ML20080B961
| ML20080B961 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 01/12/1984 |
| From: | WISCONSIN PUBLIC SERVICE CORP. |
| To: | |
| Shared Package | |
| ML111660552 | List: |
| References | |
| NUDOCS 8402070335 | |
| Download: ML20080B961 (5) | |
Text
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REVISED 1-12-84
^ ~ r%)
. E EMERGENCY PLAN IMPLEtiENTING PROCEDURES
~ g-Index-p v ,
' Procedure #. TITLE REVISION DATE EP-AD-1 Plant Eniergency' Organization D 03-10-83
'EP-AD'-2~ [ Emergency Class Determination C ,
03-l'0-83 EP-AD-3 Unusual Event [ 'D 10-27-83,
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i EP-AD-4 Alert- D 10-27-83 EP-AD-5 ' Site Emergency . D 10-27-83 EP-AD-6 General Emergency D 10-27-8.3 EP-AD-7 , Notification of Unusual Event H 10-27-83 EP-AD-8 Notification'of Alert .H 10-27-83 EP-AD-9 Not'ification of Site Emergency H 10-27-83 EP-AD-10 Notification uf General Emergency H 10-27-83 C\ EP-AD-il ' Emergency Radiation Controls C 06-21-83 V. ' EP-AD-12 Personnel Assenbly and Accountability D 10-27-83 EP-AD-13 Person.nel Evacuation 03-03-83 EP-AD-14 Search and Rescue , A 03-10-83 EP-AD-15 Recovery Planning , , A 03-10-83
.. EP-AD-16 Occupational Injuries or Vehicle Accidents A 03-10-83 During Emergencies EP-AD-17 Communications F 10-27-83 EP-AD-18 Availability of Inorganic Iodine Sa.lts for A 03-10-83 Iodine Saturation of the Human Thyroid Gland EP-AD-19 Protective Action Gui.delines . 09.-29-83 EP-ENV-1 Environmental Monitoring Team Organization B 03-10-83 EP-ENV-2 Site Access Facility (SAF) Activation B 03-10-83
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REVISED l-12-84
,m .
, (j - EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index- -
(cont'd)
., Procedure #'
TITLE - REVISION DATE
.EP-ENV-3A Environment'al Protection Director Actions and Directives I . 10.-2'7-83 EP-ENV-3B EM. Team Actions' ,
E 06-21-83.
, EP-ENV--3C.
Primary Dose Projection Calculation - IBM .
. . -Pers6nal Computer . A 10-25-83
~EP-ENV-3D .
Primary Determination of Mdteorological Data 06-21-83 ~ EP-ENV-3E Mhnual. Determination of X/Q (KNPP
. . . . Meteorological Data) ,
E 06-21-83 EP-ENV-3F Manual. Determination of X/Q (Green Bay . Meteorological Data) D 06-21-83 EP-ENV-3G. Manual Dose Projection Calculation . D 06-21-83
- m. ' EP-ENV-3H . Protective Action Recommendations B 06 0 I \
O' EP-ENV-4A Sample Acquisition Portable Instrument use
, C 03-10-83 EP-ENV-4B Sample Acquisition, Air Monitoring Devices B 05-21-82 EP-ENV-4C , Sample Acquisition, Environmental Sampling Techniques . B 05-21-82 EP-ENV-5A LCS-1 Operation . B 4-21-83 EP-ENV-5B- MS-3 Operation B 4-21-83
.EP-ENV-SC SAM II Operation C 03-10-83
^
EP-ENV-5D PAC-4G Operation A 12-21-81 EP-ENV-5E Reuter-Stokes Operation. A 03-10-83 EP-ENV-6A Relocation of Site Access Facility - (Habitability) A 03-10-83 EP-ENV-6B SAF Environmental Sample Analysis Relocation 'A 11-24-82 EP-ENV-7 Site Access Facility Communications B 03-10-83 EP-ENV-8. Total Population Dose Estimate Calculations A 7-26-83
, ,. , _ Page 3 gf 5 , REVISED l-12-84 EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index- -
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' Procedure f TITLE REVISION DATE EP-EOF-1 Corporate. Staff Emergency Response- Organization I 10-27-83
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EP-E0F-2 , Emergency Operations facility (EOF) Activation F . 10-27-83 EP-EOF-3 Corporate. Response to an unusual Evant G 10-27-83
,- EP-EOF-j -Corporate . Response to an Alert I 10-27-83
' EP-EOF-5 ' Corporate Response to a Site. Emergency -
I 10-27-83 - EP-EOF-6 Corporate Response to a General Emergency' I 10-27-83 EP-$0F 7 . Communications Documentation , E 03-10-83 EP-E0F-9 Interf. ace wit!h Support. Organizations G 10-27-83 EP-0P-1 . Control Room Emergency Organization A 1-03-83 [,) V EP-0P-2 Emergency Control Room Activation for B l-03-83 Emergency Responte EP-0P-3 Control Room Commuilications A 1-03-83
. EP-0SF-1 Operational $upport. Facility (OSF) Organization A 1-15-82 EP-0SF-2 OSF Activation A 05-21-82 EP-OSF-3 Work Requests During an Emergency A 1-15-82 EP-0SF-4 OSF Communications -
. B 03-10-83 EP-RET-1 Radiation' Emergency Team (RET) Organization C 03-10-83 EP-RET-2 Inplant RET D 09-29-83 m
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REVISED 1-12-84 EMERGENCY PLAN IMPLEMENTING PROCEDURES
. -Index- -
(cont'd) .
' Procedure # TITLE -
REVISION DATE EP-RET-2A RP0/RAF' Activation C 03-10-83
'EP-RET-2B Gaseous Effluent Sample and Analysis C 03-0~1-83 EP-RET-2D Emergency Radiation Entry, Controls and -B 03-10-83 Implementation
, EP-RET-2E ,
. Handling .of Injured. Personnel A 03-10-83
. EP-RET-I:F ,
Personnel Decontamination B 03-l'0 , EP-RET-3 Emergency C6emistry Team C' G3-10-8'3 EP-RkT-3A 'Liciuid Effluent Release Paths . A 12-21-81 EP-RET-3B Post-Accident React $r Coolant Alternate B 03-10-83 Sampling Procedure - EP-R ET-3C. Post Accident' Operation of the High Radiation
. Sample Room ,
B 01-12-84 EP-RET-3D Containment Air Sampling Analysis Using CASP A 06-21-83 EP-RET-3E Post Accident Operation of High Rad Sample Room Inline Multiported' Count Cave 07-26-83 03-10-83 EP-RET-4 Site RET , C i EP-RET-4B Radiological Controls,at Site, Access Facility (SAF) A 03-10-83 l .. EP-RET-4C Site Radiological Monitoring A 03-10-83 i.
'EP-RET-5 Plume Projections C 10-25.-83 EP-RET-SA Plume Projections (Backup Method) C 10-25-83 7-26-83 EP-RET-6 Dose Projection ,
B EP-RET-7 RAF/RP0 Communications B 10.-27-83 03-10-83 EP-RET-8 Contamination Control at the Two Rivers A Cominunity Hospital l l y
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REVISED l-12-84
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.EMEP,GENCY PLAN IMPLEMENTIt:G PROCEDURES
-Index- -
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s, , (cont'd) . P'rocedure # TITLE REVISION DATE EP-S'EC-1 Security Organization. A 03-10-83 EP-SEC-2 '. . Security Force Response to Emergencies D . 10.-27-83 EP-SEC-3 Personnel Accountability (Initi.al and Maintaining) E 10-27 _ 03-10-83
. EP-SEC-4 -
Dosimetry Issue at SAF A~ 10-27-83 ,
.EP-SEC-S 5ecurity Force Response to ,the EOF EP-TSC-1 Technical Support Center (TSC)' Organization 12-21-81 EP-TSC-2 TSC Activa +. ion C 03-10-83 EP-TSC-3 Plant Status . Procedure B 03-10-83 EP-TSC-4 IEmergency Design Change, Major Equipment Repair 12-21-81
'S
. (Q .
EP-TSC-5 TSC Communications- A 03-10-83 EP-TSC-6 Assessment of Reactor' Core Damage . A 03-10-83 EP-TSC-7 . RV Head Venting Time Calculation 01-12-84 4 I l l - t ; l-l. i \O 1 l
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WISCONSIN *PUBLIC SERVICE CORPORATION N0. EP-RET-3C REV. B Kewaunee Nuclear Power Plant TITLE : Post Accident .0peration of the High Radiation Sanple Room
/7 - EMERGENCY PLAN IMPLEMENTATION PROCEDURE b ,
DATE: JAN 12193.i PAGE 'l of 24
. REVIEWED BWtMM~ _,.M5 ??/ Yhf APPROVED BY /
/ ..
1.b PURPOSE , . 1.~ 1 This procedure is to detail the requirements, consideratioris, and
. operation of the High Radiation Sample Room during a post LQCA
.condi tion.
2.0 APPLICABILITY -
. 2.1 This is to detail the procedures to be utilized for obtaining:
- a. ' Diluted liquid sample of primary coolant, for Boron Analysi's .
and Isotopic Analysis (Sect 5.1).
. b. An inline sample for pH, conductivity, oxygen, and chl.oride (w analysis (Sect 5.2).
N c. . An inline sample of primary coolant for Hydrogen Analysis, and a dilute sample of gases, contained in Primary Coclant, for Isotopic Analysis (Sect 5.3).
. d. An undiluted sample of Primary Coolant for of f-site analysis (Sect 5.4).
- e. Containment Hydrogen Analyzer measurement (Sect 5.5).
- f. . Containment Air Sample Panel operation (Sect 5.6). ,
3.0 PRECAUTIONS - 3.1 Process an Emergency Radiation Work Permit (see EP-AD-ll). 3.2 Contact Health Physics Dept for: a., Proper personnel dosimetry.
- b. Proper radiation detection instrumentation.
- c. Personnel for continuous HP coverage duri'nq sampling.
- d. Remote area nonitor readings in area of HRSR.
r 3.3 Utilize'onsite communications with the Radiological Protection
- Director, as necessary,,during sampling.
V , 8402070339 840201
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N0. EP-RET-3C WI'SCONSIN NUBLIC SERVICE CORPORATION TITLE: Post Accident Operation of the } Kewaunee Nuclear Power Plant High Radiation Sample Room i EMERGENCY PLAN IMPLEMENTATION PROCEDURE' DATE: JAN 1 % 1984 PAGE 2 of 24 i
4.0 REFERENCES
4.1 Sentry HRSS Operating and Maintenance Manual 4.2 RC-C-82, Boron Analysis - Curcumin Method 4.3 RC-C-201, HRSR Conductivity, YSI/Rexnord Dissolved Oxygen, and pH Analysis 4.4 RC-C-202, Hydrogen-Gas Chromatography Analysis
-4.h RC-C-203, Chloride-lon 'Chromtography (IC) An.alysi s 5.0 PROCEDURE 5.1 Dilute Liquid Grab Sample 5.1.1 Proceed to HRSR per lip /RPD reccmmendations.
5.1.2 At the C.A.S.P. Control Panel c'h eck ventilation on in " normal" position and High Vacuum Lights indicate " normal" for the ,LSP and CAP. 5 . l' . 3 Check radiation levels in HRSR, and in maintenance area behind panels, if access is required. 5.1.4 Check the following Lab Equipment a) ailable and operational:
- a. Drying oven on at 55 C to 60"C.
- b. Fume hood ventilation normal .
- c. Shielded aliquoter available.
- d. DI water flush hoses connected to LSP and suppli valve on.
- e. New 24 ml diluthd sample bottle.
(large bottle) l
- f. Hand operated vacuum pump.
- g. Lights on in Diluted Sample Port o'f LSP.
- h. LSP Sample Cask available ,with diluted sample bottle piston i nst al led.
- i. Perfonn valve lineup per Attachment #1.
- j. Reach Rod for remote valve operation.
- k. All material required in section 4 of RC-C-82,
- 1. Multi-channel analyzer available for counting.
- m. 2 - ! liter poly bottles.
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- WISCONSIN PUBLIC SERVICE CORPORATION EP-RET-3C Kewaunee Nuc. lear Power Plant TITLE: Post Accident Operation of ~the liigh Radiation Sample Room O EMERGENCY PLAN IMPLEMENTATION PROCEDURE DATE:
2W PAGE 3 of 24
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5.1.5 Evacuate the diluted sample. bott,le (25 ml, large bottle) to 15 inches of va,cuu' m or greater. . Install in sample cask and check cask for pr.oper operation. (large holder in cask)
. 5.1.6 Install the sample cart under the diluted sample port and'
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. position the bottle up on the needles. -
5.1.7 Check level in dilution water reservoirs. Fill to full mark as necessa ry. . ,
. 5.1.8 Have Control Room Operator open RC-422 and RC-423, for RCHL sample.
5.1. 9 At the Sample Acquisition Panel: a.. For RCHL Sample: Open CC-314
. Open RC-423-1 . .
~
- b. For RHR Sample: , Open'CC-316
- Open RHR-81-A (81-B) .
O V c. For all Samples: Turn RC-437-1 (437-2) to DDT , 5.1.10 At the Liquid Sample Panel: Open V-3 Open V-1.2 (V-1.1 for RHR) 5.1.11 Regulate Reactor Coolant (RHR) flow using RC-VREL-1 until flow indicator RC-FI'-l indicates between 35 to 40 inches of water. Maintain this purge for a minimum of 5 minutes.
'. NOTE: A D/P of 35 to 40 inches of water on RC-FI-l is equal to approximately 1/2 gpm flow rate. ,
5.1.12 Upon completion of the purge: Shut V-3 Open V-8.2 Ooen V-8.1
- Open V-2 5.,1,13 Regulate Reactor Coolant (or RHR) flow using RC-VREL-2 until
. flow indicator RC-FI-2 indicates 18 to 22 inches of water.
Maintain this purge for a minimum of 3 minutes. NOTE: A D/P of 18 to 22 inches of water on RC-FI-2 is equal to approximately 200 cc/ min flow rate. . O
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WISCONSIN PUBLIC SERVICE CORPORATION NO. EP-RET-3C Kewaunee Nuc. lear Power Plant TITLE: Post Accident Operation ofithe
~
High Radiation Sample Room A EMERGENCY PLAN IMPLEMENTATION PROCEDURE PAGE 4 of 24 (._,) . , DATE: JN1 121934
.5.1.14 Upon completion of the purge: Turn DV-1 to " Sample"
.' . Shut V-1.2 (V-1.1 for RHR) 5.1.15 Throttle open V-21 and add 24 ml of DI water, from the graduated '
. reservoir to the sample bottle, then close RC-V-21.
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- 5.1.16 Turn DV-1 to " Bypass".
5.l.17 Open V-4. Obse'rve Flush Water Flow Ra,te of 18-22 inches of water for. a minirnum of. 3' minutes. 5'. l .1.8 Upon completion of flush: Shut V-4 - Shut V-2 Shut V-8.2 Shut V-8.1 ', 5.1.19 Have Control Room Operator shut RC-422 and RC-423 (not required for RHR). . 5.'.20 1 At the Sample Acquisition Panel: A For RCHL Sample: Open FPC-51 (). ' Open FPC-51-14 For RHR Sample: Shut RHR-81-A (81-B) Open FPC-51 5.l.21 At the Liquid Sample Panel: Open V-1.2 (V-1.1 for RHR) Open V-3 - Observe Fl'ush Water Flow Rate of 35 to 40 inches of water as indicated 'on RC'-FI-1. Maintain flush for 5 minutes while performi ng step 5.1.22. NOTE: A D/P of 35 to 40 inches of water on RC-F1-1 is equal to approximately~ 1/2 gpm flow rate. 5.1.22 Lower the diluted sample 'bottls into the sample cask. Cl ose the cask and instal'1 auxiliary shield. Place cask near fume hood. , 5.1.23 Upon completion of flushing: Shut. V-1.2 (V-1.1 for RHR) e Shut V-3 5.1.24 At the Sample Acquisition Panel:
*. For RCHL Sample: Shut RC-423-1 Shut FPC-51-14 Shut FPC-51 Shut CC-314
( WISCONSIN. PUBLJC SERVICE CORPORATION NO. EP-RfT-3C _._
, Kewaunee fiuclear Power Plant TITLE: Post Accident Operation of.the High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I '
DATE: JAN 121984 PAGE 5 of 24 s.) . For RHR Sample: Shut RHR-81-A (81-B) Shut FPC-51-41 Shut FPC-51 . Shut CC-316 For all ' samples: Turn RC-437-1 (or 437-2) to VCT -
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5.1.25. Using the shi'elded liquid aliquoter, transfer a 1.0 r.1 sample from the sample cask into a VYCOR evaporating dish.
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. NOTE: For Boron.' analysis of less than 2000 ppm, use an appropriately larger amount of sample.
5.1.26 Continue the Boron analysis'with step 6.2 of RC-C-82. 5.'1.27' For Beta Gamma analysis, transfer 1.0 ml of coolant from the ca.sk to a liter.po.ly bottle using the shielded liquid aliquoter. Dilute to 1 liter. 5.1.28 From the diluted 1 liter bottle in step 5 l.27, transfer 10 m1 to another empty liter bottle. Dilute to 1 liter. This sample may be transferred to the multi-channel analyzer for counting. (D () - . NOTE: Total dilution is ( x 108) 5.2 Inline Sample for pH, Cond, 02 and Cl 5 . 2.1. Proceed to HRSR per HP/RPD recommendations. 5.2.2 Verify ventilation is ON in " normal" position and high vacuum lights indicate ", normal" ,for the LSP and CAP.
. 5.2.3 Check radiation levels in HRSR, and in maintenance area behind panels, if access is necessary.
5.2.4. Verify the following lab equipment available and operational.
- a. DI water flush hoses connected to LSP and CAP with supply valves open. .
- b. Verify valve lineup for SAP, LSP, and CAP, per Attachment #1.
- c. Reach Rod for Remote Valve operation.
- d. Main Power switch at CMP "on".
- e. At the CMP, turn on the YSI chart recorder, pH meter, conductivity meter, and start IC unit for base line.
- f. Check HRSS calibration log for verification of latest pe rfo nnances.
- g. Check gas bottles (argon and air) for adequate supply.
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1 , WISCON3IN PUBLIC SERVICE CORPORATION N0. EP-RET-3C Kewaunee fluclear Power Plant TITLE: Post Accident Operation of the High Radiation Sample Room
' EMERGENCY PLAN IMPLEMENTATION PROCEDURE DATE: PAGE 6 of 24 5.2.5 At the CAP: ' Turn V-6 to Liquid Sample
, Turn. V-5 to Liquid Sample S.2.6 Have the. Control Room Operator open RC-422 and RC-423 (not.
requi red for P,HR sample). - 5.2.7 At the Sample' Acquisition Panel: For RCHL Sample: Open CC-314 Open RC-423-1
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For RHR.. Sample: Open CC-316 RHR 81 - A (81-B) For all samples: Turn RC-437-1 (or 437-2) to DDT. 5.2.8. At the Liquid Sample Panel: Open V-3 Open V-1.2 (V-1.1 for RHR) 5.2.9 Regulate ' Reactor Coolant (or RHR) flow using RC-VREL-1 until flow indicator RC-FI-l indicates between 35-40 inches of water.
- ), . Maintain this purge for a minimum of 5 minutes.
NOTE: A D/P' of 35 to 40 inches of water on RC-FI-l is equal to appr.oximately 1/2 gpm flow rate.. 5.2.10 Upon completion of the purge: Shut V-3 Open V-2 - Open V-7
. Turn V-22 to Chem Panel 5.2.11 Regulate Reactor Coolant (or RHR) flow using RC-VREL-2 until flow indicator RC-FI-2 indicates 18 to 22 inches of water.
Maintain this purge for a minimum of 5 minutes. NOTE: A D/P of 18 to 22 inches of water on RC-FI-2 is equal to approximately 200 cc/ min. flow rate. 5.2.12 Verify adequate flow rate to the CAP by observing the lights "on" for both 02 flow and IC flow. 5.2.13 When the YS1 02 meter chart reading has stabilized: Record the conductivity reading Record the temperature Rec'ord the 02 . reading ( Place the Load / Inject switch on the IC unit to " Inject" f
. UISCONSIT(.PUBLIC SERVICE CORPORATION N0. EP-RET-3C Kewaunee Nuclear Power Plant TITLE: Post Accident Operation of the High Radiation Sample Rnom EMERGCNCY PLAN IMPLEMENTATION PROCEDUR.E DATE: PAGE 7 of 24 JAN 12 $$4 5.2.14 At the Liquid Sample Panel:
Turn V-22 to Waste Shut V-1.2 (V-1.1 for RHR) Open V-4 5.2.15 Observe DI Water Flush to Waste as indicated on Flow Indicator RC-FI-2. After 2 minutes: Record pH reading Place the Load / Inject switch on the IC unit to " Load" 5.2.16 Flush the CAP by turning V-22 to Chem Panel position. Verify flush water flow by observing the lights "on" for both 02 Flow and IC Flow. Continue flush for' 2 minutes. , NOTE: Chloride results should read out 5 to 10 minutes af ter injection (step 5.2.13).
~5.2.17 Upon completion of flush 'to CAP:
At the LSP: Turn V-22 to Waste
- Shut V-7 ,
Shut V-2 Shut V-4 ~ At the CAP: Turn V-6 tp 02 Cal
. Turn V-5 to Clo' sed .
5.2.18 Have Control Roan Operator shut RC-422 and RC-423 (not required
~
for RHR sample). . 5.2.19 At the Sample Acquisition Panel: For RCHL Sample: Open FPC-51 Open FPC-51-14 For RHR Sample: Shut RHR 81-A (81-B) Open FPC-51 - Open FPC-51-41 5.2.20 At the Liquid Sample Panel: Open V-1.2 (V-1.l' for RHR) Onen V-3 Use V-REL-1 to control flush water flow rate of 35 to 40 inches of water as indicated on RC-FI-1. Maintain this flush for a minimum of 5 minutes. NOTC: A D/P of 18 to 22 inches of water on RC-FI-2 is equal to approximately 200 cc/ min flow rate.
MISC 0! GIN PU!11/IC SERVICE CORPORATION NO. EP-RET-3C Kewaunee Nuclear Power Plant TITLE: Post Accident Operation of the
- High Radiation Sample Room
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EMERGENCY PLAN IMPLEMEitTATION PROCEDURE DATE: PAGE 8 of 24 5.2.2T Upon comp}etion of flushing: Shut V-1.2 (V-1.1 for RHR) Shut V-3 5.2.22 At the Sample Acquisition Panel:
. For .RCHL Sample: Shut RC-423-1 Shut FPC-51-14 Shut FPC-51 Shut CC-314 For RHR Sample: Shut RHR 81-A (81-B) ,
Shut FPC-51-41 , Shut FPC-51 Shut CC-316 For all samples: Turn RC-437-1 (or 437-2) to VCT 5.3 Hydrogen and Gaseous Activity Gr' ab Sample
. 5.3.1 Proceed to HRSR per HP/RPD recommendations.
I - 5.3.2 Verify ventilation on in " normal" position and high vacuum lights indicate " normal" for the CAP and LSP. 5.3.3 Check radiation levels in HRSR, and in maintenance area behind panels, if access is necessary. 5.3.4 Verify the following lab equipment available and operational:
- a. DI water flush hoses connected to LSP and' CAP with supply valves open.
. b. Verify valve lineup for SAP, LSP, and CAP per Attachment #1.
- c. Reach Rod for remote valve operation.
- d. Main power switch at the CMP "on". ~
- c. Check the program in GC mini-computer and latest data in the HRSS Cal Log.
. f. Check Argon and Air Pressu're in' lab and at the bottles for adequate supply.
9 10 cc gas sample bottle, with septum, properly installed in face of LSP, using the special handling tool.
- h. Verify multi . channel analyzer available for counting.
l 5.3.5 Dry the expansion vessel: Turn V-ll to " Argon" (3 o' clock position) Open V-9
. Open V-8.2 7 ' Open V-10
i WISCONSIN PUBLIC SERVICE CORPORATION NO. EP-RET-3C Kewaunee Nuclear Power Plant TITLE: Post Accident Operation of the
- High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE y DATE: PAGE 9 of 24 5.3.fi Adjust RC-VREL-2 as necessary to obtain 20 psi on RC-G-3 for 1 minute. Observe flow indication en RC-FI-2 also.
5.3.7 Upon completion of Drying Expansion Vessel:
.l Turn V-ll to 9 o' clock position (counterclockwise direction)
Shut V-9 Shut V-8.2 5.3.8 Have Control Room Operator open RC-422 and RC-423 (not required for sample from RHR). , 5.3.9 At the Sample Acquisition Panel: . For RCHL Sample: Open CC-314 Open RC-423-1 For RHR Sample: Open CC-3' 16 Open RHR 81-A (81-B)
^ For all samples: Turn RC-437-1 (or 437-2) to DDT .
5.3.10 At the Liquid Sample Panel: Open V-3 Open V -1.2 (V-1.1 for RHR) 5.3.11 Regulate Reactor Coolant (RHit) flow.using' RC-VREL-1 until flow indicator RC-FI-l indicates betwden 35 to 40 inches of water. Maintain this purge for a minimum of 5 minutes. NOTE: A D/P of 35 to 40 inches of water on RC-FI-l is equal to approximately 1/2 gpm flow rate. 5.3.12 Evacuate the Gas Ex[iansion Vessel, sample. bottle and tubing: Open V-13 Open V-15 l Turn DV-2 to 12 o' clock " position Open V-12 5.3.13 When vacuum on RC-G-2.2 reads 22 inches vacuum or greater, turn DV-2 to 3 o' clock position. 5.3.14 When vacuum on RC-G-2.1 reads 22 inches of vacuum or greater:
. Shut V-15 r~3 Shut V-13 , j
. I WISCONSlit PUBLIC SERVICE CORPORATION NO. EP-RET-3C _.
Kewaunee Nuclear Power Plant T ITLE : Post Accident Operation of the liigh Radiation San;ple Room , ; EilERGEi!CY PLAN IMPLEMEi4TATION PROCEDIR'E
> DATE: PAGE 10 of 24 12 E Shut V-10 Turn V-ll to Closed Shut V-12 NOTE: Observe vacuum readirig on both gauges holding steady.
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5.3.15 Open V-14 and observe about 1.0 psi on RC-G-2.2. 5.3.16 Upon completion of purge (from step 5.3.11): Shut V-3 . Open V-8.2 -
. Open V-8.1 Open V-2 5.3.17 Regulate Reactor Coolant (RHR) flow using RC-VREL-2 until flow indicator RC-FI-2 indicates 18 to 22 inches. of water. liai ntai n this purge for a minimum of 3 minutes.
NOTE: A D/P of 18 to 22 in.ches of water on RC-F1-2 is equal
^
to approximately 200 cc/ min flow rate.
- x -
5.3.18 Upon completion of sample purge: Shut V-8.2
' Shut V-8.1 .
Shut V .1.2 (V-1.1 for RHR) Open V-9 . Open V-16 (for 1 fuli minute) 5.3.19 Upon completion of gas stripping, commence LSP flush: Shut V-16 Shut V-9 . Open V-8.2 Open V-8.1 . Open V-4 Turn V-ll to 9 o' clock position l 5.3.20 Obtain the diluted gas sample by turning DV-2 to 12 o' clock position. 5.3.21 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi:
. Turn DV-2 to 3 o'clo'ck position
, Shut V-14
WISCONSIN PUBLIC SERVICE CORPORATION N0. EP-RET-3C l Kewaunee Nuclear Power Plant -TITLE: Post Accident Operation of the
. High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE
( ! DATE: PAGE 11 of 24 JAN 121984 5.3.22 Remove the diluted gas sample bottle trom the LSP and place entire assembly in fume h.ood for later transport to multi-channel analyzer. 5.,3.23 At the CMP, operate the GC mini-compui.er te draw a vacuum on all 4 sample loops. 5.3.24 . At the LSP open V-15 and allow the gas sample to transfer to the GC. 5.3.25 Operate the GC unit to obtain 4 sample,s for hydrogen determinatio'n. By selective attenuation, starting with a high value, determine the hydrogen concentration. 5.3.26 Have Control Room Operator shut RC-422 and RC-423 (not required for RHR sample). 5.3.27 At the Sample Acquisition Panel: 5 For PCHL Sample: Open FPC-51 , Open FPC-51-14 For RHR Sample: Shut RHR 81-A (81-B) Open FDC-51, Open FPC-51-41 5.3.28 At the Liquid Sample Panel: Shut V-4 Shut V-2 Shut V-8.1 Shut V-8.2
. Open V-3 Open V-1.2 (V-1.1 for RHR)
Using V-REL-1, regulate flush water flow rate of 35 to 40 inches of water on RC-FI-1. Maintain this flush for a minimum
~
of 5 mi nut es . 5.3.29 At the completion of flushing: Shut V-1.2 (V-1.1 for RHR) Shut V-3 5.3.30 At the Sample Acquisition Panel: For RCHL Samples: Shut RC-423-1 Shut FPC-51-14 m ' Shut FPC-51 i Shut CC-314
l WISCONSIif PUBLIC ' SERVICE CORPORATI0ft NO. EP-RET-3C I . Kewaunee !!uclear Power Plant TITLE: Post Accident Operation of the High Radiation Sample Room in EMERGEliCY PLAti IMPLEMENTATION PROCEDU:tE (j DATE: JAN 121984 PAGE 12 of 24 For RHR Sample: Shut RHR 81-A (81-B) Shut FPC-Sl-41 Shut FPC-Sl Shut CC-316 For all samples: Turn RC-437-1 (or 437-2) to VCT. 5.3.31. At the LSP flush the expansion vessel: Open V-8.2 . Open V-9 Turn V-11 to "DI Water" position - Allow system to flush for 2 minutes.
.5.3.32 Upon completion of flush: Turn V-ll to " Argon" position (3 o' clock) and blow expansion vessel dry 5.3.33 Upon completion of drying expansion vessel: !a ~')
l Turn V-11 to Close (c'ounterclockwi se) Shut V-9 Shut V-8.2 5.3.34 Remove radioactive gases from gas system: Open V-10 ' Open V'-13 Open V-15 Turn V-ll to 9 o' clock position Open V-12 Evacuate systent for 1 full minute. , 5.3.35 Upon evacuation of gas system: , Shut V-12 l Turn V-ll ' clockwise to " closed" position Shut V-15 Shut V-13 Shut V-10 5.3.36 Transport diluted gas bottle to multi-channel analyzer for analysis, per RC-C-(63). ~
,/ m m
4
WISCONSIN PUBLIC SERVICE C0.RP0 RATION NO. EP-RET-3C Kewaunee Nuclear Power Plant TITLE: Post Accident Operation of the High Radiation Sample Room
^
EMERGENCY PLAN IMPLEMENTATION PROCEDURE DATE: o PAGE 13 of 24 JAff I o .eS4 _ 5.4 "ndiluted Liquid Grab' Sample 5.4.1 Proceed to HRSR per HP/RPD recommendations. 5.4.2 ' Check ventilation on, i n " normal" position and high vacuum lights indic' ate "nonnal" for the LSP and CAP. 5.4,3 Check radiation' levels in HRSR, and in maintenance area behind panels, if access' is necessary. 5.4.4 Check the following lab equipment available and operational:
- a. DI water flush hoses connected to. LSP and supply valve open.
b.- Check valve -lineup per Attachment #1.
. c. Reach rod for remote valve operation.
l d. New undiluted liquid sample bottle available. (15.ml bottle)
- e. New u.ndiluted liquid flush bottle, with special tool, available.
,' f. Sample cask available with undiluted sample piston installed.
. g. Light on in undiluted sample port of LSP.
5.4.5 Install undiiuted sample bottle (15 ml bottle) in cask and check for proper operation. (using small sample holder) 5.4.6 Install the sample cask under the undiluted sample port and position the bottle up on the needles. -
~
5.4.7 Have Control Room Operator open RC-422 and RC-423 (not required for RHR sample); 5.4.8. At the Sample Acquisition Panel: For RCHL Sample: Open CC 314 Open RC 423-1 For RHR Sample: Open CC 316 Open RHR 81-A (81-B) For all samples: Turn RC-437-1 (or 437-2) to DDT. 5.4.9 At the Liquid Sample Panel: Open V-3 Open V-1.2 (V-1.1 for RHR)
-. - . . - . - . ~ . = - - . . - . < . - - - - - - - . - - - - , -
W'ISCONSIN'PUBLIC ' SERVICE C0.RPORATION N0. 'EP-RET-3C Post Accident Operation of the
~ Kewaunee Nuclear Power Plant TITLE:
High Radiation Sample Room
/ ')' EMERGENCY PLAfi IMPLEMENTATION PROCEDURE
'~' DATE: PAGE 14 of '24 2N 5.4.10 = Regulate Reactor Coolant (RHR)' flow using RC-VREL-1 until flow indicator RC-FI-l indicates between 35-40 inches of water.
~
Maintain this purge for a minimum of 5 minutes. ,
' NOTE:
A D/P of 35-40 inches 'of water on RC-F1-1 is equal to *
, approximately 1/2 gpm flow rate.
5:4.11, Upon completion o,f the purge: Shut V-3
. Open V-2 Open V-7 5.4.12 Regulate Reactor Coolant (RHR) flow using RC-VREL-2 until flow indicator RC-F1-2 indicates 18 to 22. inches of water. Maintain
~
this purge for a minimum of 3 minutes. '. NOTE: A D/P of 18 to.22 inches of water on RC-FI-2 is equal to approximately 200 cc/ min. , 5.4.13 Upon completion of the purge: Turn V-19 to " sample".
. ' Observe flow into/thru sample bottle to waste. Purge time required 'only to insure bottle is full.
5.4.14 Upon completion of sample fill: Turn V-19 to " bypass" Shut V-1,2 (V-1.1 for RHR) Open V-4 5.4.15 While syst.em is in DI water flush, return undiluted sample to cask, close ' lead top, and remove cask from lab. Install auxiliary shield.
. NOTE: 0.1 water flush should be performed for a minimum of 3 ,
minutes before going to step 5.4.16. 5.4.i6 Place undiluted sample flush bottle, and special flush tool into position. Turn V-19 to "sampl'e" Allow system to flush for an additional 3 minutes. 5.4.17 Upon completion of sample flush: Turn V-19 to " bypass" Shut V-7 Shut V-2 5.4.18 Have Control Room shut RC-422 and RC-423 (not required for RHR sampie). {J) , ,
,, ,.-- -. c. .-- - ,. - - e. -. - - - - - - - - - - - . . - . . . ,
ll
. WISCONSIN. PUBLIC SERVICE CORPORATION NO. EP-RET-3C
~
Kewaunee Nuc, lear Power Plant TITLE: Post Accident Operation of :the High Radiation Sample Room p EMERGENCY PLAN IMPLEMENTATION PROCEDURE
-t I DATE: JM 121984 PAGE 15 of ~24 V
~
5.4.19 At the Sample Acquisition Panel:
'For RCHL' Samp.le: .Open FPC-51 Open FPC-51-14 For RHR Sample: Shut RHR 81-A (81-B)
. Open FPC-51 Open FPC-51-41 -
5.4.20 At the Sample Acquisition Panel: Open,V-1.2 (V-1.1 for RHR) Open V 3 Using V-REL-1, regulate flush water flow rate of 35 to 40 inches of water, as indicated on RC-FI-1. Maintain this flush for a minimum of 5 minutes. NOTE: A D/P of-35' to 40 inches of water on RC-FI-l is equal to approximately 1/2 gpm flow rate. 5.4.21 Upon completion 'of flushing: Shut V-1.2 (V-1.1 for RHR) Shut V-3 b.O 5.4.22 -At the Sample Acquisition Panel: For RCHL Sample: Shut RC-423-1
' Shut FPC-51-14 Shut FPC-51 Shut CC-314 For RHR Sample: Shut FPC-51-41 Shut FPC-51
. ' Shut CC-316 For All Samples: Turn RC 437-1 (437-2) to VCT.
5.5 Containment Hydrogen Monitor lA & IB Operation Procedure 5.5.1 Proceed to HRSR per HP/RPd recdamendations. 5.5.2 Check ventilation on in " normal" position. 5.5.3 Check. radiation levels in HRSR and maintenance area behind panels, if access is necessary. 5.5.4 Check to make sure remote panels are in stand-by and have had 6 hours warmup time. fD s_) 5.5.5 Insure heat tracing is energized and operational, 5.5.6 Check nonitor selection at Sample Acquisition Panel to insure
, it is not sampling same loop as the CASP.
\
WISCONSIfbPUBLIC SERVICE CORPORATION i NO. EP-RET-3C Kewaunee-Nuclear Power Plant TITLE: Post Accident Operation of the High- Radiation Sample Room EliERGENCY PLAN IMPLEMENTATION PROCEDURE DATE: PAGE 16 of 24
.Q g y 3 33g
~
5.5.7 - For' H2 Analyzer A call Control Room to open valves LOCA 2A . and LOCA 10A and SA 700 3A. 5.5.8 For H2 Analyzer B call Control Room to open valv'seLOCA 2B "and LOCA 10B and SA 700 3B.
. 5.5.9 _ Push the " remote selector" pushbutton to gain access at the remote panel ..
5.5.10 Switch analyzer to Sample Mode. Allow.10 minutes for sample , purge t.ime. , 5.5.11 Read sample in ' percent hydrogen of f remote panel meter. NOTE: If problems tre encountered with selected analyzer, go to SAP and af ter checking status of CASP switch to other analyzer, and repeat procedure. 5.6 Containment Air Sample Panel Operation
. NOTE: For normal pcst accident samp. ling' of containment use .
EP-RET-3D.
5.6.1 Proceed to HRSR per HP/RPD recommendations. . 5.6.2 Check ventilation on and in " normal" position and high' vacuum
. lights indicate " normal" for the LSP and CAP, and CASP.
5.6.3 Check radiation levels in HRSR and in maintenance area behind panels if access is required. . 5.6.4 Insure that.N2 supply regulator is set at 150 psi and bottle
, contains at least 500 psig N .2 5.6.5 Verify that CASP and CASP Control Panels are energized and operational . Ensure that the " heat tracing is on.
5.6.6 Place the four sample carts in the four sample positions and
- lock in place. Check carts are properly locked in by trying to pull away.
NOTE: Unly Sample Station 1 can be used for lodine Analysis.
-l
\. /
9 0 e 9
l WISCONSIN PUBLIC SERVICE CORPORATION NO. EP-RET-3C Kewaunee Nuclear Power Plant TITLE : Post Accident Operatio1 of the High Radiation Sample ?oom
- EMERGENCY PLAN IMPLEMENTATION PROCEDURE DATE: PAGE 17 of 24 M 121081 5.6.7 Call Control Room and verify Dome Fans lA and 1B are operational 5.6.8 Have Control Room Operator open 1 set of the following valves:
Loop A Loop B LOC A-2 A LOC A-2B LOCA-10A L OC A-10B l SA 700 3A SA 700 3B 5.6.9 Insure that when selecting sample loop A or B that either hydrogen monitor is not operating or loop selected. is opposi_te , that being used by 112 monitor. Open. AS110A or ASilCB. 5.6.10 Connect local pressure transmitter to cart selected for sampli ng. NOTE: Do not use the I.S.C. cart for this procedure 3 5.6.11 CASP two minute pre-sample back flush: ,
' ~
SV-10 Open SV-6 Open SV-5 Open , Insure flow mnitor on CASP is indi'cating flow. 5.6.12 Three minute sample capture: SV-5 Cl osed AV-2 Open For Sample Station 1 - AV-1 and SV-1.2 Op'en For Sample Station 2 - SV-2.1 and SV-2'.2 Open For Sample Station 3 - SV-3.1 and SV-3.2 Open For Sample Station 4 - SV-4.1 'and SV-4.2 Open Open manual inlet and outlet values and close manual bypass valve on sample cart selected. Check pressure transmitter for indication of negative. pressure. Insure CASP Flow Meter is still indicating flow. 5.6.13 Fif teen second flask equilibration: m SV-6 Closed Flow Monitor on CASP should go out. Pressure Transmitter should reach stability (NOTE: Equal to coritainment pressure).
. WISCONSI.N PUBLIC SERVICE CORPORATION NO. EP-RET-3C Post Accident Operation of ethe Kewaunee Nuclear Power Plant TITLE:
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE DATE: PAGE 18 of 24 JAtt 121934 5.6.14 Three Mi'nute Residual Sample Gas Removal: Close Manual inlet
.and outlet valves, open bypass valve and close corresponding solenoid valves for station selected in step 5.6.12. Flow Monitor on CASP should still be out. After 3 minutes open SV-6, 5.'6.15 Initial fif teen second post sample back . flush: AV-2 Closed .
Flow Monitor should indicate flow. 5.6.16 Second fifteen second post sample back-f. lush: SV-5 Open , Flow Monitor should indicate flow. . . 5.6.17 Three minute sample flask line flush:
~ . SV-5 Closed Open corresponding solenoid valves for sample station selected in step 5.6.12 and flush 'for three minutes.' Flow indicator should indicate flow.
f- 5.6.18 After flush is completed, close the following valves in ocder
\s,,g/ -
solenoid valves for station selected in step 5.6.12: SV-10 Closed SV-6 Cl osed - 5.6.19 Call Control Room and have containment isolation valves selected in step 5.6.8 closed. , CAUTION: Make sure correct set is closed to avoid damaging .
. hydrogen monitors. ,
5.6.20 Af ter cart is removed, reset " Active / Inactive" indicator lights '
- to Inactive mode. ,
O . 6
,.. EP-RET-3C JAN 'l 21994 Pdge 19 of.24 r Attachment 1 .
-VALVE LINEUP SHEET Sample Acquisiti6n-Panel .
FPC-51 Sample Flush Line Iso. CLOSE
, ~FPC-51-41 RHR Sample ~ Flush CLOSE
'.RHR 81-A - RHR SMPL Iso A Aux Cool CLOSE .
RHR~81-B RHR.Smp1 Iso B Aux Cool CLOSE
-FPC 51, RCHL Snpl Flush CLOSE ,,
RC-42 3 RCHL Smpl' . CLOSE . FPC-51-31 M/B Demin Inlet Flush CLOSE LD.-71 M/B Demin~ Inlet Iso. CLOSE L D-7.5 M/B Demin Inlet Smpl CLOSE FPC-51-21 _ M/B Demin Outlet Flush CLOSE ,
.LD -
M/B Demin Outlet, Iso CLOSE LD-85' M/B Demin Outlet Smpi . CLOSE
~
- FPC-51-12 ' Pzr Stm Sp Smp1 Flush- CLO5E RC-403 Przr Stm Sp Smpi ,
CLOSE
. FPC-51 -13 Pzr Liq Sp Smpl Flush CLOSE
~RC-4k3-1 Pzr Liq _Sp Smpl ,
CLOSE - CC-314 Rx Cool HRS. Hx CC Flow CLOSE
~ ~
. -CC-316 RHR HRS Hx CC Flow CLOSE MGR-545 VCT Gas 55 1 Smpl Iso A CLOSE MGR-545-1 VCT Gas SP.Smpi Iso B CLOSE RC-4 37-1 Smpi Purge Divert A TO VCT
. RC-437-2 .Smpl Purge Divert B- TO VCT a <
e 6
EP-RET-3C JAN 1.21984 Page 20 of 24 Attachment 1'(cont"d) A) Q,, LiquidSampkePanel ,
. :V-17 .
$Open Grab Sample ,
SHUT ,
, V-6.1- . Rem Smpl Bomb Inldt ,
SHUT V-6.2 Rem Smp1 Bomb Outlet SHUT ,
. V-5.1 , .
Rem Smpl Bomb Inlet Iso SHUT . V-5.2
- Rem Smpl Bomb Dutlet Iso SHUT' V-REL-1 RC' Purge Throttle -THROTTLED
- V-3 .RC Purge Stop . Shut
. -V-REL-2 RC Purge to Waste Tk THROTTLED V-7 ,
Smpl Bomb Bypass SHUT , V RC Purge.to Waste Stop ' SHUT fN V-1.1 RHR Smpi Iso- SHUT U V-1.2 RCHL/Pzr Smp1 Iso - SHUT , V-1.3 (Spare) - SHUT
. .V-1.4 (Spa re) SHUT V-1.5 'VCT Gas Sp Smpl Iso SHUT V-4 DI Water Flus _h . Iso SHUT-V-8.1 . Press Smpl Bomb Inlet SHUT-
~V-8.2 Press Smpi L}omb ~ Outlet SHUT
~ V-9 ,
Expansion Vessel Inlet SHUT V Argon Gas. Strip Purge . SHUT
'V-18 RC Backflush 6 o' clock Undiluted Liq Smpl V-19 BYPASS V-2 2 -- RC Purge Waste / CAP WASTE 4
- EP-RET-3C JAN 121984.
Page 21'of 24 79 Attachment 1 (cont'd) .
~
Liquid Sample Panel (cont'd) .
~
DV-l' Diluted Liquid Sample' BYPASS . l V-11 Expansion Vessel Outlet CLOSED Diluted Gas Smpl 3 o.' clock
. l- DV-2 ,
.V-10 -
Expansion Vessel Vacuum SHUT' V-13 .Dil Gas Smpl Vac SHUT
~
. V-14 Argon Purge to Dil Gas,Smpi SHUT V-15 Gas Smpl to GC SHUT V-12 Argon to Eductor SHUT
~
(..) -
~ Liquid Sample Panel -(Demin Sect)
DMV-1.1 CVCS Demin Inlet Iso SHUT DMV-1.2 'CVCS Demin Outlet Is6 SHUT DMV-1.3 (Spa re) SHUT DMV-3 DI Hater Flush SHUT. DhV.-2.1 CVCS Demin Inlet Smpl SHUT
. DMV-2.2 ,
CVCS Demin Outlet Smpi SHUT DMV-2.3 (Spa re) SHUT t/ ,
r . EP-RET-3C
~
JAtt 1 P.1384-Page 22 of 24
;,- 3 Attachment 1 (cont'd) -
R) . CASP Control Panel . AV-1/SV-1.2 Smpl Pos #1 Inlet /0[utlet- CLOSE SV-2.1/SV-2.2 ' Smpl Pos.#2 Inlet / Outlet CLOSE
~
SV-3.1/SV-3.2 Smpi Pos #3 Inlet / Outlet CLOSE
~
SV-4.1/SV-4.2 -Smpi Pos #4 Inlet / Outlet CLOSE SV-5 Smp1 Bypass CL,0SE SV Nitrogen to Eductor , CLOSE AV-2 Return to Containrent CLOSE SV-6 , Eductor Suct ion Iso CLOSE
~
/~'5
' (At Sample Acquisition Panel) -
, AS110A Cont Air Smpi A Iso CLOSE AS110B ' Cont Air Smpl B Iso CLOSE S
9 O e 9 6 e
#% i L.) .
z.._.-..-.._-.- --- - - - - - - " + - - - - -- ------- -- - -
* * ~
EP-RET-3C ! i e. JAN 121984 Page 23 of 24 O- Attachment 1 (cont'd) -
- %.J ~ . ' '
Chemical Analytical Pansi OP.EN V-2. IC Sspl.0utlet IC i. cop Select CLOSED l V-5 . 02- Cal - V-6 02 LOOP Select YSI
- ~ V 02 Analyzer Select' .
' CPEN V j 02 Loop Outlet SHUT 02 Anal Cal" Supply V .9 - ,
Inst Air Supply OPEN . V-10
'V-l l DI1[aterSupply .
OPEN Nitrogen S~upply OPEN
.V-12.
Argon Supply to GC OPEN
-V-14 ,
Cal-3 Supply OPEN V-15 ' ,
. O SHUT V' V-17 02 Cal Tk Recirc SHUT-V-18 02; Cal Tk Drain SHUT V-19 ,
Cal-3 Drain pH Cal Tk 2 Drain _ SHUT V-20 IC Inject,P6rt - SHUT
. V .
SHUT V-16 pH Cal Tk 2 Supply SHUT V-25 . pH Cal Tk 1 Drain. VENT V -27 ' pH Cal Tk i N2 Supply , VENT
'V-28 pH Cal Tk 2 N'2 Supply.
Cal-3 N2 Su'pply VENT V pH Cal Tk Select CAL-1 V-30 SHUT V-26 pH Cal Tk 1 Supply SHUT C LJ V-24 02 Cal Tk Fil1 6 4 4 h e . .i
^6.,
. EP-RET-3C-JAN 3 21984
. Page 24 of 24 (s I.M.C.C... CONTROL PANEL
-I HS-3 Dilution' Water Bite Valve OFE HS-4~ Air /Wat,er Flush Valve OFF HS-5 - Pr.essurized Reactor Cool to I.M.C.C. OEF
~
-HS . Reactor, Cool. Bit'e Val ve OFF
. HS-7 ,,
' Mixing Chamber Flush / Vent Valye DFF
~
flS-8 . Undil . RX. Cool . Smp1. Outlet Valve OFF HS-9 5 Undil . RX. Cool. Smpl/ Divert Valve OFF ,
. HS-10 Mixing Chamber Outlet Valve OFF Dil . RX. Coel . Smpl . Outlet Valve -
0FF
~
. HS-11 .
? HS'-12 Depressurized RX. Cool . to 1.M.C.C. OF F.
-- HS-13 _
Degassifier Outlet / Flush Valve OFF
. , HS-14 Dil. Wtr. Outlet Valve 0FF HS-15 Air Fl'ush to Mixing Chamber 0FF
-HS-16 . Gas Marinelli Bypass Valve OFF Main Power Switch ON ,
. O O
e 9 0 O O g .
, k OISCONSIN.PUBLIC SERVICE CORPORATION l10. EP-TSC-7 Kewaunee Nuclear Power Plant TITLE : RV Head Venting Ti.ne Calculation
, IMERGENCY PLAN IriPLEMENTING Pl:0CEDURE I ;
DATE: JAt112 E84 PAGE 1 of 3 r
/'j l d l
REVIEWED BY j7( gY /?f.,gM APPROVED BY E 1.0 APPLICABILITY This procedure provides instructions for determining the maximum allowable l Venting period'of the reactor vessel head when noncondensable gases are
. present ir. the RCS.
2.0 PRECAUTIONS I 2.1 This procedure should be done concurrently with 'E-0-12, ".Postaccident l Systems Operation" section -4.1, Reactor Vessel Head Vent. I 3.0 REFEPENCES
~
~
3.1 " Background Information for Westinghouse Emergency Response Guidelines, cs FR-I.3 Void.in Reactor Vessel". l (a ) Rev. LP-BASIC September, 15, 1981. 3.2 "FR-1.3, Response to Voids in Reactor Vessel". LP-Rev.1, September 1,1983. 3.3 EP-RET-3C, " Post Accident Operation of the High Radiation Sample Room". 4.0 INSTRUCTIONS l* 4.1 Ensure that the containment hydrogen analyzer has been placed in service per EP-RET-3C. Allow a~ minimum sample purge time of ten minutes. 4.2 All availa'ble ccntainment air circulating equipment should be operating
. to prevent' the formatica of hydrogen gas pockets and ensure a representative sdmple is obtained. If only one Cont,ainment dome fan is operating, the sample should be taken from the operating fan discharge.
4.3 Maximum Allowed Venting Time 4.3.1 Record or determine the following values: RCS pressure psig cntmt. hydrogen conc. % 5 max. allowable 3% cntmt. pressure psig
.m
~
l cntmt. abs. pressure (cntmt. press. + 14.7 psi) psia cntmt. temperature F cntmt, absolute temperture (cntmt. temp. +460 R) R
( ~
' WISCONSIN PU3LIC SERVICE CORPORATION
. l fl0. EP-TSC-7 Kewaunee Nuclear Power Plant TITLE: RV Head Venting Time Calculation SMERGENCY PLAN IMPLEMENTING PROCEDURE
- DATE: JM 121984 PAGE 2 of 3 4.3.2 Calculate contain:nent.volunie at STP = A (scf)
-(cntet. absolute pressure) 492 R A = 1.32E406 cf x 14.7 psia x (cntmt abs temperature)
= 'sc'f
'4.3.3 Qalculate maximum hydrogen volume that can be vented = B (scf)
'B.= J% - (cntmt. hydr > gen conc.). xA scf
=
4.3.4 Determine hydrogen flow rate as a function of RCS pressure using Fig. TSC-7 = C (scfm) . C= scfm ( 4.3.5 Calculate maximum venting time: Maximum venting time = B/C = min. O G
- e 9
0
. ..- - . . .-..._.-..._.m_ ,.
,I
*r a
EP-TSC-7 p.- , FIGURE TSC-7 JM 12 m Pcge 3 of 3 i HYDROCEN. FLOW RATE'VERSUS RCS PRESSURE l
. ~
.- .- .p t. .t .' ,-.- .-. . .- .j- .,... - . .
3600
.~.. . ..
- . 1. . .
fs, . _ . . ... . .. ,._ . .. .. .. 4
. ._.i,... _ . .
.s_ . .,.
. ....= .. _ . ,
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.e < , .
.t. . .
-....b.,...
1.o . ...
. .. ... .,, . . ,..._c.... ..
.J c. . . . l.
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. , . , . 1, a . ,
o . ,. , t ,- . : ... .,. L. .
.... . . .. .m
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.. ._ . n. .
..~....J_.......... .
...,,..r..,...-
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e .. . m...o., n
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r
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=
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2800
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t.. ... .... .. t.... . . _ m.
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. _. L_. . . .. _ . - . .
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, ... . = .
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24UU
.. ,4..-_. ._. .
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y...
. _.. . . .. . . ... . ,.-~ .. . .
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. ,. . m.. "
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