|
---|
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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
F \
'I/
~
(h 9~p s -
Davis-Besse Nuclear Power Station SP 1104.69 Unit No. 3.
9 System Procedure SP 1104.69 Control Room Emergency Ventilation System
- Procedure E3RSAElR!ED Record of Approval and Changes Prepared by W. Alton 1/1 e / 7A Date Larry C. Stalter 6/18/74 g
Section llend Date 0 2, Recom. ended by v ,1, ru.n . 4 /, a ivr.
SRB Chairnan Date QA Approved flA
- Manager of Quality. Assurance Date Approved by Jack Evans 6/19/74 Station Superintendent Data Revision SRB QA Sta. Supt No. Rec ation Date Approved Date pro- Dat
$ N , /N A/7 2 ,p k= 3 i*h7 pA 7"& ';fl,R 3 p sy>= 3 Th/ ? s- g- W ,
gg y ?hl81 g // 7'o er"= =6 P/>> he P ev'~=g"I""'
S- p, g
,luIn ,yir
(, t 'h I e- er ren 3 nm x 4- - 2 p/# 2 ./s ury 1 mm=D 2p.ipn. T'o'* "' ~ a Plant Manager Appren/al/Dato g _= g O 20 % m p a : - g 9{1l5 5 9
8507300264 050409 PDR ADOCK 05000346 F PDR
- f. .
+
1 SP 1104.69.8
, 1. PURPOSE To provide procedures for operating the Control Room Emergency Ventilation System in the following modes:
Mode Section Startup 4 Shutdown 5 Abnormal Operation 6 The Control Room Emergency Ventilation System consists of two recircula-tion centrifugal fans (3300 CFMs), two dual condenser air cooling units (water cooled and af r cooled), two motor operated fresh air intake dampers, two sets of filter banks (prefilter, high efficiency absolute filter, and charcoal adsorber) and the associated dampers and ductwork.
During normal operar. ion, the Control Room Emergency Ventilation System is held on standby. The system is continuously monitored and alarmed for high control room radiation, motor overload and high
- 8 -
filter-differential pressure. Under normal operating conditions the Control Room will be free of airborne r:dioactivity and high chlorine 1
levels. In the event of high radioactivity after a I,0CA or high chlorine levels after a chlorine leak, the Control Roon Normal
.O Ventilation System is shutdown automatically and the emergency 0 J' ventilation system is initiated manually from the Control Room in a closed complete recirculation mode in which outside air is not introduced by leaving the mini == outside air dampers in the closed position. All Control Roon Normal Ventilation System outside air dampers will automatically close to minimize the dose to operating 8 personnel due to inhalation of fission products or chlorine gas. If the suction air temperature to the CTRM EVS Fans is greater than 75'F, the CTRM EVS condensing units will start.
After the Control Room Emergency Ventilatiou Units have started, the automatic service water valves will open. If flow is received and the service water temperature is between 55 and 85 degrees Fahrenheit, the condensing unit will remain in the water cooled mode; if not, the service water valve will close and the condensing unit will automatically switch to the sir cooled mode.
The Control Room emergency ventilation system filters have a total efficiency not less than 95%, so that the limits of Criterion 19 of 8 10 CFR 50, Appendix A, are met. For habitability considerations (primarily CO2 buildup) after Control Room isolation, fresh air may be introduced into the Control Room by opening the minimum outside air dampers.
- 2. REFERENCES
'1 2.1 Davis-Besse Unit 1 Updated Safety Analysis Report, Section 9.4.1 l -
l l
. .T 4
2 SP 1104.69.8 2.2 Service Water System Procedure, SP 1104.11 . .
2.3 Control Room Ventilation System Procedure, SP 1104.14 2.4 Control Room HV and AC Piping and Instrument Diagram No. M-027A 2.5 480 V MCC (Essential) 'One Line Diagram No. E-6, Sheet 1 of 2 2.6 StanMag Order 24 - Ventilation for painting & welding 8l 2.7 AB 1203.14, Toxic Gas and Liquid Release
- 3. LIMITATIONS AND PRECAUTIONS 3.1 Do not operate the Control Room Emergency Ventilation Fans when the following limits on the filtcr elements are exceeded:
Approximate Control Room EVS Clean D/P Filter 1-1 (1-2 Limit (in H 2O)
Element Local Indicator (in H,0) Not A Limit ,
Prefilter PDI 5295 (PDI 5298) 1.0 ~.15 HEPA Filter PDI 5294 (PDI 5297) 2 ~.5 Charcoal Absorber PDI 5293 (PDI 5296) 1.5 ~.25 3.2 .inenever the Control Room Emergency Cooling System is inop,erable ." l .)
because of failure, repair work progress or routine maintenance on the system, the operator is to turn IL 4809 "CTRM CLNG" on using BS 4709 panel C5717. This light is to remain illuminated as long as the system is inoperaM e.
- 4. STARTUP 4.1 Prerequisites 4.1.1 The Control Room Emergency Ventilaiton System Air Conditioning Units must be lined up for automatic operation as per Enclosure 1.
4.1.2 The Service Water System must be in operation to supply cooling water to the air condition unit as per the Service Water System Procedure, SP 1104.11.
4.1.3 Power must be available to the following breakers and the breakers closed.
- Breaker Panel Equipment i BE1209 MCC E12A CTRM Emer Vent Fan 1-1 BE1216 MCC E12A CTRM Emer A/C Unit 1-1
'BE1232 MCC E12A SW Inlet Valve SW2927 BE1144 MCC E11C Minimum Outside Air Depr HA5261A 1
- 3 SP 1104.69.8
~( *
, BE1148 MCC EllE CTRM Emer Standby A/C Unit 1-1
. BF1149 MCC Fila CTRM Emer Vent Fan 1-2 BF1131 MCC Fila CTRM Emer A/C Unit 1-2 BF1132 MCC Fila SW Inlet Valve SW2928
-BF11A6 MCC F11B Min. Outside Air Dupe HA5262A BF1229 MCC F12A CTRM Emer Standby A/C Unit 1-2
- 3 4.1.4 Close HV 5261 and HV 5262 minimum outside air intake dampers from HIS 5261A and HIS 5262A on Control Room Panel C5720. !
r !
4.2 . Procedure The Control Room Emergency Ventilation System will be started manually using this procedure whenever the Control Roon Normal Ventilation System is shutdown by one of the following signals:
i 1. SFAS Incident Level 1 8l 1
(TS 3.3.3.7) 2. Chlorine Gas Detection (Setpoint <5 ppe by volume)
- 3. High Airborne Radiation (Setpoint as per the Radiation Monitoring setpoint book in the Control Room).
l 4.2.1 Turn the Control Room Emergency Ventilation Unit
! 3 , 1-1 and Unit 1-2 switches on Panel C5720 to START.
(",. Ensure the OFF-MANUAL-AUTO switch on RE5327 and RE5328 are in AUTO and that the radiation monitor for the i respective C.R. EVS inn started with the fan starting.
4.2.2 Check proper operation of the filters by observing that the differential pressure is within the indicated values. (Step 6.3) Listed under Limitations and Precautions, Section 3.1.
8l 4.2.3 If the temperature of Control Roon return air is l greater than 75'F, verify that the Control Room Emergency Air Conditioning Units 1-1 and 1-2 start.
. 8 The unit will start in the water cooled mode. If the service water temperature is between 55 and 85'F the
< condensing unit will remain in the water cooled mode; if not, the service water valve will close and the condensing unit will automatically switch to the air cooled mode. (The water cooled mode is noted by the Service Water Valves SW2927 - Unit 1-1 and SW2928
- Unit 1-2 opening and remaining in the open position.)
l 8' 4.2.4 open the minimum outside air intake when control' Room atmosphere needs replenishment (it is espected that con level will approach its limit within d days of
_ . . - ~ . -- . . -.- _ ,, . ..__;, _- . _ _ . . . . _ .
4 SP 1104.69.8 s
8l isolation). This is accomplished by opening dampers 1 NA 526IA and NA 5262A using the Emergency Ventilation - j Fan 1 and 2 inlet valve switches on Panel C 5720 in l 8 the Control Room. The outside air dampers should be opened periodically for about an hour to change out the air voltane of the Control Room and then close until required again.
I S. SHUTDOWN 1 This procedure will be followed any time the system is to be shutdown. l
_5.1 Shutdown the Control Room Emergency Ventilation System by turning the switches HIS5261 and HISS 262 on Panel C5720 to Stop.
NOTE: With the fans stopped, the air conditioning unit will automatically stop.
5.2 Close the minimum outside air dampers (if open) using the Emergency Ventilation Fan 1-1 and 1-2 Inlet Valve switches "
HIS5261A and HIS5262A on Panel C5720.
5.3 Stop the Radiation Monitor RE 5327 (RE 4323) for Control Room EVS Fan 1-1 (1-2) by turning off the pump at the control monitor.
Ensure the Off-Manual-Auto switch is still in the Auto position. ,,
i
- 6. ABNORMAI OPERATION _?
The following abnormal operations will be discussed.
Section Radiation Alarm 6.1 Motor Overload 6.2 High Filter Differential Pressure 6.3 6.1 Radiation Alarm i
When a high radiation alarm is sensed in the discharge from one of the Control Room Emergency Ventilation Fans, you will receive l an alarm on Computer Point R346 or R347 for Fan 1 or Fan 2 respectively. If the alarm is received on both fans, shutdown the fan with the highest radiation as read on RI5327A, B, and C (Fan 1), and RI5328A, B, and C (Fan 2).
6.2 Motor Overload I
When an overload condition occurs, you will receive a white ;
light on the indicator switch for the fan with the. overload
- - - .e,-
5 SP 1104.69.6 condition. If an overload condition occurs, these fans will not trip; therefore, it is up to the operator to determine whether the fan can be tripped or must remain operating in an emergency situation. These fans can either be tripped from Panel C 5720 or locally.
6.3 High Filter Differential Pressure If the differential pressure across any filter exceeds the limit listed in the Limits and Precautions, Section 3.1, shutdown the respective Control Room Emergency Ventilation Tan (1-1 or 1-2) as per Section 5 of this procedure.
L.
I 1
e s e ee y-- w
--4
6 SP 1104.69.8 Pre-Startup Signoff Sheet /
CONDENSER UNIT 1-1 PANEL C6708
(_'uipment No. Switch Position Verified Hot Gas Solenoid Valve SV4823 HIS4823 Auto Hot Gas Bypass Solenoid Valve SV4823A HIS4823A Auto Liquid Solenoid Valve SV4324 HIS4824 Auto Air Cooled Condenser Selector S61-1 N/A Auto Switch Air Cooled Condenser Fan S61-1 NS0611 Auto PANEL C6706 8l Water Cooled Condenser Local S33-1 NS0331 ON ,
Switch CONSENSER UNIT 1-2 PANEL C6709 Equipment No. Switch Position Verified ,
Hot Gas Solenoid Valve SV4827 HIS4827 Auto Hot Gas Bypass Solenoid Valve SV4827A HIS4827A Auto Liquid Solenoid Valve SV4828 HIS4828 Auto Air Cooled Condenser Selector S61-1 N/A Auto Switch Air Cooled Condenser Fan S61-1 NS0612 Auto PANEL C6707 Water Cooled Condenser Local S33-2 N30332 ON Switch Enclosure 1 Page 1 of 1 i
. 3 9
7 SP 1104.69.8 r
COMMITMEh"rS STEP NO. COMMENTS REFERENCE 4.2.4 USAR Step 9.4.1 Details of required assumptions used in safety analyses.
e l
I
_