PC-01,Rev 6 to OP-1903.035, Adm Potassium Iodide ML20148T0441997-07-0101 July 1997 Change PC-01 to Rev 12 to Procedures OP-1903.067, Emergency Response Facility - Emergency Operations Facility (Eof) ML20148T0221997-07-0101 July 1997 Change AP-06 to Rev 6 to Procedure OP-1903.035, Adm Potassium Iodide ML20148T0051997-07-0101 July 1997 Change PC-01 to Rev 32 to Procedure OP-1903.060, Emergency Supplies & Equipment ML20141C5421997-06-17017 June 1997 2 to Procedure Work Plan 1903.065, Emergency Response Facility Technical Support Center (Tsc) ML20148T5391997-06-0101 June 1997 Rev 0 to Third Ten-Year Interval ISI Plan for ANO Unit 1 ML20140C0951997-03-26026 March 1997 Rev 11,Change AP-11,to OP-1903.034, Emergency Operations Facility Evacuation ML20137D9271997-03-18018 March 1997 Rev 21-04-00,Change PC-04 to OP-1903.011, Emergency Response/Notifications ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20115D8901996-07-10010 July 1996 Permanent Change (Pc) PC-03 to Rev 11 to OP-1903.065, Emergency Response Facility Tsc ML20107G3981996-04-17017 April 1996 Rev 4 to Procedure 1903.053, Logistical Support, Combining Procedures 1903.054 & 1903.078 in W/Procedure 1903.053 & Deleting Procedures 1903.054 & 1903.078 Completely ML20107G4231996-04-17017 April 1996 Rev 4 to Procedure 1903.078, Emergency Response Support, Deleting Procedure.Info from Procedure Incorporated Into Procedure 1903.053, Logistical Support ML20107G4011996-04-17017 April 1996 Rev 6 to Procedure 1903.054, Addl Personnel, Deleting Procedure.Pertinent Info,Instructions & Requirements from Procedure Will Be Incorporated Into Procedure 1903.053, Logistical Support ML20101E3851996-03-13013 March 1996 Rev 15 to OP-1903.062, Communication Sys OP Procedure ML20101E3571996-03-13013 March 1996 Rev 28 to OP-1903.061, Communication Equipment Test ML20101E3771996-03-13013 March 1996 Rev 8 to OP-1903.066, Emergency Response Facility Osc ML20097B2221996-02-0606 February 1996 Change AP-33 to Rev 33 to OP-1903.010, EAL Classification ML20095F9611995-12-0707 December 1995 Permanent Change (Pc) PC-02 to Rev 27 to Procedure/Work Plan OP-1904.002, Offsite Dose Projection Rdacs Computer Method ML20091K8261995-08-28028 August 1995 Change PC-1 to Rev 9 to Procedure/Work Plan 1903.067, Emergency Response Facility - Eof ML20087B6431995-08-0808 August 1995 Rev 27 to Procedure/Work Plan 1904.002, Offsite Dose Projection Rdacs Computer Method ML20086B3901995-07-0505 July 1995 Rev 9 to Procedure/Work Plan 1903.067, Emergency Response Facility - Eof ML20084U7381995-06-13013 June 1995 Page 14 of Rev 20 to Procedure/Work Plan 1903.011, Emergency Response/Notifications ML20084L9881995-05-25025 May 1995 Rev 20 to Procedure/Work Plan 1903.011, Emergency Response/ Notifications ML20097B2201995-05-16016 May 1995 Change PC-2 to Rev 31 to OP-1903.060, Emergency Supply Equipment ML20083Q2961995-05-16016 May 1995 Rev 13 to Procedure/Work Plan 1905.002, Offsite Emergency Monitoring ML20083Q3071995-05-16016 May 1995 Rev 31 to Procedure/Work Plan 1903.060, Emergency Supplies & Equipment ML20083Q2891995-05-16016 May 1995 Rev 6 to Procedure/Work Plan 1903.064, Emergency Response Facility - Cr ML20083L6171995-05-0505 May 1995 Rev 9 to Procedure/Work Plan 1903.034, EOF Evacuation ML20083L6141995-05-0505 May 1995 Rev 4 to Procedure/Work Plan 1905.031, Airborne I-131 Determination Using RM-14.HP-210 ML20083L5941995-05-0505 May 1995 Rev 5 to Procedure/Work Plan 1905.004, EOF Radiological Controls ML20082E2211995-03-31031 March 1995 Rev 1 to Procedure/Work Plan 1903.068, Emergency Response Facility - Emergency News Center ML20081K0331995-03-16016 March 1995 Rev 27 to Procedure/Work Plan 1903.061, Communications Equipment Tests ML20078R0771995-02-0909 February 1995 Rev 21 to Procedure/Work Plan 1903.030, Evacuation ML20078G8921995-01-26026 January 1995 Rev 30 to Procedure/Work Plan 1903.060, Emergency Supplies & Equipment ML20078J1101995-01-13013 January 1995 Public Version of Rev 14 to Operating Procedure 1903.062, Communication Sys Operating Procedure ML20095J6271995-01-0303 January 1995 Permanent Change (Pc) PC-01 to Rev 11 to Procedure/Work Plan OP-1903.065, Emergency Response Facility Tsc 1999-08-04
[Table view] |
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J J gc:= ENTERg ENTERGY OPERATevNS INCORPORATED ARKANSAS NUCLEAR ONE-63 of 79 N M M. REV.
TITLE: REACTOR TRIP 1202.001 25 EXP.DATE SAFETY RELATED ,
[ N/A EVES DNO lh a N 9 CONTROLLED COPY # ,A E 1 o, ,
5DNO PAGE REV CHG PAGE REV CHG' PAGE REV CHG PAGE REV CHG 1 25 fc-i 18 25 2 25 19 25 l i
3 25 20 25 4 25 21 25 5 25 22 25 6 25 23 25 7 25 1 8 25 1
9 25 f 10 25 f'*L .)
VERIFIED BY DATE TIME .
11 25 fE li 12 25 f(-t g 13 25
- 14 25 l
15 25 25 ;
16 i
I 17 25 APPROVAL AUTHORITY: APPROVAL DATE:
s /2/za/9 FORM TITLE:
[ REQUIRED EFFECME DATE: 12 9 4 ~ '
FORM NO. REV.
UST OF AFFECTED PAGES 1000.006A 41 9606030251 960531 PDR ADOCK 05000313 '
S PDH
.p ,w-m,m -e. -am& . -. - eyrw- ~--w-- -
_ _ _ _ _ .. . ._. _ __ . _ . _ .-_. .__ _ _ _ _ _ =
lpc.g 1202 001 REACTOR TRIP RREV 25 PAGE 1 of 23
. ENTRY CONDITIONS e An automatic Rx trip or DSS trip. ,
e Failure of RPS to trip the Rx upon reaching a limit listed below:
I
- High power .......................... 104.9% )
1 High power / pumps .................... one pump per loop . 255% l 9E I O pumps in one loop . 20%
gl - High power / imbalance / flow ........... COLR Figure 9 !
- High RCS temp ...................... 2618 'F(T-hot)
High RCS press ..................... 22355 psig
- Low RCS press ....................... $1800 psig
- va riable low RCS press . . . . . . . . . . . . . . Tech Spec Figure 2. 3-1 High RB press ...................... 218.7 psia
- Turbine trip ........................ Rx power 243% AMD Turbine is tripped
- Both MFW pumps trip ................. Rx power 29% AND both MFW pumps tripped.
- PZR level dropping <100",
AND no indication of recovery.
- Any MSIV closure at power.
-e Either SG level <l5" or >95%,
AMD no indication of recovery.
- A system degradation that requires manual Rx trip based on operator judgment.
- Abnormal operating Procedure requirement.
- Ir a system degradation occurs while shutdown, above DHR operation, THEN perform applicable steps.
l
., .1202.001 REACTOR TRIP REV 25 PAGE 2 of 23 INSTRUCTI0ftS CONTINGEllCY ACTIONS Depress Rx Trip PB.
A. Verify all rods inserted A. Perform the following:
Alf 1) Depress CRD Power Supply Breaker Trip PBs on C03 (A-501 Reactor power dropping. and B-631).
- 2) H A-501 or B-631 fails to trip, IHt! manually insert rods at C03.
a) Dispatch an operator to open CRD AC Power Supply breakers.
- 3) H acre than one rod fails to fully insert 91 Rx power is ag1 dropping, IBt!
perform Energency Boration (RT 12).
Depress Turbine Trip PB.
A. Verify Turbine throttle and A. Perform the following:
governor valves closed.
- 1) II,125 V DC Bus D01 is de-energized as indicated by both of the following, IEEt!
perform Loss of 125V DC (1203.036) " Loss Of Bus D01" section in conjunction with this procedure.
- Breaker position indications on left side of C10 off.
(2. CONTINUED ON NEIT PAGE)
L _.-- ___
k202.001 REA R TRIP RIV 25 PAGE 3 ef 23 InsrRocrI0.s _ C0 r s. cr 4crIO.,
- 2. (Continued).
- 2) H SG press is <900 psig, Iggt!
perform the followings a) Actuate MSLI for affected SG(s)
AEt actuate EFV ARE verify proper actuation and control (RT 6).
b) G0 TO 1202.003, "0VERC00 LING" procedure.
Reduce Letdown by closing Orifice Bypass (CV-1223).
Check adequate SCN. 4. GO TO 1202.002, " LOSS OF SUBC00 LING MARGIN" procedure.
l'
- 5. Advise Shift Superintendent to implement Baergency Action Level Classification (1903.010).
- 6. Check for proper electrical response as follows:
A. Check 125V DC Bus D01 energized: A. Perform Loss of 125V DC (1203.036)
" Loss Of Bus D01" section in
- Turbine Trip Solenoid Power conjunction with this procedure.
Available light lit.
- Breaker position indications available on left side of C10.
B. Perform the following:
B. Check Main Generator and Exciter Pield breakers open.
- 1) H D01 is energized, IEEE manually trip Main Generator and Exciter Field breakers.
(6. CONTINUED ON NEIT PAGE)
_~_
j202001
. REACTOR TRIP- REY 25 PAGE 4 of 23 INSTRUCTI0lts 00lffDGNCY ACTI0ttS
- 6. (Continued).
- 2) H D01 is de-energized, M i leave Main Generator and Exciter Field breakers closed. 1 C. Check DGs off. C. Verify SERV VTR to running DG(s) open: ;
l El M2 !
l CV-3806 CV-3807
)
i D. Check A3 and A4 energized (4160V D. Perform the following for buses).
de-energized bus:
R associated bus'L.O. RELAY l 1)
TRIP alarm is clear on K02 E
associated EDG is running with normal voltage and frequency (4160VAC and 60HZ), M attempt to reset breaker anti-pump feature by taking handsvitch to PULL-TO-LOCK M releasing:
DG1 DG2 l
A-308 A-408 1
l l
l 3
J (6. CONTINUED ON NEIT PAGE)
..' [1202.001 REACTOR TRIP RIV 25 FAGE 5 ef 23 INSTRUCTIONS CONTDIGENCY ACTIONS i
- 6. (Continued). l
' 2) R associated EDG sa n g.1 supply 1 ES bus M .l associated bus L.O. RELAY TRIP' alars is clear on K02 l
.g associated non-vital bus is i energised, IB M attempt to close ES bus normal feeder !
breaker (use SYNC switch): l l
A3 A4 !
A-309 A-409 l
- 3) H all 4160V buses are.
de-energized, IE E GO TO 1202.008, "BIACKottt" procedure. l
- 4) R only EDG power is supplying i 4160V buses, IE E GO TO 1202.007, " DEGRADED POWER" procedure. j (6. CONTINUED ON NEIT PAGE)
,1202.001 REACTOR TRIP REV 25 PAGE 6 cf 23 INSTRUCTIONS - CONTINGENCT ACTIONS
- 6. (Continued).
Check Al and A2 energized (4160V E. Perform the following:
E.
buses).
- 1) H non-vital 4160V bus is needed to power required equipment M
associated bus L.O. RELAY TRIP alarm is clear on K02 M
off-site voltage is normal, M perform the following:
SU1 SU2 222KV 2157KV a) H SUI is available, M energize bus from SUI (use SYNC switch).
(1) IF. non-vital 4E,0V bus feeder breaker fails to close, M attempt to reset breaker anti-pump feature by taking handsvitch to PULL-TO-LOCK M releasing.
(6. CONTI MED ON NEXT PAGE)
1202.001 REACTOR TRIP EEV 25 PAGE 7 ef 23
. INSTRUCTIONS _ CONTDGNCf. ACTIONS
- 6. (Continued).
.........................................a.i
. CAUTION .
- The following step will result in load .;
- shed of non-vital 4160V buses Al and A2..l
...........................................J NOTE SU2 is considered available if all the following conditions are met:
- AUTO I-FMR energized from 500KV
- AUTO I-FMR aligned to SU2
- En Unit 2 buses aligned to SU2 i
- SU2 V REG 3% reduction disabled l b) R SU2 only is available, IgIt[ energize bus from SU2 i (use SYNC switch). j l
(1) H non-vital 4160V bus l feeder breaker fails to close, IEEl[ attempti to reset breaker anti-pump feature by taking handsvitch to t PULL-TO-LOCK AlE releasing.
- 2) H only EDG power is supplying 4160V buses, IIIl[ GO TO 1202.007, " DEGRADED POVER" procedure.
,, .1202.001 REACTOR TRIP REV 25 PAGE 8 of 23 INSTRUCTIONS . 00RTINGENGT 4CTIONS l
- 7. Check OP HPI pump supplying normal 7. Perform the following:
Makeup and Seal Injection.
A. Isolate Letdown by closing either:
Letdown Coolers Outlet (CV-1221) l DE Letdown Cooler Outlets (CV-1214 and ;
I 1216).
B. Restore normal Makeup and Seal i Injection (RT 1). l
- 8. Check both SG 1evels remain $410". 8. Trip both MW pumps Alg), perform the following:
A. Place overfilled SG E W Pump Turbine (K3) Steam Supply valve in MANUAL 4t]R close SG A SG B CV-2667 CV-2617 B. Actuate E W Atg verify proper actuation and control (RT 5).
- 1) H all MW and EW is lost, IEEE GO TO 1202.004, "0VERHEATING" procedure. l C. H SG press is <650 psig, L1EN, trip all Condensate pumps.
- 9. Check Instrument Air Header press >75 9. H Instrument Air Header press drops psig. below 35 psig, IEEE perform the following:
A. Actuate MSLI and E W AHg verify .
proper actuation and control (RT 6).'
B. Perform Loss of Instrument Air (1203.024) " Loss of Instrument Air Pressure (s35 psig)" section in conjunction with this procedure. ,