Public Version of Revised Emergency Plan Implementing Procedures 110-0 Re Station director,110-2 Re Acting Station Director (Shift Engineer) Implementing Procedure & 110-T1 Re RCT Task PrioritizationML20052E318 |
Person / Time |
---|
Site: |
Quad Cities ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
04/15/1982 |
---|
From: |
COMMONWEALTH EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20052E315 |
List: |
---|
References |
---|
PROC-820415-01, NUDOCS 8205100350 |
Download: ML20052E318 (7) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20064G1081994-02-14014 February 1994 Quad-Cities Nuclear Station 1994 Mgt Plan ML20063H8141994-02-11011 February 1994 Revised Procedures,Including Rev 16 to Qep 120-0, Technical Director Index 58 & Rev 3 to Qep 120-T10, Key Point History Listing ML20063F9231994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to ODCM,Quad-Cities Station ML20062J3681993-10-28028 October 1993 Station,Third Ten-Yr Interval IST Plan ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20099B9741992-07-27027 July 1992 Temporary Procedure Secondary Containment Preventative Maint Program ML20102A5971992-07-0202 July 1992 Corrected Chapter 11 to, Environ Radiological Monitoring Table of Contents, Odcm,Revs 0.C & G ML20097G0781992-05-31031 May 1992 Rev 0.G to Odcm,Chapter 11,pages 11-i,11-6,11-9,11-10,11-12 & 11-15 ML20079H0121991-10-0202 October 1991 Tech Spec Upgrade Program ML20082H1951991-08-15015 August 1991 Tech Spec Upgrade Program,Proposed Amend Section 3.4/4.4, 'Standby Liquid Control Sys.' ML20085B5901991-07-29029 July 1991 Tech Spec Upgrade Program ML20082M2261991-04-30030 April 1991 Rev 10 to Quad-Cities Process Control Program for Processing of Radioactive Wet Waste ML20055E8101990-07-0101 July 1990 Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2 ML20029B1981990-04-30030 April 1990 Rev 9 to, Quad-Cities Process Control Program for Processing Radioactive Wet Waste. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20059C7341989-02-28028 February 1989 Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste ML20235N4731989-01-31031 January 1989 Guidelines for Neutron Radioassay Measurements at Quad-Cities Unit One Spent Fuel Storage Pool ML20235N8151988-12-31031 December 1988 Quad-Cities Station Process Control Program for Processing Radioactive Wet Waste ML20235A8921988-07-31031 July 1988 Rev 6 to, Process Control Program for Processing of Radioactive Wet Waste ML20237J8081987-08-31031 August 1987 Rev 0 to Emergency Plan Implementing Procedure EPIP 200-T4, Containment Radiation Time Dependent Correction Factors ML20212H5851987-02-11011 February 1987 Rev 5 to Process Control Program for Processing of Radioactive Wet Waste ML20210E2111986-12-31031 December 1986 General Abnormal Manual ML20203L3551986-04-30030 April 1986 Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor ML20205F5581985-12-31031 December 1985 Rev 11 to Offsite Dose Calculation Manual List of Tables for Quad-Cities Section 7.2 ML20112G4691984-10-31031 October 1984 Inservice Insp & Testing Program,Quad Cities Nuclear Power Station,Units 1 & 2 ML20108A6551984-10-30030 October 1984 Emergency Operating Procedures Generation Package ML20093M6781984-10-0505 October 1984 Suppl 2 to Detailed Control Room Design Review Program Plan ML20087P5611984-03-0202 March 1984 Public Version of Revised Emergency Plan Implementing Procedures QEP-310-O, Notification of Responsible Authorities & QEP-310-T3, Prioritized Notification Listing. W/Jm Felton 840323 Release Memo ML20087Q0641984-01-20020 January 1984 Public Version of Revised Emergency Plan Implementing Procedure Qep 340-7 Re Chemical Spill Cleanup & Qep 520-2 Re Training for Offsite Support Agencies.W/Jm Felton 840326 Release Memo ML20086J6011983-12-19019 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure Qep 200-2 Re Classification of Incident Involving Hazardous Matls & Qep 310-1 Re Initial Notification ML20083J4771983-11-15015 November 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 350-T1, Recommended Protective Actions for Gaseous Release & Qep 350-2, Emergency Drills ML20081B7011983-11-0303 November 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 110-0 Re Station Director & Qep 110-2 Re Acting Station Directory (Shift Engineer).W/Jm Felton Release Memo ML20081L8921983-10-13013 October 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 310-1, Initial Notification & Qep 340-4, Action to Be Taken in Event of Oil Spill to Mississippi River ML20090G7031983-10-0606 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 550-1 Re First Aid & Decontamination Facilities,Qep 550-2 Re Emergency Equipment Inventory & Qep 550-T1 Re Environ Sampling Supplies ML20078M7891983-09-30030 September 1983 Rev 10 to Offsite Dose Calculation Manual for LaSalle & Quad Cities ML20078E8701983-09-0808 September 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 550-0 Re Emergency Equipment & Supplies & Qep 550-T4 Re Emergency Operations Facility Supplies ML20078G0761983-09-0808 September 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 110-2 Re Acting Station Director (Shift Director) & Procedure Qep 310-1 Re Initial Notification ML20078M8091983-08-31031 August 1983 Rev 9 to Offsite Dose Calculation Manual for Braidwood, Consisting of Chapters 7.2 & 8.0 ML20024B9721983-06-30030 June 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 330-0 Re Assessment Actions & Qep 330-11 Re Estimation of I-131 Release by Field Team Measurements.Revised Index Encl ML20085N1321983-06-0707 June 1983 Public Version of Rev 14 to Emergency Plan Implementing Procedures Qep 310-0, Notification of Responsible Authorities & Rev 8 to Qep 310-T3, Prioritized Notification Listing ML20024E1751983-06-0303 June 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 330-0 Re Assessment Actions & Qep 330-11 Re Estimation of I-131 Release by Field Team Measurements ML20081F1401983-05-24024 May 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 200-T1 Re Emergency Action Levels & Qep 310-T3 Re Prioritized Notification Listing ML20024A1901983-05-0404 May 1983 Public Version of Rev 11 to Emergency Plan Implementing Procedure Qep 550-0, Emergency Equipment & Supplies & Rev 5 to Qep 550-T1, Environ Sampling Supplies. Receipt Form Encl ML20069L0021983-04-0404 April 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 160-1 Re Administrative Director,Qep 530-0 Re Exercises & Drills & Qep 200-0 Re Emergency Conditions ML20077B9231983-03-31031 March 1983 Rev 3,to Process Control Program for Solidification of Radwaste 1999-06-30
[Table view] |
Text
..- - - -.
, QEP 110-0
., Rzvision 6 r
. April 1982 ,
ID/1A,1B STATION DIRECTOR
. 110-0 Station Director Rev. 6 04-15-82 l
110-1 Station Director Implementing Procedure Rev. 5 03-19-82 110-2 Acting Station Director (Shift Engineer) Implementing Procedure Rev. 1 04-15-82 j 110-T1 RCT Task Prioritization Rev. 1 04-15-82
(
I b
i APPROVED APR 151982 i
' Q. c. 0. s. R.
O
- l. 8205100350 B20504 (final) l r
PDR ADOCK 05000254 F PDR
(
QEP 110-2 Revision 1
=( ) ' ACTING STATION DIRECTOR (SHIFT ENGINEER)
April 1982 IMPLEMENTING PROCEDURE ID/3T A. PURPOSE The purpose of this procedure is to outline the method to implement the
-GSEP duties of the Acting Station Director (Shift Engineer, or Shift Foreman).
B. REFERENCES
- 1. QEP 200-T1, Emergency Action Leveels (EAL's).
- 2. QEP 200-T2, EAL - Procedure Cross Reference.
- 3. QEP 310-1, Initial Notification.
- 4. QEP 310-T1, Emergency Organization Augmentation.
- 5. QEP 310-T2, NARS Form. -
- 6. QEP 360-2, Plant Evacuation and Assembly.
- 7. QEP 350-T1, Protective Action Guidelines (PAG's).
C. P,REREQUISITES
- 1. None.
D. PRECAUTICNS
- 1. None.
E. LIMITATIONS AND ACTIONS
- 1. A cross-reference is contained In QEP 200-T2 which associates the EAL's with applicable station procedures..
- 2. A preface is contained in front of the QGA and QOA procedure manuals which lists those procedures which relate to GSEP events. The preface instructs the reactor operator to inform the Shift Engineer of a
, condition requiring possible classification as a GSEP event.
F. PROCEDURE
- 1. Classify the event as either a Transportation Accident, Unusual Event,
~ Alert, Site Emergency, or General Emergency using the EAL Table, QFP 200-T1.
APPROVED APR 151982 Q.C.O.S.R.
F~
QEP.110-2 g Revision 1 l
- 2. : Perform notification's as follows:
() a. Transportation Accident: '
(1) Notify System Power Dispatcher, using the 'NARS Form. Fill out as much as possible on the form. Instructions on how to fill out the form are given in step F.3 of this procedure.
(2) Notify On-Call Duty Person to initiate appropriate GSEP Station Group activation. Refer to QEP 310-T1 for notification scheme.
(3) Notify NRC Operations Center using Red Phone. A P P RCh/E D F
(4) Await further GSEP instructions. APR 151982
- b. Unususi Event: Q.C.O.S.R (1) Notify System Power Dispatcher, using the NARS Form. Fill out as much as possible on the form. Instructions on how to fill out the form are given in step F.3 of this procedure.
(2) Notify On-Call Duty Person to initiate appropriate GSEP Station Group activation. Refer to QEP 310-T! for notification scheme.
(3) Notify NRC Operations Center using Red Phone.
(o/ (4) Perform necessary immediate and subsequent corrective actions.
Await further GSEP instructions.
- c. Alert:
(1) Notify System Power Dispatcher, using the NARS Form if Corporate Command Center is not manned. Otherwise, notify the Corporate Command Center. Fill out as much as possible on the NARS Fo rm. Instructions on how to fill out the form are given in step F.3 of this procedure.
(2) Notify On-Call Duty Person to initiate appropriate GSEP Station Group activation. Refer to QEP 310-T1 for notification scheme.
(3) Notify NRC Operations Center using Red Phone.
(4) Perform necessary immediate and subsequent corrective actions.
Await further GSEP instructions.
- d. Site Emergency:
(1) Notify System Power Dispatcher, using .the NARS Form if Corporate Command Center is not manned. Otherwise, notify the Corporate f- - Command Center. Fill out as much as possible on the NARS
\ Fo rm. Instructions on how to fill out the form are given in-step F.3 of this procedure.
j
y QEP 110-2 s Revision 1
.(2) Sound the a'ssembly/ evacuation siren.
() (3) Notify On-Call Duty Person to initiate appropriate CSEP-Station Group activation. Refer to QEP 310-T1 for notification scheme.
(4) Notify NRC Operations Center using Red Phone.
(5) . Perform necessary immediate and subsequent corrective actions.
Await further GSEP instructions.
- e. General Emergency:
(1) Notify System Power Dispatcher, using the NARS Form if Corporate Command Center is not manned. Otherwise, notify the Corporate Command Center. Fill out as much as possible on the NARS Form. Instructions on how to fill out the form are given in step F.3 of this procedure.
(2) Sound the assembly / evacuation siren.
(3) Notify On-Call Duty Person to initiate appropriate GSEP Station Group activation. Refer to QEP 310-T1 for notification scheme.
(4) Notify NRC Operations Center using Red Phone.
/
/- (5) If the Corporate Command Center or the EOF have not been activated notify state and local agencies. Using the NARS (Green) Phone, Dial 23. Notify all parties utilizing the NARS Form.
(6) Perform necessary immediate and subsequent corrective actions.
Await further GSEP instructions.
- 3. NARS Form;
- a. Items 1 through 7 are self-explanatory.
- b. To complete item 8, refer to the Protective Action Guidelines (PAG's) given in QEP 350-T1 and in GSEP Table 6.3 4. 1 (1) For a Transportation Accident, check box A.
(2) For all other GSEP conditions, enter the PAG table with the classification and release situation (item 6). Since projected doses would probably not be available, use the appropriate containment radiation level to determine the recommended '
protective action, and which box to check for item 8.
- c. Item 9 is self-explanatory.
APPROVED g APR 151982 Q.C.O.S.R.
I QEP 110-2 g
Ravision 1
- d. For item 10, only the chimney is an elevated release point.
/ e. Items 11 through 14 are self-explanatory,
- f. Do not fill in item 15.
- g. Items 16 and 17 are self-explanstory.
- h. For a Transportation Accident only, fill in item 18. Item 19 is self-explanatory,
- i. Item 20 should be the Shif t Engineer or his designee at the Station.
J. Item 21 should be the addressee of the message (SPSO, NRC, etc.).
- k. Item 22 may be filled in later.
- 4. Priotitization of Tasks for RCT Personnel: Samples should be obtained in the order listed in QEP 110-T1 if practicable.
G. CHECKLISTS
- 1. None.
H. TECHNICAL SPECIFICATION REFERENCES ~
[ 1. None.
O APPROVED APR 151982
.O q.c o. s. a.
(final)
i n
Os Om u .
QEP 110-Tl Revision 1 ID/3V RCT TASK PRIORITIZATION April 1982 SYMPTOMS SAMPLING TASKS A. liigh Radiation Containment Monitors indicate high Primary A. Containment, Coolant.
Containment Activity. Main Chimney and Reactor Vent Gaseous Effluent Monitors indicate no Increase.
11 . Shift Engineer concludes th-re has been a loss of I or more fission product barriers:
- 1. Cladding Failure. B.I. Coolant, Containment.
- 2. +2 psig Drywell Pressure and -59 inches Vessel Level. B.2. Coolant, containment.
- 3. Loss of Primary Containment. B.3. Containment, Reactor Vent.
C. Indication of Loss of Coolant Accident.
- 1. Inside Containment. C.l. Containment, Coolant.
- 2. Outside Containment. C.2. Reactor Vent, Main Chimney, Coolant.
D. Fuel llandling Accident with damage to irradiated fuel and Refuel Floor ARM > 100 mR/hr.
- 1. Standby Gas Treatment System Operational and D.I. Main, Chimney Secondary Containment Isolation Effective. Reactor Vent.
- 2. Standby Gas. Treatment System not Operational or D.2. Reactor Vent, Secondary Containment Isolation Ineffective. Main Chimney. APPROVED APlLL5.1982
_i_ Q.c.o.s.a.
7 o -
O~ O.
' QEP 110-T1 Revision 1 1
SYMPTOMS SAMPLING TASKS E. Radioactivity Effluent Release from the Plant.
- 1. Gaseous Effluent Release from Main Chimney in excess of E.1. ' Main Chimney.
Technical Specification Instantaneous Release Limit.
- 2. Caseous Effluent Release,from Reactor Vent in excess of E.2. Reactor Vent.
Technical Specification Instantaneous Release Limit.
- 3. Liquid Effluents concentration of gross beta activity E.3. Discharge Hay. '
above background in discharge bay in excess of Technical Specifications.
- 4. Liquid Effluents concentration of Isotopic in the E.4. Discharge Hay.
Discharge Bay in excess of_10 CFR 20 Appendix B Table II, Column 2 MPCm Limits.
A PP R0h/E D APR 151982 q:c.Dm.a.
(final)