ML050960083

Revision 3 to EI-7.10, Post Accident Sampling, Radioactive Gaseous Effluent Monitoring.

ML050960083
Person / Time
Site:	Palisades
Issue date:	03/30/2005
From:	Consumers Energy
To:	Mcknight J Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050960083 (11)

Text

Date Entered: Mar 30, 2005

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TO: USNRC/WASHINGTON JMCKNIGHT Copy Number. 145 TRANSMITAL PROCEDURE NUMBER: El-7.10 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.

Action Required Section or Description REMOVE AND DESTROY El-7.10, R/3, ENTIRE PROCEDURE REPLACE WITH El-7.10, R/3, ENTIRE PROCEDURE EDITORIAL SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENT FORM WIHIN 5 DAYS OF THE TRANSMITTAL DATE TO THE PALISADES PLANT DOCUMENT CONTROL SIGNATURE OR INITIALS DATE If applicable, REMOVE ALL travelers and marked up pages In front of this procedure.

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Procedure No El-7.10 Revision 3 Effective Date 3/30105 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING Approved: MLGrogan / 12116104 Procedure Sponsor Date New Procedure/Revision Summary.

Specific Changes Editorial to Revision 3

PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page I TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING Table of Contents 1.0 PERSONNEL RESPONSIBILITY ................................................. 1 2.0 PURPOSE .. . . ..............................1

3.0 REFERENCES

. ................................................ 1 3.1 SOURCE DOCUMENTS . . 1 3.2 REFERENCE DOCUMENTS.........................................................................I 4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS ............................................... 2 4.1 IMPLEMENTATION ......... ........................................ 2 4.2 DOSIMETRY REQUIREMENTS ............................................ . . 3 4.3 ANTI-CONTAMINATION CLOTHING REQUIREMENTS .............................. 3 4.4 GENERAL RADIOLOGICAL PRECAUTIONS ............................................. . 3 5.0 RGEM SAMPLING ................................................. . 4 5.1 ACCESS ROUTES .................................................. 4 5.2 PRESAMPLING SURVEY ............................................. . . 4 5.3 NORMAL RANGE IODINE/PARTICULATE FILTER CHANGEOUT ............. 4 5.4 AUTOMATIC GRAB SAMPLE ............................................. . . 5 5.5 HIGH RANGE IODINE FILTER CHANGEOUT ............................................. . 5 5.6 SAMPLE COUNTING .................................................. 6 5.7 SAMPLE ANALYSIS . ................................................. 7 6.0 ATTACHMENTS AND RECORDS .................. . . . 7 6.1 ATTACHMENTS ........................ 7 6.2 RECORDS ........................ 7 7.0 SPECIAL REVIEWS .................... . . 7

PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 1 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING USER ALERT INFORMATION USE PROCEDURE The activities covered by this procedure may be performed from memory.

1.0 PERSONNEL RESPONSIBILITY The Radiation Protection Group Leader shall implement this procedure. In the absence of a Radiation Protection Group Leader, the Site Emergency Director shall delegate this responsibility.

2.0 PURPOSE To provide the ability to take post accident samples of the stack effluent, using the Radioactive Gaseous Effluent Monitor (RGEM).

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Palisades Site Emergency Plan, Section 7.0, "Emergency Facilities and Equipment" l e-3.1.2 NUREG 0654,Section I, "Accident Assessment 3.1.3 Technical Specifications ADMIN 5.5.3, "Post Accident Sampling Program" l e.

3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure El-8, "Onsite Radiological Monitoring" 3.2.2 Emergency Implementing Procedure El-9, 'Offsite Radiological Monitoring" 3.2.3 Emergency Implementing Procedure El-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions' 3.2.4 Engineering Analysis EA-WWD-98-004, "Conversion Factor for the High Range Accident Filter'

PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 2 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS USER ALERT INFORMATION USE PROCEDURE The activities covered by this procedure may be performed from memory.

4.1 IMPLEMENTATION

a. The normal range iodine and particulate filter should be sampled at high alarm, but may be sampled before this time at the direction of the Radiation Protection Group Leader. These filters isolate automatically at the RGEM high alarm.

I 4.1.1 These samples should not be taken prior to high alarm if a release is expected because a system purge removes monitoring capability.

a. The automatic grab sample should be collected after the RGEM alert alarm.

b. The high range iodine filter should be sampled after the high alarm at the direction of the Radiation Protection Group Leader.

CAUTION During a situation where the Plant has lost offsite power, the RGEM equipment may show no indication of power. This is due to the fact that source of power for the equipment is a Motor Control Center that is not automatically energized by the diesel generators.

4.1.2 In the event the RGEM has lost power due to the loss of offsite power, the Site Emergency Director (SED) or Operations should be informed that MCC 3 needs to be energized and that Breakers52-381 and 52-385 on the MCC should be closed.

Breaker 52-381 powers the radiation monitors RIA-2326 and RIA-2327 and loss of input to PPC point FT-1818. Breaker 52-385 powers the RGEM computers and controls.

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PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 3 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 4.2 DOSIMETRY REQUIREMENTS Each individual that may handle a post accident sample shall as a minimum wear beta/gamma TLDs on their chest and on the inside of both wrists.

4.3 ANTI-CONTAMINATION CLOTHING REQUIREMENTS Minimum clothing shall consist of full anti-Cs, papers, and a SCBA breathing unit.

Any persons who will handle samples shall wear lineman's gloves in addition to their other clothing.

4.4 GENERAL RADIOLOGICAL PRECAUTIONS

a. Two people should be used to gather samples. A qualified Radiation Protection Technician shall accompany a second technician. The Radiation Protection Technician shall have as a minimum a Teletector, a RO-2A, and a grab air sampler, or equivalent instruments. The Radiation Protection Technician shall monitor the area during all sampling operations. Samples shall be monitored for beta radiation prior to any handling.

b. Sampling with general area radiation levels in excess of 10 rem/hr shall not be performed without the approval of the Site Emergency Director.

c. Stay times for technicians performing post accident sampling shall be based on the formula:

Stay Time =RQ x°09 DR Where: 'RQ' is the individual's remaining yearly and "DR" is the area's general area dose rate. In cases where the dose rates vary widely during sampling, the Radiation Protection Technician shall ensure that dosimeters l C are read frequently and do not exceed 80% of remaining yearly exposure.

d. Handling of samples shall be minimized. When samples must be handled, a beta radiation dose rate reduction of 90% can be assumed for lineman's gloves.

e. When not being handled, samples shall be stored in a shielded or removed location.

f. RGEM control operations should be performed at the remote control panel located behind the C-1 1A panel in the Control Room.

PALISADES NUCLEAR PLANT Proc No EI-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 4 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 5.0 RGEM SAMPLING 5.1 ACCESS ROUTES

a. The primary access route to the RGEM room is through the main Control Room door, to the Turbine Building, and up the staircase to the RGEM room.

b. In the case of high radiation levels along the above route, the back door of the Control Room should be used to access the Turbine Building.

5.2 PRESAMPLING SURVEY A presampling survey may be performed in the RGEM room, but due to the short time required to sample, this precaution may be unnecessary. The Radiation Protection Group Leader shall make this determination.

5.3 NORMAL RANGE IODINE/PARTICULATE FILTER CHANGEOUT

a. Perform all control operations from the remote control panel in the Control Room.

b. The RGEM system should not be purged if the sample is taken after high alarm. Prior to high alarm, the system should be purged prior to sample collection as follows. Switch System Control Purge to the on position.

This will divert purge air through the system during filter change.

c. Proceed to the RGEM room per Section 4.1.

d. The normal range iodine/particulate sampler is located inside the lower cabinet on the right side of the RGEM system.

e. Open the cabinet and loosen the two wingnuts on the filter holder assembly.

Turn the handle clockwise and draw the filter holder from the sampler.

f. Unscrew the filter cap and remove the filters. Wrap the filters to prevent spread of contamination. Use forceps to handle the filters whenever possible.

Samples should be marked with type, time, date, and initials of collector.

g. Inspect the O-rings on the filter holder assembly and replace if damaged.

h. Install new filters by following Steps 5.3e and 5.3f in reverse order.

i. Return to the Control Room and turn the System Control Purge to the off position. This will return the system to sampling mode.

PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 5 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 5.4 AUTOMATIC GRAB SAMPLE

a. A 15-second grab sample will be initiated when the alert alarm is given by the Normal Range Noble Gas Monitor (RIA-2326).

Proceed to:

b. The RGEM room and close the two valves located on either side of the grab sampler.

c. The grab sample can then be removed by releasing the two quick release couplings found on both sides of the sampler. Sample should be marked with type, time, date, and initials of collector.

d. The grab sampler can then be removed for counting.

5.5 HIGH RANGE IODINE FILTER CHANGEOUT

a. A high alarm will switch the RGEM system to the high range sample mode.

b. The Accident Filter Control Operating Mode Switch is kept in the sample position during normal operation and emergency sampling. During emergency sampling, the system will alternate between sampling and purge every minute in a preset ratio.

c. To collect the high range iodine filter, switch the Accident Filter Control Operating Mode to the Filter Change position. In this mode, purge air is continuously diverted through the high range iodine filter. This change should be made on the Control Room RGEM remote control panel.

d. Proceed to the RGEM room, per Section 5.1.

e. Upon arrival at the high range iodine filter, loosen the two thumbscrews and two wingnuts on the top of the unit and pull the retainer pin located behind the lid.

f. Draw the filter holder into the carrier by pulling the filter changer handle to its fully extended position. Insert the small retainer pin on the top of the side bracket. The filter carrier can be removed for counting. Mark the carrier with sample type, time, date, and initials of collector. The filter changer may be unscrewed and removed to facilitate transport.

g. Install a new filter by following Steps 5.5e and 5.5f in reverse order.

PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 6 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 5.6 SAMPLE COUNTING

a. Purge the noble gases from the high range iodine accident filter by using the special (labeled) air sample head jig located in the OSC Equipment Locker.

b. Perform dose rate survey on both sides of the high range iodine accident filter with an E-520 or equivalent. If highest contact dose rate is < 1 mrem continue with Step 5.6c, and count the filter on the low-level ND. If dose rate is > 1 mrem/hr go to Section 5.7 methodology to determine iodine release rate.

NOTE: The ND system in the low-level count room is the only ND system that has a geometry for the high range iodine accident filter.

c. Determine sample volume of the high range iodine accident filter by multiplying the expected sample flow rate of 500 cc/m X's sample collection minutes, X's the sample collection efficiency of 0.9. Sample start time can be determined by reviewing chart recorders RR-2325, and/or RR-2327.

d. Entering the corrected sample volume determined in above step, perform a 1000 second count using the Rgem cartridge geometry in the low-level count room.

e. Counting results shall be reported to the Radiation Protection Dose Assessor l or Group Leader in the TSC or EOF.

f. These results should be incorporated into Offside Dose estimates (refer to Emergency Implementing Procedures El-6.0, Offsite Dose Calculation and Recommendations for Protective Actions.")

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PALISADES NUCLEAR PLANT Proc No El-7.10 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 7 of 7 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING NOTE: Section 5.7 should only be used in the event the high range iodine accident filter has a contact radiation reading greater than 1 mremfhr.

5.7 SAMPLE ANALYSIS

a. Determine the total Iodine Curies released by: multiplying the contact does rate obtained on the high range iodine accident filter in Step 5.6b by 1.325 E-06. (This value was calculated in EA-WWD-98-004).

Total Iodine Curles Released from Stack = Contact reading mr/hr x 1.32E-06

b. Determine the sample time (in seconds) that the high range iodine accident filter was in service. Sample start time can be determined by reviewing chart recorders RR-2325, and/or RR-2327.

c. Determine the Iodine Stack Release Rate (C/sec), by dividing Step 5.7a by Step 5.7b.

d. Iodine release rate shall be reported to the Radiation Protection Group l -

Leader or Dose Assessor in the TSC or EOF.

e. These results should be incorporated into Offsite Dose estimates (refer to Emergency Implementing Procedure El-6.0, HOffside Dose Calculation and Recommendations for Protective Actions.")

6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS None 6.2 RECORDS None 7.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review per Palisades Administrative Procedure 10.41, "Procedure and Policy Processes."

Therefore, changes to this procedure do not require a 50.59 review.