ML020440560: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 2: | Line 2: | ||
| number = ML020440560 | | number = ML020440560 | ||
| issue date = 01/16/2002 | | issue date = 01/16/2002 | ||
| title = | | title = Radiological Emergency Response Plan Implementing Procedures | ||
| author name = Webb T | | author name = Webb T | ||
| author affiliation = Nuclear Management Co, LLC | | author affiliation = Nuclear Management Co, LLC | ||
| addressee name = | | addressee name = | ||
| Line 66: | Line 66: | ||
--- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES DATE: 01-15-2002 INDEX NUMBER TITLE APPENDIX A APPX-A-I Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form) AD-07-02 State Call-Back | --- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES DATE: 01-15-2002 INDEX NUMBER TITLE APPENDIX A APPX-A-I Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form) AD-07-02 State Call-Back | ||
-Question Guideline C 11-15-2001 AD 11.1 Emergency Radiation Work Permit F 04-16-96 EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-1 1-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 PAGE 9 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-20Q1 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management | -Question Guideline C 11-15-2001 AD 11.1 Emergency Radiation Work Permit F 04-16-96 EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-1 1-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 PAGE 9 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-20Q1 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management | ||
-Status A 04-01-99 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist PAGE 10 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D 12-14-2001 Program) TSC 9A. 1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp. TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 34 Reviewed Bv Approved By ----:Z -'-,, Nuclear [] Yes AORC _ Yes SRO Approval Of 2 Yes Safety Review Temporary Related 13 N Reuired [] No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions: | -Status A 04-01-99 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist PAGE 10 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D 12-14-2001 Program) TSC 9A. 1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp. TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 34 Reviewed Bv Approved By ----:Z -'-,, Nuclear [] Yes AORC _ Yes SRO Approval Of 2 Yes Safety Review Temporary Related 13 N Reuired [] No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions: | ||
: a. Diluted liquid sample of primary coolant for: (Step 5.1)0 Boron analysis b. An inline liquid sample for: (Step 5.2)0 Gamma isotopic analysis"* pH 0 Oxygen "* Conductivity | : a. Diluted liquid sample of primary coolant for: (Step 5.1)0 Boron analysis b. An inline liquid sample for: (Step 5.2)0 Gamma isotopic analysis"* pH 0 Oxygen "* Conductivity | ||
* Chlorides | * Chlorides | ||
: c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3) d. A diluted gas sample for gamma isotopic analysis. (Step 5.3) e. An undiluted liquid sample for off-site analysis. (Step 5.4) f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5) g. Flush of liquid sample lines. (Step 5.6) 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 The following is a list of acronyms that are used throughout this procedure: | : c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3) d. A diluted gas sample for gamma isotopic analysis. (Step 5.3) e. An undiluted liquid sample for off-site analysis. (Step 5.4) f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5) g. Flush of liquid sample lines. (Step 5.6) 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 The following is a list of acronyms that are used throughout this procedure: | ||
* CAP | * CAP | ||
| Line 78: | Line 78: | ||
* LSP | * LSP | ||
* RCHL | * RCHL | ||
* SAP Chemical Analysis Panel Containment Air Sampling Panel Chemical Analysis Monitor Panel Deaerated Drain Tank HVAC/Containment Air Sample Control Panel Health Physics/Radiation Protection Director High Radiation Sample Room RCHL Liquid Sample Panel Reactor Coolant Hot Leg Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 2 of 34 3.0 Precautions and Limitations | * SAP Chemical Analysis Panel Containment Air Sampling Panel Chemical Analysis Monitor Panel Deaerated Drain Tank HVAC/Containment Air Sample Control Panel Health Physics/Radiation Protection Director High Radiation Sample Room RCHL Liquid Sample Panel Reactor Coolant Hot Leg Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 2 of 34 3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact Radiation Protection Group (HIP) for: 3.2.1 Proper personnel dosimetry 3.2.2 Proper radiation detection instrumentation 3.2.3 Personnel for continuous HIP coverage during sampling 3.2.4 Remote area monitor readings in area of HRSR 3.3 Utilize on-site communications with the HP/RPD, as necessary, during sampling. | ||
3.4 Containment sump pH should be adjusted to a pH > 7 within 48 hours following the initiation of recirculation during a small break loss of coolant accident. | |||
an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact Radiation Protection Group (HIP) for: 3.2.1 Proper personnel dosimetry | |||
radiation detection instrumentation | |||
for continuous HIP coverage during sampling 3.2.4 Remote area monitor readings in area of HRSR 3.3 Utilize on-site communications with the HP/RPD, as necessary, during sampling. | |||
sump pH should be adjusted to a pH > 7 within 48 hours following the initiation of recirculation during a small break loss of coolant accident. | |||
3.5 If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist. | 3.5 If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist. | ||
* No direct temperature indicator is available. | * No direct temperature indicator is available. | ||
| Line 99: | Line 86: | ||
* Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer. | * Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer. | ||
High Component Cooling temperature may occur if Service Water temperatures are elevated. | High Component Cooling temperature may occur if Service Water temperatures are elevated. | ||
3.6 IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling. | 3.6 IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling. | ||
3.7 Transit routes to and from the HRSR per HP/RPD recommendations. | |||
3.8 Monitor radiation levels in the HRSR upon entry and during sample manipulations. | |||
routes to and from the HRSR per HP/RPD recommendations. | CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 3 of 34 3.9 Radiation level monitoring is required if accessing the maintenance areas behind the panels. 3.10 IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates. 4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director. | ||
5.0 Procedure 5.1 Diluted Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1 In the HRSR check the following equipment available and operational: | |||
radiation levels in the HRSR upon entry and during sample manipulations. | |||
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 3 of 34 3.9 Radiation level monitoring is required if accessing the maintenance areas behind the panels. 3.10 IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates. 4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director. | |||
Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1 In the HRSR check the following equipment available and operational: | |||
"* Drying oven on at 55°C to 60*C "* All material required to perform RCC-082, "Boron Analysis Curcumin Method." "* Multi-Channel Analyzer available for counting (Technical Support Center) " 2 -1 liter poly bottles "* Shielded aliquoter available | "* Drying oven on at 55°C to 60*C "* All material required to perform RCC-082, "Boron Analysis Curcumin Method." "* Multi-Channel Analyzer available for counting (Technical Support Center) " 2 -1 liter poly bottles "* Shielded aliquoter available | ||
"* New 60 ml diluted sample bottle (large bottle) "* Hand operated vacuum pump "* Lights on in diluted sample port of LSP "* LSP Sample Cask available with diluted sample bottle piston installed | "* New 60 ml diluted sample bottle (large bottle) "* Hand operated vacuum pump "* Lights on in diluted sample port of LSP "* LSP Sample Cask available with diluted sample bottle piston installed | ||
| Line 132: | Line 111: | ||
"* WHEN RHR sample, THEN purge at least 25 minutes. | "* WHEN RHR sample, THEN purge at least 25 minutes. | ||
5.1.10.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | 5.1.10.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | ||
5.1.10.6 WHEN purge is complete, THEN perform the following: | 5.1.10.6 WHEN purge is complete, THEN perform the following: | ||
: a. Close RC-V-3. b. Open RC-V-8.2. | : a. Close RC-V-3. b. Open RC-V-8.2. | ||
: c. Open RC-V-8.1. | : c. Open RC-V-8.1. | ||
: d. Open RC-V-2.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 34 Note Purge time may be varied based on purge flow rate obtained. | : d. Open RC-V-2.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 34 Note Purge time may be varied based on purge flow rate obtained. | ||
5.1.10.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.1.10.8 Purge at least 3 minutes. | 5.1.10.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.1.10.8 Purge at least 3 minutes. | ||
| Line 140: | Line 119: | ||
5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN 20 inches of vacuum is recommended. | 5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN 20 inches of vacuum is recommended. | ||
5.1.10.11 Install the sample cart under the diluted sample port. 5.1.10.12 Position the sample bottle up on the needles. | 5.1.10.11 Install the sample cart under the diluted sample port. 5.1.10.12 Position the sample bottle up on the needles. | ||
5.1.10.13 WHEN purge is complete, THEN perform the following: | 5.1.10.13 WHEN purge is complete, THEN perform the following: | ||
: a. Turn RC-DV-1 to SAMPLE position (6 o'clock). | : a. Turn RC-DV-1 to SAMPLE position (6 o'clock). | ||
: b. IF RCHL sample, THEN close RC-V-1.2. | : b. IF RCHL sample, THEN close RC-V-1.2. | ||
: c. IF RHR sample, THEN close RC-V-1.1. | : c. IF RHR sample, THEN close RC-V-1.1. | ||
5.1.10.14 Throttle open RC-V-21. | 5.1.10.14 Throttle open RC-V-21. | ||
| Line 164: | Line 143: | ||
WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 _ Page 8 of 34 Note Dilution factor correction is required ifsample was not diluted with 24 ml of DI Water Step 5.1.10.16. | WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 _ Page 8 of 34 Note Dilution factor correction is required ifsample was not diluted with 24 ml of DI Water Step 5.1.10.16. | ||
5.1.13 Perform the following post sample analyses preparations: | 5.1.13 Perform the following post sample analyses preparations: | ||
Note For Boron analysis of< 2,000 ppm, an appropriately larger amount of sample shall be used. 5.1.13.1 WHEN analyzing for boron, THEN perform the following: | Note For Boron analysis of< 2,000 ppm, an appropriately larger amount of sample shall be used. 5.1.13.1 WHEN analyzing for boron, THEN perform the following: | ||
: a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter. | : a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter. | ||
: b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin -Method." 5.1.13.2 WHEN performing a Beta/Gamma analysis, THEN perform the following: | : b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin -Method." 5.1.13.2 WHEN performing a Beta/Gamma analysis, THEN perform the following: | ||
: a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter. | : a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter. | ||
: b. Dilute to 1 liter with DI Water. c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle. d. Dilute to 1 liter with DI Water. Dilution factor = 108. e. Transfer sample to the multi-channel analyzer for counting. | : b. Dilute to 1 liter with DI Water. c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle. d. Dilute to 1 liter with DI Water. Dilution factor = 108. e. Transfer sample to the multi-channel analyzer for counting. | ||
5.2 Inline Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.2.1 Align argon and helium as follows: 5.2.1.1 Verify open argon gas cylinder isolation. | |||
Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.2.1 Align argon and helium as follows: 5.2.1.1 Verify open argon gas cylinder isolation. | |||
5.2.1.2 Verify argon cylinder pressure >_ 400 psi. 5.2.1.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.2.1.4 Verify open helium gas cylinder isolation. | 5.2.1.2 Verify argon cylinder pressure >_ 400 psi. 5.2.1.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.2.1.4 Verify open helium gas cylinder isolation. | ||
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 9 of 34 5.2.1.5 Verify helium cylinder pressure > 400 psi. 5.2.1.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.2.2 Verify reach rod is available for remote valve operation. | CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 9 of 34 5.2.1.5 Verify helium cylinder pressure > 400 psi. 5.2.1.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.2.2 Verify reach rod is available for remote valve operation. | ||
5.2.3 Check HRSR Calibration Log for verification of latest performances. | |||
HRSR Calibration Log for verification of latest performances. | |||
5.2.4 At the CASP perform the following: | 5.2.4 At the CASP perform the following: | ||
5.2.4.1 Verify ventilation is ON and mode control switches are in NORMAL position. | 5.2.4.1 Verify ventilation is ON and mode control switches are in NORMAL position. | ||
| Line 235: | Line 210: | ||
* 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5 At the CMP perform the following: | * 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5 At the CMP perform the following: | ||
5.3.5.1 CMP Main Power switch ON. 5.3.5.2 Verify the program in Gas Chromatograph (GC) mini-computer. | 5.3.5.1 CMP Main Power switch ON. 5.3.5.2 Verify the program in Gas Chromatograph (GC) mini-computer. | ||
5.3.5.3 Check HRSR Calibration Log for verification of latest performances. | 5.3.5.3 Check HRSR Calibration Log for verification of latest performances. | ||
5.3.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.3.7 At the CAP, verify Argon, Helium, and Air regulators set as follows: 5.3.7.1 Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.3.7.2 Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.3.7.3 Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi). 5.3.8 Connect DI Water flush hoses to LSP and CAP. 5.3.9 Open DI Water supply valves.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 20(2 Page 15 of 34 5.3.10 At the LSP, dry the expansion vessel as follows: 5.3.10.1 Turn RC-V-11 to ARGON position (3 o'clock). | |||
valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.3.7 At the CAP, verify Argon, Helium, and Air regulators set as follows: 5.3.7.1 Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.3.7.2 Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.3.7.3 Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi). 5.3.8 Connect DI Water flush hoses to LSP and CAP. 5.3.9 Open DI Water supply valves.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 20(2 Page 15 of 34 5.3.10 At the LSP, dry the expansion vessel as follows: 5.3.10.1 Turn RC-V-11 to ARGON position (3 o'clock). | |||
5.3.10.2 Open RC-V-9. 5.3.10.3 Open RC-V-8.2. | 5.3.10.2 Open RC-V-9. 5.3.10.3 Open RC-V-8.2. | ||
5.3.10.4 Open RC-V-10. | 5.3.10.4 Open RC-V-10. | ||
| Line 258: | Line 231: | ||
5.3.13.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | 5.3.13.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | ||
Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waiting for the sample purge to be completed. | Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waiting for the sample purge to be completed. | ||
5.3.13.6 Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows: a. Open RC-V-13. | 5.3.13.6 Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows: a. Open RC-V-13. | ||
: b. Open RC-V-15. | : b. Open RC-V-15. | ||
: c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). | : c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). | ||
: d. Open RC-V-12. | : d. Open RC-V-12. | ||
5.3.13.7 WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock). | 5.3.13.7 WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock). | ||
5.3.13.8 WHEN vacuum on RC-G-2.1 > 22 inches of vacuum, THEN perform the following: | 5.3.13.8 WHEN vacuum on RC-G-2.1 > 22 inches of vacuum, THEN perform the following: | ||
: a. Close RC-V-15. | : a. Close RC-V-15. | ||
: b. Close RC-V-13. | : b. Close RC-V-13. | ||
: c. Close RC-V-10. | : c. Close RC-V-10. | ||
: d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock). | : d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock). | ||
: e. Close RC-V-12.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following: | : e. Close RC-V-12.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following: | ||
: a. Turn RC-DV-2 to 12 o'clock. | : a. Turn RC-DV-2 to 12 o'clock. | ||
: b. Observe vacuum on RC-G-2.2 is holding steady. c. Turn RC-DV-2 to 3 o'clock. | : b. Observe vacuum on RC-G-2.2 is holding steady. c. Turn RC-DV-2 to 3 o'clock. | ||
5.3.13.10 Open RC-V-14. | 5.3.13.10 Open RC-V-14. | ||
| Line 283: | Line 256: | ||
5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1. | 5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1. | ||
5.3.13.23 Open RC-V-9. 5.3.13.24 Open RC-V-16. | 5.3.13.23 Open RC-V-9. 5.3.13.24 Open RC-V-16. | ||
5.3.13.25 Wait 1 minute. 5.3.13.26 Close RC-V-16.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 18 of 34 5.3.13.27 Close RC-V-9. 5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows: a. Open RC-V-8.2. | 5.3.13.25 Wait 1 minute. 5.3.13.26 Close RC-V-16.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 18 of 34 5.3.13.27 Close RC-V-9. 5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows: a. Open RC-V-8.2. | ||
: b. Open RC-V-8.1. | : b. Open RC-V-8.1. | ||
: c. Open RC-V-4. d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock). | : c. Open RC-V-4. d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock). | ||
5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). | 5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). | ||
| Line 328: | Line 301: | ||
5.4.2.1 Verify ventilation is ON and mode control switches are in NORMAL position. | 5.4.2.1 Verify ventilation is ON and mode control switches are in NORMAL position. | ||
5.4.2.2 Check High Vacuum Lights indicate NORMAL for the following: | 5.4.2.2 Check High Vacuum Lights indicate NORMAL for the following: | ||
"* LSP "* CAP "* CASP 5.4.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.4.4 Connect DI Water flush hoses to LSP. 5.4.5 Open DI Water supply valve to LSP. 5.4.6 Install undiluted sample bottle in sample cask. 5.4.7 Check cask for proper operation. | "* LSP "* CAP "* CASP 5.4.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.4.4 Connect DI Water flush hoses to LSP. 5.4.5 Open DI Water supply valve to LSP. 5.4.6 Install undiluted sample bottle in sample cask. 5.4.7 Check cask for proper operation. | ||
5.4.8 Install the sample cask under the undiluted sample port. 5.4.9 Position the undiluted sample bottle up on the needles. | |||
the sample cask under the undiluted sample port. 5.4.9 Position the undiluted sample bottle up on the needles. | |||
5.4.10 WHEN performing an RCHL sample, THEN request Control Room Operator: | 5.4.10 WHEN performing an RCHL sample, THEN request Control Room Operator: | ||
9 Open RC-422. 0 Open RC-423. 5.4.11 At the SAP perform the following: | 9 Open RC-422. 0 Open RC-423. 5.4.11 At the SAP perform the following: | ||
| Line 344: | Line 315: | ||
5.4.12.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes. | 5.4.12.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes. | ||
"* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | "* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly. | ||
5.4.12.6 WHEN purge is complete, THEN perform the following: | 5.4.12.6 WHEN purge is complete, THEN perform the following: | ||
: a. Close RC-V-3. b. Open RC-V-2. c. Open RC-V-7. Note Purge time may be varied based on actual purge flow rate obtained. | : a. Close RC-V-3. b. Open RC-V-2. c. Open RC-V-7. Note Purge time may be varied based on actual purge flow rate obtained. | ||
5.4.12.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.4.12.8 Purge for at least 3 minutes. | 5.4.12.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.4.12.8 Purge for at least 3 minutes. | ||
| Line 363: | Line 334: | ||
"* IF opened, THEN Close RHR-81A. | "* IF opened, THEN Close RHR-81A. | ||
"* IF opened, THEN close RHR-81B. | "* IF opened, THEN close RHR-81B. | ||
"* Close CC-316. 5.4.28.3 Position RC-437-1 to VCT. 5.4.28.4 Position RC-437-2 to VCT. 5.4.29 WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor. | "* Close CC-316. 5.4.28.3 Position RC-437-1 to VCT. 5.4.28.4 Position RC-437-2 to VCT. 5.4.29 WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor. | ||
5.5 Containment Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1 WHEN sampling the Containment for hydrogen, THEN perform the following: | |||
Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1 WHEN sampling the Containment for hydrogen, THEN perform the following: | |||
5.5.1.1 At the CASP perform the following: | 5.5.1.1 At the CASP perform the following: | ||
5.5.1.1.1 Verify ventilation is ON and mode control switches are in NORMAL position. | 5.5.1.1.1 Verify ventilation is ON and mode control switches are in NORMAL position. | ||
| Line 397: | Line 365: | ||
5.6.2.7 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly. | 5.6.2.7 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly. | ||
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 28 of 34 5.6.3 At the SAP perform the following: | CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 28 of 34 5.6.3 At the SAP perform the following: | ||
5.6.3.1 Close FPC-51. 5.6.3.2 WHEN RCHL line flush, THEN perform the following: | 5.6.3.1 Close FPC-51. 5.6.3.2 WHEN RCHL line flush, THEN perform the following: | ||
: a. Close FPC-51-14. | : a. Close FPC-51-14. | ||
: b. Close RC-423-1. | : b. Close RC-423-1. | ||
: c. Close CC-314. 5.6.3.3 WHEN RHR line flush, THEN perform the following: | : c. Close CC-314. 5.6.3.3 WHEN RHR line flush, THEN perform the following: | ||
: a. Close FCP-51-41. | : a. Close FCP-51-41. | ||
: b. Close CC-316. c. Close RC-V-1.l. | : b. Close CC-316. c. Close RC-V-1.l. | ||
5.6.4 At the LSP perform the following: | 5.6.4 At the LSP perform the following: | ||
| Line 411: | Line 379: | ||
5.6.4.10 Close RC-V-3. 5.6.4.11 Close RC-V-4. 5.6.4.12 Close RC-VREL-1, then open RC-VREL-1 approximately | 5.6.4.10 Close RC-V-3. 5.6.4.11 Close RC-V-4. 5.6.4.12 Close RC-VREL-1, then open RC-VREL-1 approximately | ||
/2 turn.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C | /2 turn.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C | ||
]Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date 152002 Page 29 of 34 6.0 Final Conditions | ]Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date 152002 Page 29 of 34 6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References 7.1 Sentry HRSS Operating and Maintenance Manual 7.2 RCC-063, RCS Gaseous Activity 7.3 RCC-082, Boron Analysis Curcumin Method 7.4 RCC-201, HRSR Conductivity, YSI Dissolved Oxygen, and pH Analysis 7.5 RCC-202, Hydrogen -Gas Chromatography (G.C.) Analysis -7.6 RCC-203, HRSR Post Accident Chloride-Ion Chromatography (IC) Analysis 7.7 RCC-520, DX-500 Startup and Shutdown Procedure 7.8 Commitment PLS-84-022 RQMT 2 -Step 5.3.14 (NOTE) 7.9 Commitment TEC-84-005, Step 5.1.13 and 5.1.14 7.10 EPIP-AD-11, Emergency Radiation Controls 7.11 OEA 93-160 7.12 KAP 1136, Corrective Action 2 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. | ||
Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References | |||
HRSS Operating and Maintenance Manual 7.2 RCC-063, RCS Gaseous Activity 7.3 RCC-082, Boron Analysis Curcumin Method 7.4 RCC-201, HRSR Conductivity, YSI Dissolved Oxygen, and pH Analysis 7.5 RCC-202, Hydrogen -Gas Chromatography (G.C.) Analysis -7.6 RCC-203, HRSR Post Accident Chloride-Ion Chromatography (IC) Analysis 7.7 RCC-520, DX-500 Startup and Shutdown Procedure | |||
PLS-84-022 RQMT 2 -Step 5.3.14 (NOTE) 7.9 Commitment TEC-84-005, Step 5.1.13 and 5.1.14 7.10 EPIP-AD-11, Emergency Radiation Controls 7.11 OEA 93-160 7.12 KAP 1136, Corrective Action 2 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. | |||
These records shall be maintained according to the KNPP Records Management Program. | These records shall be maintained according to the KNPP Records Management Program. | ||
8.1.1 QA Records None 8.1.2 Non-OA Records None CONTINUOUS USE HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 1 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom. SAMPLE ACQUISITION PANEL FPC-51 ........................................ | 8.1.1 QA Records None 8.1.2 Non-OA Records None CONTINUOUS USE HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 1 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom. SAMPLE ACQUISITION PANEL FPC-51 ........................................ | ||
| Line 662: | Line 620: | ||
Gas M arinelli Bypass Valve ............................................................. | Gas M arinelli Bypass Valve ............................................................. | ||
M ain Power Switch ............................................................................................................ | M ain Power Switch ............................................................................................................ | ||
Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 CONTINUOUS USE Page 34 of 34 AV-1i/SV-1.2 Closed Closed Closed Closed Closed Closed Closed Closed Closed Off Off Off Off Off Off Off Off Off Off Off Off Off Off On WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 10 Reviewed By (2_-Approved By Nuclear 0 Yes PORC 0 Yes SRO Approval Of 0 Yes Safety Review Temporary Related 0 No Required El No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for drawing and analyzing containment samples when directed by the Radiological Protection Director (RPD). 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 This procedure is to detail the requirements, considerations, and operations of the Containment Air Sample Panel (CASP) during a Post LOCA condition, to obtain a grab--sample of Containment air for Gross Gas, Iodine, Hydrogen, and Oxygen analyses. | Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 CONTINUOUS USE Page 34 of 34 AV-1i/SV-1.2 Closed Closed Closed Closed Closed Closed Closed Closed Closed Off Off Off Off Off Off Off Off Off Off Off Off Off Off On WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 10 Reviewed By (2_-Approved By Nuclear 0 Yes PORC 0 Yes SRO Approval Of 0 Yes Safety Review Temporary Related 0 No Required El No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for drawing and analyzing containment samples when directed by the Radiological Protection Director (RPD). 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 This procedure is to detail the requirements, considerations, and operations of the Containment Air Sample Panel (CASP) during a Post LOCA condition, to obtain a grab--sample of Containment air for Gross Gas, Iodine, Hydrogen, and Oxygen analyses. | ||
3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit as needed per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact the Radiation Protection (HP) Group and obtain the following: | |||
and Limitations | |||
an Emergency Radiation Work Permit as needed per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact the Radiation Protection (HP) Group and obtain the following: | |||
* Proper personnel dosimetry | * Proper personnel dosimetry | ||
* Proper radiation detection instrumentation | * Proper radiation detection instrumentation | ||
| Line 676: | Line 628: | ||
3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude: | 3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude: | ||
* Gas 5.0 Millicuries/cc | * Gas 5.0 Millicuries/cc | ||
* Iodine 0.2 Millicuries/cc | * Iodine 0.2 Millicuries/cc 4.0 Initial Conditions 4.1 The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure. | ||
n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach 5.0 Procedure 5.1 Obtain all necessary equipment prior to beginning to sample the Containment atmosphere. | |||
Conditions 4.1 The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure. | |||
n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach | |||
all necessary equipment prior to beginning to sample the Containment atmosphere. | |||
This equipment includes: | This equipment includes: | ||
* Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1 | * Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1 | ||
| Line 696: | Line 640: | ||
* Portable shields for transporting syringes | * Portable shields for transporting syringes | ||
* Marinelli beaker (give to HIP to be counted prior to sample injection) | * Marinelli beaker (give to HIP to be counted prior to sample injection) | ||
* Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2 WHEN preparing for CASP operation, THEN perform the following: | * Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2 WHEN preparing for CASP operation, THEN perform the following: | ||
5.2.1 Proceed to HRSR per HP/RPD recommendations. | |||
5.2.2 Determine radiation levels in HRSR and in maintenance area behind panels, if access is required. | |||
to HRSR per HP/RPD recommendations. | 5.2.3 Verify that heat tracing is ON. 5.2.4 Verify ventilation is ON and in NORMAL position and high vacuum lights indicate NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel (CAP), and CASP. 5.2.5 Verify that instrument air supply is available at >_ 70 psi. 5.2.6 Verify that CASP and CASP control panels are energized and operational. | ||
5.2.7 Verify valve lineup per Attachment A, "Containment Air Sample Valve Lineup Sheet." CONTINUOUS USE Note The sample cart may be checked to verify it is properly locked in place by carefully pulling. | |||
5.2.8 Verify the ISC in the #1 position is locked in place. Note Only Sample Station 1 shall be used for Iodine Analysis. | |||
Due to ALARA considerations, if available, both containment air sample trains should be aligned. | |||
radiation levels in HRSR and in maintenance area behind panels, if access is required. | 5.2.9 Contact the Control Room and verify Dome Fans 1A and lB are operational. | ||
that heat tracing is ON. 5.2.4 Verify ventilation is ON and in NORMAL position and high vacuum lights indicate NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel (CAP), and CASP. 5.2.5 Verify that instrument air supply is available at >_ 70 psi. 5.2.6 Verify that CASP and CASP control panels are energized and operational. | |||
valve lineup per Attachment A, "Containment Air Sample Valve Lineup Sheet." CONTINUOUS USE Note The sample cart may be checked to verify it is properly locked in place by carefully pulling. | |||
the ISC in the #1 position is locked in place. Note Only Sample Station 1 shall be used for Iodine Analysis. | |||
Due to ALARA considerations, if available, both containment air sample trains should be aligned. | |||
the Control Room and verify Dome Fans 1A and lB are operational. | |||
5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel: "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Position LOCA 2B (Local/Remote) to LOCAL. "* Position SA 7003B (Local/Remote) to LOCAL. "* Open LOCA 2B. "* Open LOCA 1OB. "* Open SA 7003B. 5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B): a. The hydrogen monitor is NOT in operation, OR b. The sample loop selected is opposite that being used by H 2 monitor. | 5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel: "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Position LOCA 2B (Local/Remote) to LOCAL. "* Position SA 7003B (Local/Remote) to LOCAL. "* Open LOCA 2B. "* Open LOCA 1OB. "* Open SA 7003B. 5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B): a. The hydrogen monitor is NOT in operation, OR b. The sample loop selected is opposite that being used by H 2 monitor. | ||
5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A. 5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B. 5.2.14 Open SV-10. 5.2.15 Open SV-6. 5.2.16 Open SV-5. 5.2.17 Verify flow monitor on CASP is indicating flow. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 202 Pa 4 5.2.18 Wait at least 2 minutes. | 5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A. 5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B. 5.2.14 Open SV-10. 5.2.15 Open SV-6. 5.2.16 Open SV-5. 5.2.17 Verify flow monitor on CASP is indicating flow. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 202 Pa 4 5.2.18 Wait at least 2 minutes. | ||
5.2.19 Open AV-1/SV 1.2. 5.2.20 Close SV-5. 5.2.21 Open AV-2. 5.2.22 Wait at least 3 minutes. | 5.2.19 Open AV-1/SV 1.2. 5.2.20 Close SV-5. 5.2.21 Open AV-2. 5.2.22 Wait at least 3 minutes. | ||
5.2.23 Align the ISC Cart as follows: 5.2.23.1 Open V-4, Cart Inlet Valve. 5.2.23.2 Open V-6, Outlet Valve. 5.2.23.3 Close V-5, Bypass Valve. 5.2.23.4 Verify CASP flow monitor is indicating flow. 5.3 WHEN collecting a Containment Air sample, THEN perform the following: | 5.2.23 Align the ISC Cart as follows: 5.2.23.1 Open V-4, Cart Inlet Valve. 5.2.23.2 Open V-6, Outlet Valve. 5.2.23.3 Close V-5, Bypass Valve. 5.2.23.4 Verify CASP flow monitor is indicating flow. 5.3 WHEN collecting a Containment Air sample, THEN perform the following: | ||
5.3.1 Close SV-6. 5.3.2 Verify flow monitor on CASP indicates NO flow. Note An appropriate period for flow monitor pressure equalization is one minute. 5.3.3 Allow the flow monitor to equalize pressure for at least 1 minute. 5.3.4 WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows: 5.3.4.1 Draw the following samples from the ISC. a. Two 5 microliter samples b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 -1.0 cc syringe samples. | |||
SV-6. 5.3.2 Verify flow monitor on CASP indicates NO flow. Note An appropriate period for flow monitor pressure equalization is one minute. 5.3.3 Allow the flow monitor to equalize pressure for at least 1 minute. 5.3.4 WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows: 5.3.4.1 Draw the following samples from the ISC. a. Two 5 microliter samples b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 -1.0 cc syringe samples. | |||
: c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 -2.0 cc syringe sample.CONTINUOUS USE VlA ,ilq/ilft l r , I.RI,. ir"* ~rVi..a .i vvRN. .......... | : c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 -2.0 cc syringe sample.CONTINUOUS USE VlA ,ilq/ilft l r , I.RI,. ir"* ~rVi..a .i vvRN. .......... | ||
...Re. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 5 of 10 5.3.4.2 IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following: | ...Re. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 5 of 10 5.3.4.2 IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following: | ||
5.3.4.2.1 Lock the tips. 5.3.4.2.2 Insert the needle of each syringe in a rubber stopper to prevent damage. 5.3.4.2.3 Place the syringes in a portable shield for transport. | 5.3.4.2.1 Lock the tips. 5.3.4.2.2 Insert the needle of each syringe in a rubber stopper to prevent damage. 5.3.4.2.3 Place the syringes in a portable shield for transport. | ||
5.3.5 Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis. | 5.3.5 Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis. | ||
5.4 WHEN shutting down and cleaning out the system, THEN perform the following: | 5.4 WHEN shutting down and cleaning out the system, THEN perform the following: | ||
5.4.1 Close AS 11 OA OR AS 11 B, as appropriate. | |||
5.4.2 Open SV-6 and evacuate the ISC cart. 5.4.3 Wait at least 2 minutes. | |||
AS 11 OA OR AS 11 B, as appropriate. | 5.4.4 Close V-4, Cart Inlet Valve. 5.4.5 Close V-6, Outlet Valve. 5.4.6 Open V-5, Bypass Valve. 5.4.7 Open AS 11OA OR AS 11GB, as appropriate. | ||
5.4.2 Open SV-6 and evacuate the ISC cart. 5.4.3 Wait at least 2 minutes. | 5.4.8 Close AV-2. 5.4.9 Verify flow monitor has flow. 5.4.10 Wait at least 2 minutes. | ||
V-4, Cart Inlet Valve. 5.4.5 Close V-6, Outlet Valve. 5.4.6 Open V-5, Bypass Valve. 5.4.7 Open AS 11OA OR AS 11GB, as appropriate. | |||
AV-2. 5.4.9 Verify flow monitor has flow. 5.4.10 Wait at least 2 minutes. | |||
5.4.11 Open SV-5. 5.4.12 Close AV-1/SV1.2. | 5.4.11 Open SV-5. 5.4.12 Close AV-1/SV1.2. | ||
5.4.13 Verify flow monitor has flow. 5.4.14 Wait at least 1 minute. 5.4.15 Close SV-10. 5.4.16 Close SV-6. 5.4.17 Close SV-5.CONTINUOUS USE I Rev. N WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D I Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 10 5.4.18 Close AS11 OA OR AS1 OB, as appropriate. | 5.4.13 Verify flow monitor has flow. 5.4.14 Wait at least 1 minute. 5.4.15 Close SV-10. 5.4.16 Close SV-6. 5.4.17 Close SV-5.CONTINUOUS USE I Rev. N WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D I Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 10 5.4.18 Close AS11 OA OR AS1 OB, as appropriate. | ||
5.4.19 Reset "Active/Inactive" indicator lights to INACTIVE. | 5.4.19 Reset "Active/Inactive" indicator lights to INACTIVE. | ||
5.5 WHEN analyzing a sample for Iodine, THEN perform the following: | 5.5 WHEN analyzing a sample for Iodine, THEN perform the following: | ||
5.5.1 Place a Silver Zeolite sample cartridge in a holder. 5.5.2 Attach a hose from the holder to a vacuum source in the HRSR Fume Hood. 5.5.3 Establish air flow through the filter cartridge. | |||
5.5.4 Inject a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge. | |||
a Silver Zeolite sample cartridge in a holder. 5.5.2 Attach a hose from the holder to a vacuum source in the HRSR Fume Hood. 5.5.3 Establish air flow through the filter cartridge. | 5.5.5 Remove the Silver Zeolite cartridge from its holder and monitor it for radiation. | ||
a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge. | |||
the Silver Zeolite cartridge from its holder and monitor it for radiation. | |||
-7 5.5.6 Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting. | -7 5.5.6 Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting. | ||
Note Point Beach Nuclear Plant uses an identical geometry as Kewaunee for counting iodine samples. | Note Point Beach Nuclear Plant uses an identical geometry as Kewaunee for counting iodine samples. | ||
| Line 761: | Line 678: | ||
5.6.2 IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following: | 5.6.2 IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following: | ||
5.6.2.1 Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle. 5.6.2.2 Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination. | 5.6.2.1 Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle. 5.6.2.2 Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination. | ||
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 7 ofl1 5.7 WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following: | CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 7 ofl1 5.7 WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following: | ||
5.7.1 Based on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows: RCC-080, "Gas Chromatograph, Baseline 1010A " Baseline 101OA Gas Operation Using a Chart Recorder" Chromatograph RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software" " SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2 Verify that the gas chromatograph is: "* Turned on "* Operating properly "* Correctly calibrated 5.7.3 WHEN the gas chromatograph is verified operable, THEN perform the following: | |||
on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows: RCC-080, "Gas Chromatograph, Baseline 1010A " Baseline 101OA Gas Operation Using a Chart Recorder" Chromatograph RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software" " SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2 Verify that the gas chromatograph is: "* Turned on "* Operating properly "* Correctly calibrated 5.7.3 WHEN the gas chromatograph is verified operable, THEN perform the following: | |||
5.7.3.1 WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results. | 5.7.3.1 WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results. | ||
5.7.3.2 WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results. | 5.7.3.2 WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results. | ||
5.7.4 Report all results obtained to the RPD.CONTINUOUS USE 5.8 WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel: | |||
all results obtained to the RPD.CONTINUOUS USE 5.8 WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel: | |||
* Close LOCA 2A. | * Close LOCA 2A. | ||
* Close LOCA 1OA. | * Close LOCA 1OA. | ||
| Line 777: | Line 690: | ||
* Close SA 7003B. | * Close SA 7003B. | ||
* Position LOCA 2B (Local/Remote) to REMOTE. | * Position LOCA 2B (Local/Remote) to REMOTE. | ||
* Position SA 7003B (Local/Remote) to REMOTE. 6.0 Final Conditions 6.1 This procedure is closed out when the Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References | * Position SA 7003B (Local/Remote) to REMOTE. 6.0 Final Conditions 6.1 This procedure is closed out when the Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References 7.1 Sentry HRSS Operating and Maintenance Manual 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4 RCC-080C, Operation of the SRI 8610 Gas Chromatograph 7.5 RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer Software 7.6 TS 6.1 l.b.2 CONTINUOUS USE 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. | ||
HRSS Operating and Maintenance Manual 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4 RCC-080C, Operation of the SRI 8610 Gas Chromatograph 7.5 RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer Software 7.6 TS 6.1 l.b.2 CONTINUOUS USE | |||
8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. | |||
These records shall be maintained according to the KNPP Records Management Program. | These records shall be maintained according to the KNPP Records Management Program. | ||
8.1.1 QA Records None 8.1.2 Non-QA Records None CONTINUOUS USE CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL A V -1 / SV -1.2 .................. | 8.1.1 QA Records None 8.1.2 Non-QA Records None CONTINUOUS USE CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL A V -1 / SV -1.2 .................. | ||
Revision as of 06:42, 14 July 2019
| ML020440560 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 01/16/2002 |
| From: | Webb T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| -RFPFR, NRC-02-009 | |
| Download: ML020440560 (58) | |
Text
Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 NM C 920.388.2560 920.755.2321 Committed to Nuclear Excellence Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-009 January 16, 2002 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:
DOCKET 50-305 OPERATING LICENSE DPR-43 KEWAUNEE NUCLEAR POWER PLANT RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50 Appendix E, attached is the latest revisions to the Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures (EPIPs). These revised procedures supersede the previously submitted procedures.
Pursuant to 10 CFR 50.4, two additional copies of this letter and attachment are hereby submitted to the Regional Administrator, U. S. Nuclear Regulatory Commission, Region III, Lisle, Illinois.
As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.
Sincerely, Thomas J. Webb Site Licensing Director SLC Attachment cc -US NRC Senior Resident Inspector, w/attach.
US NRC, Region III (2 copies), w/attach.
Electric Division, PSCW, w/o attach. QA Vault, w/attach.
A Cos DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL -KNPP TRANSMITTAL DATE 01-15-2002"EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20) T. Webb -NRC Document Control Desk (1)* Krista Kappelman
-PBNP -EP (10)* T. Webb -NRC Region m (2 & 3)* Craig Weiss -Wisconsin Power & Light (11)* T. Webb -NRC Resident Inspector (4) (receives Appx. A phone numbers)*
T. Webb -State of Wisconsin (5)* Jim Holthaus -Nuclear Management Company (12)* T. Webb -KNPP QA Vault w/NRC Letter (15)* PERSONAL COPIES (21-40) These copies are for the personal use of the listed individuals for reference or emergency response.J. Bennett (33) D. Masarik (32)D. Mielke (35) D. Seebart (24)H. Kocourek (13) B. Bartelme (34)T. Coutu (28)REFERENCE COPIES -CUSTODIAN (41-100) These copies are for general reference by anyone. They are -distributed throughout the plant and corporate offices. The named individual is the responsible custodian for the procedures and shall insure they are properly maintained.
STF (86, 87, 88) L. Welch -Fuel Services (65) NO Library -KNPP (59) C. Sternitzky
-ATF-2 (44) D. Braun -ATF-3 (45) P. Ehlen -I&C Office (42) M. Daron -Security Building (46) P&FS Adm -GB D2-3 (EOF) (81) H.Kocourek
-OSF (52) C. Hutter -ATF-1 (64)LOREB -STF (62, 66, 67, 68, 70, 72, 73, 74) STF Library (43) Resource Center -Training (82, 89, 94, 131) D. Schrank -Maintenance Off. (41) D. Krall -CR/SS Office (51, 56) P&FS Adm -GB-D2 (Nuclear Library) (84) H. Kocourek -TSC (50) W. Galarneau
-RAF (53) W. Galarneau
-SBF/EMT (54) W. Galarneau
-RPO (55)WORKING COPIES (101-199)
These copies of procedures are kept in the areas designated for use in response to an emergency.
These are not complete sets, but contain only those procedures that are used to implement activities in the location where they are kept. Please dispose of any sections distributed that are not tabbed in the indicated copy.W. Galarneau
-RAF/RPO (106, 107) W. Galarneau
-SBF/ENV (108, 109) W. Galarneau
-SBF/EM Team (110, 111, 1llA) W. Galarneau
-Aurora Medical Center (118, 119) W. Flint -Cold Chem/HR Sample Room (113) N. Deda -SBF/SEC (114)D. Krall -CR/Communicator (1 16)(Partial Distribution)
Simulator/Communicator (117) M. Fencl -Security (121) N. Deda -Security Building (120) S. VanderBloomen (125) J. Stoeger (126)Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!!
These are controlled procedures and random checks may be made to ensure the manuals are kept up-to-date.
- THIS IS NOT A CONTROLLED COPY. ITIS A COPYFOR INFORMATION ONLY.1 KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES January 15, 2C02 Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719. If you are a controlled copy holder (see cover page), return this page to Diane Fencl by February 15, 2002, SIGNED AND DATED to serve as a record of revision.
EPIP Index, dated 01-15-2002.
REMOVE INSERT PROCEDURE RE
V. PROCEDURE
REV. EP-RET-3C 0 EPIP-RET-03C P EP-RET-3D M EPIP-RET-03D N Returnii a~signed and dated copy, of this transmittal letter, -within 10 days of receipt, to the sender. Ifyou have any questions or comments, please call Dave Seebart.Diane end Enclosure 2 I I CERTIFY Copy No.__ (WPSC No.) of the Kewaunee Nuclear Power Plant's EPIPs has been updated.
SIGNATURE DATE Please return this sheet to DIANE FENCL.g I I EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. N. TITLE REV. DATE EP-AiD EPIP-AD-01 Personnel Response to the Plant-Emergency J 01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AC 11-15-2001 EPIP-AD-03 KNPP Response to an Unusual Event AD 12-14-2001 EPIP-AD-04 KNPP Response to Alert or Higher AP 12-14-2001 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief C 06-05-2001 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AN 11-15-2001.
EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD- 10 Notification of General Emergency Deleted 04-27-87 EPIP-AD- 1 I Emergency Radiation Controls Q 09-27-2001 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD- 13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 0 10-30-2001 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution 0 06-05-2001 EPIP-AD-1 9 Protective Action Guidelines Q 11-27-2001 PAGE I OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROC. NO. TITLE EPIP-AD-20 KNPP Response to a Security Threat EP-ENV DATE: 01-15-2002 EPIP-ENV-01 Environmental Monitoring Group Organization V 10-02-2001 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X 10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 V 10-09-2001 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data) EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use S 06-15-2000 EPIP-ENV-04B Air Sampling and Analysis W 10-09-2001 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis W 10-09-2001 EPIP-ENV-04D Plume Tracking for Environmental Monitoring N 10-02-2001 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 PAGE 2 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-ENV-6 I Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of Deleted 04-14-86 EM Team EP-ENV-6A Relocation of Site Access Facility (Habitability)
Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation Z 11-29-2001
_ EPIP-EOF-03 EOF Staff Action for Unusual Event AB 12-14-2001 EPIP-EOF-04 EOF Staff Action for Alert or Higher AH 12-14-2001 EP-EOF-5 Corporate Staff Action for Site Emergency Deleted 04-24-87 EP-EOF-6 Corporate Staff Action for General Emergency Deleted 04-24-87 EP-EOF-7 Notification of Unusual Event Deleted 04-06-94 EP-EOF-8 Relocation of EOF Deleted 03-01-83 EPIP-EOF-08 Continuing Emergency Notifications T 11-27-2001 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-1I Internal Communication and Documentation U 11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation P 07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations T 11-29-2001 EPIP-OSF-03 Work Requests During an Emergency 0 09-27-2001 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87-_
EPIP-OSF-04 Search and Rescue D 09-12-2000 EP-RET EP-RET- 1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team U 11-27-2001 EPIP-RET-02A Radiation Protection Office/Radiological' T 11-29-2001 Analysis Facility (RPO/RAF)
Activation EP-RET-2B Gaseous Effluent Sample and Analysis Q 03-03-98 EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EPIP-RET-03C Post Accident Operation of the High Radiation P 01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N 01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation R 10-02-2001 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H 10-09-2001 Plant Cooldown EP-RET-5A Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical P 10-30-2001 Center EPIP-RET-09 Post-Accident Population Dose K 08-29-2000 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies W 08-28-2001 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AC 12-14-2001 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation F 07-05-2001 EP-TSC EPIP-TSC-01 Technical Support Center Organization and P 10-02-2001 Responsibilities EPIP-TSC-02 Technical Support Center Activation S 11-29-2001 EPIP-TSC-03 Plant Status Procedure V 10-09-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment M 10-02-2001 Repair EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation I 10-19-2001 EPIP-TSC-08A Calculations for Steam Release from Steam N 12-14-2001 Generators EPIP-TSC-08B*
STMRLS Computer Program F 10-02-2001 EP-TSC-8C*
See EP-TSC-8B Deleted 04-16-92
- EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EP-TSC-9A*
Core Damage Assessment I 02-23-99 EPIP-TSC-09B*
CORE Computer Program J 10-02-2001 EP-TSC-9C*
See EP-TSC-9B Deleted 04-16-92
EP-TSC-9B was previously EP-TSC-9C.
EPIP-TSC-10 Technical Support for IPEOPs I 03-20-2001 PAGE 6 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FIGURES EPIP FIG # 1 Figure EPIPFG DESCRIPTION REV. DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003 APPX-A-06-03 Center -KNP Floor Plan B 06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-oos APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis Facility -KNP Floor EPIP-APPX-A-06 EP-FIG-008 APPX-A-06-01 Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG-009 EOF- 12-01 (2nd Floor) Floor Plan B 10-24-2000 State/County Work Area -WPSC D2-1 EPIP-APPX-A-06 EP-FIG-012 APPX-A-06-08 Floor Plan C 10-31-2000 NRC Work Area EPIP-APPX-A-06 EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution by Geographical Sub EPIP-AD-19 EP-FIG-014 AD-19-01 Areas (with sectors) A 10-31-2000 EOF -WPSC D2-3 EPIP-APPX-A-06 EP-FIG-022 APPX-A-06-04 Floor Plan C 10-30-2001 Map -Location of JPIC, EPIP-EOF-12 EP-FIG-024 EOF-12-02 MBC, GOB, DOB, etc. B 09-27-2001 EP-SEC-5 EP-FIG-026 SEC-05-01 Site Map B 09-27-2001 Floor Plan -Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 EPIP-EOF-12 General Office Building -WPSC (1st EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C 10-24-2000 Floor Plan -Corporate APPX-A-6 EP-F-o37 ---Response Center Deleted 08-04-98 APPX-A-6 EP-FIG-038
---Floor Plan -JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FIG-039 OSF-02-01 High Priority Work A 10-02-2001 EPIP-OSF-02 EP-FIG-039A OSF-02-02 Lower Priority Work A 10-02-2001 JPIC -Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area -WPSC D2-9 B 12-21-2001 JPIC -State and County Work Area EPIP-APPX-A-06 EP-FIG-044 APPX-A-06-07 WPSC D2-8 C 12-21-2001 JPIC -Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area -WPSC D2-7 C 12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location A 06-15-2000 EPIP-APPX-A-02
--- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES DATE: 01-15-2002 INDEX NUMBER TITLE APPENDIX A APPX-A-I Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form) AD-07-02 State Call-Back
-Question Guideline C 11-15-2001 AD 11.1 Emergency Radiation Work Permit F 04-16-96 EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-1 1-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 PAGE 9 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-20Q1 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management
-Status A 04-01-99 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist PAGE 10 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D 12-14-2001 Program) TSC 9A. 1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp. TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 34 Reviewed Bv Approved By ----:Z -'-,, Nuclear [] Yes AORC _ Yes SRO Approval Of 2 Yes Safety Review Temporary Related 13 N Reuired [] No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions:
- a. Diluted liquid sample of primary coolant for: (Step 5.1)0 Boron analysis b. An inline liquid sample for: (Step 5.2)0 Gamma isotopic analysis"* pH 0 Oxygen "* Conductivity
- c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3) d. A diluted gas sample for gamma isotopic analysis. (Step 5.3) e. An undiluted liquid sample for off-site analysis. (Step 5.4) f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5) g. Flush of liquid sample lines. (Step 5.6) 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 The following is a list of acronyms that are used throughout this procedure:
- CASP
- CMP *DDT
- HVAC/CCP
- HP/RPD
- HRSR
- LSP
- RCHL
- SAP Chemical Analysis Panel Containment Air Sampling Panel Chemical Analysis Monitor Panel Deaerated Drain Tank HVAC/Containment Air Sample Control Panel Health Physics/Radiation Protection Director High Radiation Sample Room RCHL Liquid Sample Panel Reactor Coolant Hot Leg Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 2 of 34 3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact Radiation Protection Group (HIP) for: 3.2.1 Proper personnel dosimetry 3.2.2 Proper radiation detection instrumentation 3.2.3 Personnel for continuous HIP coverage during sampling 3.2.4 Remote area monitor readings in area of HRSR 3.3 Utilize on-site communications with the HP/RPD, as necessary, during sampling.
3.4 Containment sump pH should be adjusted to a pH > 7 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following the initiation of recirculation during a small break loss of coolant accident.
3.5 If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist.
- No direct temperature indicator is available.
- Sample flow is automatically isolated when sample temperatures exceed 120°F and automatically resets when the temperatures are reduced.
- If sample flow is restored without having to take action, then high temperature isolation is confirmed.
- Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer.
High Component Cooling temperature may occur if Service Water temperatures are elevated.
3.6 IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling.
3.7 Transit routes to and from the HRSR per HP/RPD recommendations.
3.8 Monitor radiation levels in the HRSR upon entry and during sample manipulations.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 3 of 34 3.9 Radiation level monitoring is required if accessing the maintenance areas behind the panels. 3.10 IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates. 4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director.
5.0 Procedure 5.1 Diluted Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1 In the HRSR check the following equipment available and operational:
"* Drying oven on at 55°C to 60*C "* All material required to perform RCC-082, "Boron Analysis Curcumin Method." "* Multi-Channel Analyzer available for counting (Technical Support Center) " 2 -1 liter poly bottles "* Shielded aliquoter available
"* New 60 ml diluted sample bottle (large bottle) "* Hand operated vacuum pump "* Lights on in diluted sample port of LSP "* LSP Sample Cask available with diluted sample bottle piston installed
"* Reach Rod for remote valve operation CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 4 of34 5.1.2 At the CASP perform the following:
5.1.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.1.2.2 Check High Vacuum Lights indicate NORMAL for the following:
"* LSP " CAP "* CASP 5.1.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.1.4 Connect DI Water flush hose to LSP. 5.1.5 Open DI Water supply valve to LSP. 5.1.6 Evacuate the diluted sample bottle (60 ml, large bottle) to > 15 inches of vacuum. IF possible, THEN >20 inches of vacuum is recommended.
5.1.6.1 Install sample bottle in sample cask. 5.1.6.2 Check cask for proper operation (large holder in cask). 5.1.7 At the LSP perform the following:
5.1.7.1 Inspect dilution water reservoir level. 5.1.7.2 IF necessary, THEN fill to full mark. 5.1.8 WHEN performing an RCHL sample, THEN request Control Room Operator perform the following:
"* Open RC-422. "* Open RC-423.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 5 of 5.1.9 At the SAP perform the following:
5.1.9.1 WHEN performing an RCHL sample, THEN perform the following: " Open CC-314. "* Open RC-423-1.
5.1.9.2 WHEN performing a Residual Heat Removal (RHR) sample, THEN perform the following:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
"* WHEN sampling B RHR, THEN open RHR-81-B.
5.1.9.3 Position RC-437-1 to DDT. 5.1.9.4 Position RC-437-2 to DDT. 5.1.10 At the LSP perform the following:
5.1.10.1 Open RC-V3. 5.1.10.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.1.10.3 WHEN performing a RHR sample, THEN open RC-V-1.1.
Note Purge time may be varied based on actual purge flow rate obtained.
5.1.10.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
"* WHEN RHR sample, THEN purge at least 25 minutes.
5.1.10.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.1.10.6 WHEN purge is complete, THEN perform the following:
- a. Close RC-V-3. b. Open RC-V-8.2.
- c. Open RC-V-8.1.
- d. Open RC-V-2.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 34 Note Purge time may be varied based on purge flow rate obtained.
5.1.10.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.1.10.8 Purge at least 3 minutes.
5.1.10.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN 20 inches of vacuum is recommended.
5.1.10.11 Install the sample cart under the diluted sample port. 5.1.10.12 Position the sample bottle up on the needles.
5.1.10.13 WHEN purge is complete, THEN perform the following:
- a. Turn RC-DV-1 to SAMPLE position (6 o'clock).
- b. IF RCHL sample, THEN close RC-V-1.2.
- c. IF RHR sample, THEN close RC-V-1.1.
5.1.10.14 Throttle open RC-V-21.
5.1.10.15 Add 24 ml of DI Water to the sample bottle. 5.1.10.16 IF less than 24 ml of DI Water is used, THEN note sample volume. 5.1.10.17 Close RC-V-21.
5.1.10.18 Turn RC-DV-1 to BYPASS position (3 o'clock).
5.1.10.19 Open RC-V-4. Note Flush time may be varied based on actual flush flow rate obtained.
5.1.10.20 Throttle RC-VEL-2 until flow indicator RC-FI-2 indicates 180 to 200 cc/min. 5.1.10.21 Flush for at least 3 minutes.
5.1.10.22 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
CONTINUOUS USE
~AIgr./4, NJi%.II 1 IR V IC~l, ~Fv ICF COR I .N.........
.....C.ev. Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 7 of 34 Note The following step may be performed during the flush. 5.1.10.23 Lower the diluted sample bottle into the sample cask. "* Close the cask "* Place cask near fume hood "* Install auxiliary shield 5.1.10.24 Close RC-V-4. 5.1.10.25 Close RC-V-2. 5.1.10.26 Close RC-V-8.2.
5.1.10.27 Close RC-V-8.1.
5.1.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close RC-422. "* Close RC-423. 5.1.12 At the SAP perform the following:
5.1.12.1 WHEN RCHL sample, THEN perform the following:
"* Close RC-423-1.
"* Close CC-314. 5.1.12.2 WHEN RHR sample, THEN perform the following:
"* IF opened, THEN close RHR-81A.
"* IF opened, THEN close RHR-81B.
"* Close CC-316. 5.1.12.3 Position RC-437-1 toVCT. 5.1.12.4 Position RC-437-2 to VCT. 5.1.12.5 Close DI Water supply valve. 5.1.12.6 Disconnect DI Water hose.CONTINUOUS USE I Rev. P No.
WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 _ Page 8 of 34 Note Dilution factor correction is required ifsample was not diluted with 24 ml of DI Water Step 5.1.10.16.
5.1.13 Perform the following post sample analyses preparations:
Note For Boron analysis of< 2,000 ppm, an appropriately larger amount of sample shall be used. 5.1.13.1 WHEN analyzing for boron, THEN perform the following:
- a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter.
- b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin -Method." 5.1.13.2 WHEN performing a Beta/Gamma analysis, THEN perform the following:
- a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter.
- b. Dilute to 1 liter with DI Water. c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle. d. Dilute to 1 liter with DI Water. Dilution factor = 108. e. Transfer sample to the multi-channel analyzer for counting.
5.2 Inline Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.2.1 Align argon and helium as follows: 5.2.1.1 Verify open argon gas cylinder isolation.
5.2.1.2 Verify argon cylinder pressure >_ 400 psi. 5.2.1.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.2.1.4 Verify open helium gas cylinder isolation.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 9 of 34 5.2.1.5 Verify helium cylinder pressure > 400 psi. 5.2.1.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.2.2 Verify reach rod is available for remote valve operation.
5.2.3 Check HRSR Calibration Log for verification of latest performances.
5.2.4 At the CASP perform the following:
5.2.4.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.2.4.2 Check High Vacuum Lights indicate NORMAL for the following:
5.2.5.1 CMP Main Power switch ON. 5.2.5.2 Verify the YSI chart recorder is ON. 5.2.5.3 Verify the pH meter is ON. 5.2.5.4 Verify the conductivity meter is ON. 5.2.5.5 Start Ion Chromatograph (IC) in accordance with RCC-520, "DX-500 Startup and Shutdown Procedure." 5.2.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.2.7 At the CAP, verify argon, helium, and air regulators set as follows: 5.2.7.1 Adjust argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.2.7.2 Adjust helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.2.7.3 Adjust air pressure regulator to obtain 75 psi (75 to 85 psi). 5.2.8 Connect DI Water flush hoses to LSP and CAP. 5.2.9 Open DI Water supply valve to LSP. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Inmplementing Procedure Date AN 152002 Page 10 of 34 5.2.10 Open DI Water supply valve to CAP. 5.2.11 At the CAP perform the following:
5.2.11.1 Position V-6 to LIQUID SAMPLE (9 o'clock).
5.2.11.2 Position V-5 to LIQUID SAMPLE (9 o'clock).
5.2.12 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Open RC-422. "* Open RC-423. 5.2.13 At the SAP perform the following:
5.2.13.1 WHEN performing an RCHL sample, THEN perform the following:
"* Open CC-314. "* Open RC-423-1.
5.2.13.2 WHEN performing a RHR sample, THEN perform the following:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
"* WHEN sampling B RI{R, THEN open RHR-8 1-B. 5.2.13.3 Position RC-437-1 to DDT. 5.2.13.4 Position RC-437-2 to DDT. 5.2.14 At the LSP perform the following:
5.2.14.1 Open RC-V3. 5.2.14.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.2.14.3 WHEN performing a RHR sample, THEN open RC-V-1.1.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C -TRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 11 of 34 Note Purge time may be varied based on actual purge flow rate obtained.
5.2.14.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
"* WHEN RHR sample, THEN purge at least 25 minutes.
5.2.14.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.14.6 WHEN purge is complete, THEN perform the following:
"* Close RC-V-3. "* Open RC-V-2. "* Open RC-V-7. "* Position RC-V-22 to CHEM PANEL. Note Purge time may be varied based on actual purge flow rate obtained.
5.2.14.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.2.14.8 Purge at least 5 minutes.
5.2.14.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.15 At the CAP perform the following:
5.2.15.1 Verify adequate flow to the CAP by observing the red lights ON for both Oxygen and IC. 5.2.15.2 WHEN the YSI 02 meter chart reading has stabilized, THEN record the following on the Reactor Coolant Analysis Log (routine logsheet):
- Conductivity reading
- Temperature
- 02 reading CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C 1 Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 12 of 34 5.2.15.3 Inject sample on IC unit.
- WHEN IC run complete, THEN record Chloride value on the Reactor Coolant Analysis Log (routine logsheet) and attach chart recorder printout.
5.2.16 At the LSP perform the following:
5.2.16.1 Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.2 WHEN RCHL sample, THEN close RC-V-1.2.
5.2.16.3 WHEN RHR sample, THEN close RC-V-1.1.
5.2.16.4 Open RC-V-4. 5.2.16.5 Observe DI Water flush to waste as indicated on Flow Indicator RC-FI-2.
5.2.16.6 Flush for 2 minutes.
5.2.16.7 Record pH reading on the Reactor Coolant Analysis Log (routine logsheet).
5.2.16.8 Turn RC-V-22 to CAP position (12 o'clock).
5.2.16.9 Verify flush water flow by observing the lights ON for both 02 Flow and IC Flow. 5.2.16.10 Flush for at least 2 minutes.
5.2.16.11 Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.12 Close RC-V-7. 5.2.16.13 Close RC-V-2. 5.2.16.14 Close RC-V-4. 5.2.17 At the CAP perform the following:
5.2.17.1 Position V-6 to 02 CAL (6 o'clock).
5.2.17.2 Close V-5 (6 o'clock).CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date AN1 5 2002 Page 13 of 34 5.2.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close RC-422. "* Close RC-423. 5.2.19 At the SAP perform the following:
5.2.19.1 WHEN RCHL sample, THEN perform the following:
"* Close RC-423-1.
"* Close CC-314. 5.2.19.2 WHEN RJ{R sample, THEN perform the following:
"* IF opened, THEN close RHR-81A.
"* IF opened, THEN close RHR-81B.
"* Close CC-316. 5.2.19.3 Position RC-437-1 to VCT. 5.2.19.4 Position RC-437-2 to VCT. 5.2.19.5 Close DI Water supply valve. 5.2.19.6 Disconnect DI Water hose. 5.3 Inline Hydrogen and Gaseous Activity Grab Sample 5.3.1 Verify the multi-channel analyzer available for counting.
Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.3.2 Align argon and helium as follows: 5.3.2.1 Verify open argon gas cylinder isolation.
5.3.2.2 Verify argon cylinder pressure 400 psi. 5.3.2.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.3.2.4 Verify open helium gas cylinder isolation.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 14 of 34 5.3.2.5 Verify helium cylinder pressure _> 400 psi. 5.3.2.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.3.3 At the CASP perform the following:
5.3.3.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.3.3.2 Check High Vacuum Lights indicate NORMAL for the following:
"* LSP "* CA-P "* CASP 5.3.4 Verify the following equipment available and operational:
- Reach Rod for remote valve operation
- 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5 At the CMP perform the following:
5.3.5.1 CMP Main Power switch ON. 5.3.5.2 Verify the program in Gas Chromatograph (GC) mini-computer.
5.3.5.3 Check HRSR Calibration Log for verification of latest performances.
5.3.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.3.7 At the CAP, verify Argon, Helium, and Air regulators set as follows: 5.3.7.1 Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.3.7.2 Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.3.7.3 Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi). 5.3.8 Connect DI Water flush hoses to LSP and CAP. 5.3.9 Open DI Water supply valves.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 20(2 Page 15 of 34 5.3.10 At the LSP, dry the expansion vessel as follows: 5.3.10.1 Turn RC-V-11 to ARGON position (3 o'clock).
5.3.10.2 Open RC-V-9. 5.3.10.3 Open RC-V-8.2.
5.3.10.4 Open RC-V-10.
5.3.10.5 Regulate RC-VREL-2 to obtain 20 psi on RC-G-3. 5.3.10.6 Observe flow indication on RC-FI-2.
5.3.10.7 Wait at least 1 minute. 5.3.10.8 Turn RC-V-1 1 counterclockwise to VACUUMISAMPLE position (9 o'clock).
5.3.10.9 Close RC-V-9. 5.3.10.10 Close RC-V-8.2.
5.3.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Open RC-422. "* Open RC-423. 5.3.12 At the SAP perform the following:
5.3.12.1 WHEN performing an RCHL sample, THEN perform the following:
"* Open CC-314. "* Open RC-423-1.
5.3.12.2 WHEN performing a RHR sample, THEN perform the following:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
"* WHEN sampling B RIR, THEN open RHR-81-B.
5.3.12.3 Position RC-437-1 to DDT. 5.3.12.4 Position RC-437-2 to DDT.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 16 of 34 5.3.13 At the LSP perform the following:
5.3.13.1 Open RC-V3. 5.3.13.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.3.13.3 WHEN performing a RHR sample, THEN open RC-V- 1.1. Note Purge time may be varied based on actualpurge flow rate obtained.
5.3.13.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
"* WHEN RIR sample, THEN purge at least 25 minutes.
5.3.13.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waiting for the sample purge to be completed.
5.3.13.6 Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows: a. Open RC-V-13.
- b. Open RC-V-15.
- c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
- d. Open RC-V-12.
5.3.13.7 WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.8 WHEN vacuum on RC-G-2.1 > 22 inches of vacuum, THEN perform the following:
- a. Close RC-V-15.
- b. Close RC-V-13.
- c. Close RC-V-10.
- d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock).
- e. Close RC-V-12.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following:
- a. Turn RC-DV-2 to 12 o'clock.
- b. Observe vacuum on RC-G-2.2 is holding steady. c. Turn RC-DV-2 to 3 o'clock.
5.3.13.10 Open RC-V-14.
5.3.13.11 Observe RC-G-2.2 about 1.0 psi. Note Sample purge must be completed before proceeding.
5.3.13.12 Close RC-V-3. 5.3.13.13 Open RC-V-8.2.
5.3.13.14 Open RC-V-8.1.
5.3.13.15 Open RC-V-2. Note Purge time may be varied based on actual purge flow rate obtained.
5.3.13.16 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.3.13.17 Purge at least 3 minutes.
5.3.13.18 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.3.13.19 Close RC-V-8.2.
5.3.13.20 Close RC-V-8.1.
5.3.13.21 WHEN RCHL sample, THEN close RC-V-1.2.
5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1.
5.3.13.23 Open RC-V-9. 5.3.13.24 Open RC-V-16.
5.3.13.25 Wait 1 minute. 5.3.13.26 Close RC-V-16.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 18 of 34 5.3.13.27 Close RC-V-9. 5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows: a. Open RC-V-8.2.
- b. Open RC-V-8.1.
- c. Open RC-V-4. d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock).
5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
To obtain the diluted gas sample. 5.3.13.30 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi. 5.3.13.31 Turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.32 Close RC-V-14.
5.3.13.33 Remove the diluted gas sample bottle from the LSP. 5.3.14 Place entire assembly in fume hood for later transport to multi-channel analyzer.
5.3.15 At the CMP, operate the GC mini-computer to draw a vacuum on all 4 sample loops. 5.3.16 At the LSP, open RC-V-15 and allow the gas sample to transfer to the GC. 5.3.17 Operate the GC unit to obtain 4 samples for hydrogen determination.
By selective attenuation, starting with a high value, determine the hydrogen concentration.
"* Cycle through the four loops. "* Stop at each loop at least 1 minute. Note Start attenuation selection with high values. "* Determine hydrogen concentration using selective attenuation.
"* Record information on the Reactor Coolant Analysis Log (routine logsheet).
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 19 of 34 5.3.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close RC-422. "* Close RC-423. 5.3.19 At the LSP perform the following:
5.3.19.1 Close RC-V-4. 5.3.19.2 Close RC-V-2. 5.3.19.3 Close RC-V-8.1.
5.3.19.4 Close RC-V-8.2.
5.3.20 At the SAP perform the following:
5.3.20.1 WHEN RCHL sample, THEN perform the following:
"* Close RC-423-1.
"* Close CC-314. 5.3.20.2 WHEN RHR sample, THEN perform the following:
"* IF opened, THEN Close RHR-81A.
"* IF opened, THEN close RHR-81B.
"* Close CC-316. 5.3.20.3 Position RC-437-1 to VCT. 5.3.20.4 Position RC-437-2 to VCT. 5.3.21 At the LSP to flush the expansion vessel perform the following:
5.3.21.1 Open RC-V-8.2.
5.3.21.2 Open RC-V-9. 5.3.21.3 Turn RC-V-11 to DI WATER position (6 o'clock).
5.3.21.4 Flush for at least 2 minutes.
5.3.21.5 Turn RC-V- 11 to ARGON position (3 o'clock).
5.3.21.6 Wait 2 minutes.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 20 of 34 5.3.21.7 Turn RC-V-11 counterclockwise to CLOSE position (12 o'clock).
5.3.21.8 Close RC-V-9. 5.3.21.9 Close RC-V-8.2.
5.3.22 To remove radioactive gases from the system perform the following:
5.3.22.1 Open RC-V-10.
5.3.22.2 Open RC-V-13.
5.3.22.3 Open RC-V-15.
5.3.22.4 Turn RC-V- 11 to VACUUM/SAMPLE position (9 o'clock).
5.3.22.5 Open RC-V-12.
5.3.22.6 Evacuate system for at least 1 minute. 5.3.22.7 Close RC-V-12.
5.3.22.8 Turn RC-V-1 1 clockwise to CLOSE position (12 o'clock).
5.3.22.9 Close RC-V-15.
5.3.22.10 Close RC-V-13.
5.3.22.11 Close RC-V-10.
5.3.23 Transport diluted gas bottle to multi-channel analyzer for analysis in accordance with RCC-063, RCS Gaseous Activity." 5.4 Undiluted Liquid Grab Sample 5.4.1 In the HRSR check the following equipment available and operational:
"* Sample cask available with undiluted piston installed
"* Two -15 ml undiluted sample bottle "* New undiluted liquid flush bottle "* Undiluted liquid sample flush bottle handling tool "* Lights ON in undiluted sample port of LSP "* Reach Rod for remote valve operation CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 21 of 34 5.4.2 At the CASP perform the following:
5.4.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.4.2.2 Check High Vacuum Lights indicate NORMAL for the following:
"* LSP "* CAP "* CASP 5.4.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.4.4 Connect DI Water flush hoses to LSP. 5.4.5 Open DI Water supply valve to LSP. 5.4.6 Install undiluted sample bottle in sample cask. 5.4.7 Check cask for proper operation.
5.4.8 Install the sample cask under the undiluted sample port. 5.4.9 Position the undiluted sample bottle up on the needles.
5.4.10 WHEN performing an RCHL sample, THEN request Control Room Operator:
9 Open RC-422. 0 Open RC-423. 5.4.11 At the SAP perform the following:
5.4.11.1 WHEN performing an RCHL sample, THEN perform the following:
"* Open CC-314. "* Open RC-423-1.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 22 of 34 5.4.11.2 WHEN performing a RHR sample, THEN perform the following:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
"* WHEN sampling B RHR, THEN open RHR-81-B.
5.4.11.3 Position RC-437-1 to DDT. 5.4.11.4 Position RC-437-2 to DDT. 5.4.12 At the LSP perform the following:
5.4.12.1 Open RC-V-3. 5.4.12.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.4.12.3 WHEN performing a RHR sample, THEN open RC-V-1.1.
Note Purge time may be varied based on actual purge flow rate obtained.
5.4.12.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
"* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.4.12.6 WHEN purge is complete, THEN perform the following:
- a. Close RC-V-3. b. Open RC-V-2. c. Open RC-V-7. Note Purge time may be varied based on actual purge flow rate obtained.
5.4.12.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.4.12.8 Purge for at least 3 minutes.
5.4.12.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
CONTINUOUS USE 5.4.12.10 Turn RC-V-19 to SAMPLE position (3 o'clock).
5.4.12.11 Observe flow into undiluted sample bottle. 5.4.12.12 WHEN undiluted sample bottle is full, THEN position RC-V-19 to BYPASS position (12 o'clock).
5.4.13 Remove undiluted sample bottle from the needles.
5.4.14 Store the undiluted sample. "* Return undiluted sample to cask. "* Close lead top. "* Install auxiliary shield. "* Remove cask from HRSR. 5.4.15 IF RCHL sample, THEN close RC-V-1.2.
5.4.16 IF RHR sample, THEN close RC-V-1.1.
5.4.17 Open RC-V-4. 5.4.18 Place new undiluted sample bottle in special handling tool. 5.4.19 Position tool and bottle up on undiluted sample needles in LSP. 5.4.20 Turn RC-V-19 to SAMPLE position (3 o'clock).
5.4.21 Flush for at least 3 minutes.
5.4.22 Turn RC-V-19 to BYPASS position (12 o'clock).
5.4.23 Close RC-V-7. 5.4.24 Close RC-V-2. 5.4.25 Close RC-V-4. 5.4.26 Remove undiluted flush bottle and handling tool. 5.4.27 WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close RC-422. "* Close RC-423. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 1 Page 23 of 34 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 24 of 34 5.4.28 At the SAP perform the following:
5.4.28.1 WHEN RCHL sample, THEN perform the following:
"* Close RC-423-1.
"* Close CC-314. 5.4.28.2 WHEN RHR sample, THEN perform the following:
"* IF opened, THEN Close RHR-81A.
"* IF opened, THEN close RHR-81B.
"* Close CC-316. 5.4.28.3 Position RC-437-1 to VCT. 5.4.28.4 Position RC-437-2 to VCT. 5.4.29 WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor.
5.5 Containment Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1 WHEN sampling the Containment for hydrogen, THEN perform the following:
5.5.1.1 At the CASP perform the following:
5.5.1.1.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.5.1.1.2 Check High Vacuum Lights indicate NORMAL for the following:
- LSP 9 CAP
- CASP 5.5.1.2 Verify remote panels are in standby and have had 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> warm-up time. 5.5.1.3 Verify heat tracing is energized and operational.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 25 of 34 Note Due to ALARA considerations, both containment air sample trains will be lined up to preclude additional valve lineups.
5.5.1.4 Contact the Control Room and perform the following:
5.5.1.4.1 Verify that Containment Dome Fans IA and lB are operating.
5.5.1.4.2 Inform the Control Room that both containment air sample trains will be lined up for sampling.
5.5.1.4.3 Request the Control Room perform the following valve lineup: "* Close SA 7010A. "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Close SA7010B.
"* Position LOCA 2B LOCAL/REMOTE to LOCAL. "* Open LOCA 2B. "* Open LOCA 10B. "* Position SA 7003B LOCAL/REMOTE to LOCAL. "* Open SA 7003B. Note Damage to the Hydrogen Analyzer will result if CASP is monitoring the same Train. 5.5.1.5 WHEN H 2 Monitor 1A is to be used, THEN open AS-1 OA. 5.5.1.6 WHEN H 2 Monitor 1B is to be used, THEN open AS- 11OB. 5.5.1.7 Inform the Control Room that the H 2 Monitors are going to be started so that they can monitor their indication.
5.5.1.8 Switch selected analyzer to ANALYZE.
5.5.1.9 Switch selected analyzer to SAMPLE MODE. 5.5.1.10 Push the remote selector pushbutton to gain control at the remote panel. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 26 of 34 5.5.1.11 Allow at least 10 minutes for sample purge time. Note The Containment Hydrogen Monitors read out remotely in the Control Room. 5.5.1.12 IF desired, THEN record Hydrogen Monitor indication on the Reactor Coolant Analysis Log (routine logsheet).
5.5.2 WHEN all Containment hydrogen sampling is complete, THEN perform the following:
5.5.2.1 Switch selected H 2 Monitor to STANDBY.
5.5.2.2 WHEN H 2 Monitor 1A was used, THEN close AS- 11OA. 5.5.2.3 WHEN H 2 Monitor lB was used, THEN close AS- I10B. 5.5.2.4 Request the Control Room perform the following valve lineup: "* Close LOCA 2A. "* Close LOCA 10A. "* Close SA 7003A. "* Open SA 7010A. "* Close LOCA 2B. "* Position LOCA 2B LOCAL/REMOTE to REMOTE. "* Close LOCA lOB. "* Close SA 7003B. "* Open SA 7010B. "* Position SA 7010B LOCAL/REMOTE to REMOTE.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Paqe 27 of 34 5.6 Flush of Liquid Sample Lines Note The purpose of this section is to reduce radiation levels behind the liquid sample panel during post accident conditions.
5.6.1 At the SAP perform the following:
5.6.1.1 Position RC-437-1 to DDT. 5.6.1.2 Position RC-437-2 to DDT. 5.6.1.3 Open FPC-51. 5.6.1.4 WHEN performing an RCHL flush, THEN perform the following:
"* Open FPC-51-14.
"* Open CC-314. "* Open RC-423-1.
5.6.1.5 WHEN performing a RHR flush, THEN perform the following:
"* Open FPC-51-41.
"* Open CC-316. 5.6.2 At the LSP perform the following:
5.6.2.1 WHEN performing a RCHL flush, THEN open RC-V-1.2.
5.6.2.2 WHEN performing a RHR flush, THEN open RC-V-1.1.
5.6.2.3 Open RC-V-2. 5.6.2.4 Open RC-V-7. Note Flush time may be varied based on actualflush flow rate obtained.
5.6.2.5 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.6.2.6 Flush at least 45 minutes.
5.6.2.7 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 28 of 34 5.6.3 At the SAP perform the following:
5.6.3.1 Close FPC-51. 5.6.3.2 WHEN RCHL line flush, THEN perform the following:
- a. Close FPC-51-14.
- b. Close RC-423-1.
- c. Close CC-314. 5.6.3.3 WHEN RHR line flush, THEN perform the following:
- a. Close FCP-51-41.
- b. Close CC-316. c. Close RC-V-1.l.
5.6.4 At the LSP perform the following:
5.6.4.1 WHEN RCHL line flush, THEN close RC-V-1.2.
5.6.4.2 WHEN RHR line flush, THEN close RC-V-.1.l.
5.6.4.3 Close RC-V-2. 5.6.4.4 Close RC-V-7. 5.6.4.5 Close RC-VREL-2, then open RC-VREL-2 approximately 1/2/2 turn. 5.6.4.6 Continue flush by opening RC-V-4. 5.6.4.7 Open RC-V-3. 5.6.4.8 Throttle RC-VREL-1 until positive indication of flow on RC-FI-1.
Note Additional time may be required if radiation levels behind LSP have NOT stabilized.
5.6.4.9 Flush at least 15 minutes.
5.6.4.10 Close RC-V-3. 5.6.4.11 Close RC-V-4. 5.6.4.12 Close RC-VREL-1, then open RC-VREL-1 approximately
/2 turn.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C
]Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date 152002 Page 29 of 34 6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References 7.1 Sentry HRSS Operating and Maintenance Manual 7.2 RCC-063, RCS Gaseous Activity 7.3 RCC-082, Boron Analysis Curcumin Method 7.4 RCC-201, HRSR Conductivity, YSI Dissolved Oxygen, and pH Analysis 7.5 RCC-202, Hydrogen -Gas Chromatography (G.C.) Analysis -7.6 RCC-203, HRSR Post Accident Chloride-Ion Chromatography (IC) Analysis 7.7 RCC-520, DX-500 Startup and Shutdown Procedure 7.8 Commitment PLS-84-022 RQMT 2 -Step 5.3.14 (NOTE) 7.9 Commitment TEC-84-005, Step 5.1.13 and 5.1.14 7.10 EPIP-AD-11, Emergency Radiation Controls 7.11 OEA 93-160 7.12 KAP 1136, Corrective Action 2 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule.
These records shall be maintained according to the KNPP Records Management Program.
8.1.1 QA Records None 8.1.2 Non-OA Records None CONTINUOUS USE HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 1 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom. SAMPLE ACQUISITION PANEL FPC-51 ........................................
Sam ple Flush Line Iso ................................................
Closed RHR 81-B ....................................
RHR Smpl Iso B Aux Cool ..................
Closed FPC-51-41
...................................
RH R Sam ple Flush .....................................................
Closed RHR 81-A ................
RRR SMIPL Iso A Aux Cool .................
Closed R C-423-1 .....................................
R CH L Sm pl ................................................................
C losed CC-316 ...................
RHR HRS HIx CC Flow ....................
Closed FPC 51-14 ...................................
RCHL Sm pl Flush ......................................................
Closed MGR-545-1
...............
VCT Gas Sp Smpl Iso B ....................
Closed MGR-545 .................
VCT Gas Sp Smpl Iso A ....................
Closed -LD -75 ..........................................
M /B D em in Inlet Sm pl ...............................................
Closed FPC-51-31
................
M/B Demin Inlet Flush .....................
Closed LD -71 ..........................................
M/B D em in Inlet Iso ...................................................
Closed LD-85 ...................
M/B Demin Outlet Smpl ....................
Closed RC-437-1 .....................................
Sm pl Purge Divert A ..................................................
V CT FPC-51-21
................
M/B Demin Outlet Flush ....................
Closed LD -81 ..........................................
M fB Dem in Outlet Iso ................................................
Closed RC-437-2 .....................................
Sm pl Purge D ivert B ..................................................
V CT R C-403-1 .....................................
Przr Stm Sp Sm pl ........................................................
Closed FPC-51-12
................
Pzr Stm Sp Smpl Flush .....................
Closed R C-413-1 .....................................
Pzr Liq Sp Sm pl .........................................................
Closed FPC-51-13
................
Pzr Liq Sp Smpl Flush .....................
Closed "CC-314 ........................................
Rx Cool HRS Hx CC Flow .........................................
Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 Page 30 of 34 CONTINUOUS USE HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 2 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom.LIQUID SAMPLE PANEL R C-V -12 ........................................
R C-V -15 ........................................
R C-V -14 ........................................
R C-V -13 ........................................
RC-V -10 ........................................
R C-D V -2 .......................................
R C-V -11 ........................................
R C-V -REL-1 .................................
RC-V -REL-2 .................................
RC-V -3 ..........................................
R C-V -7 ..........................................
R C-V -8.2 .......................................
R C-V -9 ..........................................
R C-V -17 ........................................
R C-V -2 ..........................................
R C-V -18 ........................................
R C-V -22 ........................................
R C-V -6.2 .......................................
R C-V -5.2 .......................................
R C-V -19 ........................................
R C-D V -1 .......................................
R C-V -1.1 .......................................
Argon to Eductor .........................................
Closed Gas Smpl to GC ..........................................
Closed Argon Purge to Dil Gas Smpl .....................
Closed Dil Gas Smpl Vac ........................................
Closed Expansion Vessel Vacuum ..........................
Closed Diluted Gas Smpl ........................................
TO GC Expansion Vessel Outlet .............................
CLOSED RC Purge Throttle .......................................
Throttled RC Purge to Waste Tk .................................
Throttled RC Purge Stop .............................................
Closed Smpl Bomb Bypass .....................................
Closed Press Smpl Bomb Outlet .............................
Closed Expansion Vessel Inlet ................................
Closed Glove Box Grab Sample .............................
Closed RC Purge to Waste Stop ..............................
Closed RC Purge/Backflush
....................................
PURGE RC Purge Waste/CAP
.................................
WASTE Rem Smpl Bomb Outlet ..............................
Closed Rem Smpl Bomb Outlet Iso ........................
Closed Undiluted Liq Smpl .....................................
BYPASS Diluted Liquid Sample ................................
BYPASS RHR Smpl Iso .............................................
Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 15 2002 Page 31 of 34 CONTINUOUS USE (3 o'clock) (12 o'clock) (6 o'clock) (6 o'clock) (12 o'clock) (3 o'clock)
HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 3 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom. LIOUID SAMPLE PANEL (continued)
RC-V-1.2 .......................................
RCHL/Pzr Smpl Iso ...................................................
Closed RC-V-1.3 ....................................... (Spare) ........................................................................
Closed RC-V-1.4 ....................................... (Spare) ........................................................................
Closed RC-V-1.5 .......................................
VCT Gas Sp Smpl Iso ................................................
Closed RC-V-21 ........................................
Dilution H 2 0 to Diluted Sample ................................
Closed RC-V-8.1 .......................................
Press Smpl Bomb Inlet ...............................................
Closed RC-V-16 ........................................
Argon Gas Strip Purge ...............................................
Closed RC-V-4 ..........................................
DI W ater Flush Iso .....................................................
Closed --RC-V-6.1 .......................................
Rem Smpl Bom b Inlet ................................................
Closed "- RC-V-5.1 .......................................
Rem Smpl Bomb Inlet Iso ..........................................
Closed LIOUID SAMPLE PANEL (Demin Section) DM -V-l.1 ......................................
CVCS M /B Inlet .........................................................
Closed DM -V-1.2 ......................................
CVCS M /B Outlet ......................................................
Closed DM -V-1.3 ...................................... (Spare) ........................................................................
Closed DM -V-3 .........................................
DI W ater Flush ...........................................................
Closed RW -V-6 .........................................
Radwaste ....................................................................
Closed DM -V-2.1 ......................................
CVCS Demin Inlet Smpl ............................................
Closed DM -V-2.2 ......................................
CVCS Dem in Outlet Smpl .........................................
Closed DM -V-2.3 ...................................... (Spare) ........................................................................
Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 CONTINUOUS USE Page 32 of 34 HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 4 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom. CHEMICAL ANALYTICAL PANEL V -10 ...............................................
Inst A ir Supply .........................................
Open V-12 .............
.........
V-14 ...............................................
V-13 ...............................................
V-7 .......,..........
........o... V-8 ... ....,.......................
V-6 .... .............
.............
V -5 ...............
....... .................
V -2 ..... ................
................
V-.1 .. ....................................
V -27 ...............................................
V -28 ...............................................
V -29 ...............................................
V -1I ...............................................
V -24 ...............................................
V-17 ...............................................
V -9 .........
....... ..........
V -26 ...............................................
V -16 ...............................................
V -15 ...............................................
V -30 ...............................................
V -25 ...............................................
V-20 ...............................................
V -19 ...............................................
V -18 ...............................................
Nitrogen Supply .......................................
Open Argon Supply to GC ................................
Open IC Inject Port ............................................
Closed 02 Analyzer Select ...................................
YSI 02 Loop Outlet .........................................
Open 02 Loop Select .........................................
0 2 -Cal IC Loop Select ..........................................
Closed IC Smpl Outlet .........................................
Open GC Smpl Inlet ..........................................
Open pH Cal Tk 1 N 2 Supply ............................
VENT pH Cal Tk 2 N 2 Supply ............................
VENT Cal-3 N 2 Supply .......................................
VE NT DI W ater Supply ......................................
Closed 02 Cal Tk Fill ...........................................
Closed 02 Cal Tk Recirc ......................................
Closed 02 Anal Cal Supply ..................................
Closed pH Cal Tk 1 Supply .................................
Closed pH Cal Tk 2 Supply .................................
Closed Cal-3 Supply ............................................
Closed pH Cal Tk Select ......................................
CAL-1 pH Cal Tk 1 Drain ....................................
Closed pH Cal Tk 2 Drain ....................................
Closed Cal-3 Drain ...............................................
Closed 02 Cal Tk Drain .......................................
Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 CONTINUOUS USE Page 33 of 34 (3 o'clock) (6 o'clock) (6 o'clock) (6 o'clock) (6 o'clock) (6 o'clock) (6 o'clock)
VALVE LINEUP SHEET Page 5 of 5 CASP CONTROL PANEL..............
Sm pl Pos #1 Inlet/Outlet
.................................................................
Closed SV-2.1/SV-2.2
............
SV-3.1/SV-3.2
............
SV-4. 1/SV-4.2 ............
SV-5 ...........................
SV-10 .........................
AV-2 ...........................
SV-6 ...........................
AS110A ......................
ASl10B ......................
Smpl Pos #2 Inlet/Outlet
.................................................................
Smpl Pos #3 Inlet/Outlet
.................................................................
Smpl Pos #4 Inlet/Outlet
.................................................................
Sm pl Bypass ....................................................................................
Air to Eductor ..................................................................................
Return to Containm ent ....................................................................
Eductor Suction Iso ......................................................................... (At Sample Acquisition Panel) Cont Air Sm pl A Iso .......................................................................
Cont Air Smpl B Iso .......................................................................
I.M.C.C. CONTROL PANEL HS-3 ...........................
Dilution W ater Bite Valve ................................................................ "HS-4 ...........................
Air/W ater Flush Valve ......................................................................
HS-5 ...........................
Pressurized Reactor Cool. To I.M .C.C .............................................
HS-6 ...........................
Reactor Cool. Bite Valve .................................................................
HS-7 ...........................
M ixing Chamber Flush/Vent Valve ..................................................
HS-8 ...........................
Undil. RX. Cool. Smpl Outlet Valve ................................................
HS-9 ...........................
Undil. RX. Cool. Smpl/Divert Valve ................................................
I.M.C.C. CONTROL PANEL HS-10 .........................
M ixing Chamber Outlet Valve ..........................................................
HS-11 .........................
Dil. RX. Cool. Smpl Outlet Valve ....................................................
HS-12 .........................
Depressurized RX. Cool. to I.M .C.C ................................................
HS-13 .............
Degasifier Outlet/Flush Valve ....................................................
HS-14 .........................
Dil. W tr. Outlet Valve .......................................................................
HS-15 .........................
Air Flush to M ixing Chamber ...........................................................
HS-16 .........................
Gas M arinelli Bypass Valve .............................................................
M ain Power Switch ............................................................................................................
Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 CONTINUOUS USE Page 34 of 34 AV-1i/SV-1.2 Closed Closed Closed Closed Closed Closed Closed Closed Closed Off Off Off Off Off Off Off Off Off Off Off Off Off Off On WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 10 Reviewed By (2_-Approved By Nuclear 0 Yes PORC 0 Yes SRO Approval Of 0 Yes Safety Review Temporary Related 0 No Required El No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for drawing and analyzing containment samples when directed by the Radiological Protection Director (RPD). 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 This procedure is to detail the requirements, considerations, and operations of the Containment Air Sample Panel (CASP) during a Post LOCA condition, to obtain a grab--sample of Containment air for Gross Gas, Iodine, Hydrogen, and Oxygen analyses.
3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit as needed per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact the Radiation Protection (HP) Group and obtain the following:
- Proper personnel dosimetry
- Proper radiation detection instrumentation
- Personnel for continuous HP coverage during sampling
- Remote area monitor readings in area of High Radiation Sample Room (HRSR) 3.3 Utilize on-site communications with the RPD as necessary during sampling.
3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude:
- Gas 5.0 Millicuries/cc
- Iodine 0.2 Millicuries/cc 4.0 Initial Conditions 4.1 The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure.
n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach 5.0 Procedure 5.1 Obtain all necessary equipment prior to beginning to sample the Containment atmosphere.
This equipment includes:
- Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1
- 5.0 microliter gas syringe (2)
- 1.0 cc gas syringe or equivalent (2)
- 2.0 cc gas syringe or equivalent (1)
- An iodine cartridge holder (1)
- Silver Zeolite Cartridge (1)
- Several small rubber stoppers (3 to 5)
- Portable shields for transporting syringes
- Marinelli beaker (give to HIP to be counted prior to sample injection)
- Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2 WHEN preparing for CASP operation, THEN perform the following:
5.2.1 Proceed to HRSR per HP/RPD recommendations.
5.2.2 Determine radiation levels in HRSR and in maintenance area behind panels, if access is required.
5.2.3 Verify that heat tracing is ON. 5.2.4 Verify ventilation is ON and in NORMAL position and high vacuum lights indicate NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel (CAP), and CASP. 5.2.5 Verify that instrument air supply is available at >_ 70 psi. 5.2.6 Verify that CASP and CASP control panels are energized and operational.
5.2.7 Verify valve lineup per Attachment A, "Containment Air Sample Valve Lineup Sheet." CONTINUOUS USE Note The sample cart may be checked to verify it is properly locked in place by carefully pulling.
5.2.8 Verify the ISC in the #1 position is locked in place. Note Only Sample Station 1 shall be used for Iodine Analysis.
Due to ALARA considerations, if available, both containment air sample trains should be aligned.
5.2.9 Contact the Control Room and verify Dome Fans 1A and lB are operational.
5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel: "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Position LOCA 2B (Local/Remote) to LOCAL. "* Position SA 7003B (Local/Remote) to LOCAL. "* Open LOCA 2B. "* Open LOCA 1OB. "* Open SA 7003B. 5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B): a. The hydrogen monitor is NOT in operation, OR b. The sample loop selected is opposite that being used by H 2 monitor.
5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A. 5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B. 5.2.14 Open SV-10. 5.2.15 Open SV-6. 5.2.16 Open SV-5. 5.2.17 Verify flow monitor on CASP is indicating flow. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 202 Pa 4 5.2.18 Wait at least 2 minutes.
5.2.19 Open AV-1/SV 1.2. 5.2.20 Close SV-5. 5.2.21 Open AV-2. 5.2.22 Wait at least 3 minutes.
5.2.23 Align the ISC Cart as follows: 5.2.23.1 Open V-4, Cart Inlet Valve. 5.2.23.2 Open V-6, Outlet Valve. 5.2.23.3 Close V-5, Bypass Valve. 5.2.23.4 Verify CASP flow monitor is indicating flow. 5.3 WHEN collecting a Containment Air sample, THEN perform the following:
5.3.1 Close SV-6. 5.3.2 Verify flow monitor on CASP indicates NO flow. Note An appropriate period for flow monitor pressure equalization is one minute. 5.3.3 Allow the flow monitor to equalize pressure for at least 1 minute. 5.3.4 WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows: 5.3.4.1 Draw the following samples from the ISC. a. Two 5 microliter samples b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 -1.0 cc syringe samples.
- c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 -2.0 cc syringe sample.CONTINUOUS USE VlA ,ilq/ilft l r , I.RI,. ir"* ~rVi..a .i vvRN. ..........
...Re. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 5 of 10 5.3.4.2 IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following:
5.3.4.2.1 Lock the tips. 5.3.4.2.2 Insert the needle of each syringe in a rubber stopper to prevent damage. 5.3.4.2.3 Place the syringes in a portable shield for transport.
5.3.5 Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis.
5.4 WHEN shutting down and cleaning out the system, THEN perform the following:
5.4.1 Close AS 11 OA OR AS 11 B, as appropriate.
5.4.2 Open SV-6 and evacuate the ISC cart. 5.4.3 Wait at least 2 minutes.
5.4.4 Close V-4, Cart Inlet Valve. 5.4.5 Close V-6, Outlet Valve. 5.4.6 Open V-5, Bypass Valve. 5.4.7 Open AS 11OA OR AS 11GB, as appropriate.
5.4.8 Close AV-2. 5.4.9 Verify flow monitor has flow. 5.4.10 Wait at least 2 minutes.
5.4.11 Open SV-5. 5.4.12 Close AV-1/SV1.2.
5.4.13 Verify flow monitor has flow. 5.4.14 Wait at least 1 minute. 5.4.15 Close SV-10. 5.4.16 Close SV-6. 5.4.17 Close SV-5.CONTINUOUS USE I Rev. N WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D I Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 10 5.4.18 Close AS11 OA OR AS1 OB, as appropriate.
5.4.19 Reset "Active/Inactive" indicator lights to INACTIVE.
5.5 WHEN analyzing a sample for Iodine, THEN perform the following:
5.5.1 Place a Silver Zeolite sample cartridge in a holder. 5.5.2 Attach a hose from the holder to a vacuum source in the HRSR Fume Hood. 5.5.3 Establish air flow through the filter cartridge.
5.5.4 Inject a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge.
5.5.5 Remove the Silver Zeolite cartridge from its holder and monitor it for radiation.
-7 5.5.6 Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting.
Note Point Beach Nuclear Plant uses an identical geometry as Kewaunee for counting iodine samples.
5.5.7 IF the Count Room is NOT accessible OR the Multi-Channel Analyzer (MCA) is NOT operable, THEN the cartridge may be sent to Point Beach Nuclear Plant for analysis.
Note Further dilution may be necessary for counting.
5.6 WHEN analyzing a sample for Gross Gas activity, THEN perform the following:
5.6.1 WHEN the Count Room is habitable AND the MCA is operable, THEN perform the following:
5.6.1.1 Inject a 5 microliter gas sample into a marinelli beaker that has been cleared for use by the Radiation Protection Group. 5.6.1.2 Return the sample to the Radiation Protection Group for counting.
5.6.2 IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following:
5.6.2.1 Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle. 5.6.2.2 Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 7 ofl1 5.7 WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following:
5.7.1 Based on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows: RCC-080, "Gas Chromatograph, Baseline 1010A " Baseline 101OA Gas Operation Using a Chart Recorder" Chromatograph RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software" " SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2 Verify that the gas chromatograph is: "* Turned on "* Operating properly "* Correctly calibrated 5.7.3 WHEN the gas chromatograph is verified operable, THEN perform the following:
5.7.3.1 WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results.
5.7.3.2 WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results.
5.7.4 Report all results obtained to the RPD.CONTINUOUS USE 5.8 WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel:
- Close LOCA 2A.
- Close LOCA 1OA.
- Close SA 7003A.
- Close LOCA 2B.
- Close LOCA lOB.
- Close SA 7003B.
- Position LOCA 2B (Local/Remote) to REMOTE.
- Position SA 7003B (Local/Remote) to REMOTE. 6.0 Final Conditions 6.1 This procedure is closed out when the Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs. 7.0 References 7.1 Sentry HRSS Operating and Maintenance Manual 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4 RCC-080C, Operation of the SRI 8610 Gas Chromatograph 7.5 RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer Software 7.6 TS 6.1 l.b.2 CONTINUOUS USE 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule.
These records shall be maintained according to the KNPP Records Management Program.
8.1.1 QA Records None 8.1.2 Non-QA Records None CONTINUOUS USE CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL A V -1 / SV -1.2 ..................
Sm pl Pos #1 Inlet / Outlet ................................................................
Close SV -2.1 / SV -2.2 ................
Sm pl Pos #2 Inlet / Outlet ................................................................
Close SV -3.1 / SV -3.2 ................
Sm pl Pos #3 Inlet / Outlet ................................................................
Close SV -4.1 / SV -4.2 ................
Sm pl Pos #4 Inlet / Outlet ................................................................
Close SV -5 .................................
Sm pl Bypass ....................................................................................
Close SV -10 ...............................
Instr. Air to Eductor .........................................................................
Close AV -2 .................................
Return to Containm ent .....................................................................
Close_ SV -6 .................................
Eductor Suction Isol .........................................................................
Close SAMPLE ACQUISITION PANEL A S 110A ............................
Cont Air Sm pl A Isol .......................................................................
Close A S110B ............................
Cont Air Sm pl B Isol .......................................................................
Close INLINE SAMPLE CHAMBER (SF1) V -4 ....................................
Sam ple Inlet V alve ...........................................................................
Close V -5 ....................................
Sam ple Bypass V alve ......................................................................
Open V -6 ....................................
Sam ple Outlet V alve ........................................................................
Close Attachment A EPIP-RET-03D Rev. N........ .......Do n a f l n f 1j Cate: JAN U b =1 CONTINUOUS USE w i