ML110060775
| ML110060775 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/26/2010 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S2.OP-AB.RAD-0001(Q), Rev 28 | |
| Download: ML110060775 (25) | |
Text
PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.
SALEM/OPERATIONS S2.OP-AB.RAD-0001(Q) REV. 28 ABNORMAL RADIATION Biennial Review Performed: Yes ____ No ____ NA T DCP Packages and Affected Document Numbers incorporated into this revision: None The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
Incorporated DCP 80057594, RMS Channels 2R5, 2R34, & 2R47 as follows:
[80057594]
C, Updated the Remote Display Location for RMS Channels 2R5, 2R34, 2R45, & 2R47.
IMPLEMENTATION REQUIREMENTS Effective Date:
March 26, 2010 DCP 80057594, RMS Channels 2R5, 2R34, & 2R47
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 1 of 20 Rev. 28 Time Time ABNORMAL RADIATION 1.0 ENTRY CONDITIONS Date: ________ Time: ________
1.1 Any unexpected rise in activity on any Process, Filter, or Area Radiation Monitor.
1.2 Any unexpected warning or alarm on any Process, Filter, or Area Radiation Monitor.
2.0 IMMEDIATE ACTIONS 2.1 None 3.0 SUBSEQUENT ACTIONS
___ 3.1 DETERMINE affected Radiation monitor.
3.2 Is the alarm, warning, or rising indication valid? (EVALUATE the following):
Chem istry Sampling Rising activity on related Radiation Monitors Maintenance activities in vicinity of radiation detector Transfer of radioactive resins or other materials in affected area No indication of failure or fault on affected Radiation Monitor Radioactive release from Salem or Hope Creek NO
___ YES))))>
V GO TO Step 3.5
___ 3.3 NOTIFY SM/CRS to Refer to Event Classification Guide AND PERFORM ACTION REQUIRED in applicable Technical Specifications and ODCM for inoperable Radiation Monitor.
___ 3.4 GO TO Section 4.0
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 2 of 20 Rev. 28 3.5 CONTINUE NOTE, RMS Channel Summary, provides information for monitor locations and functions.
___ 3.6 ANNOUNCE the following on Plant PA system:
Affected Radiation Monitor number and name Location of Radiation Monitor area with elevated indication
___ 3.7 IF a release to the environment is in progress, THEN DIRECT Shift Radiation Protection Technician (SRPT) to complete and provide Page 2 of the Station Status Checklist (SSCL) for release rate determination.
___ 3.8 NOTIFY SM/CRS to REFER TO Event Classification Guide, ODCM and Technical Specifications.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 3 of 20 Rev. 28
___ 3.9 INITIATE the applicable attachment for affected Radiation Monitor:
ATTACHMENT 1 Process Monitor Description Process Monitor Description Process Monitor Description 2R1B-1 Control Room Air Intake Duct (Unit 2 side) 2R15 Condenser Air Ejector 2R37 Non-Rad Liquid Waste Basin 2R1B-2 Control Room Air Intake Duct (Unit 1 side) 2R17A-B Component Cooling Header 21, 22 2R41D Plant Vent Noble Gas Release Rate 2R11A Containment Particulate 2R18 Liquid Waste Disposal 2R45A-D Emergency Plant Vent Background, Medium Range, High Range, Particulate and Iodine 2R12A-B Containment Gas Effluent/Iodine 2R19A-D 21-24 S/G Blowdown 2R46A-D 21-24 Common Discharge, S/G Steam Line Monitors 2R13A-B 21-25 CFCU SW 2R31 Letdown Line -
Failed Fuel 2R53A-D 21-24 N 16 MS Line Rad. Monitors ATTACHMENT 2 ATTACHMENT 3 Process Filter Monitor Description Area Monitor Description Area Monitor Description 2R26 Reactor Coolant Filter 2R1A Control Room 2R10A-B Personnel Airlock 2R40 Condensate Filter 2R2 Containment -
130N Elevation 2R32A Fuel Handling Crane (local) 2R4 Charging Pump Room 2R34 Mechanical Penetration Area -
100N Elevation 2R5 Fuel Handling Building 2R44A Containment Equipment Hatch - 130N Elevation 2R7 Seal Table Area 2R9 Fuel Storage Area 2R44B Stairway to Reactor Sump -
96N Elevation
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 4 of 20 Rev. 28
___ 3.10 When Radiation Monitor indication has returned to normal:
3.10.1 ANNOUNCE on Plant PA System that Radiological conditions have cleared.
3.10.2 RESTORE affected systems to service as available.
3.10.3 RETURN equipment actuated by automatic interlocks to normal operation.
4.0 COMPLETION AND REVIEW
___ 4.1 CIRCLE Entry Condition number in Section 1.0, OR EXPLAIN Entry Condition in COMMENTS Section of Attachment 6.
___ 4.2 COMPLETE Attachment 6, Sections 1.0 and 2.0, AND FORWARD this procedure to SM/CRS for review and approval.
4.3 SM/CRS PERFORM the following:
4.3.1 REVIEW this procedure with Attachments 1 - 4 (as applicable) and for completeness and accuracy.
4.3.2 COMPLETE Attachment 6, Section 3.0.
4.3.3 FORWARD completed procedure to Operations Staff.
END OF PROCEDURE
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 5 of 20 Rev. 28 Time Time ATTACHMENT 1 (Page 1 of 5)
PROCESS RADIATION MONITORS
___ 1.0 IF 2R1B-1 or 2R1B-2, Control Room Intake Duct, is the affected monitor, THEN:
1.1 COORDINATE with Unit 1 NCO to ensure Control Room Ventilation is aligned to ACCIDENT PRESSURIZED mode IAW the following procedures:
S2.OP-SO.CAV-0001(Q), Control Room Ventilation Operation S1.OP-SO.CAV-0001(Q), Control Room Ventilation Operation 1.2 COORDINATE with Radiation Protection to:
SAMPLE intake air to determine the source of elevated activity.
LOCATE AND ISOLATE the source of activity.
___ 2.0 IF any of the following is the affected monitor:
2R11A, Containment Particulate 2R12A, Containment Gas Effluent 2R12B, Containment Gas Effluent-Iodine THEN:
2.1 IF fuel movement is in progress, THEN STOP the fuel movement.
2.2 IF the source of high radiation is due to a fuel handling incident, THEN GO TO S2.OP-AB.FUEL-0001(Q), Fuel Handling Incident.
2.3 IF the Containment Equipment Hatch is open, THEN INITIATE S2.OP-AB.CONT-0001(Q),Containment Closure.
2.4 IF the Containment Equipment Hatch is closed, THEN:
A.
TERMINATE any in-progress Containment Purge IAW S2.OP-SO.WG-0006(Q), Containment Purge to the Plant Vent.
B.
ENSURE 2VC1, 2VC4, 2VC5 AND 2VC6 are CLOSED.
2.5 COORDINATE with Chemistry and Radiation Protection to:
SAMPLE determine the source of elevated activity LOCATE AND ISOLATE source of activity.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 6 of 20 Rev. 28 Time ATTACHMENT 1 (Page 2 of 5)
PROCESS RADIATION MONITORS
___ 3.0 IF 2R13A or 2R13B, CFCU Service Water Monitor(s), is the affected monitor, THEN:
3.1 CLOSE associated SW72 valve for the affected CFCU to determine the source of activity (Isolate one at a time).
2R13A - 21, 22, 23 CFCU 2R13B - 23, 24, 25 CFCU 3.2 STOP affected CFCU(s).
3.3 Send an Operator to DE-ENERGIZE 125VDC Control Power to affected CFCU(s).
3.4 NOTIFY SM/CRS to review applicable Technical Specifications and ODCM.
3.5 NOTIFY Chemistry to sample to determine the source of elevated activity.
___ 4.0 IF 2R17A OR 2R17B is the affected monitor, THEN:
4.1 ENSURE 2CC149, Surge Tank Vent Valve is CLOSED.
4.2 NOTIFY Chemistry to sample Component Cooling, to verify rise in activity.
4.3 IF rise in activity is verified in Component Cooling, THEN GO TO S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak,, to identify the source of inleakage.
___ 5.0 IF 2R18, Liquid Waste Disposal, is the affected monitor, THEN:
5.1 ENSURE 2WL51, TO CIRC WTR DISCHARGE, is CLOSED to stop all Liquid Waste releases.
5.2 TERMINATE Liquid Waste Release procedure in effect.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 7 of 20 Rev. 28 Time Time Time ATTACHMENT 1 (Page 3 of 5)
PROCESS RADIATION MONITORS
___ 6.0 IF 2R19A, 2R19B, 2R19C, or 2R19D (21 - 24 Steam Generator Blowdown Monitors) is the affected monitor, THEN:
6.1 CLOSE the following valves:
2GB50, VALVE FROM 21 SGBT 21-24GB10, FROM 21 THROUGH 24 SG 21-24GB185, FROM 21 THROUGH 24 SG Associated GB4, SG OUTLET 6.2 GO TO S2.OP-AB.SG-0001(Q), Steam Generator Tube Leak.
___ 7.0 IF 2R53A, B, C, or D, 16N MS Line Radiation Monitor, is in alarm, THEN GO TO S2.OP-AB.SG-0001(Q), Steam Generator Tube Leak.
___ 8.0 IF 2R31, Letdown Line-Failed Fuel, is the affected monitor, THEN GO TO S2.OP-AB.RC-0002(Q), High Activity in the Reactor Coolant.
___ 9.0 IF R37, Non-Rad Liquid Waste Basin, is the affected monitor, THEN:
9.1 NOTIFY Chemistry of 2R37 alarm, and the trip of Ground Water Remediation Pumps.
9.2 Direct Chemistry to TERMINATE Non-Rad Liquid Waste discharge.
9.3 IF a release is in progress using Waste Monitor Tank Pumps, THEN TERMINATE release.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 8 of 20 Rev. 28 Time ATTACHMENT 1 (Page 4 of 5)
PROCESS RADIATION MONITORS
___ 10.0 IF 2R41D, Plant Vent Release Rate is the affected monitor, THEN:
10.1 ENSURE 2VC1, 2VC4, 2VC5 AND 2VC6 are CLOSED.
10.2 ENSURE 2WG41, GAS DECAY TK TO PLANT VENT DISCHARGE VALVE, is CLOSED.
10.3 TERMINATE gaseous release IAW appropriate Discharge of Gaseous Waste procedure in effect.
10.4 Is at least one R1B Control Room Intake Duct Radiation Monitor channel (in each Unit intake duct) OPERABLE?
___ NO YES ))))>
V GO TO Step 10.6 10.5 Coordinate with Unit 1 NCO to ALIGN Control Room Ventilation for ACCIDENT PRESSURIZED IAW the following procedures:
S2.OP-SO.CAV-0001(Q), Control Room Ventilation Operation S1.OP-SO.CAV-0001(Q), Control Room Ventilation Operation 10.6 DIRECT the Shift Radiation Protection Technician (SRPT) to COMPLETE dose assessment, every 30 minutes, IAW NC.EP-EP.ZZ-0309(Q),
Dose Assessment, AND PROVIDE Page 2 of the Station Status Checklist (SSCL) for release rate determination.
10.7 OBTAIN release rates every 30 minutes using one of the following:
Release Rates from SSCL, page 2 (ECG Att. 8) (preferred)
, Total Release Rate Calculation
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 9 of 20 Rev. 28 Time ATTACHMENT 1 (Page 5 of 5)
PROCESS RADIATION MONITORS 10.8 PLACE Auxiliary Building HEPA Plus Charcoal in service IAW S2.OP-SO.ABV-0001(Q), Auxiliary Building Ventilation Operation.
10.9 PLACE Fuel Handling Building HEPA Plus Charcoal in service IAW S2.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation Operation.
10.10 COORDINATE with Chemistry and Radiation Protection to:
SAMPLE to determine the source of elevated activity.
LOCATE AND ISOLATE the source of activity.
10.11 RECORD sample results in Control Room Log.
___ 11.0 IF 2R45A, B, C or D is the affected monitor, THEN:
11.1 COORDINATE with Chemistry and Radiation Protection (TSC and OSC if activated) to perform the following as appropriate:
SAMPLE to determine the source of elevated activity LOCATE AND ISOLATE the source of activity OBTAIN R45 skid grab sample
___ 12.0 IF any of the following monitors are affected:
2R15, Condenser Air Ejector Monitor 2R46A, 22 Steam Generator Main Steam Line Monitors 2R46B, 24 Steam Generator Main Steam Line Monitors 2R46C, 21 Steam Generator Main Steam Line Monitors 2R46D, 23 Steam Generator Main Steam Line Monitors THEN GO TO S2.OP-AB.SG-0001(Q), Steam Generator Tube Leak.
___ 13.0 IF any other Process Radiation Monitor (not specifically identified in this Attachment) is affected, THEN COORDINATE with Chemistry and Radiation Protection to:
SAMPLE to determine the source of elevated activity LOCATE AND ISOLATE the source of activity
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 10 of 20 Rev. 28 ATTACHMENT 2 (Page 1 of 1)
PROCESS FILTER RADIATION MONITORS
___ 1.0 NOTIFY Chemistry Department to sample affected filter influent and effluent to determine if filter breakthrough has occurred.
___ 2.0 EVALUATE filter differential pressure to determine if filter overload has occurred.
___ 3.0 Notify Radiation Protection to SURVEY filter.
___ 4.0 INITIATE actions to isolate, flush, or replace filter as necessary.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 11 of 20 Rev. 28 Time ATTACHMENT 3 (Page 1 of 2)
AREA RADIATION MONITORS
___ 1.0 IF 2R1A, Control Room Area, is the affected monitor, THEN:
1.1 Coordinate with Unit 1 NCO to ALIGN Control Room Ventilation for ACCIDENT PRESSURIZED IAW the following procedures:
S2.OP-SO.CAV-0001(Q), Control Room Ventilation Operation S1.OP-SO.CAV-0001(Q), Control Room Ventilation Operation 1.2 Notify Radiation Protection to SURVEY area to determine source of elevated activity.
___ 2.0 IF 2R5, Fuel Handling Building Area Monitor, OR 2R9, Fuel Storage Area Monitor, is the affected monitor, THEN:
2.1 PRESS FHB Ventilation Exhaust Filter HEPA 22 PLUS CHAR pushbutton.
2.2 ENSURE all available Fuel Handling Building Exhaust Fans are running.
2.3 VERIFY HEPA 22 PLUS CHAR and SEQUENCE COMPLETE lights illuminate.
2.4 VERIFY HEPA 21 ONLY and SEQUENCE COMPLETE lights extinguish.
2.5 NOTIFY Radiation Protection to survey the area to determine the source of elevated activity.
2.6 ENSURE a negative pressure is maintained in the Fuel Handling Building IAW S2.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation Operation.
2.7 IF fuel handling is in progress, THEN GO TO S2.OP-AB.FUEL-0001(Q), Fuel Handling Incident.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 12 of 20 Rev. 28 ATTACHMENT 3 (Page 2 of 2)
AREA RADIATION MONITORS NOTE High radiation indicated on 2R32A, Fuel Handling Crane Monitor, will prevent crane hoist UP operation.
Containment radiation levels of $1.0E+5 R/HR indicated on 2R44A or 2R44B inserts ADVERSE CONTAINMENT correction factors into the Subcooling Monitor.
___ 3.0 IF any other Area Radiation Monitor is affected, THEN NOTIFY Radiation Protection to survey the area to determine the source of elevated activity.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 13 of 20 Rev. 28 ATTACHMENT 4 (Page 1 of 3)
TOTAL RELEASE RATE CALCULATIONS 1.0 CALCULATING TOTAL RELEASE RATE NOTE Additional copies of applicable section(s) may be made as necessary to support half-hour calculation requirements.
1.1 IF the following instrumentation is operable:
Radiation Monitor 2R41D Radiation Monitor 1R41D THEN PERFORM Total Release Rate Calculation IAW Section 2.0 of this Attachment.
1.2 IF 1R41D is unavailable, THEN PERFORM Total Release Rate Calculation IAW Section 3.0 of this Attachment.
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 14 of 20 Rev. 28 ATTACHMENT 4 (Page 2 of 3)
TOTAL RELEASE RATE CALCULATIONS Page ___ of ___
2.0 TOTAL RELEASE RATE USING 2R41D AND 1R41D TOTAL RELEASE RATE INITIALS TIME DATE
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R41D)
=
____________ µCi/sec (Total)
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R41D)
=
____________ µCi/sec (Total)
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R41D)
=
____________ µCi/sec (Total)
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R41D)
=
____________ µCi/sec (Total)
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R41D)
=
____________ µCi/sec (Total)
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 15 of 20 Rev. 28 ATTACHMENT 4 (Page 3 of 3)
TOTAL RELEASE RATE CALCULATIONS Page ___ of ___
3.0 ALTERNATE METHOD - TOTAL RELEASE RATE USING 2R41D AND 1R45B/C RELEASE PARAMETERS TOTAL RELEASE RATE INITIALS TIME DATE
( ___________ µCi/sec 2R41D
( ___________ µCi/cc X 472 X __________cfm ) =
1R45B/C Unit 1 Plant Vent Flow Rate
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R45B or C)
= ____________ µCi/sec (Total)
( ___________ µCi/sec 2R41D
( ___________ µCi/cc X 472 X __________cfm ) =
1R45B/C Unit 1 Plant Vent Flow Rate
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R45B or C)
= ____________ µCi/sec (Total)
( ___________ µCi/sec 2R41D
( ___________ µCi/cc X 472 X __________cfm ) =
1R45B/C Unit 1 Plant Vent Flow Rate
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R45B or C)
= ____________ µCi/sec (Total)
( ___________ µCi/sec 2R41D
( ___________ µCi/cc X 472 X __________cfm ) =
1R45B/C Unit 1 Plant Vent Flow Rate
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R45B or C)
= ____________ µCi/sec (Total)
( ___________ µCi/sec 2R41D
( ___________ µCi/cc X 472 X __________cfm ) =
1R45B/C Unit 1 Plant Vent Flow Rate
____________ µCi/sec (2R41D)
+
____________ µCi/sec (1R45B or C)
= ____________ µCi/sec (Total)
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 16 of 20 Rev. 28 ATTACHMENT 5 (Page 1 of 3)
RMS CHANNEL
SUMMARY
CHANNEL DESCRIPTION REMOTE DISPLAY LOCATION LOCAL DISPLAY LOCATION HIGH RAD ACTUATIONS 2R1A Control Room (Area) 2RP1 2RP1 None 2R1B-1 Unit 2 Control Room Duct (Process)
None Align suction to Unit 1 intake and sends start signal to 21 EACS Fan in ACCIDENT PRESSURIZED mode.
2R1B-2 Unit 1 Control Room Duct (Process) 1RP1 Align suction to Unit 2 intake and sends start signal to 12 EACS Fan in ACCIDENT PRESSURIZED mode.
2R2 Containment (Area)
RMS CRT Containment Elev 130N None 2R4 Charging Pumps (Area)
Aux Bldg Elev 84N 2R5 FHB - SFP (Area)
Rack 236C FHB Elev 130N, east wall center of SFP Transfers FHB ventilation to HEPA and Charcoal Filters.
Starts FHB Exhaust Fans.
2R7 In-Core Seal Table (Area)
RMS CRT Containment Elev 100N Energizes warning lights at 100N and 130N airlocks 2R9 FHB - New Fuel Storage (Area)
FHB Elev 130N, east wall center of NFP Transfers FHB ventilation to HEPA and Charcoal Filters.
Starts FHB Exhaust Fans.
2R10A Personnel Hatch - Cntmt Elev 100N (Area)
Containment Elev 100N, by airlock Energizes warning lights at 100N and 130N airlocks 2R10B Personnel Hatch - Cntmt Elev 130N (Area)
Containment Elev 130N, by airlock 2R11A Ctnmt Particulate (Process) 2RP1 Elev 78N Electrical Pen.
Closes 2VC1, 2VC4, 2VC5, AND 2VC6 on fail or Hi Rad 2R12A Ctnmt Noble Gas (Process) 2R12B Ctnmt Iodine (Process) 2R13A 21, 22, 23 CFCU Service Wtr (Process)
Rack 236B Circulating Water Thermal Monitoring Enclosure None 2R13B 23, 24, 25 CFCU Service Wtr (Process) 2R15 Condenser Air Ejector (Process)
Panel 236A Elev 100N TGA, near 23B waterbox 2R17A 21 Component Cooling (Process)
RMS CRT None Closes 2CC149 2R17B 22 Component Cooling (Process) 2R18 Liquid Waste Disposal (Process)
Rack 236B Elev 84N Aux Bldg, near MWT Closes WL51
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 17 of 20 Rev. 28 ATTACHMENT 5 (Page 2 of 3)
RMS CHANNEL
SUMMARY
CHANNEL DESCRIPTION REMOTE DISPLAY LOCATION LOCAL DISPLAY LOCATION HIGH RAD ACTUATIONS 2R19A 21 SG Blowdown (Process) 2RP1 Elev 122N Aux Bldg Warning closes: 21-24GB10 21-24GB185 and 2GB50 Alarm closes: associated GB4 2R19B 22 SG Blowdown (Process) 2R19C 23 SG Blowdown (Process) 2R19D 24 SG Blowdown (Process) 2R26 Reactor Coolant Filter (Process Filter)
Rack 236B Elev 100N Aux Bldg, Demin area None 2R31 Letdown Hx/Failed Fuel (Process)
RMS CRT Elev 84N Aux Bldg, entrance to Letdown Hx room 2R32A Fuel Handling Crane (Area)
None Elev 130N FHB, on Spent Fuel Handling Crane Locks out all crane motion other than downward movement of suspended load 2R34 South Pipe Pen. (Area)
Rack 236C Elev 100N Aux Bldg, near entrance to south Mech. Pen. area None R37 Non-Rad Liquid Waste Basin (Process)
RMS CRT Yard, west end of Non-Radwaste Basin (in transfer house)
Trips Ground Water Remediation System well pumps 2R40 Condensate Filter (Process Filter)
Yard, CPS None 2R41A Plant Vent Noble Gas Low Range 2RP1 Elev 122N Aux Bldg None 2R41B Plant Vent Noble Gas Inter. Range 2R41C Plant Vent Noble Gas High Range 2R41D Plant Vent Release Rate None Alarm: Closes 2VC1, 2VC4, 2VC5, 2VC6 AND 2WG41, also bypasses chem sample flowpath (F-1 Filter) 2R44A Cntmt High Range (Area)
Rack 236A None 2R44B Rack 236B 2R45A Plant Vent Noble Gas
Background
Elev 100N between Aux. Bldg and FHB 2R45B Plant Vent Noble Gas Intermediate Range (Process) 2R45C Plant Vent Noble Gas High Range (Process) 2R45D Plant Vent Filter (Process)
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 18 of 20 Rev. 28 ATTACHMENT 5 (Page 3 of 3)
RMS CHANNEL
SUMMARY
CHANNEL DESCRIPTION REMOTE DISPLAY LOCATION LOCAL DISPLAY LOCATION HIGH RAD ACTUATIONS 2R46A-D Main Steam Line (Process)
Cabinet 158 Elev 100N Aux Bldg, Relay Room None 2R47 Electrical Pen. (Area)
Rack 236C Elev 78N Electrical Pen.
2R52 Liquid PASS Room (Area)
None Elev 100N Aux Bldg, PASS room Energizes warning light outside PASS room 2R53A-D 21 - 24 16N MS Line Rad Monitors 2RP1 Elev 100N Aux Bldg, Relay Room None
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 19 of 20 Rev. 28 ATTACHMENT 6 (Page 1 of 2)
COMPLETION SIGN-OFF SHEET
1.0 COMMENTS
(Include procedure deficiencies and corrective actions. Attach additional pages as necessary.)
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 20 of 20 Rev. 28 ATTACHMENT 6 (Page 2 of 2)
COMPLETION SIGN-OFF SHEET
2.0 SIGNATURES
Print Initials Signature Date 3.0 SM/CRS FINAL REVIEW AND APPROVAL:
This procedure with Attachments 1-4 and 6 is reviewed for completeness and accuracy.
Entry conditions and all deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section above.
Signature: _______________________________________________________
Date:_______
SM/CRS
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 1 of 4 Rev. 28 ABNORMAL RADIATION TECHNICAL BASES DOCUMENT
1.0 REFERENCES
1.1 Technical Documents A.
Updated Final Safety Analysis Report:
Section 9.4, Heating, Ventilation, and Air Conditioning Systems Section 11.4, Radiological Monitoring B.
Technical Specifications - Unit 2:
3.3.3.1, Radiation Monitoring Instrumentation 6.8.4.g, Radioactive Effluent Control Program C.
Salem Nuclear Generating Station Event Classification Guide D.
Emergency Plan:
Section 10, Assessment Section 11, Response Section 12, Exposure E.
Technical/Engineering Letters:
Salem 1 and 2 Core Exit Thermocouple Processing System Technical Manual, 5587-ICE-0527, Rev. 2 Letter from D.L. Branham, Lead Engineer, Radiation Protection/Chemistry Services, 16 October 1991 Letter RMS 92-0019 dated May 22, 1992 from T. Murphy, Project Engineer-RMS to F. Wiltsee, PUP Group Letter to L. Catalfomo, Operations Manager Salem from Craig Bersak, Engineering Analysis Group dated 05/25/95; "Review of operability determination for the single failure concern related to Salem Unit 1 & 2 Control Area Ventilation System as a result of PR 950524316" 1.2 Procedures A.
S1.OP-AB.RAD-0001(Q), Abnormal Radiation B.
S2.OP-AR.ZZ-0001(Q), Overhead Annunciators Window A C.
S2.OP-AR.ZZ-0015(Q), 2RP1 Radiation Alarm Annunciator D.
S2.OP-AR.ZZ-0017(Q), 2RP1 Accident Range Annunciator E.
S2.OP-SO.CAV-0001(Q), Control Area Ventilation System Operation F.
S2.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation System Operation G.
S2.OP-SO.RM-0001(Q), Radiation Monitoring Systems Operation H.
S2.OP-SO.WG-0008(Q), Discharge of No. 21 Gas Decay Tank to the Plant Vent I.
S2.OP-SO.WG-0009(Q), Discharge of No. 22 Gas Decay Tank to the Plant Vent J.
S2.OP-SO.WG-0010(Q), Discharge of No. 23 Gas Decay Tank to the Plant Vent K.
S2.OP-SO.WG-0011(Q), Discharge of No. 24 Gas Decay Tank to the Plant Vent L.
S2.OP-SO.WL-0001(Q), Release of Radioactive Liquid Waste from 21 CVCS MT M.
S2.OP-SO.WL-0002(Q), Release of Radioactive Liquid Waste from 22 CVCS MT N.
S2.OP-SO.WL-0003(Q), Release of Radioactive Liquid Waste from 2 WMHUT
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 2 of 4 Rev. 28 1.3 Drawings A.
203566, 1 & 2 Units Fuel Handling Area Vent. 11, 12, 21 & 22 Exhaust Filter Units B.
205315, 1 & 2 Units Heating Steam & Condensate Return C.
232310, 1 & 2 Units Heating Steam & Condensate Return D.
239077, 1 Unit Radiation Monitoring Gaseous Effluent Discharge E.
239078, 1 Unit Radiation Monitoring Liquid Effluent Discharge F.
239989, 1 & 2 Units Fuel Handling Area Vent. 1 & 2 Supply Units
& 11, 21, 12 & 22 Exhaust Filter Units G.
242772, No. 2 Control Room Recorder Panel 2RP1 1.4 Other A.
Emergency Plan Implementing Procedures:
100 Series, SNSS/EDO Response 300 Series, Radiation Protection Response B.
T/S Amendment 245, Refueling Operations - Relaxation of Requirements Applicable During Movement of Irradiated Fuel C.
DCP 1EC-3505, Control Room Ventilation Modification D.
DCP 1EC-3244, Plant Vent ADP Change Out E.
DCP 2EC-3212, Radiation Monitor 2R41D skid F.
DCP 2EC-3265, Removal of Radiation Monitors 2R35 and 2R38 G.
DCP 2EC-3449, Main Steam Line N16 Detectors H.
DCP 2EC-3559, FHA Ventilation Exhaust Fans Interlock With Radiation Monitors I.
DCP 80004831, 2R24A, 2R24B, 2R25, 2R28, 2R29, 2R30 and 2R33 Removal J.
DCP 80005320, 2R42A-D and 2R27 Removal K.
DCP 80030824, Deletion of RMS Channel 1R16 L.
DCP 80045432, Deletion of RMS Channel 2R16 M.
DCP 80045601 Rev. 0, AD P11 Rev. 0, RMS Channel 2R15 Replacement N.
DCP 80057146, 2R36 Removal O.
DCP 80057503, 2R1A & 2R11/12 Mod to P250 & Annunciator P.
DCP 80057587 Rev. 0, AD P31 Rev. 0, RMS Channel 2R46 Upgrade Q.
DCP 80057593, Relocate 2R44B to new Cab 236B R.
DCP 80057594, Relocate 2R45 to new Cab 236C / 2R5, 2R34, 2R47 Upgrade S.
DCP 80073267, Ground Water Remediation T.
DCP 80059614, 2R13 Radiation Monitor Replacement / Relocation 1.5 Conformance Documents None
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 3 of 4 Rev. 28 2.0 DISCUSSION 2.1 This procedure provides the direction necessary for recognizing and mitigating abnormal radiological events. This discussion provides the reasoning behind procedure logic and flowpath. This discussion is not intended to provide additional direction.
2.2 Entry Conditions - Entry conditions are based on the Operator receiving one or more alarms associated with radiation monitoring, or detection of an abnormal rise in indication on a radiation monitor. The Radiation Monitoring System is divided into three main subsystems: Process Monitoring, Area Monitoring, and Process Filter Monitoring.
The Process Monitoring System continuously samples and analyzes systems which have potential to cause uncontrolled or unmonitored releases to the environment, or would indicate a failure of a major boundary between radioactive materials and non-radioactive systems. Included with Process Monitors are Attachments 4 and 5 for determining release rates to the environment to aid in event classification.
The Area Monitoring System continuously monitors radiation levels in numerous areas throughout the plant to rapidly detect any changes in local radiological conditions. These changes may be due to various events including local maintenance activities, or transfer of radioactive materials, such as resin flushes or movement of tools, waste, or equipment.
Changes may also indicate fuel failure with the transport of highly activated material through piping systems.
The Process Filter Monitoring System continuously monitors the Condensate Polishing System Filter and Reactor Coolant Filter installed in plant systems to indicate system malfunctions or filter depletion.
The following alarms are installed to alert the Operator of Abnormal Radiological conditions:
OHA-A6, RMS HI RAD OR TRBL 2RP1-A3, RADIATION ALARM AREA 2RP1-A4, RADIATION ALARM FILTER 2RP1-A5, RMS TEST/LOCAL 2RP1-A7, RADIATION ALARM PROCESS In addition to alarms, the Operator may be alerted to abnormal Radiological conditions by any of the following:
Radiation Monitor Recorder located on Control Room panel 2RP1 Indications on Control Room Radiation Monitor Computer Reports or local observation by plant personnel Reports of survey or sample results by Chemistry or Radiation Protection personnel Process Computer RMS Readings
S2.OP-AB.RAD-0001(Q)
Salem 2 Page 4 of 4 Rev. 28 2.3 Immediate Actions None 2.4 Subsequent Actions - The Operator initially determines the affected Radiation Monitor and verifies the validity of the alarm or rising indication. If the instrument proves to be inoperable, the Operator is directed to refer to appropriate Technical Specification and ODCM requiring operable Radiation Monitoring System.
If a valid warning, alarm, or rise in indication occurs, the Operator is directed to:
Notify plant personnel of the affected area to minimize exposure Refer to Technical Specifications and Event Classification Guide Initiate applicable Attachment for affected monitor Each Attachment contains actions and information pertinent to the affected radiation monitor, including verification of interlocks and required actions. Action is taken to notify Chemistry and Radiation Protection personnel to assist Operators in locating and correcting the source of the problem.
When required actions have been performed, and all abnormal Radiological conditions are cleared, the Operator completes administrative requirements for procedure use and resumes normal operation.
2.5 The methodology used in this procedure for calculation of noble gas release rates is the same used in the SPDS computer software. Digital Systems Group (DSG) controls SPDS software, therefore procedure methodology changes require coordination with DSG.
END OF DOCUMENT