ML021480507
| ML021480507 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/10/2002 |
| From: | Mcelrath J, Shewmaker T Consumers Energy |
| To: | Mcknight J Office of Nuclear Reactor Regulation |
| References | |
| EI-7.0, Rev 7 | |
| Download: ML021480507 (25) | |
Text
Date Entered: May 10, 2002 TO:
USNRC/WASHINGTON JMCKNIGHT Copy Number:
145 TRANSMITAL NUBR 21 6849 PROCEDURE NUMBER: EI-7.0 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.
Action Required Section or Description REMOVE AND DESTROY EI-7.0, R/6, ENTIRE PROCEDURE REPLACE WITH EI-7.0, R/7, ENTIRE PROCEDURE SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENT FORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL.
SIGNATURE OR INITIALS DATE Ak0115
Procedure No EI-7.0 Revision 7 Issued Date 5/10/02 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES rocedurq;ponsor JWMcElrath Technical Reviewer TEShewmaker User Reviewer Date
/ 3/20/02 Date
/ 3/27/02 Date
PALISADES NUCLEAR PLANT Proc No EI-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revision 7 Page i TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES Table of Contents PERSONNEL RESPONSIBILITY 1
PU RPO SE.....................................
REFERENCES...................................
3.1 SOURCE DOCUMENTS.....................
3.2 REFERENCE DOCUMENTS...................
INITIAL CONDITIONS AND/OR REQUIREMENTS 4.1 PRELIMINARY INDICATORS..................
4.2 PRELIMINARY DOSE RATE SURVEYS...........
PRO CEDURE...................................
5.1 PRIMARY COOLANT SYSTEM SAMPLE LINE RECIRCULATION FOR FAILED FUEL CLASSIFICATION 5.2 SUBSEQUENT POST ACCIDENT SAMPLING ATTACHMENTS AND RECORDS.....................
6.1 ATTACHMENTS..........................
6.2 RECO RDS..............................
1.0 2.0 3.0 4.0 5.0 6.0 7.0 1
1 1
2 2
3 4
5
.......... 5
............ 8
............. 9
............ 9
............ 9
................ 10 ATTACHMENTS, "Jumpering CV-1910 and CV-1911 for PCS Sample or Sample Line Flush", "Primary Coolant System Sample Line Flush and PCS Sampling", "NSSS Sample Panel Piping Dose Rates" SPECIAL REVIEWS...
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-7.0 Revision 7 Page 1 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 1.0 PERSONNEL RESPONSIBILITY The Operations Support Group Leader shall implement this procedure.
The Technical Support Center (TSC) Chemistry Support Team and the Operations Support Center (OSC) Chemistry Supervisor shall provide support. In the absence of the Operations Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE To determine if fuel failure is less than or greater than 5% through the use of Primary Coolant System (PCS) sample line dose rate correlations.
To specify PCS sampling requirements if fuel failure is less than 5%
and a sample has been requested. NOTE: If fuel failure is greater than 5%, PCS sampling will not be performed.
3.0 REFERENCES
3.1 SOURCE DOCUMENTS 3.1.1 Reg Guide 1.97 3.1.2 EA-JBB-01-04, "Failed Fuel Rates on NSSS Piping" 3.1.3 Palisades Site Emergency Plan, Section 7, "Emergency Facilities and Equipment" 3.1.4 Combustion Engineering Report, "Technical Justification for the Elimination of the Post-Accident Sampling System from the Plant Design and Licensing Basis for CEOG Utilities," CE NPSD-11 57, Revision 1 USER ALERT REFERENCE USE PROCEDURE Refer to the procedure periodically to confirm that all procedure segments of an activity will be or are being performed. Where required, sign appropriate sign-off blanks to certify that all segments are complete.
I
PALISADES NUCLEAR PLANT Proc No El-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revision 7 Page 2 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure El-i, "Emergency Classification and Actions" 3.2.2 Emergency Implementing Procedure EI-7.10, "Post Accident Sampling, Radioactive Gaseous Effluent Monitoring" 3.2.3 Palisades Administrative Procedure 9.31, "Temporary Modification Control" 3.2.4 Emergency Implementing Procedure El-1 1, "Determination of Extent of Core Damage" 3.2.5 Palisades Administrative Procedure 1.15, "Performance of Job Briefings" 3.2.6 System Operating Procedure SOP-1 6, "Component Cooling Water System" 3.2.7 Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision" 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS This procedure shall be implemented as a result of Emergency Implementing Procedure El-i, "Emergency Classification and Actions."
The Site Emergency Director (SED) reviews the above procedure to categorize the emergency into one of the Site Emergency Plan Classifications and to determine the required actions.
NOTE:
At Primary Coolant System pressures of < 150 psi, CV-1 903, PCS hot leg sample valve, may not be capable of opening. This procedure should be performed at PCS pressures > 150 psi. If PCS pressure is < 150 psi, this procedure should not be performed.
PALISADES NUCLEAR PLANT Proc No EI-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revision 7 Page 3 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 4.1 PRELIMINARY INDICATORS If any of the following Plant conditions are present, it is possible that clad failure has occurred. The Palisades Plant Computer (PPC) can be used to find many of the following monitor readings.
- a.
Off Gas Monitor (RIA-0631) high radiation indication or alarm.
- b.
Charging Pump Entrance Monitor (RIA-2301) high radiation indication or alarm.
- c.
Waste Gas Monitor (RIA-1 113) high radiation indication or alarm.
- d.
Containment High Range Monitors (RA-2321/-2322) high radiation alarm.
- e.
Containment Isolation Monitors (RIA-1805, 1806, 1807, and 1808) high radiation indication.
- f.
Containment Radiation Monitor (RA-231 5) high radiation indication.
- g.
Containment Noble Gas Monitor (RIA-1817) high radiation alarm.
- h.
Containment Hydrogen Monitors indicate high concentration.
- i.
Core Exit Thermocouples indicate high temperature.
- j.
Primary Coolant System analysis indicates high activity.
- k.
Abnormally high radiation levels in vicinity of letdown line, NSSS panel, etc.
I.
Containment Building Sump Level increasing level indication.
High radiation indications on radiation monitors should be discussed with Health Physics personnel. Emergency Implementing Procedure El-1 1, "Determination of Extent of Core Damage," may be useable in determining core damage using containment radiation monitor readings.
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-7.0 Revision 7 Page 4 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 4.2 PRELIMINARY DOSE RATE SURVEYS 4.2.1 OSC Chemistry Supervisor requests OSC Health Physics (HP) Supervisor for performance of dose rates and/or air sample surveys of the following areas:
- a.
NSSS Sample Panel Room
- b.
Hall to Chemistry Hot Lab
- c.
Chemistry Hot Lab
- d.
Count Room
- e.
Chemistry Grey Lab 4.2.2 OSC HP Supervisor shall ensure:
- a.
Stay times are computed for ALL High Radiation areas as surveyed
- b.
HP coverage at sample panel and dose rates and may include:
individuals required to work in in Step 4.3.1.
in labs is commensurate with
- 1.
Monitoring dose rates at and around sample panel during all sample acquisition activities.
- 2.
Continuous air sampling at sample panel and in labs during sample analysis.
- c.
Dosimetry requirements and anti-contamination clothing requirements shall be dictated by the OSC Health Physics Supervisor.
Emergency Implementing Procedure EI-2.1, "Site Emergency Director,"
contains guidance on Dose Limits and provides for a dose limit of 5 Rem/hr. The Health Physics Supervisor will determine the dose rate and decide if sampling should be performed.
PALISADES NIICLEAR PLANT EMERGENCY IMPLEMENTWNG PROCEDURE Proc No El-7.0 Revision 7 Page 5 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES PROCEDURE 5.0 5.1 PRIMARY COOLANT SYSTEM SAMPLE LINE RECIRCULATION FOR FAILED FUEL CLASSIFICATION 5.1.1 Perform a pre-job brief in accordance with Palisades Administrative Procedure 1.1 5, "Performance of Job Briefings."
USER ALERT REFERENCE USE PROCEDURE Refer to the procedure periodically to confirm that all procedure segments of an activity will be or are being performed. Where required, sign appropriate sign-off blanks to certify that all segments are complete.
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-7.0 Revision 7 Page 6 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 5.1.2 IF Containment Isolation Signal (CIS) is received I
THE
- 1. Request I&C to jumper CV-1 910 and CV-1911 per the directions found in. This Jumpering can only be performed if instrument air is available. I&C should verify availability before starting Jumpering.
- 2.
Request Operations to reopen CCW Valve CV-944A so that cooling is supplied to the sample coolers per System Operating Procedure SOP-1 6,"Component Cooling Water System." Inform Operations that PCS sample flow will be routed to the Volume Control Tank.
Containment Isolation Signal Request Operations to open CV-1 910 and (CIS) is not received CV-1 911. Inform Operations that PCS sample flow will be routed to the Volume Control Tank.
5.1.3 Initiate the PCS flush in accordance with Attachment 2, Section 2.0, "PCS Hot Leg Sample Line Flush."
5.1.4 Report the dose rate reading to the OSC and TSC Chemistry Supervisors.
Dose rate mR/hr Dose Rate Date/Time Shutdown Date/Time Hours since shutdown CAUTION This flush will result in transferring sample water from the reactor or containment sump to the VCT or Chemistry lab drain tank. This may result in increased dose rates in these areas.
THEN
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-7.0 Revision 7 Page 7 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 5.1.5 Use the "NSSS Sample Panel Piping Dose Rates" graph in Attachment 3 to determine fuel failure. Fuel Failure should be defined as < 1%, 1-5%,
or >5%.
Fuel Failure Determined By Signature IF Fuel failure > 5%
Fuel failure _< 5%
THEN Report results to the Operation Support Group Leader. Refer to El-i, "Emergency Classification and Actions," Section Fission Product Barriers/Fuel Damage. El-i, "Emergency Classification and Actions,"
does not discriminate between 1-5% and
>5%.
Ensure CV-'1 910 and CV-1911 are closed.
A PCS sample will not be obtained.
Report results to the Operation Support Group Leader. Refer to El-i, "Emergency Classification and Actions," Section Fission Product Barriers/Fuel Damage.
If PCS sample will not be required immediately, ensure CV-1910 and CV-1911 are closed.
If PCS sample is required, go to, Step 3.9 ("Open Valve MV-V1 7...).
5.1.6
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-7.0 Revision 7 Page 8 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 5.2 SUBSEQUENT POST ACCIDENT SAMPLING Post accident sampling may be performed at the NSSS sample panel or in other areas of the plant using normal or evaluated sample points.
5.2.1 Perform a pre-job brief in accordance with Palisades Administrative Procedure 1.15, "Performance of Job Briefings."
5.2.2 Chemistry Supervision shall ensure pre-determined storage and disposal sites of used and unused portions of the sample are specified. Consider returning sample to the containment building if possible.
CAUTION This sampling will result in transferring sample water from the reactor or containment sump to the VCT or Chemistry lab drain tank. This may result in increased dose rates in these areas.
5.2.3 IF Containment Isolation Signal (CIS) is received Containment Isolation Signal (CIS) is not received THEN
- 1. Request I&C to jumper CV-1910 and CV-1 911 per the directions found in. This Jumpering can only be performed if instrument air is available. I&C should verify availability before starting Jumpering.
- 2.
Request Operations to reopen CCW Valve CV-944A so that cooling is supplied to the sample coolers per System Operating Procedure SOP-1 6,"Component Cooling Water System." Inform Operations that PCS sample flow will be routed to the Volume Control Tank.
Request Operations to open CV-1 910 and CV-1 911.
Inform Operations that PCS sample flow will be routed to the Volume Control Tank.
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEURE TITLE: EMERGENCY POST ACCIDENT DETERMINATION OF FUEL FAILURE Proc No EI-7.0 Revision 7 Page 9 of 10 SAMPLING AND USING DOSE RATES 5.2.4 Initiate PCS sampling in accordance with Attachment 2, Section 3.0, "PCS SAMPLE."
- a.
Contingency sampling will be performed using appropriate Chemistry Operating Procedures as well as Chemistry Supervisory guidance.
5.2.5 Perform sample and analysis preparation in the Hot Lab Hood. Use sample shield in the Hot Lab as necessary.
5.2.6 Chemistry will perform analyses in accordance with the appropriate analytical procedures. Dilutions may be done to ensure sample dose rates are reduced.
5.2.7 Report results to OSC and TSC Chemistry Supervisors.
ATTACHMENTS AND RECORDS 6.0 6.1 ATTACHMENTS 6.1.1, "Jumpering CV-1 910 and CV-1 911 for PCS Sample or Sample Line Flush" 6.1.2, "Primary Coolant System Sample Line Flush and PCS Sampling" 6.1.3, "NSSS Sample Panel Piping Dose Rates" 6.2 RECORDS None
PALISADES NUCLEAR PLANT Proc No EI-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revision 7 Page 10 of 10 TITLE: EMERGENCY POST ACCIDENT SAMPLING AND DETERMINATION OF FUEL FAILURE USING DOSE RATES 7.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review per Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision." Therefore, changes to this procedure do not require a 50.59 review.
The scope of this procedure does include activities that require a PRC review per Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision." Therefore, changes to this procedure do require a PRC review.
Proc No EI-7.0 JUMPERING CV-1910 AND CV-1911 FOR PCS SAMPLE Revision 7 OR SAMPLE LINE FLUSH Page 1 of 3 NOTE:
This Attachment cannot be performed if instrument air is not available.
1.0 PURPOSE This attachment describes the method to be used to jumper containment isolation valves CV-1 910 and CV-1911 should they become closed during accident conditions (Containment Isolation). In order to sample the Primary Coolant System (PCS), CV-1910 and CV-1911 must be open.
2.0 REFERENCE 2.1 Palisades Administrative Procedure 9.31, "Temporary Modification Control" 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS 3.1 CV-1 910 and CV-1 911 are the containment isolation valves on the PCS chemistry sample lines. In the event of a containment isolation signal due to Containment High Pressure (CHP) and/or Containment High Radiation (CHR), CV-1910 and CV-1 911 will close.
3.2 To obtain a sample of the PCS under accident conditions using the NSSS panel, it will be necessary to bypass the CHP and/or CHR relay contacts to open these valves.
4.0 PROCEDURE 4.1 I&C or Electrical Maintenance may obtain jumper set and #10 link nuts from Emergency Maintenance Kit 9 in the Operations Support Center (OSC).
4.2 Request Operations to place HS-1910 and HS-1911 in the open position (CV-1910 and CV-1911 should remain shut.) Advise Operations that while jumpers are being placed, they will lose valve indications. Valve indications will be restored after jumpers are in place.
4.3 Inside C-13 Panel NOTE:
Circuits involved labeled P1 are 125 VDC positive supply to valve position indication.
- a.
Locate 13TV4-28 (P1) scheme S-21 (M201, Sheet 40) and open link.
JUMPERING CV-1910 AND CV-1911 FOR PCS SAMPLE OR SAMPLE LINE FLUSH Proc No EI-7.0 Revision 7 Page 2 of 3
- b.
Attach appropriate end of jumper to P1 side to link using #10 nut and link wrench.
- c.
Locate 13TV6C-19 (91) scheme S-21 (M201, Sheet 113), string jumper so that it is out of the way so as not to be pulled apart, and attach other end of jumper using #10 nut and link wrench.
- d.
Close link at 13TV4-28 (P1) scheme S-21 (opened in a). Verify position indication restored and CV-1 910 still closed.
- e.
Locate 13TV1 1-112 (P1) scheme S-22 (M201, Sheet 35) and open link.
- f.
Attach appropriate end of jumper to P1 side of link using #10 nut and link wrench.
- g.
Locate 13TV8C-24 (91) scheme S-22 (M201, Sheet 113), string jumper along floor under grating so it is out of the way and attach other end of the jumper using #10 nut and link wrench.
- h.
Close link at 13TV1 1-112 (P1) scheme S-22 (opened in e). Verify position indication restored and CV-1911 still closed.
Inform Operations that jumpering operation is complete and to place HS-1 910 and HS-1 911 in the closed position. Returning either handswitch back to the open position will now cause valves to open.
4.5 Request Operations to caution tag HS-1 910 and HS-1 911 indicating that CHlP and CHR relay contacts are jumpered out for CV-1 910 and CV-1 911.
4.5.1 If the valves remain jumpered open for longer than one shift, then caution tags shall be required.
4.4 WARNING Once sampling valves are open, a potential exists for High Radiation Fields to be created at the NSSS Panel.
I I
Proc No EI-7.0 JUMPERING CV-1910 AND CV-191 1 FOR PCS SAMPLE Revision 7 OR SAMPLE LINE FLUSH Page 3 of 3 4.6 Removal of Jumpers 4.6.1 I&C or Electrical Maintenance obtain permission from Shift Supervisor to remove jumpers on CV-1 910 and CV-1 911.
4.6.2 Inside C-13 Panel NOTE:
Circuits involved labeled P1 are 125 VDC positive supply to valve position indication.
- a.
Locate 13TV1 1-112 (P1) scheme S-22 and open link.
- b.
Remove appropriate end of jumper using a link wrench.
- c.
Locate 13TV8C-24 (91) scheme S-22 (M201, Sheet 113) and remove jumper using a link wrench.
- d.
Locate 13TV11-112 (P1) scheme S-22 (M201, Sheet 35) and close link.
- e.
Locate 13TV4-28 (P1) scheme S-21 and open link.
- f.
Remove appropriate end of jumper using a link wrench.
- g.
Locate 13TV6C-19 (91) scheme S-21 (M201, Sheet 113) and remove appropriate end of jumper using a link wrench.
- h.
Locate 13TV4-28 (P1) scheme S-21 (M201, Sheet 40) and close link.
4.6.3 Inform Operations that removal of jumpers is complete.
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING 1.0 Establish the methods for the recirculation of the Primary Coolant System (PCS) Hot Leg through the NSSS Sampling Station(C-32) to the VCT during accident conditions.
2.0 2.1 2.2 PCS HOT LEG SAMPLE (SX-1023) LINE RECIRCULATION Notify the Control Room Supervisor of the intent to open the PCS sample point.
At the EC-1 68 Control Panel:
2.2.1 Check or place HS-1912 (RC or LPSI selector switch) in the OFF position, to block flow to the EC-1 68 Control Panel.
2.2.2 Verify CV-1 912 (Reactor Coolant Sample block valve) CLOSED (green indicator light).
2.2.3 Place SS-0210 and SS-0211 (selector switches for continuous sample) in the ON position.
2.2.4 Verify that temperature indicating switch TIS-1 901 is in service. If the Green LED is ON (unit in Manual Mode), enable the alarm function by pushing A/M touch pad. This enters Auto Mode with Green LED off. The lower display will now show SP 0.0.
2.2.5 IF THEN HI-HI Sample Temp Alarm on Place HS-1 91 9 to MANUAL, and C-168 panel exists.
proceed to Step 2.2.6.
HI-HI Sample Temp Alarm on Check that HS-1919 is in AUTO, C-168 panel does not exist.
and proceed to Step 2.2.6.
2.2.6 Place HS-1 91 6 (Reactor Coolant sample flush switch) in the SAMPLE position.
2.2.7 Verify SV-1 917 CLOSED (green indicator light) 2.2.8 Verify SV-1916 OPEN (red indicator light).
Proc No El-7.0 Revision 7 Page 1 of 8
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No El-7.0 Revision 7 Page 2 of 8 2.2.9 Verify the following valves are CLOSED:
MV-V37 MV-V 17 MV-V41 MV-V42 (gas collection bomb vent)
(primary coolant sample/flush switch)
(gas collection bomb inlet)
(gas collection bomb outlet) 2.2.10 Verify the following valves OPEN:
MV-V38 MV-V39
,MV-V40 (SX-2022 inlet to bomb isolation)
(gas collection bomb bypass)
(panel outlet from gas collection bomb)
IF THEN PCS pressure is < 2000 psig Fully Open MV-PC606 PCS pressure is > 2000 psig Go to Step 2.3.
At the C-32 panel, ensure the NSSS selector handswitch HS-1 901 (NSSS panel C-32 sample selector switch) is in Position 3.
IF THEN HS-1 901 is in Position 3.
No adjustment is necessary. Proceed to Step 2.4.
HS-1 901 is not in Ensure air control switch CS-5057 in the OFF Position 3.
position. Place the selector handswitch HS-1 901 to Position 3.
Open the bottom of the C-32 panel and verify position of the solenoid valve as follows:
Open discharge from SV-1 909 by opening MV-PC163 (SV-1 909 isolation). Close discharge from SV-1906 and SV-1908 by closing MV-PC1 61 (SV-1 906 isolation) and MV-PC162 (SV-1 908 isolation).
Proceed.to Step 2.4.
Place air control switch CS-5057 in the ON position.
- a.
- b.
C.
d.
- a.
- b.
C.
2.2.11 2.3 2.4
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No EI-7.0 Revision 7 Page 3 of 8 2.5 2.6 2.8 At the C-32 panel, allow sample flow and discharge to the VCT for a minimum of 20 minutes.
2.9 Radiation Protection shall measure the dose rate on contact at the Failed Fuel Survey Point on the PCS sample line.
2.10 Place the C-32 panel air control switch CS-5057 in the OFF position.
2.11 At the C-1 68 panel, place HS-1 916 (reactor coolant sample/flush switch) in the OFF position.
2.12 Notify the Control Room Supervisor that PCS flush is complete and that the following step will cause a "PASM Panel Trouble" alarm.
At the C-168 panel: Verify CV-1910, CV-1911 indicate open (red indicator light). Verify CV-1 903 (primary coolant loop 2 hot leg sample point) indicates open.
Purge for 3 minutes.
IF THEN Dose rate at the NSSS panel is SECURE sample flow by placing greater than 5 Rem/hr when SV-1 916 to OFF and CS-5057 to OFF.
sample flow is initiated.
Report to OSC Chemistry Supervisor.
Elevated dose rates will occur in the Auxiliary Building if sample flow dose rates exceed this value.
Dose rate at the NSSS panel is Continue to Step 2.7.
less than 5 Rem/hr when sample flow is initiated.
IF THEN HI-HI Temperature Alarm is Place HS-1919 to AUTO, go to Clear.
Step 2.8.
HI-HI Temperature Alarm is not Verify MV-CC175, and MV-CC176 are Clear.
open, and contact OSC Chemistry Supervisor.
2.7
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No El-7.0 Revision 7 Page 4 of 8 2.13 SS-021 0 and SS-0211 (selector switches for continuous sample) in the OFF position.
2.14 To disable the alarm function for TIS-1901 perform the following:
- a.
If the Green LED is not lit, push A/M touch pad to enter the Manual Mode (Green LED on).
- b.
Push the down-arrow pad until output equals 0.0. The display will read OUT 0.0. The Red LED labeled ALl will remain "ON" if sample temperature is > 900 F.
2.15 Return to Step 5.1.4 in the main body of the procedure.
3.0 PoAMPLE 3.1 Notify the Control Room Supervisor of the intent to sample the PCS.
3.2 At the EC-168 Control Panel:
3.2.1 Check or place HS-1912 (RC or LPSI selector switch) in the OFF position, to block flow to the EC-168 Control Panel.
3.2.2 Verify CV-1 912 (Reactor Coolant Sample block valve) CLOSED (green indicator light).
3.2.3 Place SS-0210 and SS-0211 (selector switches for continuous sample) in the ON position.
3.2.4 Verify that temperature indicating switch TIS-1 901 is in service. If the Green LED is ON (unit in Manual Mode), enable the alarm function by pushing A/M touch pad. This enters Auto Mode with Green LED off. The lower display will now show SP 0.0.
3.2.5 IF THEN HI-HI Sample Temp Alarm on Place HS-1919 to MANUAL, and C-1 68 panel exists.
proceed to Step 3.2.6.
HI-HI Sample Temp Alarm on Check that HS-1 919 is in AUTO, C-1 68 panel does not exist, and proceed to Step 3.2.6 I !
PRIMARY COOLANTLSYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No EI-7.0 Revision 7 Page 5 of 8 3.2.6 Check or place HS-1 916 (Reactor Coolant sample flush switch) in the SAMPLE position.
3.2.7 Verify SV-1917 CLOSED (green indicator light) 3.2.8 Verify SV-1916 OPEN (red indicator light).
3.2.9 Verify the following valves are CLOSED:
- a.
- b.
C.
d.
MV-V37 MV-V17
'MV-V41 MV-V42 (gas collection bomb vent)
(primary coolant sample/flush switch)
(gas collection bomb inlet)
(gas collection bomb outlet) 3.2.10 Verify the following valves OPEN:
- a.
- b.
C.
MV-V38 MV-V39 MV-V40 (SX-2022 inlet to bomb isolation)
(gas collection bomb bypass)
(panel outlet from gas collection bomb) 3.2.11 IF THEN PCS pressure is < 2000 psig Fully Open MV-PC606 PCS pressure is > 2000 psig Go to Step 3.3.
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No EI-7.0 Revision 7 Page 6 of 8 3.3 At the C-32 panel, ensure the NSSS selector handswitch HS-1 901 (NSSS panel C-32 sample selector switch) is in Position 3.
IF THEN HS-1 901 is in Position 3.
No adjustment is necessary.
Proceed to Step 3.4.
HS-1901 is not in Position 3.
Ensure air control switch CS-5057 in the OFF position.
Place the selector handswitch HS-1 901 to Position 3.
Open the bottom of the C-32 panel and verify position of the solenoid valve as follows: Open discharge from SV-1 909 by opening MV-PC163 (SV-1 909 isolation).
Close discharge from SV-1906 and SV-1 908 by closing MV-PC1 61 (SV-1906 isolation) and MV-PC162 (SV-1 908 isolation).
I IProceed to Step 3.4.
Place air control switch CS-5057 in the ON position.
At the C-168 panel: Verify CV-1910, CV-1911 indicate open (red indicator light). Verify CV-1 903 (primary coolant loop 2 hot leg sample point) indicates open.
3.4 3.5 1
PRIMARY COOLANT SYSTEM SAMPLE LINE FLUSH AND PCS SAMPLING Proc No El-7.0 Revision 7 Page 7 of 8 Purge for 3 minutes.
IF THEN Dose rate at the NSSS panel is SECURE sample flow by placing greater than 5 Rem/hr when sample SV-1 916 to OFF and CS-5057 to flow is initiated.
OFF. Report to OSC Chemistry Supervisor. Elevated dose rates will occur in the Auxiliary Building if sample flow dose rates exceed this value.
Dose rate at the NSSS panel is less Continue to Step 3.7.
than 5 Rem/hr when sample flow is initiated.
IF THEN HI-HI Temperature Alarm is Clear.
Place HS-1 919 to AUTO, go to Step 3.8.
HI-HI Temperature Alarm is not Verify MV-CC1 75, and MV-CC176 Clear.
are open, and contact OSC Chemistry Supervisor.
3.8 At the C-32 panel, allow sample flow and discharge to the VCT for a minimum of 20 minutes.
3.9 OPEN Valve MV-V17 (primary coolant sample/flush switch).
3.10 CLOSE Valve MV-V40 (panel outlet from gas collection bomb).
Flush sample line for 5 minutes.
NOTE:
PCS sample volume collected depends on the analyses that will be performed. At the very least, boron and gamma spectroscopy analyses will be done.
3.12 Obtain appropriate volume of PCS sample.
3.13 OPEN valve MV-V40 (panel outlet from gas collection bomb).
3.6 3.7 3.11
Proc No El-7.0 PRIMARY COOLANT SYSTEM SAMPLE Revision 7 LINE FLUSH AND PCS SAMPLING Page 8 of 8 3.14 CLOSE Valve MV-V17 (primary coolant sample/flush switch).
3.15 Place the C-32 panel air control switch CS-5057 in the OFF position.
3.16 At the C-168 panel, place HS-1916 (reactor coolant sample/f lush switch) in the OFF position.
3.17 Notify the Control Room Supervisor that PCS flush is complete and that the following step will cause a "PASM Panel Trouble" alarm.
3.18 Place SS-0210 and SS-0211 (selector switches for continuous sample) in the OFF position.
3.19 To disable the alarm function for TIS-1 901 perform the following:
- a.
If the Green LED is not lit, push A/M touch pad to enter the Manual Mode (Green LED on).
- b.
Push the down-arrow pad until output equals 0.0. The display will read OUT 0.0. The Red LED labeled ALl will remain "ON" if sample temperature is Ž 90' F.
3.20 Return to Step 5.2.5 in the main body of the procedure.
(
NSSS Sample Panel Piping Dose Rates vs Fuel Failure 15MI 1
1 1200 1100 1000 800 500 400 300__
a_
11% Fuel Failure 200 100-12 24 36 48 60 7
Hours since Shutlown
'2 84 se 108 120 z
CO r
z I
- 0
-a)
M
-0 01 I M
CoZ 0
)0 40AA
(
I A Al U
0 F
Y1 I
r I
i,-,----
+ -,----,------.
,-----,----
4 1 _______________ 1 ________________
i m
i I
q i
k