ML20077Q048
| ML20077Q048 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 07/26/1983 |
| From: | Luoma C WISCONSIN PUBLIC SERVICE CORP. |
| To: | |
| Shared Package | |
| ML111671208 | List: |
| References | |
| PROC-830726-01, NUDOCS 8309150194 | |
| Download: ML20077Q048 (60) | |
Text
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REVISED 7-26-83
'Page 1 of 5 o
EMERGENCY PLAN IMPLEMENTING PROCEDURES
(-
-Index-REVISION DATE Procedure #
TITLE D
03-10-83 EP-AD-1 Plant Emergency Organization C
03-10-83 EP-AD-2 Emergency Class Determination B
03-10-83 EP-AD-3 Unusual Event B
03-10-83 EP-AD-4 Alert B
03-10-83 EP-AD-5 Site Emergency B
03-10-83 EP-AD-6 General Emergency CP-AD-7 Notification of Unusual Event F
03-10-32 F
03-10-83
. EP-AD-8 Notification of Alert F
03-10-83 l
EP-AD-9 Notification of Site Emergency EP-AD-10 Notification of General Emergency F
03-10-83 C
06-21-83 EP :AD-11 Emergency Radiation Controls EP.-AD-12 Personnel Assembly and Accountability 0
03-13-83 03-03-83 EP-AD-13 Personnel Evacuation EP-AD-13A Limited Area Evacuation DELETED 03-1-83 EP-AD-13B Emergency Assembly / Evacuation DELETED 03-1-83 EP-AD-13C Site Evacuation DELETED 03-1-83 I
EP-AD-14 Search and Rescue A
03-10-83 A
03-10-83 EP-AD-15 Recovery Planning l
EP-AD-16 Occupational Injuries or' Vehicle Accidents A
03-10-33 During Emergencies EP-AD-17 Communic'ations 0
03-10-83 EP-AD-18 Availability of Inorganic Iodine Salts tor A
03-10-83 Iodine Saturation of the Human Thyroid Gland EP-ENV-l' Environmental Monitoring Team Organization.
B 03-10-83 f
EP-ENY-2 Site Access Facility (SAF) Activation B
03-10-83 8309150194 830907 i
PDR ADOCK 05000305 l
F PDR
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REVISED 7-26-83 Rage.2 of 5 EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index-(cont'd)
REVISION DATE Procedure #
TITLE EP-ENV-3A Environmental Protection Director H
06-21-83 Actions and Directives E
06-21-83 EP-ENV-3B EM Teain Actions-EP-ENV-3C Primary Dose Projection Calculation - IBM 06-21-83 Personal Computer 06-21-83 EP-ENV-3D Primary Detemination of Meteorological Data EP-ENV-3E Manual Det'ermination of X/Q (KNPP E
06-21-83 Meteorological Data)
EP-ENV-3F Manual Determination of X/Q (Green Bay Meteorological Data)
D 06-21-83 0
06-21-83 EP-ENV-3G Manual Dose Projection Calculation B
06-21-83 EP-ERV-3H Protictive Action Recommendations
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C 03-10-83 EP-ENV-4 A Sample Acquisition, Portable Instrument Use B
05-21-82 EP-ENY-4B Sample Acquisition, Air Monitoring Devices EP-ENV-4C Sample Acquisition, Environmental B
05-21-82 Sampling Techniques B
4-21-83 EP-ENV-5A LCS-1 Operation B
4-21-83 EP-ENY-5B MS-3 Operation C
03-10-83 EP-ENV-5C SAM II Operation A
12-21-81 EP-ENY-5D PAC-4G Operation
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A 03-10-83 EP-ENY-5E Reuter-Stokes Operation EP-ENV-6 Data Analysis, Dose Projections and Protective DELETED Action Recommendations EP-ENV-6A Relocation of Site Access Facility
'A 03-10-83 l
(Habitability) l l
EP-ENV-6B SAF Environmental Sample Analysis
- Relocation A
11-24-82 EP-ENY-7 Site Access Facility Ccmmunications B
03-10-83
~A 7-26-83 EP-ENV-8 Total Population Dose Estimate Calculations 2-
Page 3 of 5 REVISED 6-21-83 EMERGENCYPLANIMPLEMENTIi1GPROCEDURES
-Index-(cont'd)
Procedure #
TITLE REVISION DATE EP-EOF-1 Corporate Staff Emergency Response Organization G
43-10-83 EP-EOF-2 Emergency Operations Facility (E0F) Activation D
03-10-83 EP-EOF-3 Corporate Response to an Unusual Event F
03-10-83 EP-EOF-4 Corporate Respoase to an Alert G
03-10-83 EP-E0F-5 Corporate Response to a Site Emergency G
03-10-83 EP-E0F-6 Corporate Response to a General Emergency G
03-10-83 EP-E0F-7 Communications Documentation E
03-10-83 EP-EOF-8 Relocation of EOF DELETED 03-01-83 EP-EOF-9 Interface with Support Organizations E
03-10-83 EP-OP-1 Control Room Emergency Organization A
1-03-83 EP-OP-2 Emergency Control Roan Activation for B
1-03-83 Emergency Response EP-0P-3 Control Room Communications A
'1-03-83 l
EP-OSF-1 Operational Support Facility (OSF) Organization A
1-15-82 EP-0SF-2 OSF Activat,fon A
05-21-82
'EP-OSF-3 Work Requests During an Emergency A
1-15-82' EP-OSF-4 OSF Communications B
03-10-83 i
EP-RET-1 Radiation Emergency. Team (RET) Organization C-03-10-83 EP-RET-2 Inplant RET C
03-10-83 G
- Page 4 of 5 REVISED 7-26-83 s
EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index-(*
(cont'd) '
Procedure #
TITLE REVISION DATE 3
EP-RET-2A RP0/RAF Activation C
03-10-83
.EP-RET-2B Gaseous Effluent Sample and Analysis C
'03-01-83 EP-RET-2C Containment Air Sampling and Analysis DELETED 03-01-83 EP-RET-2D Emergency Radiation Intry, Controls and B
03-10-83 Implementation EP-RET-2E Handling of Injured Personnel A
03-10-83 l
EP-RET-2F Personnel Decontamination B
03-10-83 EP-RET-3 Emergency Chemistry Team C
03-10-83 EP-RET-3A Liquid Effluent Release Paths A
12-21-81 EP-RET-3B Post-Accident Reactor Coolant Alterriate B
03-10-83 Sampling Procedure j
[
EP-R,ET-3C Post Accident Operation of the High Radiation A
Sample Room A
07-26-83 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 EP-RET-4 Site RET C
03-10-83 EP-RET-4B Radiological Controls at Site Access Facility (SAF) A 03-10-83 EP-RET-4C Site Radiological Monitorin'g A
03-10-83 EP-RET-5 Plume Projections B
7-26-83 EP-RET-5A Plume Projections (Backup Method)~
A 12-21-81 EP-RET-6 Dose Projection B
7-26-83 i
EP-RET-7 RAF/RPO Communications A
03-10-83 EP-RET-8 Contamination Control at the Two Rivers A
03-10-83 Community Hospital
Pag 3 5 of 5 REVISED 7-26-83 EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index-(
(cont'd)
Procedure #
TITLE REVISION DATE
.EP-SEC-1 Security Organization A
03-10-83 EP-SEC-2 Security Force Response to Emergencies C
03-01-83 EP-SEC-2(a)
Manual Activation of Emergency Sirens DELETED 1-29-82 EP-SEC-3 Personnel Accountability (Initial and Maintaining) D 03-1,0-83 EP-SEC-4 Dosimetry Issue at SAF A
03-10-83 EP-TSC-1 Technical Support Center (TSC) Organization 12-21-81 EP-TSC-2 TSC Activation C
03-10-83 EP-TSC-3 Plant Status Procedure B
03-10-83
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EP-TSC-4 Emergency Design Change, Major Equipment Repair 12-21-81 EP-TSC-5 TSC Communications A
03-10-83 EP-TSC-6 Assessment,0f Reactor Core Damage A
03-10-83 l
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WISCONSIN PUBLIC SERV,. ICE CORPORATION l
NO.
EP-ENV-8 REY. A y
- Kewaunee Nuclear Power Plant l
TITLE: Total Population Dose l
Estimate Calculations l
1 C_
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
DATE 7-26-83
! PAGE 1 of 6 I
I b4/# d /,7 [ 7)f d.
APPROVED BY M _b4%w IEVIEWED BY 1.0 APPLICABILITY This procedure is implemented by the Environmental Protection Director (EPD) after a release of radioactive effluents during an emergency to calculate the total population dose.
2.0 PRECAUTIONS 2.1 Accurate recording of data is essential.
2.2 Double check all calculations.
3.0 REFERENCES
3.1 EP-ENV-3 series of procedures.
4.0 INSTRUCTIONS 4.1 Utilize the EP-ENV-3 series of procedures and field samples to determine the sectors.af fected by plume track.
4.2 Dispatch Envircomental Monitoring teams to the appropriate sample locations
. (Table ENV-8.1) of the plume-af fected sectors to exchange environmental TLDs.
NOTE: The TLDs removed must have a label attached indicating their location Number.
4.3 Direct that the Envirorsnental TLDs be taken to the Site Radiation Emergency Team for transfer to the plant for readings.
Ensure the Location Number is recorded with the TLD Serial Number during reading.
4.4 Obtain the Environmental TLD loc ~ation and Serial Numbers and readings from the RP0/RAF.
4.5 Calculate the total Whole Body and Iodine Sector Doses by completing Form ENV-8.1 for each affected sector and Fonn ENV-8.2 for total population dose.
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EP-ENV-8 7-26-83 Page 2 of 6
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TABLE ENV-8.1 TLD MONITORING AllD SAMPLING LOCATIONS 1.
Lakeshore ild (M) 1/4 mile north of Zander Rd.
l 6.
County BBB 1/2 mile south of BB
- 10. County B 1/4 mile north of Zander Rd.
- 16. Access Rd. off of Tappawingo Rd.1/4 mile east of Tannery Rd.
- 17. Tappawingo Rd. 3/4 mile west of Tannery Rd.
- 23. Lakeshore Rd. (M) 1/4 mile north of Nuclear Rd. (M)
- 46. Nuclear Rd. (K) 0.4 mile east of State Hwy 42
- 47.. Nuclear Rd. (K) 1/2 mile west of Hwy 42
- 48. County Hwy BB and State Hwy 42 intersection ~
l 49. Geman Lane 1/4 mile west of State Hwy. 42
- 53. State Hwy 42 and intersection of Nuclear Rd. (K)
- 56. State Hwy 42 and intersection of Sandy Bay Rd.
' 5 7.
Sandy Bay Rd. and intersection of Cemetary Rd.
- 58. Cemetary Rd. and intersection of Sandy Bay Rd.
- 59. Lakeshore Rd. (K) and intersection of Cemetary Rd.
- 60. Lakeshore Rd. (K) 1/2 mile east of State Hwy 42
- 61. Lakeshore Rd. (K) and State Hwy 42' intersection
- 63. Sandy Bay Rd.1/2 mile west of State Hwy 42
- 65. Woodside Rd.1/2. mile north of Nuclear Rd. (K)
- 69. Town Hall Rd.1/4 mile north of County Hwy BB l
- 70. Town Hall Rd.1/4 nile north of Nuclear Rd. (K)
- 74. Woodside Rd. and County Road G intersection I 85. County Hwy B 1/4 mile north of County Hwy G e eo.
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EP-ENV-8 7-26-83 Page 3 of 6 TABLE ENY-8.1' (cont'd)
TLD MONITORING'AND SAMPLING LOCATIONS
- 89. Nuclear Rd. (K) 1/2 mile east of Range Line Rd.
l 105. County Hwy 81/4 mile south of County Hwy J 109. Town Line Rd. and State Hwy 42 intersection t
111. Lake Rd.1/2 mile ea:t of State Hwy 42 1 129. East end of Krok Rd, along the lakeshore 133. Lakeshore Rd.1/2 mile north of Kewaunee city 135. County Hwy F 1-1/4 miles west of State Hwy 42 136. Maple Lane 1/2 mile west of County Hwy C l 138. Sleepy Hollow Rd.1/4 mile north of Hwy 29' 140. Schweiner Rd.1/2 mile south of County Hwy J
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141.. Schultz Rd. and State Hwy 96
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143. County Hwy Q 1/4 mile north of Stat'e Hwy 147 144. Fisherville Rd. and Cherney Rd. intersection 1 145. Steiners Corr:ers Rd.1/2 mile west of ' State Hwy.147 i
l 147. Point Beach Rd.1/2 mile south of County Hwy. VV i
i (K) = Kewaunee County (M) = Manitowoc County l
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EP-ENV-8 7-26-83 o
Page 4 of 6 i
TABLE ENV-8.2 POPULATION AND TLD DISTRI,BUTION BY' SECTOR _
B SECTOR ENY. TLD LOCATION #'s POPULATION / SEGMENT 0-2 mi 2-5 mi 5-10 mi (a)
(b)
(c)
(d)
(e)
( f)
(g)
J N/A 1
23 147 0
17 439 K
48 6
16 145 10 186 970 L
49 6
17 144 20 99 1735 M
47 69 10 143 17 194 462 N
46 70 89 141 7
82 436 P.
58 65 85 140 10 112 567 Q
63 74 105 138 ~
14 133 660 R
56 61 109 136 10 119 610 A
57 60 l'11 135 10 126 2618
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B 58 59 129 133 7
91 616 e
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EP-ENV-8 7-26-83 Page 5 of 6 FORM ENV-8.1 -
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SECTOR POPULATION DOSE WORKSHEET SECTOR DOWNQIND ENY. TLD ENY. TLD TLD DOSE AVERAGE W.B.
SEGMENT LOCATION #'s SERIAL #'s READINGS (REM)
DOSE / SEGMENT (REM)
(a) 0-2 mi
+
/2
=
(b) 2-5 mi
+
/2
=
(c) 5-10 mi
+
/2
=
(d)
AVERAGE W.B.
POP!!LATION/
TOTAL DOSE /
DOSE / SEGMENT (REM)
. SEGMENT SEGMENT (MAN-REM) 0-2 mi x
(e)~
=
2-5 mi x
(f)
=
5 x
(g)
, -10 mi
=.
TOTAL SECTOR W.B. DOSE =
MAN-REM ESTIMATED IODINE DOSE / POPULATION /
TOTAL IODINE DOSE /
SEGMENT (REM)
SEGMENT SEGMENT (MAN-REM) 0-2 mi x
(e)
=
2-5 mi x
(f)
=
5-10 mi x
(g)
=
TOTAL SECTOR IODINE DOSE =
MAN-REM i
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EP-ENY-8 1
7 83
- Page 6 of 6 FORM ENY-8.2 TOTAL. POPULATION EXPOSURE' CALCULATION TOTAL SECTOR TOTAL SECTOR W.B. DOSE (MAN-REM)
IODINE DOSE (MAN-REM)
SECTOR SECTOR SECTOR SECTOR SECTOR.
SECTOR SECTOR 4
SECTOR
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SECTOR
- SECTOR, TOTAL POPULATION W.B. DOSE TOTAL POPULATION IODINE DOSE e
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WISCONSIN PUBLIC SERVICE CORPORATION I NO.
EP-RET-3C REY. A l
a Kewaunee Nuclear Power Plant i TITLE: Post Accident Operation of the l
High Radiation Sampic Room EMERGDCY PLAN IMPLEMENTATION PROCEDURE l.
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l DATE:
JUL 2 6 1983 l PAGE 1 of 24 I
I IEVIEWED B 1 APPROVED BY M /// M v N*I 1.0 PURPOSE 1.1 This procedure is to detail the requirements, considerations, and operation of the High Radiation Sample Room during a post LOCA condi tion.
2.0 APPLICABILITY 2.1 This is to detail the procedures to be utilized for obtaining:
Diluted liquid sample of primary coolant, for Boron Analysis a.
and Isotopic Analysis (Sect 5.1).
b.
An inline sample for pH, conductivity, oxygen, and chloride analysic (Sect 5.2).
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c.
An inline sample of. primary coolant for Hydrogen Analysis, i-and a dilute sample of gases, contained in Primary Coolant.
for Isotopic Analysis (Sect 5.3).
d.
An undiluted sample of Primary Coolant for of f-site ana' lysis (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 Pennit (see EP-AD-ll).
i 3.2 Contact Health Physics Dept for:
a.
Pi oper personnel dosimetry.
l b.
Proper radiation detection instrumentation.
c.
Personnel for continuous HP coverage during sampling.
d.
Remote area monitor readings in area of HRSR.
3.3 Utilize onsite conmunications with the Radiological Protection Director, as necessary, during sampling.
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WISCONSIN PUBLIC SERVICE CORPORATION l NO.
-l Kewaunee Nuclear Power Plant l TITLE:
Post Accident Operation of the l
High Radiation Sampic Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
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l PAGE 2 of 24 l DATE: R 26 1983
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 4.7 RC-C-203, Chloride-Ion Chromatography (IC) Analysis 5.0 PROCEDURE l
5.1 Dilute Liquid Grab Sample 5.1.1 Proceed to HRSR per HP/RPD reconmendations.
l 5.1.2 At the C.A.'S.P. Control Panel check ventilation on in "nomal" l
. position and High Vacuum Lights indicate."nomal" for the LSP
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l and CAP.
5.1.3 Check radiation levels in HRSR, and in maintenance area behind panels, if access is required.
5.1.4 Check 'the followin'g Lab Equipment available and operational:
a.
Drying oven on at 55'C to 60*C.
b.
Fume hood ventilation noma 1.
c.
Shielded aliquoter available.
d.
DI water flush hoses connected to LSP and supply valve on.
e.
New 24 ml diluted sample bottle, f.
Hand operated vacuum pump.
g.
Lights on in Diluted Sample Port of LSP.
h.
LSP Sample Cask available with ' diluted sam'ple bottle piston install ed.
1 Perform 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 - 1 liter poly bottles.
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WISCONSIN PUBLIC SERVICE CORPORATION 1 NO.
Kewaunee Nuclear Power Plant i TITLE:
Post Accident Operation of the l
High Radiation Sample Room l
l C
EMERGENCY PLAN IMPLEMENTATION PROCEDURE l DATE: JUL 2 6 1983 l
PAGE 3 of 24 l
l 5. 1. '57 Evacuate the diluted sample bcttle to 15 inches of vacuum or greater.
Install in sample cask and check cask for proper operation.
5.1.6 Install the sample cart under the diluted ' sample port and position the bottle up on the needles.
5.1.7 Check level in dilution water reservoirs. Fill to full mark as necessary.
I 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)
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'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-1 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-1 is equal to approximately 1/2 gpm flow rate.
5.1.12 Upon completion of the purge: Shut V-3 Open V-8.2 Open 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.
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WISCONSIN PUBLIC SERVICE CORPORATION l NO.
}
~ Kewaunee Nuclear Power Plant i TITLE:
Post Accident' Operation of the l
High Radiation Sample Room i
EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
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I: DATE: JUL i.6 1983 i PAGE 4 of 24 I
l 5.1.14 Upon completion of the purge: Turn DV-1 to " Sample" Shut Y-1.2 (V-1.1 for RHR}
5.1.15 Throttle open V-21 and add 24'm1 of DI. water, from the graduated reservoir to the sample bottle, then close RC-V-21.
5.1.16 Turn DV-1 to " Bypass".
5.1.17 Open V-4.
Observe Flush Water Flow Rate of 18-22 inches of water for a minimum of 3 minutes.
5.1.18 Upon canpletion of flush:
Shut Y-4 Shut Y-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).
5.1.20 At the Sampie Acquisition Panel:
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'For RLHL Sample: Open FPC-51 Open FPC-51-14 For RHR Sample:
Shut RHR-81-A (81-B)
Open FPC-51 5.1.21 At the Liquid Sample Panel: Open V-1.2 (V-1.1 for RHR)
Open V-3 Observe Flush Water Flow Rate of 35 to 40 inches of water as indicated on RC-FI-1. Maintain flush for 5 minutes while perfonning step 5.1.22.
NOTE: A D/P of 35 to 40 inches of water on RC-FI-1 is equal to approximately 1/2 gpm flow rate.
5.1.22 Lower the diluted sample bottle into the sample cask. Close the cask and install auxiliary shield. Place cask near ' fume hood.
5.1.23 Upon completion of flushing: Shut V-1.2 (V-1.1 for RHR)
Shut V-3 5.1.24 At the Sample Acquisition Panel:
For RCHL Sample: Shut RC-423-1 Shut FPC-51-14
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Shut FPC-51
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Shut CC-314 G
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, ISCONSIN PUBLIC SERVICE CORPORATION NO.
Kewaunee Nuclear Power Plant i TITLE:
Post Accident Operation of the l
High. Radiation Sample Room 1
i C
EMERGENCY PLAN IMPLEMENTATION PROCEDURE l DATE: JUL 2 6 1993 l
PAGE 5 of 24 I
I For RHR Sample: Shut RHR-81-A (81-8)
Shut FPC-51-41 Shut FPC-51 Shut CC-316 For all samples: Turn RC-437-1 (or 437-2) to VCT 5.1.25 Using the shielded liquid aliquoter, transfer a 1.0 m1 sample from the, sample cask into a VYCOR evaporating dish.
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 cask to a liter poly bottle using the shielded liquid aliquoter.
Dilute to i liter.
5.1.28 From the diluted 1 liter bottle' in step 5.1.27, transfer 10 ml
'to another empty liter bottle. Dilute to 1 liter. This' sample
.may be transferred to the multi-channel analyzer for counting.
C 8
NOTE: Total dilution is ( x 10 )
5.2 Inline Sample for pH, Ccnd, 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 "nonnal" 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.
i b.
Verify valve lineup for SAP, LSP, and CAP, per Attachment #1.
c.
Reach Rod for Remote Valva 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 l'
performances.
g.
Check gas bottles (argon and air) for adequate supply.
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I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
- l Kewaunee Nuclear Power Plant l TITLE : Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l
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M 26 @
l*DATE:
l PAGE 6 of 24 5.2.5 At the CAP: Turn V-6 to Liquid Sample Turn V-5 to Liquid Sample 5.2.6 Have the Control Room Operator open RC-422 and RC-423 (not required for RHR sample).
5.2.7 t the Sample Acquisition Pa'nel:
For RCHL Sample: Open CC-314 Open RC-423-1 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.
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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 ap' proximately 1/2 gpm flow rate.
5.2.10 Upon completion of the purge: ShutY-3 Open V-2 Open V-7 1
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 YSI 02 meter chart reading has stabilized:
Record the conductivity reading Record the temperature l
Record the 0. reading 2
l Place the Load / Inject switch on the IC unit to " Inject"
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i WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant i TITLE:
Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l
I
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l DATE:
JUL 2 6 1983 i PAGE 7 of 24 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" l
5.2.16 Flush the CAP by turning V-22 to Chem Panel position. Verify I
flush water flow by observirg the lights "on" for both 02 Flow and IC Flow. Continue Cush for 2 minutes.
NOTE: Chloride results should read out 5 to 10 minutes after 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 to 02 Cal Turn V-5 to Closed 5.2.18 Have Control Room 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-51441 5.2.20 At the Liquid Sample Panel:
Open V-1.2 (V-1.1 for RHR)
Open V-3 l
Use V-REL-1 to control flush water flow rate of 35 to 40 I
inches of water as indicated on RC-FI-1. Maintain this flush 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.
i l
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
.I l
,Kewaunee Nuclear ' Power Plant
- 1. TITLE : Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE i
I l PAGE 8 of 24 l DATE:
JUL 16 50
(
5.2.21 Upon completion of flushing: Shut V-1.2 (V-1.1 for RHR)
Shut V-3 5.2.22 At the Sample Acquisition Pariel:
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 l
5.3 Hydrogen and Gaseous Activity Grab Sample 5.3.1 Proceed to'HRSR per HP/RPD reconmendations.
(
5.3.2 ' Verify ventilation on in "nonnal" positio'n and high vacuum T
lights indicate " normal" for the CAP and LSP.
5.3.3 Check radiation levels in HRSR, and in maintenar.ce 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".
j e.
Check the progr.am in GC ' mini-computer and latest data in the HRSS Cal Log.
i f.
Check Argon and Air Pressure 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.
I l
l~
5.3.5 Dry the expansion vessel: Turn V-11 to " Argon" l
Open V-9 Open.V-8.2 Open V-10 MH e.
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l WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant I TITLE:
Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l
i DATE:
9 of 24 JUL 2 6 1933 lPAGE 5.3.6 Adjust RC-VREL-2 as necessary to obtain 20 psi on RC-G-3 for 1 minute. Observe flow indication on RC-FI-2 also.
5.3.7 Upon completion of Drying Expansion Vessel:
1 Turn V-11 to 9 o' clock position Shut Y-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-316 Open RHR 81-A (81-B)
For all samples: Turn RC-437-1 (or 437-21 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 Regula.te Reactor Coolant (RHR) flow using.RC-VREL-1.until flow indicator RC-FI-1 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-1 is equal to approximately 1/2 gpm flow rate.
5.3.12 Evacuate the Gas Expansion Vessel, sample bottle and tubing:
Open V-13 Cpen V-15 1
Turn DV-2 to 6 o' clock position Open V-12 1
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 Shut.V-13 e
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l l
l l.
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
l
-l
.Kewaunee Nuclear Power Plant i TITLE: Post Accident Operation of the i
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
l
(
DATE: JUL 2 6 1983 i PAGE 10 of 24 Shut Y-10 i
Turn V-11 to Closed Shut Y-12 NOTE: Observe vacuum reading on both gauges holding steady.
5.3.15 bpen V-14 and observe about '1.0 p'st on RC-G-2.2.
5.3.16 Upon cmpletion of. purge (fron 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. Maintai n 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.
(
5.3.18 Upon completion of sample purge:
Shut V-8.2 Shut V-8.1 Shut V-1.2 (V-1.1 fo r RHR)
Open V-9 Open V-16 (for 1 full 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 l
Turn V-11 to 9 o' clock' position 1
5.3.20 Obtain the diluted gas sample by turning DV-2 to 6 o' clock position.
I 5.3.21 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi:
Turn DV-2 to 5 o' clock position Shut V-14 D
~y e
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant i TITLE: Post Accident Operation of the 1
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
I
(
i PAGE 11 of 24 l DATE:
,J(JL 2 6 g 5.3.22 Remove the diluted gas sample bottle from the LSP and place entire assembly in fume hood for later transport to mult,i-channel analyzer.
5.3.23 At the CMP, operate the GC mini-computer to 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 samples for hydrogen determination.
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:
~
For RCHL Sample: Open FPC-51
(
Open FPC-51-14 For RHR Samp,le:
Shut'RHR 81-A (81-B)
Open FPC-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) i Using V-REL-1, regulate flush water flow rate of 35 to 40 l
inches of water on RC-FI-1. Maintain this flush for a minimum i
of 5 minutes.
5.3.29 At the cmpletion 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 Shut FPC-51 Shut CC-314 1
e l
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant l TITLE: Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l-l l DATE:
l PAGE 12 of 24
(
gg
Shut FPC-51-41 Shut FPC-51 Shut CC-316 For a.11 samples: Turn RC-437-1 (or 437-2) to VCT.
5.3.31 At the L-SP flush the expansion vessel:
Open V-8.2 Open V-9 Turn V-ll to "DI Water" position Allow system to flush for 2 minutes.
5.3.32 Upon canpletion of flush:
Turn V-ll to " Argon" position and blow expansion vessel dry 5.3.33 ' Upon completion of drying expansion vessel:
(
Turn V-ll to Close Shut Y-9 Shut Y-8.2 5.3.34 ' Remove radioactive gases fran gas system:
Open V-10 Open V-13 Open V-15 l
Turn V-11 to 9 o' clock position Open V-12 Evacuate system for 1 full minute.
l 5.3.35 Upon evacuation of gas system:
Shut V-12 Turn V-ll to " closed" position Shut V-15
' Shut V-13 Shut V-10 5.3.36 Transport diluted gas bottle to muTti-channel analyzer for I
analysis, per RC-C-(63).
l
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I l
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant l TITLE: Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l
l
(
lTATE: JtJL 26 1983 l PAGE 13 of 24 l
5.4 Undiluted Liquid Grab Sample 5.4.1 Proceed to HRSR per HP/RPD recommend 1tions.
5.4.2 Check ventilation on, in "ncmal" p'o'sition and high vacuum l'ights indicate " normal" 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:
D'I water flush hoses connected to LSP and supply valve a.
open.
b.
Check valve lineup per Attachment #1.
c.
Reach rod for remote valve operation.
d.
New undiluted liquid sample. bottle available.
e.
New undiluted liquid flush bottie, with special tool, available.
f.
Sample cask available with undiluted sa'mple piston installed.
'g.
Light on in undiluted sample port of LSP.
5.4.5 Instal-1 undiluted sample bottle in cask and check for proper operation.
5.4.6 Install the sample cask under the un' diluted sample port arid 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 Sampie Acquisiti,on 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 Y-1.2 (Y-1.1 for RHR)
L
~
- G O
l WISCONSIN PUBLIC SERVICE CORPORATION I NO.
.I Xewaunee Nuclear Power Plant l TITLE : Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE l
I l DATE:
l PAGE 14 of 24
(
g 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 minicium of 5 minutes.
NOTE: A D/P of 35-40 inches of water on RC-FI-1 is equal to approximately 1/2 gpm flow rate.
5.4.11 Upon completion of 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-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.
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 Y-1.2 (V-1.1 for RHR)
Open V-4 5.4.15 While system is in'DI water flush, return undiluted sample to cask, close lead top, and remove cask from lab.
Install auxiliary shield.
NOTE: DI water flush should be performed for a minimum of 3 minutes before going to step 5.4.16.
5.4.16 Place undiluted sample flush bottle, and special flush tool into position.
Turn Y-19 to " sample" 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 sample).
an. me c
l I
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant i TITLE: Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
i C
l DATE:
JUL 2 6 1983 l PAGE 15 of 24 I
I 5.4.1S_ 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 5.4.20 At the Sample Acquisition Panel:
Ope'1 V-1.2 (V-1.1 for RHR)
Open V-3 1
Using V-REL-1, regulate flush water flow rate of 35 to 40 l
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-1 is equal to approximately 1/2 gpm flow rate.
5.4.21 13pon completion of flushing: Shut V-1.2 (V-1.1 for RHR)'
Shut Y-3
(
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 1 A & 1B Operation Procedure 5.5.1 Proceed to HRSR per HP/RPD recommendations.
5.5.2 Check ventilation on in " normal" position.
5.5.3 Check radiat. ion 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> wamup time.
L 5.5.5 Insure' heat tracing is energized and operational.
5.5 6 Check monitor selection at Sample Acquisition Pinel to insure it is not sampling same loop as the CASP.
I I
nilSCONSIN PUBLIC SERVICE CORPORATION l NO.
1 TITLE:
Post Accident Operation of the Kewaunee Nuclear Power Plant
' l High Radiation Sample Room C
EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
l l PAGE 17 of 24 l DATE:
M 2 6 1983 l
I I
5.6.7 Call Control Room 'and verify Dome Fans 1 A and 1B are operational.
5.6.8 Have Control Room Operator open 1 set of the following valves:
Loop A Loop B.
I LOCA-2A
- LOCA-2B l
LOCA-10A LOCA-10B l
LOCA-3A LOCA-3B 1
5.6.9 Insure that when selecting sample loop' A or B that either 1
l hydrogen monitor is not operating or loop, selected is opposite I
that being used by H2 monitor. Open AS110A or AS1108.
5.6.10 Connect local pressure transmitter fo cart selected for sampli ng.
I NOTE: Do not' use the I.S.C. cart for this procedure 5.6.11 CASP two minute pre-sample back flush:
SV-10 -Open SV-6 Open -
~
SV-5 Open Insure flow monitor on CASP is indicating flow.
5.6.12 Three minute sample capture:
SV-5 Closed AV-2 Open For Sample Station 1 - AV-1 and SV-1.2 Open 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 Fifteen second flask equilibration:
l {
SV-6 Closed Flow Monitor on CASP should go out. Pressure Transmitter' should reach stability (NOTE: Equal to containme.nt pressure).
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WISCONSIN PUBLIC SERVICE CORPORATION 1 NO.
Kewaunee Nuclear Power Plant l TITLE:
Post Accident Operation of the l
High Radiation Sample Room EMERGENCY PLAN IMPLEMENTATION PROCEDURE I
I C
JUL 'ab 1983 l
PAGE 18 of 24 l DATE:
I l
5.6.14 Three Minute 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. Af ter 3 minutes op'en SV-6.
5.6.15 I'nitial fifteen second post sample back-flu'sh:
AV-2 Closed Flow Monitor should. indicate flow.
5.6.16 Second fifteen second post sample back-flush:
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.
5.6.18 After flush is completed, close the followi'ng valves in order
(
solenoid valves for station selected in step 5.6.12:
SV-10 Close,d
~
SV-6 Closed 5.6.19 Call Control Room and have containmeht isolation valves selected I
in step 5.6.8 closed.
I CAUTION: Make 'sure correct set is closed to avoid damaging hydrogen moni tors.
5.6.20 After cart is removed, reset " Active / Inactive" indicator lights to Inactive mode.
g, 4
Ow 4
EP-RET-3C JUL 2 6 1983 Page 20 of 24
, (cont'd)
Liquid Sample Panel Y-17 Open Grab Sample SHUT V-6.1 Rem Smp1 Bomb Inlet SHUT Y-6. 2 Rem Smp1 Bomb Outlet SHUT V-5.1 Rem Smp1 Bomb Inlet Iso SHUT V-5.2 Rem Smp1 Bomb Outlet 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 Smpi Bomb Bypass SHUT V-2 RC Purge to Waste Stop SHUT V-1.1 RHR Smpl Iso SHUT V-1.2 RCHL/Pzr Smp1 Iso.
SHUT V-1.3 (Spare)
SHUT V-1.4 (Spare)
SHUT V-1. 5 VCT Gas Sp Smp1 Iso SHUT Y-4 DI Water Flush Iso SHUT V-8.1 Press Smp1 Bomb Inlet SHUT V-8.2 Press Smpi Bomb Outlet SHUT V-9 Expansion Vessel Inlet-
- SHUT, V-16
. Argon Gas Strip Purge SHUT l V-18 RC Backflush 6 o' clock V-19 Undiluted Liq Smpi BYPASS
~V-22 RC Purge Waste / CAP WASTE 5
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- - ~.
JUL 26 1983 Page 21 of 24
' (cont'd)
Liquid Sample Panel (cont'd)
. / DV-1 Diluted Liquid Sample BYPASS
/ V-11 Expansion Vessel Outlet SHUT
/l DV-2 Diluted Ga,s Smp1 9 o' clock V-10 Expansion Vessel Vacuum SHUT V-13 Dil Gas Smp1 Vac SHUT Y-14 Argon Purge to Dil Gas Smp1 SHUT V-15 Gas Smp1 to GC SHUT V-12 Argon to Eductor SHUT
(
Liquid Sample Panel (Demhn Sect)
I DMV-1.1 CVCS Demin Inlet Iso SHUT I DMV-1.2 CVCS Demin Outlet Iso SHUT l DMV-1.3 (Spare)
SHUT l DMV-3 DI Water Flush SHUT l-DMV-2.1 CVCS Demin Inlet Smpi SHUT l DMV-2.2 CVCS Demin Outlet Smpl-SHUT l DMV-2.3 (Spare)
SHUT e
6
EP-RET-3C JUL 26 1983 o
Page 22 of 24
, (cont'd)
.CASP Control Panel AV-1/SV-1.2
Smpi Pos #1 Inlet /Outl et CLOSE SV-2.1/SV-2.2 Smpi Pos #2 Inlet / Outlet CLOSE SV-3.1/SV-3.2 Smp1 Pos #3 Inlet /Outl et CLOSE SV-4.1/SV-4.2 Smpi Pos #4 Inlet /0utlet CLOSE SV-5 Smp1 Bypass CLOSE SV-10 Nitrogen to Eductor CLOSE AV-2 Return to Containment CLOSE S,Y-6 Eductor Suction Iso CLOSE (At Sample Acquisition Panel) l AS110A Cont Air Smpi A Iso CLOSE l
ASfl0B Cont Air Smp1 B Iso CLOSE e
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A i
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EP-RET-3C JUL 26 1983 Page 23 of 24
' (cont'd)
Chemical Analytical Panel V-2 IC Smpi Outle't OPEN V-5 IC Loop Select SHUT V-6 02 Loop Select 02 - Cal V-7 02 Analyzer Select YSI Y-8 02 Loop Outlet OPEN f Y-9 02 Anal Cal Supply SHUT V-10 Inst Air Supply OPEN V-11
' DI Water Supply OPEN V-12 Nitrogen Supply OPEN V-14 Argon Supply to GC OPEN
[ V-15 Cal-3 Supply OPEN
(
V-17 02 Cal Tk Recirc SHUT
/ Y-18
~0 Cal. Tk Drain' SHUT 2
' Y-19 Cal-3 Drain SHUT V-20 pH Cal Tk 2 Drain SHUT V-13 IC Inject Port SHUT V-16 pH Cal Tk 2 Supply SiluT V-25 pH Cal Tk 1 Drain SHUT V-27 pH Cal Tk 1 N2 Supply VENT l
V-28 pH Cal Tk 2 N2 Supply
- VENT Y-29 Cal-3 N2 Supply VENT l
l V-30 pH Cal Tk Select CAL-1 l
Y-26 pH Cal Tk 1 Supply SHUT V-24 02 Cal.Tk Fill SHUT m ew -
-n
EP-RET-3C JUL 26 1983 Page 24 of 24
(
I.M.b.C.
CONTROL PANEL HS-3 Dilution Water Bite Valve OFF HS-4 Air / Water Flush Valve OFF NS-5 Pressurized Reactor Cool to I.M.C.C.
OFF HS-6 Reactor Cool. Bite Valv,e OFF HS-7 Mixing Chamber Flush / Vent Valve OFF HS-8 Undil. RX. Coo'1. Smp1.' Outlet Yalve OFF HS-9 Undil. RX. Cool. Smpl/ Divert Valve OFF HS-10 Mixing Chamber Outlet Valve 0FF HS-11 Dil. RX. Cool. Smp1. Outlet Valve OFF HS-12 Depressurized RX. Cool. *to.I.M.C.C.
OFF HS-13 Degassifier Outlet / Flush Valve OFF
{
HS-14 Dil. Wtr. Outlet Valve OFF HS-15 Kir Flu,sh to Mixing Chamber 0FF HS-16 Gas Marinelli Bypass Valve OFF Main Power Switch' ON O
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i
.,'i WISCONSIEl PUBLfC SERVICE CORPORAT10N I N00 EP-RET-3E Xewaunee Nuclear Power Plant
' 1 Post Accifen'tOperatio'n or HigII' l TITLE: Rad Sample Room Inline Multiport-l' Count Cave
~
EMERGE!CY PLAN IMPLEMENTING PROCEDURE l
l 1 of 20 e
l DATE:
JUL 2 6 1983 I.PAGE Il.
[JgM
- tEVIEWED BY
,,_ _ M,7 x,-
APPROVED BY tot. f W m !O,, _
l 1.0 PURPOSE, This procedure is to detail the requirements, considerations and operation of the Inline Multiported Count cave (I.M.C.C.) during a post LOCA condition.
2.0 APPLICABILITY' i
4 This is to detail the procedures to be utilized for obtaining:
- a.
- Inline Diluted Reactor Coolant (Sec 5.1) b.
Inline Undiluted Reactor Coolant (Sec 5.2) c.
Inline Hydrogen and Gaseous Activity (Batch) (Sec 5.3.)
(
3.0 PRECAUTIONS 3.1 Process an Emergency Radiation Work Pennit. (See EP-AD-ll) 3.2 Contact Health Physics Department for:
j a.
Proper personnel dosimetery l
b.
Proper radiation detection i nstrumentation c.
Personnel for continous HP coverage during sa.npling d.
Remote area monitor readings in area of H.R.S.R.
3.3 Utilize onsite communication with the Radiological Protection Director, as necessary, during sampling.
4.0 REFERENCES
None e
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WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident Operation of High
,Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiported l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l-l C
l DATE:
l PAGE 2 of 20 l
JUL 2 6 1993 1
5.0 PROCEDURE 5.1.
Inline Diluted Reactor Coolant 5.1.1 Proceed to H.R.S.R. per HP/RPD recommendations.
5.1.2 At the C.A.S.P. control panel, check ventilation on in " NORMAL" position and high vacuum lights indicate " NORMAL" for the L.S.P.
and C. A.P.
5.1.3 Check radiation levels in H.R.S.R. and in maintenance area behind panels, if access is required.
5.1. 4 Remove the shielding plug from the Diluted Reactor Coolant port of the I.M.C.C.
5.1. 5 Remove the portable E.G.G. Ortec detector from the Dewar ar.d place properly in the Diluted Reactor Coolant port of the I.M.C.C.
5.1. 6 Request the RPD to have the detector operationally checked from the R. A.F. using the ND 6700.
NOTE: The detector must be functioning properly prior to continuing with the next steps of this procedure.
5.1. 7 ChecR valve lineup per Attachment 1.
~
5.1. 8 For RCHL sample have control room, operator OPEN RC-422 and RC-423.
5.1.9 At the Sample Acquistion 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) c.
For' All Samples:
Turn RC-437-1 (437-2) to 'D.D.T.
l 5.1.10 At the Li, quid Sample Panel: OPEN V-3 OPEN Y-1.2 for RCHL (V-1.1 for RHR)
Regulate Reactor Coolant (RHR) flow usin'g RC-V-REL-1 until flow indicator RC-FI-l indicates 35 to 40 inches of water. Maintain l
this purge for a minimum of 5 minutes.
NOTE 1: A d/p of 35 to 40 inches of water on RC-FI-1 is equal to approximately 1/2 gpm flow rate.
NOTE 2: Continue with Step 5.1.11 during tl11s purge.
I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident. Operation of High
.Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiportec l
Count Cave
('-
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l 1: DATE:
JUL 26 1983 l
PAGE 3 of 20 1
i 5.1.11 At the I.M.C.C. control panel, place HS-6 ON HS-15 ON purge for a minimum of 2 minutes:
5.1.12 At the I.M.C.C. control panel, place HS-15 0FF HS-7 ON HS-10 ON HS-11 ON purge for a minimum of 2 minutes.
5.1.13 At the I.M.C.C. control panel, place HS-7 OFF HS-10 0FF HS-11 0FF C
HS-14 ON 5.1.14 Upon completion of the 5 minute flush from step 5.1.10, at the LSP:
SHUT V-3 OPEN V-8.2 OPEN V-8.1 OPEN V-2 5.1.15 Regulate Reactor Coolant (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 2 minutes.
NOTE: A d[p of 18 to 22 inches of wate'r on RC-FI-2 represents approximately 200 cc/ min. flow rate.
5.1.16 Upon comp 1.etion of purge:
SHUT V-8.2 5.1.17 At the I.M.C.C. contr.o1 panel, place HS-5 ON HS-8 ON HS-3 '
ON HS-15 ON continue this purge for 1 minute.
>c
i l
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident Operation of High
~
~
Kewaunee Nuclear
- Power Plant l JITLE: Rad Sample Room Inline Multiportea l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE I
I
(.
lPAGE 4 of 20 DATE:
JUL 26 1983 1
i 5.1.18 At the I.M.C.C. control panel, place HS-3 0FF HS-15 0FF 4
wait for 1 minute.
i 5.1.19 At the I.M.C.C. control panel, place HS-6 0FF HS-3 ON HS-15 ON l
HS-8 0FF HS-5 0FF wait for 3 minutes.
i NOTE: Continue with step 5.1.20 while waiting for sample dilution mixing.
5.1.20 At the L.S.P. commence D.I. wate'r flush:
4 OPEN V-8.2 SHUT V-1.2 (V-l '.1 for RHR) i OPEN Y-4 THROTTLE RC-VREL-2 as necessary.
NOTE: Maintain this flush for a minimum of 5 minutes while continuing on with step 5.1.21.
5.1.21 After completing the 3 minute wait from step 5.3.19, continue.
3
)
At the I.M.C.C. control panel place l
HS-15 0FF HS-3 0FF HS-10 ON l
HS-7 ON l
the diluted primary sample is now in the sample chamber. Request the RPD to have the ND 6700 operated as per RC-C-10 to count the j
sample.
l 5.1.22 After completing the 5 minute wait from step 5.1.20. -Have control room operator shut RC-422 and RC-423 (not required for RHR sample).
t sulism w e 4
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EP-RET-3E Post Accident Operation o I ~NO.
WISCONSIN PUBLIC SERVICf CORPORATION l
l TITLE: Count Cave Kewaunee Nuclear Power Plarit l
l S of 20
(-
i PAM l' TE:
JUL 26 1983 I
EMERGENCY PLAN IMPLEMENTING PROCEDURE 1 DA l-At the Sample Acquistion Panel 5.1.23 For RCHL Sample:
~
OPEN FPC-51 FPC-51-14 OPEN For RHR Sample:
RHR 81-A (81-B)
SHUT OPEN FPC-51 FPC-51-41 OPEN At the Liquid Sample Panel:
5.1.24 SHUT Y-4 SHUT V-2 SHUT 8.1
~
SHUT 8.2 V-3 Y-1.2 (V-1.1 for RHR)
OPEN te of 75 to 40 OPEN -
(
Using V-REL-1, regulate SFP flush wate h for a minimum I 1 is equal of S minutes.
A d/p of 35 to 40 inches of water on RC-F -
to' approximately 1/2 gpm flow rate.
50TE 1:
~
5.1.25 At the completion of flushing:
V-1.2 (Y-1.1 for RHR)
SHUT SHUT V-3 At the Sample Acquistion Panel:
5.1.26 For RCHL Sat 6ples:
SHUT RC-423-1 FPC-51-14 SHUT SHUT FPC-51 SHUT CC-314 For RHR Ssmple:
RHR 81-A (81-B)
SHUT FPC-51 -41 SHUT SHUT - FPC-51 CC-316 SHUT
~
For All Sampies:
Turn RC-437-1 (or 437-2) to VCT' position.
r
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WISCONSIN PUBLIC SERVICE CORPORATION I NO.
EP-RET-3E "PiUit A ciVe'n't075t'fisilf hT li '
- c ~
g I
pe Xewaunee Nuclear Poder Plant i TITLE: Rad Sample Room Inline Multiport:
l' Count Cave
~ ~ ~ - -
EMERGENCY PLAN IMPLEHENTING PROCEDURE 1
i I
l OATE:
M 26 J983 l PAGE 6 of 20 I
l 5.1.27, Verify with the RPD that all counting of the sa:nple is completed.
5.1.28 At the LSP:
OPEN V-4 OPEN V2 OPEN V-8.1 At the I.M.C.C. control panel, place:
4 s
HS-11 04 HS-4 ON HS-6 ON HS-8 ON HS-5 ON continue this. flush for 5 minutes.
5.1.29 At the 'I.M.C.C. control panel, place:
HS-4 0FF
(
HS-7 0FF HS-15 ON HS-3 ON HS-5 0FF HS-8 0FF continue this flush for 1 minute.,
5.1.30 At the I.M.C.C. control panel, place
.HS-3 0FF HS-15 0FF HS-7 04 continue this flush for 1 minute.
l l
5.1.31 At the I.M.C.C. control panel, place HS-7 0FF
, HS-10 (FF HS-11 0FF HS-14 : 0FF 5.1.32 At the LSP:
l SHUT Y-4 SHUT
'V-2
' SHUT V-9.1 g
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I
\\
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident Operation of Hign
~
.Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiportec l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l
(.
l DATE:
JLll 2 6 1983 l
PAGE 7 of 20 5.2 Inline Undiluted Reactor Coolant 5.2.1 Proceed to the H.R.S.'R. per HP/RPD recommendations.
5.2.2 Verify ventilation is in " NORMAL" position and high vacuum lights indicate " NORMAL" for the C. A.P. and L.S.P.
5.2.3' Check radiation level.s in H.R.S.R. and in maintenance area behind panels, if access is necessary.
5.2.4 Verify the following lab equipment available and operational:
a.
D.I. water flush hoses connected to L.S.P. with supply valve open.
b.
Verify valve lineup per Attachment 1.
c.
Check air pressure in lab.
d.
Verify ND 6700 analyzer available for coanting.
C 5.2.5 Remo've the shielding plug from the undiluted reactor coolant port of the I.M.C.C.
5.2.6 Remove the portable E.G.G. Ortec detector from the Dewar and place properly in the undiluted reactor coolant port of the I.M.C.C.
5.2.7 Request the RPD to have the detector operationally checked from the R. A.F. using the ND 6700.
NOTE: The detector must be functioning properly prior to con-tinuing with this procedure.
5.2.8 For RCHL sample have control room operator open RC-422 and RC-423.
5.2.9 At the Sample Acquistion Panel:
a.
For RCHL sample: OPEN CC-314-OPEN RC-423-1 b.
For RHR sample:
OPEN CC-3;5 i
OPEN RHR-81-A (81-B) c.
For All Samples: TURN RC-437-1 (437-2) to D.D..T.
I I
WISCONSIN PUBLIC SERVICE CORPORATION 1 NO.
~
1 Post Accident operation of High
'Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiported l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l
I 8 of 20 lPAGE
- DATE:
JUL 2S 1983 5.2.10 At the Liquid Sample Panel: OPEN V-3 OPEN V-1.2 for RCHL (V-1.1 for RHR)
Regulate Reactor Coolant (RHR) flow rate using RC-VREL-1, until flow indicator RC-FI-1 indicates 35 to 40 inches of water. Main-tain this purge for a minimum of,5 minutes.
NOTE 1: A d/p of 35 to 40 inches of water on RC-FI-1 is equal to approximately 1/2 gpm flow rate.
j 5.2.11 Upon the completion of the 5 minute flush, at the L.S.P.:
SHUT V-3 I
OPEN V-8.2 i
OPEN Y-8.1 OPEN V-2
^
Regulate Reactor Coolant flow (RHR) using RC-VREL-2, until flow indicator RC-FI-2 indicates'18 to 22 inches of water. Mai n-tain this purge for a minimum of 2 minutes.
1 NOTE: A d/p of.18 to 22 inches of water on RC-FI-2 represents approximately 200 cc/ min. flow rate.
5.2.12 Upon the completion of the 2 minute purge, at the I.M.C.C. control panel place:
HS-5 ON
- l
.HS-8. ON HS-9 ON l
5.2.13 At the L.S.P. SHUT V-8.2.
NOTE:
Infonn the RPD that reactor coolant flow is established.
Continue flow until informed by RPD that the system is to be shutdown - then continue with step 5.2.14.
l 5.2.14 Upon completion of analyzer at the L.S.P.:
SHUT V-1.2 (V'-1.1 to RHR)
OPEN V-4 Allow a 3 minute flushing of the undiluted reactor coolant sample port.
5.2.15 Upon completion of the 3 minute flush at the I.M.C.C. control panel place:
HS-5 0FF HS-9 0FF HS-8 0FF
(
At the LSP open V-8.2 and throttle RC-iREL-2 as necessary to maintain
\\
a 18-22 inches of water flow rate on RC-FI-2. Maintain this flow rate for 5 minutes.
NOTE: A d/p of 18 to 22 inches of water on RC-FI-2~r~epresents approximately 200 cc/ min. flow rate.
-.-~ -
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I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
EP-RET-3E Post Accident Operation of High Kewaunee Nuclear, Power Plant l TITLE: Rad Sample Room Inline Multiportec l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l
(
l DATE:
.JUL 2 6 1983 lPAGE 9 of 20 5.2.16 After the 5 minute flush, have the control room operator shut RC-422 and RC-423 (not required for RHR sample) 5.2.17 At ths Sample Acquistion Panel:
For RCHL Sample:
OPEN FPC-51 OPEN FPC-51-14 For RHR Sampie:
SHUT'RHR 81-A'(81-B)
OPEN FPC-51 OPEN FPC-51-41 5.2.18 At the Liq ~uid Sample Panel:
SHUT Y-4 SHUT V-2 SHUT V-8.1 OPEN V 3 OPEN V-1.2 (V-1.1 for RHR)~
C Using RC-VREL-1, regulate SFP flush water flow rate of 35 to 40 inches of water on RC-FI-1. Maintain this flush for a minimum of 5 minutes.
NOTE 1: A d/p of 35 tc 40 inches of water on RC-FI-l is equal to approximately 1/2 gpm flow rate.
5.2.19 At the completion of flushing:
SHUT V-1.2 SHUT V-3 5.2.20 'At the Sample Acquistion Pan'el:
For RCHL Samples: SHUT RC-423-1 SHUT FPC-51-14 l
SHUT FPC-51 SHUT CC-314 For RHR Samples:
SHUT RHR-81-A (81-B)
SHUT FPC-51-41 l
SHUT FPC-51 SHUT CC-316 l
For All Samples:
TURN RC-437-1 (or 437-2) to the VCT position.
i o
4 l
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Fost Accident Operation of High
,Kewaunee Nuclear Power Plant 1 TITLE: Rad Sample Room Inline Multiportec I
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l-1 I
l DATE: JtJL 26 1983 I
PAGE 10 of 20 I
I 5.3 Inline Hydrogen Gaseous Activity (Batch)
. 5.3.1 Proceed to HRSR per HP/RPO recommendations.
5.3.2 Verify ventilation on in " normal" position and high vacuum lights indicate "nonnal" 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".
e.
Check the program in GC mini-computer and latest data in the -HRSS Cal Log.
f.
Check Argon and Air Pressure in lab and at the bottles for adequate supply.
(
9 Verify ND-6700 analyzer available for counting.
5.3'5 Remove the shielding plug from the gaseous activity port of the I.M.C.C.
5.3.6 Remove the portable E.G.G. Ortec detector from the Dewar and place properly in the gaseous activity port of the I.M.C.C.
5.3.7 Request the RPD to have the detector operationally checked from the R.A.F. using the ND 6700.
NOTE: The detector must be functioning properly prior to continuing with this procedure.
l 5.3.8 Dry the expansion vessel: Turn V-ll to " Argon" l
OPEN V-9 l
. OPEN V-8.2 l
OPEN V-10 5.3.9 Adjust RC-VREL-2 as necessary to obtain 20 psi on RC-G-3 for 1 minute. ' Observe flow indication on RC-FI-2 al so.
l 5.3.10 Upon completion of Drying Expansion Vess'el:
Turn V-ll to 9 o' clock position SHUT V-9 SHUT V-8.2 m emn r
l WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident. Operation of High
.Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiported l
Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l f-l.DATE: JUL 2 6 1983 l
PAGE 11 of 20
(
I l
5.3.11 Have Control Room Operator open RC-422 and RC-423 (not required for sample from RHR).
5.3.12 At the Sample Acquisition Panel:
For RCHL Sample: OPEN CC-314 OPEN RC-423-1 i
For RHR Sample: OPEN CC-316 OPEN RHR 81-A (81-B)
For all samples: Turn RC-437-1 (or 437-2) to DDT 5.3.13 At the Liquid Sample Panel: OPEN V-3 OPEN V-1.2 (V-1.1 for RHR) 5.3.14 Regulate Reactor Coolant (RHR) flow using RC-VREL-1 until flow indicator RC-FI-1 indicates between 35 to 40 inches of water.
Maintain this purge for a minimum of 5 minutes.
(
NOTI: A d/p of 35 to 40 inches of water on R'C-FI-1 is equal to approximately 1/2 gpm flow rate.
. 5.3.15 Evacuate the Gas Expansion Vessel, sample bottle and tubing:
~
OPEN V-13 OPEN V-15 TURN DV-2 to 6 o' clock position OPEN V-12 5.3.16 When vacuum on RC-G-2.2 reads 22 inches vacuum or greater, turn DV-2 to 3 o' clock position.
5.3.17 When' vacuum on RC-G-2.1-reads 22' inches of. vacuum or greater:
SHUT V-15 SHUT V-13 SHUT V-10 TURN V-11 to Closed SHUT Y-12 NOTE: Observe vacuum reading on both gauges holding steady.
5.3.18 Upon completion of purge (from step 5.3.14):
(
SHUT 9-3 L
OPEN V-8.2 OPEN V-8.1 0 PEN Y-2
,,--%-r.-
I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Post Accident Operation of High i
.Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiporter.
l Count Cave EMERGENCY PLAN IMPLEMENTING PROCEDURE 1-1
- f-(
JUL 2 6 1983 PAGE 12 of 20 l DATE:
5.3.19 Regulate Reactor Coolant (RHR) flow using RC-VREL-2 until flow hdicator 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.
5.3.20 Upon completion of sample purge:
SHUT Y-8.2 SHUT V-8.1 SHUT V-1.2 (V-1.1 for RHR)
OPEN Y-9 OPEN V-16 (for 1 full minute) 5.3.21 Upon completion of gas stripping, commence LSP flush:
SHUT V-16 SHUT Y 9 OPEN V-8.2 OPEN V-8.1
(
OPEN V-4 TURN V-ll to 9 o' clock position 5.3.22 At the CMP, operate the GC mini-computer to draw a vacuum on all 4 sample loops.
5.3.23 At the LSP open V-15 and allow the gas sample to transfer to the GC.
5.3.24 Operate the GC unit to obtain 4 samples for hydrogen determination.
By selective attenuation, starting with a high value, determine the hydrogen concentration.
NOTE: At this time inform the RPD that the gaseous activity sample is in the I.M.C.C. and request that he have it analyzed using the ND 6700, as per RC-C-10.
5.3.25 Have Control Room Operator shut RC-422 and RC-423 (not required for RHR sample).
5.3.26 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 y
l WISCONSIN PUBLIC SERVICE CORPORATION I NO.
l Post Accident Operation of High
.Kewaunee Nuclear Power Plant i TITLE: Rad Sample Room Inline Multiportec.
I Count. Cave f-EMERGENCY PLAN IMPLEMENTING PROCEDURE I
I l DATE:
JUL E6 1983 l PAGE 13 of 20
(
l I
5.3.27 bt the Liquid Sample Panel: SHUT V 4 SHUT V-2 SHUT V-8.1
~
SHUT Y-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 witer on RC-FI-1. Maintain this flush for a minimum of 5 minutes.
NOTE 1: A d/p of 35 to 40 inches of water on RC-FI-l is equal to approximately 1/2 gpm flow rate.
5.3.28 At the cmpletion of flushing: SHUT V-1.2 (V-1.1 for RHR)
SHUT V-3 5.3.29 At the, Sample Acquisition Panel: '
Foi RCHL Samples: 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.
5.3.30 At the LSP flush the expansion vessa'..
SHUT V-15 OPEN V-8.2 OPEN V-9 TURN V-11 to "DI Water" position Allow system to flush for 2 minutes.
5.3.31 Upon cmpletion of flush:
Turn V-11 to " Argon" position and blow expansion vessel dry 5.3.32 Upon completion of drying expansion vessel:
TURN V-11 to Close
(
SHUT V-9 A.
SHUT V-8.2 NOTE: Prior to continuing v.ith the next step, verff9' with the RPD that all counting of the sample has been completed.
l J
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
' ' ' Fos t fc ciiTe'n't" Ope ~ra'tTon~df lfi'gli
- l
, Kewaunee Nuclear Power Plant l TITLE: Rad Sample Room Inline Multiporte l'
Count Cave
~~
2 r'
EMERGENCY PLAN IMPLEMENTING PROCEDURE i
l
(-
l DATE:
l PAGE 14 of 20 JUL 2 6 1983 l
l 5.3.33 Remove radioactive gases fron gas system:
OPEN Y-10 OPEN Y-13 OPEN V-15 TURN Y-il to 9 o' clock position
'i OPEN Y-12 Evacuate system for 1 full minute.
5.3.34 Upon evacuation of gas system:
l SHUT Y-12 TURN V-ll to " closed" pcsition SHUT V-15 SHUT V-13 SHUT V-10 t
e h
9 9
4 i
e 1
5 i
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=mm ee-.
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EP-RET-3E JUL 2 6 1983 Page 15 of 20 VALVE LINEUP SfiEET Sample Acquisition 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 51-14 RCHL Smpi Flush CLOSE RC-423-1 RCHL Smp1 CLOSE M/B Demin Inlet Flush CLOSE FPC-51-31 LD-71 M/B Demin Inlet Iso CLOSE LD-75 M/B Demin Inlet Smpl CLOSE M/B Demin Outlet Flush CLOSE FPC-51-21 C
LD-81 M/B Demin Outlet Iso CLOSE LD',85 M/B Demin Outlet Smp1 CLOSE
~
P'r Stm Sp Smpi Flush CLOSE FPC-51-12 z
RC-403-1 Przr Stm Sp Smp1 CLOSE FPC-51-13 Pzr Liq Sp Smpi Flush CLOSE RC-413-1 Pzr Liq Sp Smp1 CLOSE CC-314 RX, Cool HRS Hx.CC Flow CLOSE CC-316 RHR HRS Hx CC Flow CLOSE
~
l MGR-545 VCT Gas Sp Smp1 Iso A CLOSE MGR-545-1 VCT Gas SP Smpl Iso B CLOSE Smp1 Purge Divert A TO VCT RC-437-1 RC-437-2 Smp1 Purge Divert B TO VCT l
o EP-RET-3E JUL 2 6 1983 Page 16 of 20
. (cont'd)
. Liquid Sample Panel V-17 Open Grab Sample SHUT V '6.1 Rem Sapl Bomb Inlet SHUT V-6.2 Rem Smp1 Bomb Outlet SHUT Y-5.1 Rem Smpl Bomb Inlet Iso SHUT V-5.2 Rem Smpl Bonb Outlet Iso SHUT V-REL-1 RC Purge Throttle THROTTLED V-3 RC Purge Stop SHUT V-REL-2 RC Purge to Waste Th THROTTLED
-7 Smpl Bomb Bypass SHUT V-2 RC Purge to Waste Stop SHUT.
V-1.1 RHR Smpi Iso SHUT
.RCHL/Pzr Smpl Iso SHUT V-1.2 V-1.3 (Spare)
SHUT V-1.4 (Spare)
SHUT Vi.5 VCT Gas Sp Smpl Iso SHUT V-4 DI Water Flush Iso SHUT V-8.1 Press Smpi Bomb Inlet SHUT V-8.2 Press Sapl Bo.nb Outlet SHUT V-9 Expansion Vessel Inlet SHUT V-16 Argon Gas Strip Purge SHUT V-18 RC Backflush 5 o' clock V-19 Undiluted Liq Smpl BYPASS V-22 RC Purge Waste / CAP WASTE l
y y
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=
EP-R ET-3E JUL 2 6 1983 Page 17 of 20 Attachme[it 1 (cont'd) g-
\\.
Liquid Sample Panel (cont'd)
DV-1 Diluted Liquid Sample BYPASS V-11 Expansion Vessel Outlet SHUT DV-2 Diluted Gas Smpi
~
9 o' clock V-10 Expansion Yessel Vacuum SHUT V-13 Dil Gas Sopi Vac SHUT V-14 Argaq Nrge to Dil Gas Smp1 SHUT Y-15 Gas Smp1 to GC SHUT V-12 Arpn to Eductor SHUT
(
Liquid Samp1_e, Panel (Demin Sect)
DMV-1.1 CVCS Demin Inlet Iso SHUT DMV-1.2 CVCS Demin Dutlet Iso SHUT DMV-1.3 (Spare)
SHUT DMV-3 DI Water Flush SHUT DMV-2.1 CVCS Demin Inlet Smpi SHUT DMV-2.2 CVCS Demin Outlet Smpl, SHUT DMV-2.3 (Spare)
SHUT I
r-e v
+
rm -
c
~m
EP-RET-3E JUL 26 1983 Page 18 of 20
. (cont'd)
CASP Control Panel AY-1/SV-1.2 Smpi Pos #1 Inlet /Out1 et CLOSE SV-2.1/SV-2.2 Smpi Pos #2 Inlet / Outlet CLOSE SV-3.1/SV-3.2 Sapi Pos #3 Inlet /0 >tlet CLOSE SV-4.1/SV-4.2 Smp1 Pos #4 Inlet / Outlet CLOSE SV-5 Smp1 Bypass CLOSE SV-10 Nitroiyn to Eituctor CLOSE CLOSE
- AV-2 Return to Contain1ent SV-6 Eductor Suction Iso CLOSE
(
( At Sample Acqui si tio a canel)
AS110A
' Cont Air Smp1 A Iso CLOSE AS1103 Cont Air Smpl~ B Iso CLOSE O
e S
9 9
i O
ew.
b a
9 n.
EP-RET-3E JUL '16 1983 Page 19 of 20 C' (cont'd)
' Chemical Analytical Panel V-2 IC Smpi Outlet OPEN V-5 IC Loop Select SHUT Y-6 02 Loop Select 02 - Cal V-7 02 Analyzer Select YSI V-8 02 Loop Outlet OPEN V-9 02 Anal Cal Supply SHUT OPEN V-10 inst Air Supply V-11 DI Water Supply OPEN OPEN l
V-12 Nitrogen Supply l
Y-14 Argon Supply to GC OPEN-
! (
, V-15 Cal-3 Supply OPEN V-17 02 Cal Tk Recirc SHUT V-18 02 Cal Tk Drain SHUT V-19 Cal-3 Drain SHUT V-20 pH Cal Tk 2 Drain SHUT V-13 IC Inject Port SHUT V-1.6 pH Cal Tk 2 Supply SHUT V-25 pH Cal Tk 1 Drain SHUT V-27 pH Cal Tk 1 N2 Supply VENT Y-28 pH Cal Tk 2 N2 Supply VENT Y-29 Cal-3 N2 Supply VENT Y-30 pH Cal Tk Select CAL-1 V-26 pH Cal Tk 1 Supply SHUT V-24 02 Cal Tk Fill SHUT O
e
EP-RET-3E JUL 26 1983 Page 20 of 20 I.M.C.C.
CONTROL PANEL HS-3 Dilution Wate'r Bite Valve OFF HS-4 Air / Water Flush Valve OFF HS-5 Pressurized Reactor Cool to I.M.C.C.
OFF HS-6 Reactor Cool. Bite Valve OFF HS-7 Mixing Chamber Flush / Vent Valve 0FF HS-8 Undil. RX. Cool. Smp1. Outlet Valve OFF HS-9 Undil. RX. Cool. Smpl/ Divert Val ve 0FF HS-10 Mixing Chamber Outlet Valve 0FF HS-11 Dil. RX. Cool. Smpl. Outiet Valve OFF HS-12 Depressurized Rx. Cool.' to. I.M.C.C.
OFF HS-13 Degassifier Outlet / Flush Valve OFF
(
HS.14 Dil. Wtr. Outlet Valve OFF HS-15
' Air Flush to Mixing Chamber OFF Main Power Switch ON e
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l
? WISCONSIN PUBLIC SERVIC. CORPORATION l
NO.
EP-RET-5 REY. B l
l TITLE :
Plume Projection
, Kewaunee Nuclear Power Plant l
EMERGENCY PLAN IMPLEMENTING PROCEUDRE l'
l
(
JUL 26 1983 lPAGE 1 of 4 DATE:
iEVIEWED BY PA/Filudd a.
l APPROVED BY
/
N i
1.0 APPLICABILITY This procedure is applicable for all abnormal releases of airborne radio-activi ty.
2.0 PRECAUTIONS 2.1 This program utilizes a straight line Gaussian mode'. to determine diffusion coefficients. The model does not take into account building wake, lake ef fects, or inland wind shifts.
2.2 Isotopic input data is limited to the predominent fission gases and iodine 131. The program can be used to calculate X/Q's for subsequent hand calculation of ground level concentrations.
Dose projections caa then be made using EP-RET-6, 2.3 The dose data is only valid for releases from the Auxiliary Building C
stack in Zone SV mode. The X/0 values can be used for the Shield Bui.lding Vent.
2.4 The procedure requires use of the Green Bay IBM Computer.
If terminal access is n'ot available, see EP-ENV-3C.
3.0 REFERENCES
3.1 NRC Regulatory Guide 1.145, August 1979.
3.2 NRC Regulatory Guide 1.23, Rev.1 (Proposed), September 1980.
4.0 APL. USER INFORMATION 4.1 The minus sign (-) is the upper case 2.
4.2 The plus sign (+) is not required when using scientific notation.
4.3 # means depress the enter key.
4.4 The closed bracket sign ) must be entered using the red ).
4.5 To clear the screen hold down the ALT key and 'epress the clear key.
d 4.6 If the terminal locks up because of an entry error, ty.pe in DOSE #
(see 5.9).
This will restart the program.
4.7 The letter Y shall be used for all yes answers and N for all no answers.
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,5CONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-RET-5 l
, Kewaunee Nuclear Power Plant 1
TITLE: Plume Projection i
EMERGENCY PLAN IMPLEMENTING PROCEUDRE I
l l
PAGE 2 of 4
- DATE:
.g ggg3 h
r 5.0 INSTRUCTIONS 5.1 Complete Plume Projection Data ' Sheet (Fonn RET-5.1). All data should be available in the TSC.
5.2 Sign on with 5.3 Turn on the APL Keyboard by holdin.g down the ALT key and then depressing the APL on/off key.
5.4 RUN 1 APL #
5.5 Clear the screen.
5.6. KNPP #
5.7 ORILL f i
5.8
) LOAD IS000SE #
5.9 DOSE # (This starts the program).
5.10 Answer the questions one at a time.as they appear using the data from Form RET-5.
6.0.0055 PROJECTION FROM STACK ANALYTICAL RESULTS 6.1 Enter the delta.T (o'r sigma theta) and wind speed.
6.2 Enter the expected release duration.
6.3 Enter the isotopic concentrations.
Separa.te each concentration by a space.
NOTE: Plus signs are not required but minus signs (upper case 2) are.)
6.4 The program will ec'ho the input data and ask if the data i's correct.
6.5 The program then computes whole body dose, iodine concentration, child thyroid dose, impact time of the plume, and X/Q at mile intervals along the plume centerline out to ten miles. Whole body dose and iodine con-centration is also computed along isodose lines based on each factor of i
10 reduction in X/Q.
1 7.0 DOSE PROJECTION FROM SPING 4 DATA
' 7.1 Enter meteorological da,ta and expdcted release
- duration.
Od 7.2.When asked for stack sample analysis results answer No or N.
7.3 The program will ask if you have SPING readings and which exhaust SV fans l
are running.
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,e f WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-RET-5 l
=
.Kewaunee Nuclear Power Plant l
TITLE:
Plume Projection l
l' l
C EMERGENCY PLAN IMPLEMENTING PROCEUDRE l DATE:
l PAGE 3 of 4 1
JUL 26 1983 l 7.4 The iodine average requested is the last 10 minute average from the SPING4. '-
7.5 The noble gas average requested is the last 10 minute average from the SPING4. If the reading is from the midrange or high range channel, convert from gamma Bq Mev/cc to uCi/cc prior to entering the value.
NOTE: The conversion factors are posted on the SPING consoles.
7.6 The program calculates the noble gas isotopic mixture from the predicted core inventory as a function of time after trip. The results are used to make the plume projection.
8.0 MAIN STEAM LINE RELEASES 8.1 Enter the meteorological data.
8.2 Enter the release duration. This duration is the time the steam dump valves were (or are expected to be) open.
8.3 Answer No (!1) when asked for stack sample results.
'.4 Answer No (N) when asked for SPING readings.
8 8.5 The program will request the reading in R/hr from the main steam line direct radiation monitor.
8.6 The program requests safety injection flow rate and assumes this value
' to be the rate of water loss through a primary to secondary tube rupture.
If the charging system is maintaining pressurizer levels, use the charging flow rate.
8.7 The program then calculates the dose projection.
9.0 RESNLTSANALYSIS 9.1 Make a hard' copy of the Dese Projection and transmit to the Radiological Protection Director.
9.2 10FF HOLD #
9.3 OUTPUT * #
(the is an upper case P).
9.4 LOAD DRILL #
9.5 RUN HCPY #
9.6 PRINT ORILL NOL,# (The hard copy prints out at this tinie on the printer assigned to hard copy.)
9.7 0FF f
__-____-__--__-___---____-___________a
's '. '. 't EP-RET-5 JUL 26 1983
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Page 4 of 4 FORM RET-5 PLUME PROJECTION DATA SHEET Re.ctor Trip Date Time MET Conditions:
+
T
- F Wind Speed mph Sigma Theta Wind Direction Expected Release Duration hrs Operating Fans Aux A Aux B Both SVA SYB Both None (circle one) i Stack Analytical Results:
Isotope 1
Conc.(uCi/cc) l I
i i
IKr 85 I
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I I
lKr 85m I
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I I
f IKr 87 1
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.I lKr 88 l
1
(
IXe 133 I
I I
I IXe.133m l
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I I
IXe 135 I
1 I
i i
IXe 135m i
l I
I i
11-131 l
l Flow Rates Aux A Aux B Both SVA SVB Both
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l cc/sec 2.04E+7 1.96E+7 3.36E+7 4.36E+6 4.00E+6 8.61E+6 SPING RESULTS Latest 10 min Iodine Average uCi/cc Late'st 10 min Gas Average uCi/cc STEAM RELEASE Main Steam Line Monitor R/hr SI flow rate gpm
{
By DATE TIME e
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4 d WISCONSIN PUBLIC SERVICE, CORPORATION l
NO.
EP-RET-6 REY. 8 r
i Kewaunee Nuclear Power Plant I ' TITLE:
Dose Projection 1
EMERGENCY PLAN IMPLEMENTING PROCEUDRE l
l O7 M 26 %
DATE:
l PAGE 1 of 3 I.
REVIEWED BY M %}t M /
l APPROVED BY
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1.0 APPLICABILITY The dose rates calculated by this procedure can be used u determine action levels of Alert, Site Emergency, and General Emergency.
i'he procedure can also be utilized to predict individual doses from submersion or inhalation of radioactive materials.
2.0 PRECAUTIONS None
3.0 REFERENCES
None 4.0 INSTRUCTIONS O
1 4.1 Call up VSPC with 4.2 Type in RUN ODP and enter.
4.3 Press the PF-1 key.
NOTE: Make sure the' keybo'ard is not in the APL mode.
4.4 Press PF-2 key. The screen is now in the view mode and isotopes are listed by isotope code number (isotopes 1-19).
1 4.5 Type in all the ground level concentrations from the Form;RC-HP-110 or
,1 Fonn AD-TT 2 for a specific ground level point- (e.g.,.ST HWY 42 NW).
4.6 Press PF-3 key. Screen will list isotopes 20-39; repeat step 4. 5.
4.7 Isotope number 40 plus date, time, location, and comments wil.1 appear on the screen.
O O
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o s
4ISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-RET-6 l
Kewaunee Nuclear Power Plant i TITLE: Dose Projection g
EMERGENCY PLAN IMPLEMENTING PROCEUDRE l'
l C
l DATE: JUL 26 1983 l PAGE 2 of 3 I
I 4.9 Type,in the following:
a.
Ground level concentration for isotope number 40, if needed.
I b.
Sample date and time.
.1 c.
Location, ground level point from step 4.5.
d.
Comments, any explanatory or informational notes.
l 4.10 Press PF-5 key. SAVE will appear in the command space and a code should be entered for calling up the above file at a later date.
Type in the code as follows and enter:
(Record the file name.)
,.S-._
_1,,_0 _0 _0 _0,,_S, W
- t i
T I
I I
Compa ss Time from l'
direction, step 2.9b.
V all spaces Use S for Site Boundary H must be filled.
for 'STH 42.
Use a slash in T for Ten Mile.
last 2 spaces if needed.
i 4.11 Press PF-6 key. Type in file code name from step 4.10 and enter.
Note and record job number. (i.e., KJ228R00-000).
4.12 Press PF-7 key. Type in the two digits after the R in the job number and enter.
4.13 The computer will then calculate and print out the results. Make a printout of the information on the screen and transmit data immediately to the Radiclogical Protection Director.
5.0 EMERGENCY CLASS DETERMINATION (RADIOLOGICAL PROTECTION DIRECTOR) 5.1 Compare the results obtained in section 4.13 with Table 1 considering the sample type.
l NOTE: The dction Limits in Table RET-6 are based on State Protective Action Guides for protection of the,public. 'They do not correspond in all cases to the Emergency Classes stated in EP-AD-2.
5.2 Report any recommendations to the Emergency Director.
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2 6 nC3' TABLE RET-6 SAMPLE TYPE LOCATION DATA ANALYSIS ACTION LIMITS I
11 III Gas Ef fluent Aux Stack EP-RET-5, EP-RET-6 Whole Body <1 REM Whole Body 1-5 REM Whole Body >5 REM SPING 4 GRAB (10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> exposure)
Thyroid 25 REM HIVol/ RAP In Plume Gros beta-gamma Whole Body <1 REM Whole Body 1-5 REM Whole Body >5 REM Thyroid' <5 REM Thyroid 5-25 REM Thyroid >25 REM Gamma Scan 3
RC-IIP-46, EP-RET-6 Liquid Effluent R-24 1 1. gamma scan
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GRAB I-131 (uCi/ml)
< 1.2 E-5 1.2 E-5 to 1.2 E-4
>l.2 E-5 Cs-137 (uCi/ml)
< 3.4 E-4 3.4 E-4 to 3.4 E-3
>3.4 E-3 Direct Survey In Plume None
< 2.5mR/hr 2.5 to 12 mR/hr
>l2 mR/hr 1 m. above Ground Deposi tion In Plume at Gross beta-gamma
< 1 E+6 dpm 1 E+6 to 3.5 E+7 dpm
>3. 5 E+7 (Fallout Plate)
Ground Level Gamn:a Scan RC-HP-46 Milk or Watbr At request of 1 1. gamma s an State Radiological I-131 (uCi/ml)
< l.2 E-5 '
1.2 E-5 to 1.2 E-4
, 1.2 E-4 Coordinator Cs-137 (uCi/ml)
< 3.4. E-4 3.4 E-4 to 3.4 E-3
>3.4 E-3 Environmental in Plume Integrated Dose None None 1 REM Total TLD Readout integrated dose i
Action,Limi.s I Transmit data to State Radiologcial Coordinator & Emergency Director. No recommended actions.
i' 11 Recommend sheltering and transfer of livestock to stored feed.
(Preventative Action Level)
III Recommend evacuation and restrict access to area. Reconmend transfer of livestock to stored feed.
(Emergency Action Level) e 9