ML022810571

Emergency Plan Implementing Procedure Changes

ML022810571
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	09/23/2002
From:	Tkaczyk L Entergy Nuclear Northeast, Entergy Nuclear Vermont Yankee
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
BVY 02-74
Download: ML022810571 (77)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc Vermont Yankee 185 Old Ferry Rd Brattleboro, VT 05302 Tel 802-257-5271 September 23, 2002 BVY 02-74 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-27 1)

Vermont Yankee Emergency Plan Implementing Procedure Change In accordance with 10 CFR 50.54(q), enclosed are the latest changes to the Vermont Yankee Emergency Plan Implementing Procedures, OP 3533, Rev. 6, OP 3534, Rev. 4, and OP 3542, Rev. 1, LPC#l, the change memos and the 10 CFR 50.54(q) Evaluation Checklists. These changes were determined to not need prior NRC review and approval.

If you have any questions, please contact Audra Williams, Emergency Planning Coordinator, in our Brattleboro office at (802) 258-4177.

Sincerely, ENTERGY NUCLEAR NORTHEAST VERMONT YANKEE Lori Tkaczy _

Emergency Planning Manager Attachments cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS (no attachments)

David M. Silk, Senior Emergency Preparedness Specialist, USNRC Region 1 Vermont Department of Public Service

I 0P zii P 'c- e- d i' s To: Eplan Implementing Procedure Controlled Set Holders From: Diane McCuC,,.t* -

• Date: 09/25/2002 Re: VY EPlan Implementing Procedure Change #209nstruction Sheet A new Table of Contents is included.

REVISIONS: Please replace the following procedures:

Proc/Rev # Procedure Title OP 3533/6 Post Accident Sampling of Reactor Coolant OP 3534/4 Post Accident Sampling of Plant Stack Gaseous Release LPC's: The fol.lowing LPC should be incorporated into the appropriate procedures:

Proc/Rev # LPC # Procedure Title OP 3542/1 1 Operation of the TSC a Iphna I

Vermont Yankee Emergency Plan Implementing Procedures K> Table of Contents September 24, 2002 Emergency Plan Classification and Action Level Scheme AP 3125 Rev. 19 "R" Emergency Communications OP 3504 Rev. 34 "R" OP 3505 Rev. 24 'IT Emergency Preparedness Exercises and Drills Emergency Equipment Readiness Check OP 3506 Rev. 41 "R" Emergency Radiation Exposure Control OP 3507 Rev. 29 "R" On-Site Medical Emergency Procedure OP 3508 Rev. 23 "R" Environmental Sample Collection During an Emergency OP 3509 Rev. 17 "R" Off-Site and Site Boundary Monitoring OP 3510 Rev. 26 "R1' Off-Site Protective Action Recommendations OP 3511 Rev. 11 "R" Evaluation of Off-Site Radiological Conditions OP 3513 Rev. 21 "R" OP 3524 Rev. 19 "R" SEmergency Actions to Ensure Accountability and Security Response Radiological Coordination OP 3525 Rev. 9 "1" Emergency Call-In Method OP 3531 Rev. 15 "R" AP 3532 Rev. 10 'IT Emergency Preparedness Organization OP 3533 Rev. 6 "C" Post Accident Sampling of Reactor Coolant OP 3534 Rev. 4 "C" Post Accident Sampling of Plant Stack Gaseous Releases OP 3535 Rev. 4 "C" Post Accident Sampling and Analysis of Primary Containment OP 3536 Rev. 1 "C" In Plant Air Sample Analysis with Abnormal Condition Control Room Actions During an Emergency OP 3540 Rev. 1 "1" Activation of the Technical Support Center OP 3541 Rev. 1 "R" Operation of the Technical Support Center OP 3542 Rev. 1 "R" Operation of the Operations Support Center OP 3544 Rev. 2 "R" Activation of the Emergency Operations Facility/Recovery Center OP 3545 Rev. 1 "R" Operation of the Emergency Operations Facility/Recovery Center OP 3546 Rev. 1 "R" OP 3547 Rev. 1 1"R Security Actions During an Emergency OP 3712 Rev. 16 I"T Emergency Plan Training

LPC's VERMONT YANKEE NUCLEAR POWER STATION SI' 1 0(DU q,,D!RCVTTTT1) 1 '

PE'J'I OP 3542 REVISION 1 OPERATION OF THE TECHNICAL SUPPORT CENTER (TSC)

USE CLASSIFICATION: REFERENCE LPC Effective Affected Pages No. Date 1 09/17/02 7-12 of 16 Implementation Statement: N/A I Issue Date: 06/06/02 OP 3542 Rev. 1 Page 1 of 16

Time/Date Initials NOTES SS/PED retains responsibility for off-site States' notifications (NAS - Orange Phone) until Site Recovery Manager assumes responsibility for implementation of VY Emergency Plan

• The FTS NRC ENS phone (#41) is located in the southwest comer of the room (see Figure 4 of OP 3504) 1.3. Contact the SSJPED when ready to assume overall responsibility for the implementation of the VY Emergency Plan. This includes the following primary responsibilities: / ________________

1.3.1. Escalation of the emergency, 1.3.2. Notification of off-site NRC authorities (FTS ENS phone), and 1.3.3. Authorization of off-site protective action recommendations (PARs).

NOTE Facility activation may be modified or suspended if the safety of personnel may be jeopardized by a security event or other event hazardous to personnel.

1.4. Assign an individual to implement OP 3541, Activation of the TSC.

Name: / ________________

1.5. Assign an individual to read AP 3125 and track all subsequent EAL entries.

Name: / ________________

1.6. Ensure that a TSC staff member is assigned to record in the TSC Logbook all TSC activities associated with exercising effective direction and control of the emergency. /

I OP 3542 Rev. 1 Page 7 of 16 LPC #1

Time/Date Initials 1.7. If a release is in progress or expected, ensure that (circle event)

OP 3513, Evaluation of Off-Site Radiological A S G Conditions, is implemented by a qualified individual.

/

I 1.8. IF conditions warrant escalation to a GENERAL EMERGENCY, THEN implement OP 3511, "Off-Site G I Protective Action Recommendations."

NOTE Minimum staffing for activation includes:

1) TSC Coordinator

2) Engineering Representative

3) Maintenance Representative

4) Security Representative

5) Operations Representative

6) Reactor Engineering Representative

7) Radiation Protection Representative

8) Chemistry Representative

9) OSC Coordinator (circle event) 1.9. Ensure that Technical Support Center Staff is in place for A S G activation and that the minimum required staffing is fulfilled.

1.10. Notify the SS/PED (and the SRM, if applicable) that the (circle event)

TSC is activated. A S G I

I 1.11. Announce over the plant paging system that the TSC is activated. ("Attention in the Plant, Attention in the Plant, the Technical Support Center is now activated, repeat, the Technical Support Center is now activated") (Repeat) / _______________

NOTE The Emergency Response Data System (ERDS) must be enabled as soon as possible, but not later than one hour, after the initial declaration of an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY 1.12. Ensure the ERDS data link with the NRC has been enabled per RP 2454. I OP 3542 Rev. 1 Page 8 of 16 LPC #1

Time/Date Initials 1.13. Maintain overall responsibility until relieved by the Site Recovery Manager.

1.14. Record time when Site Recovery Manager calls to assume responsibility for implementation of the VY Emergency Plan.

SRM Name: I _______________

1.15. Assign the Operations Support Center Coordinator (OSCC).

OSCC Name: / ________________

NOTE All work assignments from the TSC to the OSC should be made through the phone to the Communicator. Do not use the ring down phone or Gaitronics.

1.16. IF the possibility of a radiological release is likely to occur, THEN the TSC Coordinator or designee initially directs the activities and maintains communications with site boundary and off-site teams until the EOF/RC is /

deemed operational.

NOTE Accountability may be suspended if the safety of personnel may be jeopardized by a security event or other event hazardous to personnel.

1.17. Direct a staff member to perform initial and continuous (circle event) personnel accountability of the TSC, OSC and CR A S G personnel as stipulated in, Appendix A, Personnel Accountability Check, and OP 3524 guidance.

1.18. When notified by Security that the initial accountability check has been completed, contact the SRM at the EOF to report status (including any missing personnel).

OP 3542 Rev. 1 Page 9 of 16 LPC #1

Time/Date Initials 1.19. IF any persons are reported missing during the accountability checks, THEN perform the following steps:

1.19.1. Page the unaccounted for individual(s) in an attempt to locate them, 1.19.2. Verify missing person has not reported to GHH as part of on-site evacuation.

1.19.3. As necessary, direct the OSC Coordinator to dispatch an on-site search and rescue team to locate the individual(s), and, 1.19.4. Inform the Security Access Control Officer once the individual(s) are located.

1.20. Once accountability is complete, make decision regarding further disposition of company and contractor evacuees, either to stand by or leave the site completely.

NOTE If ERFIS is not available, the assigned individual (in Step 1.19) will also relay appropriate meteorological and radiological information to the Radiological Assistant at the EOF.

1.21. When necessary, assign an individual to report to the (circle event)

Control Room to relay appropriate radiological A S G information to the RP Checkpoint.

1.22. Direct and coordinate the on-site assistance team activities as follows:

1.22.1. Prioritize job tasks to be implemented with the SS/PED, and OSC Coordinator, if staffed.

1.22.2. Ensure that the applicable work control process defined in AP 0021, "Work Orders", is used.

1.22.3. Authorize emergency dose commitments for required job tasks in accordance with OP 3507, "Emergency Radiation Exposure Control."

OP 3542 Rev. 1 Page 10 of 16 LPC #1

Time/Date I Initials 1.22.4. Obtain periodic updates of job tasks implemented.

1.22.5. Periodically re-evaluate job priorities to mitigate the emergency condition and prevent or minimize release of radioactive material.

1.23. Ensure that a licensed individual reviews and approves all 10 CFR 50.54(x) considerations. Document any 10CFR50.54(x) considerations made in TSC Log Book.

1.24. When informed by the SRM that the EOF/RC is activated, make the announcement over the plant paging system that the EOF is activated. ("Attention in the (circle event)

Plant, attention in the Plant. The Emergency Operations A S G Facility and Recovery Center is activated. Repeat the Emergency Operations Facility and Recovery Center is activated.") (Repeat) 2.0 Subsequent Actions NOTE Activation of the TSC and the EOF constitutes an ALERT per AP 3125.

2.1. Initiate the escalation of the emergency classification as (circle event) conditions warrant. IF conditions warrant escalation to a A S G GENERAL EMERGENCY, THEN implement OP 3511, "Off-Site Protective Action Recommendations."

2.2. If warranted, ensure that manpower and planning is being (circle event) conducted to provide for response efforts over an A S G extended period.

2.3. If the NRC requests an open, continuous ENS communications channel (FTS ENS Phone), assign a technically competent individual to continuously (circle event) maintain the FTS ENS Phone (LAI-801). A S G Name:

2.4. Notify the Control Room that the TSC is assuming responsibility for transmitting plant parameter sheets to the EOF. (VYOPF 3504.02) I OP 3542 Rev. 1 Page 11 of 16 LPC #1

Time/Date Initials 2.5. After consultation with the OSC Coordinator, notify the Control Room that the TSC is assuming responsibility for deployment of the AOs.

/

I NOTE Refer to OP 3504 to establish the HPN channel.

2.6. If the NRC requests an open, continuous Health Physics Network (HPN) Communications Channel, assign a technically competent individual to continuously maintain the HPN phone until relieved by the EOF staff (circle event)

(LAI-801). A S G

/ _________________

2.7. Provide continuous technical support and assistance to the Site Recovery Manager concerning Emergency Action Levels (EALs) and emergency classifications changes (INS8626-02).

2.8. Transfer status information to the Site Recovery Manager as appropriate.

2.9. Verify that continuous accountability per Appendix A, Step 5 is maintained. IF any persons are reported missing during the accountability checks, THEN perform

/

IrtC_ Step 1.19 in the Immediate Actions Section. ________________

2.10. Using Appendix B, brief the TSC staff periodically on the status of the emergency and pertinent plant conditions.

2.11. Engage in periodic discussion with the SS/PED to maintain up-to-date plant status/priorities and review intended plans.

2.12. If deemed necessary to request emergency assistance from the General Electric BWR Emergency Support Program, refer to OP 3504 (SIL0324R3). /

OP 3542 Rev. 1 Page 12 of 16 LPC #1

VERMONT YANKEE NUCLEAR POWER STATION OPERATING PROCEDURE OP 3534 REVISION 4 POST ACCIDENT SAMPLING OF PLANT STACK GASEOUS RELEASES USE CLASSIFICATION: CONTINUOUS Effective Date Affected Pages LPC No.

.1 1

______ I _______ I ________________________________________

Implementation Statement: N/A I Issue Date: 0 9 / 2 7 / 2 0 0 2 OP 3534 Rev. 4 Page 1 of 13

TABLE OF CONTENTS PURPOSE .......................................................................................................................................................... 3 DISCU SSION .................................................................................................................................................... 3 ATTA CHME ENTS ............................................................................................................................................. 3 REFERENCES AN D COMMN I vTM ENTS ..................................................................................................... 4 PRECAUTIONS/LIMR TATIONS .................................................................................... ............ 4 PREREQU ISITES ............................................................................................................................................. 5 PR O CED URE .................................................................................................................................................... 5 A. Low Dose Rate Stack Iodine/Particulate and Gas Sampling ................................................... 5 B. High Dose Rate Post Accident Iodine/Particulate Sampling using a Silver Zeolite Cartridge at the Stack Post-Accident Sampling Panel ....................................................... 6 C. G as Sam pling ............................................................................................................................ 8 D. Sam ple Analysis w ith M CA O perable ............................................................................... 9 E. Sam ple Analysis with M CA Inoperable ............................................................................. 10 F. Counting Techniques for Highly R adioactive Sam ples ......................................................... 11 FIN AL C OND ITIO N S .................................................................................................................................... 13 OP 3534 Rev. 4 Page 2 of 13

PURPOSE To outline the special procedures necessary to collect samples of plant vent stack gaseous releases, perform analyses and interpret results during post accident conditions.

No Technical Specifications Sections apply to this procedure.

DISCUSSION Plant vent stack gaseous effluents are sampled and analyzed to determine actual release mixtures and concentrations of radioactive materials being discharged to the environment during accident conditions. This information is then utilized to determine dose impact to the public.

During post accident conditions, system samples may be highly radioactive. Because of the high radiation levels, these samples require special handling. This procedure outlines the special handling required. The Chemistry Manager is responsible for implementation of this procedure.

During certain postulated accidents, the availability of on-site counting equipment may be compromised. In these instances, post accident samples may be counted at laboratories at Yankee Atomic in Rowe, Massachusetts or Maine Yankee in Wiscasset. A determination will be made by the Operations Support Center Coordinator's Assistant, in conjunction with the Radiological Assistant at the Emergency Operations Facility/Recovery Center, as to the most appropriate alternative laboratory facility to be used, based on existing conditions.

Table 1 is provided for use by the OSC Coordinator's Assistant and the sampling and analysis teams in their evaluation of sampling conditions prior to obtaining the isotopic results after analysis. The information contained in this table is generated from design basis accident assumptions and this fact should be taken into account in the use of this table.

VYOPF 3534.02, Sample Accountability Log shall be utilized to track the location of emergency samples collected in accordance with this procedure. Stack sampling kit inventory is controlled by OP 3506, Emergency Equipment Readiness Check.

In accordance with AP 6002, Preparing 50.59 Evaluations, the results of an Applicability Determination (AD) has determined that an AD is not required for future changes provided the procedure scope is not changed. The basis for this conclusion is that this document is an Emergency Implementing Procedure and is subject to 10CFR50.54(q) to determine if the changes decrease the effectiveness of the Emergency Plan and if they have the potential to affect our ability to meet the standards of 10CFR50.47(b) and the requirements of 10CFR50 Appendix E.

ATTACHMENTS

1. VYOPF 3534.01 Post Accident Stack Sampling

2. VYOPF 3534.02 Stack Sample Accountability Log

3. Appendix A Deleted

4. Table 1 VY-Dose Rates (R/hr) at Different Sampling Stations at Different Times After Shutdownc OP 3534 Rev. 4 Page 3 of 13

REFERENCES AND COMMITMENTS

1. Technical Specifications and Site Documents

a. None

2. Codes, Standards, and Regulations

a. None

3. Commitments

a. None

4. Supplemental References

a. "Assessment of the Vermont Yankee High-Range Particulate and Iodine Stack Monitor" Rev. 1, Science Applications International Corporation, Rockville, Md.

dated December 7, 1984 (iodine plate-out factor)

b. NUREG 0737, Sec. ll.B.3

c. OP 0642, Sample Valve Lineup and Control

d. OP 2611, Stack Effluent Sampling and Analysis

e. DP 2630, Analytical Instrumentation

f. DP 2631, Radiochemical Instrumentation

g. OP 3506, Emergency Equipment Readiness Check

h. OP 3510, Off-Site and Site Boundary Monitoring

i. OP 3536, In-Plant Air Sample Analysis with Abnormal Conditions

j. AP 6807, Collection, Temporary Storage and Retrieval of QA Records PRECAUTIONS/LIMITATIONS

1. During sampling, communications should be maintained using either a portable radio or a Gai-Tronics.

2. High levels of Kr 88 may cause an interference with 131 identification. If this is suspected, purge sample if possible or count sample again at a later time.

OP 3534 Rev. 4 Page 4 of 13

PREREQUISITES

1. Stack Post Accident Sampling Kit.

2. Copy of OP 2611, Stack Effluent Sampling and Analysis.

3. Stack PASS valves lined up according to OP 0642, Sample Valve Lineup and Control (18 month Surveillance requirement).

4. Take a dose rate meter.

5. Evaluate whether or not respiratory protection should be worn during sampling.

6. Evaluate with RP whether or not extremity dosimetry and high range pocket dosimeters should be worn during sampling.

7. Dose commitment limits have been established and should be adhered to for all Post Accident Sampling. Consult with the OSC Coordinator for specific instructions. Table 1 should be consulted by the OSC Coordinator and sample team members for information concerning expected dose rates.

PROCEDURE A. Low Dose Rate Stack Iodine/Particulate and Gas Sampling

1. If dose rates permit, (<1 R/hr at Stack Victoreen Room door or dose commitment has been established) the samples will be taken the same as the routine stack iodine/particulate and gaseous grab samples utilizing OP 2611, except as specified below, otherwise proceed to Section B.

a. No background determination will be made during post accident sampling.

b. A dose rate will be determined on the gas grab container and filter holder prior to removal of the samples. A dose commitment (review Table 1) will be established by the OSC Coordinator for this sample prior to the sample being removed. The dose rate will be used to determine that the dose commitment will not be exceeded. If it appears from the dose rate survey that the dose commitment will be exceeded, the sample should not be taken until the need for the sample is re-evaluated.

c. A vehicle should be used to transport the samples from the stack to the point of analysis to maximize the distance between the sample and the person doing the sampling and to minimize the transport time. A shield may be used to minimize the exposure rate during transportation (e.g., concrete blocks or lead blankets etc., in car trunk).

OP 3534 Rev. 4 Page 5 of 13

d. If the Main Chemistry Lab and Counting Room are accessible, the sample will be taken to the Main Chemistry Lab and placed in an isolated area.

e. The noble gases should be purged from the charcoal cartridge prior to counting using plant air, bottled air or nitrogen. A purge rate and duration should be utilized to approximately equal 1 cfm for 10 minutes.

f. Count samples per Section D.

g. If the Chemistry Lab and Counting Room are not accessible, the charcoal cartridge can be purged as in Step e. above and counted using an RM-14 as I in OP 3510, a SAM-II (outlined in Section E) or transported to an off-site multi-channel analyzer for analysis. The particulate filter can be counted this way also but need not be purged prior to counting.

B. High Dose Rate Post Accident Iodine/Particulate Sampling using a Silver Zeolite Cartridge at the Stack Post-Accident Sampling Panel INITIALS NOTE Continuous sampling can be established by replacing the cartridge/filter assembly at periodic time intervals. This practice will be initiated and terminated at the request of the PED or TSC Coordinator in consultation with the Chemistry Manager or RP Manager.

1. Ensure a dose commitment has been established prior to the sample being drawn.

2. Notify the OSC of intent to sample.

3. Obtain a loaded filter holder, tongs, and evacuated 14 ml vial and if required, lead shielded pig for transportation. Shield pig is in room west of stack base.

4. Obtain vehicle and portable radio, then proceed to stack base (vehicle not necessary if pig is not required).

5. Establish communication via portable radio with TSC.

OP 3534 Rev. 4 Page 6 of 13

INITIALS

6. Align the 3-way sample valve to allow through flow with the needle isolated. (SRS-2 at T)

7. OPEN filter outlet (SRS-24) valve.

8. Ensure bypass valve (SRS-25) is CLOSED.

9. Note time and start pump by turning switch ON.

a. Record start time on VYOPF 3534.01 CAUTION Dose rates will increase when flow is established. Do not exceed established dose commitment. If it appears that dose commitment will be exceeded, notify OSC Coordinator for further instructions.

10. Adjust flow through rotometer to approximately 452 cc/min.

a. Record pressure gauge reading and flow rate on VYOPF 3534.01.

11. Run pump for 10 minutes.

12. Disengage inlet quick disconnect. Note time.

13. Record Stop Time on VYOPF 3534.01.

14. Run pump for 15-30 sec. to purge gases from holder. (Sampling times may vary due to radionuclide concentrations.)

WARNING DOSE RATES ON FILTER HOLDER MAY BE HIGH. USE TONGS TO REMOVE FILTER HOLDER TO MINIMIZE EXPOSURE TO EXTREMITIES.

15. Disengage outlet quick disconnect.

16. Remove filter holder.

17. Secure pump.

18. Close valve SRS-24.

OP 3534 Rev. 4 Page 7 of 13

IN1TIALS

19. Log all samples on VYOPF 3534.02 for accountability.

20. Place filter holder assembly into lead shield pig and place pig in back of vehicle (if pig is required).

21. Install a fresh filter holder assembly onto panel.

22. Return samples to the Chemistry Lab.

NOTE I Multiple samples may be requested per contact with TSC.

C. Gas Sampling NOTE Vials can be evacuated in lab prior to sampling or by using hand vacuum pump.

1. Perform Steps B.1 through B.5 above.

2. Align the 3-way sample valve to allow through flow with the needle isolated. (SRS-2 at T )

3. OPEN bypass (SRS-25) valve.

4. Start pump, wait for line to purge -30 sec.

5. Place evacuated vial (14 ml gas bottle) on top of hypodermic needle.

6. Rotate the 3-way sample valve clockwise 900 to allow flow from the inlet to the needle and isolating the discharge. (SRS-2 at -I)

WARNING DOSE RATES ON SAMPLE VIAL MAY BE HIGH. IT MAY BE NECESSARY TO USE TONGS AND/OR SHIELDED TRANSPORT CART TO MINIMIZE EXPOSURE.

7. After the pressure indicator equilibrates near zero, using tongs remove the sample vial and place in lead pig (if used).

OP 3534 Rev. 4 Page 8 of 13

INITIALS

8. Immediately rotate the 3-way sample valve 1800 to purge the needle (SRS-2 at [- )

9. Record sample time on VYOPF 3534.01.

10. After at least 10 seconds, rotate the 3-way valve clockwise 900.

(SRS-2 atT )

11. CLOSE bypass valve (SRS-25).

12. Secure the pump.

13. Place sample in pig (if pig is used) in back of vehicle and return samples to the Chemistry Lab for analysis.

D. Sample Analysis with MCA Operable

1. Iodine and particulate filters

a. Prepare and count samples per OP 0631 (dead time limit

<20%) or Section E (High Activity .... ) as applicable based on dead time:

1) Separate the particulate and cartridge filters.

2) Wrap samples to secure activity.

3) Count particulate filter 500 seconds (minimum) as "General" isotopic to obtain results as [tCi/cc.

4) Count the cartridge 250 seconds (minimum) per side as "General" isotopic to obtain results as [tCi/cc.

5) Multiply iodine results from the previous step by 1.67 (plate out correction factor for stack PAS sampler (References 3.a)).

2. Gas Samples

a. Count the gas grab sample 500 seconds (minimum) as "General" isotopic to obtain results as jtCi/cc.

b. If the dead time on the MCA is >20%, remove aliquot sample to achieve <20% dead time.

OP 3534 Rev. 4 Page 9 of 13

INITIALS

3. Report all results as P.Ci/cc to the OSC Coordinator.

4. Submit VYPOF 3534.01 to OSC Coordinator.

5. Log all samples on VYOPF 3534.02 for accountability.

E. Sample Analysis with MCA Inoperable NOTES

• If it is necessary to do Plant Vent Stack gas sampling with the MCA out of service, accurate iodine results can be achieved by analyzing the iodine cartridge as follows.

• If Silver Zeolite cartridges are used, purging is not necessary.

1. Purge the noble gases from the charcoal cartridge per Section A.l.e).

2. Wrap the charcoal/zeolite cartridge to protect the detector from contamination.

3. Deliver to Radiation Protection personnel for analysis using the SAM II per OP 3536.

4. Obtain sarfiple analysis net count per minute and SAM II efficiency.

5. Calculate the iodine-131 concentration as follows:

(C)(4.5 x 10 10) 1131 11Ci/cc =

(E)(V)(T)

Verified by:

Where: C = Net counts (cpm) (sample counts-background counts)

E = Efficiency V = Flow rate of sample (liters/min)

T = Duration of sample (min) 4.5 x 10-10 = Constant OP 3534 Rev. 4 Page 10 of 13

INITIALS

6. Use of Silver Zeolite Sampler Cartridges

a. If 13 1 concentration calculated in Step E.5 (from above) is greater than or equal to 1 x 10.6 p.Ci/cc 1131, then resample and verify results using silver zeolite cartridge (except omit purge I step outlined in Step E. 1.

Verified by:

b. Report results to OSC Coordinator and record results in logbook.

7. Log all samples on VYOPF 3534.02 for accountability.

F. Counting Techniques for Highly Radioactive Samples NOTE If sample size or dilutions can be used to permit a sample to be counted by conventional techniques, this should be done. If this is not possible, the following techniques can be used.

1. Use of the MCA at extended distances.

NOTE If general area dose rate in the Counting Room exceeds 5 mR/hr, the use of the MCA at extended distance with shield top removed is prohibited (LAI-417B).

a. Open the shield top from the 10% germanium detector.

b. Using rod and holder, suspend the sample above the detector at a distance that will give a dead time of <20% (must be >1 ft.).

c. Measure the distance from the sample to the top of the detector.

d. Count the sample using a 2" filter paper geometry efficiency.

OP 3534 Rev. 4 Page 11 of 13

INITIALS NOTE Step e. or f. below may be used to calculate sample activity.

e. Analyze the sample using the MCA selection for "PASS Elevated Samples" OR

f. Calculate the sample activity as follows:

gCi/ml = (X) (d2) (17)

NOTE The below correction factor must be re-evaluated if the detector geometry for the filter paper with a 2" shelf is modified at the time the efficiency calibration (DP 2631) is performed.

where: X = ýtCi/ml from isotopic printout d = distance in ft. measured in E.l.c above 17 = correction factor 9Ci/ml Verified by:

2. Use of portable instruments.

NOTE I If neither conventional methods or those in Step F.1 can be used, portable gamma survey meter can be used to determine sample activities.

a. If the MCA is available, it can be used to give a qualitative measure of major isotopes. If it is not available, an assumption must be made based on what is known about the sample at the time.

b. Measure the radiation level of the sample at 1 meter.

OP 3534 Rev. 4 Page 12 of 13

INITIALS

c. Calculate the sample activity as follows:

[1Ci/ml = (R/hr at 1 meter)(10 6 )

(T) (V) where: 106 = ýICi/ci V = sample volume (milliliters)

T = R/hr @ 1 meter/Ci Values for T (R/hr @ 1 meter/Ci)

Time Degassed Liquid* Containment Air**

1 hr 0.60 0.41 4 hr 0.43 0.28 8 hr 0.35 0.22 12 hr 0.31 0.18 24 hr 0.26 0.14

• Assumed mix of 0% of core noble gas inventory, 50% of core halogen inventory and 1% of core solids inventory.

For convenience, the mix ratio is expressed as 00/50/1 (%

NOBLE GAS/% HALOGENS/% SOLIDS)

"**Assumedmix of 100/50/1.

FINAL CONDITIONS

1. Submit all forms for review and filing as per AP 6807.

2. If any portion of the PASS Panel is found to be inoperable, submit a Work Order and report the problem at the daily Operations Planning meeting.

OP 3534 Rev. 4 Page 13 of 13

POST ACCIDENT STACK SAMPLING INITIALS

"_-ROM SECTION B AND C HIGH DOSE RATE POST ACCIDENT IODINE AND PARTICULATE SAMPLING USING A SILVER ZEOLITE CARTRIDGE AT STACK POST-ACCIDENT SAMPLING PANEL

1. Record the following:

Flow ratecc/min Start Time Stop Time Total Time min Sample Volume = Total time x Flow rate = cc.

2. Record Pressure Gauge reading:

Pressure in Hg

3. Record results or attach isotopic printout form.

4. Multiply iodine results from previous step by 1.67 plate out factor. Record K_> results on printout.

5. Copy all printouts and this form and retain for filing.

6. Report all results to the OSC Coordinator or their Assistant.

GAS SAMPLE

1. Record sample time:

2. Log all samples on VYOPF 3534.02 for accountability.

3. Attach isotopic printout form.

4. Copy all printouts and this form and retain for filing.

5. Report all results to the OSC Coordinator or their Assistant.

Review by:

OSC Coordinator's Assistant VYOPF 3534.01 OP 3534 Rev. 4 Page 1 of I

STACK SAMPLE ACCOUNTABILITY LOG 1 1 1

'Sample Location Identification (Update after each movement) Date Time Initials 4- 1 1

+ I t t t 1*

+ 1- t i i 4 +

I t t 4- 1 I +

i -i -

I F I i i i 4 t I 1- 1 1 VYOPF 3534.02 OP 3534 Rev. 4 Page 1 of 1

TABLE 1 VY - DOSE RATES (R/hr) AT DIFFERENT SAMPLING STATIONS AT DIFFERENT MIMES AFTER SHUTDOWNc Time (hr) Post-Accident Containment Air Vent Stack Sampling Station Sampling Station Sampling Room 6.OE+oa 1.OE+Ob 1 4.5E-1a 3 1.9E-1 2.6E+O 5.1E-1 8 5.4E-02 1.1E+0 2.2E-1 24 6.8E-03 4.7E-1 5.8E-02 72 4.1E-03 3.1E-1 1.8E-02 NOTES:

a. Per Calculation VYC-70.

b Per Calculation VYC-83, Vent Stack Only.

Dose Rates at other decay times are based on Table 11 of EDS Nuclear, Report No.

c. 02-0180-1126, December 29, 1979.

Table 1 OP 3534 Rev. 4 Page 1 of 1

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

534, Pew 4. Po- Acuc cn+ Sam 011 ngof PClcu-)

39 G\korx 6acciewis PeA1Qa&_S A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibilities YES (N)

(2) Assignment of on-shift Emergency Response Organization personnel YES (3) Arrangements for Emergency Response Support and Resources YS(

(4) Emergency Classification and Action levels, including facility system and effluent parameters Y YESN

-SON (5) Notification Methods and Procedures Y YES

-N (6) Emergency Communications among principal response organizations and the public YES O (7) Public Education and Information YES (

(8) Adequacy of Emergency Facilities and Equipment YES (9) Adequacy of Accident Assessment methods, systems and equipmep YESNO actions 9 'N (10)

(11)

Plume exposure pathway EPZ protective Emergency Worker Radiological Exposure Control YES N YES S

(12) Medical Services for contaminated injured individuals YES NO Plans (13) Recovery and Reentry YES (14) Emergency response periodic drills and exercises YES NO (15) Radiological Emergency Response Training e YES Y D---

(16) Plan development, review and distribution YES VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. 10.E06.171

10 CFR 50.54 (q) Evaluation Checklist (Continued)

I 2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization YES S (2) Section IV. B - Assessment Actions

@ NO (3) Section IV. C - Activation of Emergency Organizations YES (4) Section IV. D - Notification Procedures YES (5) Section IV. E - Emergency Facilities and Equipment YES (6) Section IV. F - Training YES NO (7) Section IV. G - Maintaining Emergency Preparedness YES NO (8)Section IV. H - Recovery YES §NO B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For apvlic ble item 10 CFR 50,.1(bXQ)AAPbP 5~t?7enon-A above, this change (DOES D ES-M-Tý decrease the effectiveness of the Emergency Plan and

ýtORYDOES NOT) continue to meet the stated applicable standard or r';-!ýirement.

BASIS FOR ANSWER: *hd*c*hxS m ck_ AD e xorkey.*Ne*W MO b 0 WA Wi I1 j in r) -W *bCLr T DrOCC CiLtIMZ !OSVZ U\(e C c "eitt~oo\ lcAl VhoiM CUY\(Q_~\C (s 0Juc Iu~k! (Thr .

I o 11/2s Iicoi L- une VaS I I

VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54 (q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

El The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

o The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

0 Revise proposed changes to meet applicable standards and requirements.

O Cancel the proposed changes.

o Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search:

VThis change does not affect any other documents.

O This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search:

Additional Comments:

"Thcg charqes ref1ca actuai palace of StmpO-rc, nCL do f)of Cox'qe ntitnf o(pr[Xfeduu(e n*r CkCdrOrae Prepared By: Auki Vfw*Jy\i*nt/j A [ate: 4 k5"lS"2..

(Print/Sihn)

Reviewed By: L a le- Date: l 0 t-(Emergency Plan Coordinator) (Print! 'gn)

VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3

VERMONT YANKEE NUCLEAR POWER STATION 777

.','2*.......

. "°*'" -.....* * ....... ... ... '*% V,* **"' ",* , "Ok OP 3533 REVISION 6 POST ACCIDENT SAMPLING OF REACTOR COOLANT USE CLASSIFICATION: CONTINUOUS LPC Effective Affected Pages No. Date Implementation Statement: N/A I Issue Date: 09/27/2002 OP 3533 Rev. 6 Page 1 of 7

TABLE OF CONTENTS PURPOSE .......................................................................................................................................................... 3 D ISCU SSION .................................................................................................................................................... 3 ATTACH VENTS ............................................................................................................................................. 4 REFERENCES AND COM M ITM ENTS ......................................................................................................... 4 PRECAUTION S/LIM ITATIONS ......................................................................................................... 5 PREREQUISITES ............................................................................................................................................. 5 PROCEDURE .................................................................................................................................................... 6 FINAL COND ITION S ...................................................................................................................................... 7 OP 3533 Rev. 6 Page 2 of 7

PURPOSE To outline the special procedures necessary to collect and handle samples, perform analyses and interpret results during post accident conditions.

Primary containment integrity issues are addressed in Technical Specifications section 3.7.

DISCUSSION Post accident sampling and analysis of reactor coolant is performed to provide information on the nature and extent of fuel damage, boron concentration following SLC injection and damage information on other in-core components such as control rods.

NUREG-0737 requires a combined time of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less for sampling and selected analyses from the time the decisions is made to collect a sample (TSC).

During post accident conditions, samples of reactor coolant may be highly radioactive.

Because of the high radiation levels, these samples require special handling. This procedure outlines the special handling required. The Chemistry Manager is assigned responsibility for implementation of this procedure.

In addition to the above concerns, conductivity readings of the reactor coolant may be useful during an accident. Readings can be obtained in the Control Room up to 10 tmho/cm; if exceeded, conductivity readings may be taken at a later date at the discretion of the Chemistry Manager.

During certain postulated accidents, the availability of on-site counting equipment may be compromised. In these instances, post accident samples may be counted at alternative laboratories. A determination will be made by the Operations Support Center Coordinator's Assistant, in conjunction with the Radiological Assistant at the Emergency Operations Facility/Recovery Center, as to the most appropriate alternative laboratory facility to be used, based on existing conditions.

Tables 1, 2, 3 and 4 are provided for use by the OSC Coordinator's Assistant and the sampling and analysis teams in their evaluation of sampling conditions prior to obtaining the isotopic results after analysis. The information contained in these tables is generated from design basis accident assumptions and this fact should be taken into account in the use of these tables.

VYOPF 3533.02, Sample Accountability Log shall be utilized to track the location of emergency samples collected in accordance with this procedure.

OP 3533 Rev. 6 Page 3 of 7

In accordance with AP 6002, Preparing 50.59 Evaluations, the results of an Applicability Determination (AD) has determined that an AD is not required for future changes provided the procedure scope is not changed. The basis for this conclusion is that this document is an Emergency Implementing Procedure and is subject to 10CFR50.54(q) to determine if the changes decrease the effectiveness of the Emergency Plan and if they have the potential to affect our ability to meet the standards of 10CFR50.47(b) and the requirements of 10CFR50 Appendix E.

ATTACHM ENTS

1. Figure 1 Post Accident Sampler

2. Figure 2 Post Accident Sampling System VYOPF 3533.01 Reactor Coolant PASS Data/Analysis I 3.

4. VYOPF 3533.02 RV PASS Sample Accountability Log

5. Appendix A Reactor Coolant Sampling and Analysis - RB 303' Sample Sink

6. Appendix B Operation of the PASS to Sample Reactor Coolant

7. Appendix C Flushing and Restoring the PASS Following Use

8. Appendix D PASS Sample Analysis

9. Appendix E Deleted

10. Table 1 VY Radioactivity Concentration (ptCi/g) in Reactor Coolant Based on Design Basis Source Term (100/5011)

11. Table 2 VY Dose Rates (R/hr) at Different Sampling Stations at Different Times After Shutdown

12. Table 3 VY Reactor Coolant and Containment Air Samples Dose Rates (R/hr) at Different Times After Shutdown

13. Table 4 VY Reactor Coolant and Containment Air Samples Dose Rates (R/hr) at Different Times after Shutdown REFERENCES AND COMMITMENTS

1. Technical Specifications and Site Documents

a. TS 3.7

b. UFSAR, Section 10.20

2. Codes, Standards, and Regulations

a. NUREG 0737, Sec. II.B.3

3. Commitments

a. None OP 3533 Rev. 6 Page 4 of 7

4. Supplemental References

a. EDCR 97-407 on FCV-39 and FCV-40

b. OP 0630, Water Chemistry

c. OP 0634, Operation of the Dionex Ion Chromatograph

d. DP 0647, Operation of the Perkin Elmer Autosystem XL Gas Chromatograph

e. DP 2630, Analytical Instrumentation

f. DP 2631, Radiochemical Instrumentation

g. OP 3506, Emergency Equipment Readiness Check

h. OP 4612, Sampling and Treatment of the Reactor Water System

i. AP 6807, Collection, Temporary Storage and Retrieval of QA Records PRECAUTIONS/LIMITATIONS

1. During sampling, communications should be maintained using either a portable radio or a Gai-Tronics.

2. High levels of Kr 88 may cause an interference with 1131 identification. If this is suspected, purge sample if possible or count sample again at a later time.

3. Be aware of the radiological concerns and RWP requirements. Dose rates during sampling could increase rapidly.

PREREQUISITES

1. Post accident sampling equipment and tools, as needed.

2. Dose rate meter.

3. Evaluate with RP whether or not respiratory protection should be worn during sampling.

4. Evaluate with RP whether or not extremity dosimetry and high range pocket dosimeters should be worn during sampling.

5. Maximum Dose Rate and Dose commitment limits have been established, if needed, and should be adhered to for all Post Accident Sampling. Consult with the OSC Coordinator for specific instructions. Tables 3 and 4 should be consulted by the OSC Coordinator and sample team members for information concerning expected dose rates.

OP 3533 Rev. 6 Page 5 of 7

PROCEDURE A. Reactor Coolant Sampling and Analysis - RB 303' Sample Sink NOTE Sampling the reactor coolant at the RB 303' sample sink is only allowed if the Reactor Building is accessible with acceptable dose rates. If the RB is not accessible, sample the Reactor Coolant at the PASS panel per Appendix B of this procedure.

1. Utilize Appendix A to sample and analyze the Reactor Coolant via the RB 303' sample sink.

2. IF serial dilutions of the sample are required during analysis, THEN

a. Indicate dilution factor (see nomenclature in A.2.b., below) and resultant volume on VYOPF 3533.02, AND

b. Identify each dilution sample as the sample identification followed by the dilution factor in parentheses (e.g., RV(20:1) or serially RV(20:1)(100:1)).

B. Operation of the PASS to Sample Reactor Coolant I NOTE Chemistry Emergency Equipment Readiness Check is maintained per VYOPF 3506.05.

1. Utilize Appendix B to sample the Reactor Coolant via the PASS Panel.

2. IF serial dilutions of the sample are required during analysis, THEN

a. Indicate dilution factor (see nomenclature in B.2.b., below) and resultant volume on VYOPF 3533.02, AND

b. Identify each dilution sample as the sample identification followed by the dilution factor in parentheses (e.g., RV(20: 1) or serially RV(20:1)(100: 1)).

C. Flushing and Restoring the PASS Following Use

1. Utilize Appendix C to flush and restore the PASS Panel following use.

OP 3533 Rev. 6 Page 6 of 7

D. PASS Sample Analysis

1. Utilize Appendix D to analyze the PASS liquid and gas samples.

2. Make a copy of VYOPF 3533.01 and any printouts and retain for filing.

3. Submit original VYOPF 3533.01 and printouts to the OSC Coordinator or OSC Assistant.

FINAL CONDITIONS

1. Submit all forms for review and filing as per AP 6807.

2. Report all results to the OSC Coordinator or Assistant.

3. If any portion of the PASS Panel is found to be inoperable, submit a high priority Work Request.

OP 3533 Rev. 6 Page 7 of 7

C C FIGURE 1 POST ACCIDENT SAMPLER VENT NOTE: Watoken line Indicates tubing on operating panel side.

Figure 1 OP 3533 Rev. 6 Page 1 of 1

FIGURE 2 POST ACCIDENT SAMPLING SYSTEM FOfl COnr. 91`1 Wt- FOR COWi. art! a-lu1018 to 114(t.-Il a-~t 191-0 7 VIIHMIAT1Ot4 011017 EL.~'0 111-1 11" -ru 120011-01 PlAJllPA

)(V72-15 )~y7g1S ilIW mo I Usi rollusCol.

JE1 "o 3' 3' 4

102 Figrep 111 3r3 Re.

1Pag 1oof5I Page 1 of 1

REACTOR COOLANT PASS DATA/ANALYSIS (For Use with Appendix B and D)

SAMPLE DATA: Date Time By DILUTION WATER VOL: ml GAS: High (Cyl B and C) OR Low Activity (Cyl B) (CIRCLE ONE)

1. GASEOUS Analyses from PASS RV System:

A. Gas Sample correction factor when diluting with carrier gas (CIRCLE ONE):

1. If App. B. Step F.3.a. 1) is performed (high activity, Cyl B and C) CF=29 OR

2. If App. B. Step F.3.a.2) is performed (low activity, Cyl B only) CF=7.2 BASIS: Vole + VOIc VOIB = 329 cc MassA = CF Volc = 1005 cc MasSA = 46 g B. Hydrogen Concentration Input Needed: 1) Hydrogen concentration _H 2 con c (from analysis as decimal)

2) Gas Sample CF (from I.A) CF

1. Calculate H2 concentration in Reactor Coolant:

14* X H2conc X CF = Coolant Hydrogen Concentration in Coolant

• 14 = volume of offgas vial in cc X X = cc H2 per g. Rx Coolant

2. Attach printouts to this form.

I VYOPF 3533.01 OP 3533 Rev. 6 Page 1 of 3

REACTOR COOLANT PASS DATA/ANALYSIS (Continued)

C. Oxygen Concentration Input Needed: 1) Oxygen concentration _ O2con C (from analysis as decimal)

2) Gas Sample CF (from I.A) CF

1. Calculate 02 concentration in Reactor Coolant:

14* X O2 conc X CF = Coolant Oxygen Concentration in Coolant

• 14 = volume of offgas vial in cc X X = cc 02 per g. Rx Coolant

2. Attach printouts to this form.

I D. GASEOUS Isotopic Analysis Input Needed: 1) Gas Sample CF (from I.A) CF

1. Calculate volume of gas to be analyzed on MCA:

1 CF x 14 = cc (enter as MCA sample volume)

2. Attach isotopic printout to this form. Results are tCi/cc of gas per gram of Rx coolant.

If. LIQUID Analyses from PASS RV System:

A. Calculate sample PASS Dilution factor (DFp~s):

Input Needed: PASS Dilution Water volume _VDIL ml VDIL - DFpass 0.5 ml 0.5 DFpass VYOPF 3533.01 OP 3533 Rev. 6 Page 2 of 4

REACTOR COOLANT PASS DATA/ANALYSIS (Continued)

B. Chloride Concentration NOTE A lab dilution may be required for this analysis due to the small initial sample size.

1. Calculate lab dilution factor (DFLab):

DFLb Final Volume (ml) (ml)

Aliquot (ml) (ml) = DF*b

2. Analyze sample with IC.

3. Calculate chloride concentration in coolant:

Input needed: DFpass from II.A. and analysis result.

Analysis (ppb) X DFpass X DFULb = Coolant ClI (ppb) ppb X X = ppb coolant ClI (analysis)

4. Attach any printout to this form.

C. Boron Concentration NOTE A lab dilution may be required for this analysis due to the small initial sample size.

1. Calculate lab dilution factor (DFUab):

_ Final Volume (ml) (ml)

DFtD - Aliquot (ml) (ml) = DFLb

2. Analyze sample with ICP or Titration (circle one).

3. Calculate BORON concentration in coolant:

Input needed: DFpass from II.A. and analysis result.

VYOPF 3533.01 OP 3533 Rev. 6 Page 3 of 4

REACTOR COOLANT PASS DATA/ANALYSIS (Continued)

Analysis (ppb) X DFpa, X DFab = Coolant Boron (ppb) ppb X X = ppb coolant Boron (analysis)

4. Attach any printout to this form.

D. LIQUID Isotopic Analysis

1. Calculate corrected sample volume for MCA analysis entry:

Input needed: DFPass from II.A.

Aliquot (ml) = Corrected sample vol. for MCA entry DFpass (ml)

DFpass ml (corrected vol)

2. Attach any printout to this form.

Reviewed By:

OSC Coordinator's Assistant (Print/Sign)

> VYOPF 3533.01 OP 3533 Rev. 6 Page 4 of 4

RV PASS SAMPLE ACCOUNTABILITY LOG Sample Location Volume of Original Identification (Update after each movement) Sample or Dilution Date Time Initials VYOPF 3533.02 OP 3533 Rev. 6 Page 1 of 1

APPENDIX A REACTOR COOLANT SAMPLING AND ANALYSIS - RB 303' SAMPLE SINK NOTES Although this procedure is Continuous Use, each Appendix may be used individually and the entire procedure Does Not need to be in hand.

The following procedure assumes the Reactor Building is accessible, otherwise utilize Appendix B to operate the PASS panel.

• Samples can be obtained from one of three points depending on what systems are in service. All sample points are at the Reactor Building sample sink. The sample points are:

Reactor Cleanup System Reactor Recirc Loop A RHR System CAUTION A maximum dose rate and dose commitment (review Tables 2 and

3) will be established for this sample prior to it being taken. Dose rates will be monitored during sampling and if it appears the dose commitment will be exceeded, the sampling will be terminated until further evaluation.

A. Sampling of the Reactor Cleanup System

1. Refer to OP 4612.

B. Sampling of the Reactor Water System (Recirc Loop)

1. Request the OSC to CLOSEIVERIFY CLOSED V10-199A & B.

2. Request the OSC to:

a. OPEN FCV-39 and FCV-40 isolation valves.

Appendix A OP 3533 Rev. 6 Page 1 of 3

APPENDIX A (Continued)

b. Notify Chemistry when valves are OPEN.

WARNING EXPECT THAT RADIATION LEVELS WILL INCREASE AT THE SAMPLE SINK DURING THE SAMPLE PURGING AND SAMPLING. DO NOT STAY AT THE SAMPLE SINK TO WAIT FOR THE SAMPLE LINES TO PURGE. SEEK A LOW RADIATION AREA IN WHICH TO WAIT.

3. OPEN RSS-44B and RSS-60.

4. Draw samples per Steps D, E and F below.

I I

5. Close RSS-44B and RSS-60.

C. Sampling of the RHR System (RB 303' Sample Sink)

1. Request the OSC to OPEN V10-198A or B.

2. OPEN RSS-160/161 (common switch at sample panel).

3. OPEN RSS-96.

4. Draw samples per Steps D, E and F below.

5. CLOSE RSS-96.

6. CLOSE RSS-160/161.

D. Sample lines must be purged prior to sampling to ensure a representative sample is taken.

If the sample lines have not been running, they must be purged for 30 minutes at a rate of about 500 ml/minute prior to obtaining the sample.

E. After the sample line is flushed, if a dissolved oxygen analysis is requested to be run, use a CHEMET or Orbisphere analyzer and run the analysis at the sample panel.

F. As dose rates permit, obtain about a 50 ml sample or less for further analysis in the Chemistry Lab.

Appendix A OP 3533 Rev. 6 Page 2 of 3

APPENDIX A (Continued)

G. Place the sample bottle in a carrier to maintain distance between you and the sample.

Proceed promptly to the Chemistry Lab.

H. Once at the Chemistry Lab, place the sample behind a shield, as necessary, to reduce exposure.

I. If a RHR System sample was taken, request the OSC to CLOSE root valve V10-198A or B which ever was opened in Step C.

I J. If a Recirc Loop sample was taken, request OSC to CLOSE FCV-39, FCV-40.

K. If a chloride analysis is required, use OP 0634 with a 1 ml sample volume diluted to 30 ml. (See A.2.b. to document dilution.)

I L. If a pH analysis is required, insert the probe into the sample bottle while the bottle is still behind the shield and read the pH.

M. If an isotopic analysis is required, perform serial dilutions on 1 ml of the sample until standard counting techniques can be used. Do not exceed 20% dead time. (See A.l.b. to document dilution.)

N. If a boron analysis is required, refer to OP 0630. Use a small sample volume, preferably 1 milliliter with dilutions as needed. Use ICP if available. (See A.2.b. to document dilution.)

0. Report all results to the OSC Coordinator.

P. Log all samples on VYOPF 3533.02 for accountability.

Appendix A OP 3533 Rev. 6 Page 3 of 3

APPENDIX B OPERATION OF THE PASS TO SAMPLE REACTOR COOLANT NOTE Although this procedure is Continuous Use, each Appendix may be used be in hand.

individually and the entire procedure Does Not need to WARNING FAILURE TO FOLLOW THESE PROCEDURES VERBATIM COULD RESULT IN DAMAGE TO THE SYSTEM OR PERSONNEL INJURY.

A. If the Gai-Tronics is unavailable, obtain a portable radio from the OSC.

B. Obtain the RV Post Accident Sample Kit from the Chemistry Lab.

C. Obtain a dose commitment from the OSC Coordinator for this sample prior to the start of sampling.

CAUTION Do not exceed 900 ml of dilution water.

D. Obtain the following from Chemistry supervision:

1. Dilution water volume (Enter here and on VYOPF 3533.01) ml

2. Information as to whether high noble gas activity is present.

HIGH / LOW (circle one here and on VYOPF 3533.01)

3. Request if a gas sample or gas stripping of the liquid sample is required.

4. PASS Diluted Liquid Sample volume desired:

ml Appendix B OP 3533 Rev. 6 Page 1 of 12

APPENDIX B (Continued)

E. Prerequisites for Sample Panel Set-Up

1. Perform the following:

a. Evacuate and label three off-gas vials; obtain one 2-dram vial and place in lead shield pig.

b. Obtain RV Pass Sample Kit.

CAUTION Breaker 11 on AC-DP-5 affects primary containment isolation (PCIV) valves PAS-102/104 (PASS SW-1) and valves PAS-101/103 (PASS SW-2). Failure to maintain positive control of the breaker while primary containment integrity is required by Technical Specifications (plant other than in cold shutdown) could violate LCO 3.7.A.2.

c. Request the OSC to:

1) CLOSE Breaker 11 on AC-DP-5 located in Turbine Building Switchgear Room.

2) POST an Operator at Breaker 11 while the breaker is closed.

3) Notify the OSC that PASS panel operation may affect calibrated jet pump flow indicator FI-2-3-87A/C at CRP 9-4 (jet pumps 1 and

11) from transmitter FT-2-3-63A/C.

d. Notify the OSC when you are ready to leave for sampling.

1) Verify with the OSC that the breaker is closed.

CAUTION If it appears maximum dose rate or dose commitment will be exceeded, leave high dose rate area and contact OSC Coordinator for further instructions.

2. Argon bottle is >500 psi with tank valve open.

Appendix B OP 3533 Rev. 6 Page 2 of 12

APPENDIX B (Continued)

3. CLOSE PAS-27.

4. Verify:

a. Valves PAS-17 and PAS-18 (3-way valves) are positioned with the arrow pointing to the left.

b. At the panel front, all other valves, with the exception of PAS-112, are in the CLOSED position.

c. IF dose rates permit, PAS-32 (rear of panel) OPEN.

d. IF dose rates permit, PAS-38 (rear of panel) CLOSED.

WARNING PAS-112 MUST BE LEFT OPEN EXCEPT WHEN SPECIFIED HEREIN TO PRECLUDE CROSS-CONNECTION OF THE DEMIN WATER SYSTEM WITH THE REACTOR VESSEL.

5. Install new rubber septa on sample valves PAS-39 and PAS-40.

CAUTION Do not exceed 900 ml of dilution water.

6. Place graduated cylinder under PAS-1 12 and OPERATE PAS-1 10 to obtain dilution water.

a. Fill the dilution water funnel with the recommended volume of demineralized water.

F. Sample Panel Operation Instruction

1. Evacuate cylinders B and C and gas septum.

a. START vacuum pump SW-5.

b. OPEN valves PAS-12, PAS-13, PAS-14 and PAS-15.

c. Run vacuum pump until approximately 0 psia reads on PI-2.

d. CLOSE valve PAS-13.

Appendix B OP 3533 Rev. 6 Page 3 of 12

APPENDIX B (Continued)

e. STOP vacuum pump SW-5.

f. Check PI-2 is stable to ensure no leaks.

g. CLOSE PAS-12 and PAS-14.

2. Obtaining a coolant sample in Cylinder A.

NOTES

• Obtain sample from Reactor Vessel by following instructions in Section a. below unless otherwise instructed.

To obtain sample from HP Heater, go to Section b. below.

a. Reactor Vessel Sampling (From JP-1 unless otherwise directed to sample JP-1 1)

1) OPEN SW-1 to open PAS-102/104 (inboard sample valves).

2) OPEN SW-2 to open PAS-101/103 (outboard sample valves).

3) OPEN SW-4 to open PAS-105/106 (purge valves).

CAUTION If there is no pressure indication on PI-1 when sampling, it's possible the line may be plugged. Obtain sample from other reactor sample point and observe pressure indication on PI-1.

4) OPEN valve PAS-2 (for JP-1) or valve PAS-3 (for JP-1 1).

5) OPEN valves PAS-5, PAS-6 and PAS-8 on panel.

Appendix B OP 3533 Rev. 6 Page 4 of 12

APPENDIX B (Continued)

6) THROTTLE valve PAS-7 on panel to initiate flow to approximately 20 gph. Monitor pressure on PI-I and flow on FI-109-36. Sample lines are now purging.

a) Record FI-109-36 flow:

_____gph CAUTION Retreat to low dose area during sample purge.

7) Perform the following calculation to determine purge time.

60 min 12 gallons (Purgetime in minutes) hr gal/hr(Flowrate on FI - 109 - 36)

8) After the line is purged:

a) CLOSE valves PAS-6 and PAS-5 to isolate sample cylinder A.

b) Record sample isolation time.

Time:

c) CLOSE SW-2, SW-1 and SW-4.

d) CLOSE valves PAS-2 or PAS-3.

e) CLOSE PAS-8.

Appendix B OP 3533 Rev. 6 Page 5 of 12

APPENDIX B (Continued)

9) Fill bath tank with cooling water via bath water funnel (takes approximately 6 liters):

a) Place cylinder under PAS-1 12 and, b) OPERATE PAS-1 10 to obtain demin water.

c) Add -6 liters of water to the water bath funnel.

10) Proceed to section F.3 ("Gas Strip the Liquid Sample").

b. High Pressure Feedwater Sampling CAUTION Sampling of the high pressure feedwater via the pass panel will probably cause solids to make flow indicator FI-109-36 inoperable.

Permission of Chemistry supervision is required to proceed with feedwater sampling.

1) OPEN SW-4 (purge valves).

2) OPEN valves PAS-1, PAS-5, PAS-6 and PAS-8.

CAUTION Keep pressure high to avoid flashing the sample. Monitor area dose rates.

3) THROTTLE valve PAS-7 on panel to initiate flow, monitor pressure on PI-1 and flow on FI-109-36. Sample lines are now purging.

a) Record FI-109-36 flow:

_ _ gph Appendix B OP 3533 Rev. 6 Page 6 of 12

APPENDIX B (Continued)

CAUTION Retreat to low dose area during purge.

4) Perform the following calculation to determine purge time.

60 min 60 mi= 12 gallons 2galn (Purgetime in minutes) hr gaI/hr(Flowrate on FI - 109 - 36)

5) After the line is purged:

a) CLOSE valves PAS-6 and PAS-5 to isolate sample Cylinder A.

b) Record sample isolation time.

Time:

c) CLOSE SW-4.

d) CLOSE valves PAS-1 and PAS-8.

6) Fill bath tank with approximately 6 liters of demin cooling water via the bath water funnel:

a) Place graduated cylinder under PAS-1 12 and, b) OPERATE PAS- 110 to obtain demin water.

c) Add -6 liters of water to the water bath funnel.

Appendix B OP 3533 Rev. 6 Page 7 of 12

APPENDIX B (Continued)

3. Gas Strip the Liquid Sample NOTE Gas stripping may be omitted if gas stripping or sampling is not required. If Step 3. is omitted, proceed to Step 4. to fill liquid grab sample assembly.

a. OPEN Valves PAS-10 and PAS-1 1 and observe pressure change on PI-2.

NOTE If pressure is >14.7 psi or if a high concentration of noble gases are assumed present, perform Step a.1) to use cylinders B and C; if pressure is <14.7 psi perform Step a.2) to use cylinder B. If cylinders used are a change from initial instructions from supervision, be sure to change VYOPF 3533.01 data to reflect the change.

1) If high concentration of noble gas is assumed present, or if PI-2 shows a positive pressure (>14.7 psi), then:

a) OPEN valve PAS-16.

CAUTION The following step requires Argon gas to be purged very slowly through the liquid sample.

b) While observing PI-2, operate valve PAS-26 to bring PI-2 to approximately 64 psi.

I c) CLOSE PAS-16.

Appendix B OP 3533 Rev. 6 Page 8 of 12

APPENDIX B (Continued)

NOTE This action will ensure good mixing of the internal volumes and will return the system to approximately one atmosphere (14.7 psia).

d) Open PAS-12 to re-expand Cylinder A and B into Cylinder C.

e) If the system is not at 14.7 psia, then OPEN PAS-16.

f) OPERATE PAS-26 and add argon until 14.7 psia is achieved.

g) CLOSE valves PAS-26 and PAS-16 and proceed to Step F.3.a.3) below.

2) If noble gas concentration is not significant or PI-2 remains in vacuum (<14.7 psi), then:

a) OPEN PAS-16.

b) OPERATE PAS-26 to very slowly purge argon gas through the sample and bring PI-2 up to one atmosphere (14.7 psia).

c) CLOSE PAS-16.

3) Perform the following:

a) OPEN valve PAS-14 and PAS-39 and extract 1 ml gas samples with a 11/2"syringe at the gas septum.

b) Inject each I ml sample into three separate pre-labeled 14 ml vials (e.g., #1, 2, 3) and place vials in shielded container.

4) CLOSE valves PAS-14, PAS-39, PAS-15, PAS-1 1 and PAS-10.

5) If sample was gas stripped (Step 3.a.1)), CLOSE PAS-12.

Appendix B OP 3533 Rev. 6 Page 9 of 12

APPENDIX B (Continued)

6) Return to Chemistry Lab with gas sample or continue with sampling.

7) Enter sample data on VYOPF 3533.02 for accountability of samples.

4. Fill liquid grab sample assembly.

a. OPEN/CHECK OPEN PAS-1 1, PAS-10 and PAS-15.

b. OPEN PAS-16.

c. OPERATE PAS-26 to achieve 64 psi on pressure gauge PI-2.

d. CLOSE PAS-16.

e. OPEN PAS-21.

f. POSITION PAS-18 with the arrow to the RIGHT for 30 seconds, then POSITION PAS-18 with the arrow to the LEFT.

g. CLOSE PAS-21.

h. OPEN PAS-19 and PAS-16. Note slight pressure drop on PI-2.

i. Allow one minute before proceeding for the grab sample assembly to fill.

j. POSITION PAS-17 and PAS-18 to their mid positions (ARROW DOWN).

k. POSITION the grab sample assembly valves PAS-17 and PAS-18 to the RIGHT.

1. OPEN SW-4.

m. OPEN PAS-8.

n. OPEN PAS-6, PAS-7 and PAS-12 to vent the pressure in Cylinders A, B, and C to the Torus.

o. When the pressure has equalized as indicated on PI-2, CLOSE PAS-6, PAS-7, PAS-8, PAS-10, PAS-11, PAS-12, PAS-16, PAS-19, and PAS-15.

Appendix B OP 3533 Rev. 6 Page 10 of 12

APPENDIX B (Continued)

p. CLOSE SW-4.

q. Request the OSC to OPEN Breaker 11.

5. Dilute sample and remove for analysis.

CAUTION I The following drain-down step may take approximately 5 minutes to occur. During this evolution, retreat to a low dose area to reduce exposure.

a. OPEN valves PAS-21 and PAS-24. Allow the dilution water funnel to drain for 1 minute after water is no longer visible in the funnel.

b. CLOSE valve PAS-24.

NOTE This action will blow argon gas into the line and push all the water into Cylinder D. Read Steps 5.c through 5.f BEFORE PROCEEDING.

c. CRACK OPEN valve PAS-25 approximately 1/4 turn.

I

d. Allow the argon gas to bubble slowly through Cylinder D for approximately 30 seconds.

e. SLOWLY CLOSE valve PAS-21 and pressurize Cylinder D with argon to approximately 5 psig on PI-3.

AND IMMEDIATELY

f. CLOSE valve PAS-25.

g. OPEN valves PAS-8, PAS-22 and PAS-20.

Appendix B OP 3533 Rev. 6 Page 11 of 12

APPENDIX B (Continued)

CAUTION

• In the following step PAS-23 should be opened only long enough to verify sample flow and ensure that sample is at the sample valves. If the inside edge of tygon tubing is not visible, then it has water in it. Do not allow sample to run out.

This action will allow the diluted sample to flow from Cylinder D through the liquid septum.

Be aware of area dose rate changes.

h. OPEN valve PAS-23 and observe sample flow at liquid septun/sightglass.

Use flashlight if needed.

I

i. As soon as flow has been observed, CLOSE PAS-23.

j. OPEN valve PAS-21 to release any remaining argon overpressure on PI-3.

I

k. To obtain a sample:

1) OPERATE sample valve PAS-40 to extract a liquid sample with a syringe (<5 ml) or,

2) OPERATE valve PAS-35 for larger volumes.

1. Place appropriate samples in lead shielding and transport to the Chemistry Lab for analysis.

1) Enter sample information on VYOPF 3533.02 to ensure accountability.

Appendix B OP 3533 Rev. 6 Page 12 of 12

APPENDIX C FLUSHING AND RESTORING THE PASS FOLLOWING USE I NOTES Although this procedure is Continuous Use, each Appendix may be used individually and the entire procedure Does Not need to be in hand.

This Appendix assumes the PASS Panel is configured as-left at the completion of Appendix B.

CAUTION Breaker 11 on AC-DP-5 affects primary containment isolation (PCIV) valves PAS-102/104 (PASS SW-1) and valves PAS-101/103 (PASS SW-2). Failure to maintain positive control of the breaker while primary containment integrity is required by Technical Specifications (plant other than in cold shutdown) could violate LCO 3.7.A.2.

A. Request the OSC to:

1. CLOSE Breaker 11 on AC-DP-5 located in the Switchgear Room.

2. POST an Operator at Breaker 11 while the breaker is energized.

B. CLOSE or check closed valves PAS-21, PAS-22, and PAS-35 or PAS-40.

C. To repressurize and drain Cylinder D, perform the following:

1. OPEN SW-4.

2. OPERATE valve PAS-25 until PI-3 reads approximately 25 psig.

3. OPEN valves PAS-23 and PAS-22.

Appendix C OP 3533 Rev. 6 Page 1 of 5

APPENDIX C (Continued)

"I 1NOTE Use a flashlight to facilitate sightglass view of water flow.

4. When flow has ceased through the sightglass, then CLOSE valves PAS-23 and PAS-22.

5. Repeat Steps 2 through 4 until no more liquid remains in Cylinder D.

D. OPERATE PAS-1 10 to obtain 900 ml of water from PAS-1 12.

E. Fill the dilution water funnel with 900 ml of water.

F. OPEN valves PAS-21 and PAS-24.

G. Allow the flush water in the funnel to gravity drain into Cylinder D for 1 minute after it is no longer visible in the funnel.

H. CLOSE valves PAS-24 and PAS-21.

I. CRACK OPEN valve PAS-25 to allow Cylinder D to pressurize to 25 psig on PI-3.

J. CLOSE valve PAS-25.

K. OPEN valve PAS-23 and PAS-22 to allow Cylinder D to drain.

L. CLOSE valves PAS-22 and PAS-23.

M. Repeat Steps I through L a minimum of 3 times to ensure that no liquid remains in Cylinder D.

N. CYCLE PAS-21 open and closed to bleed off any residual pressure indicated on PI-3.

0. POSITION grab sample valves PAS-17 and PAS-18 so that the arrow points to the LEFT.

Appendix C OP 3533 Rev. 6 Page 2 of 5

APPENDIX C (Continued)

CAUTION Ensure that the inboard sample valve SW-1 remains closed for the following operation (steps P-U).

P. OPEN SW-2 and SW-3 (outboard sample and flush valves).

Q. CLOSE valves PAS-1 12 and PAS-20.

R. OPEN valves PAS-110, PAS-111.

S. OPEN PAS-2 (JP-1) or PAS-3 (JP-11).

T. OPEN PAS-5, PAS-6.

U. THROTTLE PAS-7 while MONITORING FI-109-36 (do not exceed 25 gph).

V. After 5 minutes, CLOSE valves PAS-2 or PAS-3.

W. CLOSEPAS-111.

X. CLOSE SW-3 and SW-2.

CAUTION For steps Y and FF below, throttle PAS-7 so as not to exceed 25 gph on FI-109-36.

Y. CLOSE PAS-7.

Z. OPEN valves PAS-4, PAS-16 and PAS-19.

AA. THROTTLE PAS-20 to achieve 15 gph on FI-109-36.

BB. THROTTLE PAS-7 to achieve 25 gph on FI-109-36.

CC. After 1 minute, CLOSE valve PAS-16.

DD. FULLY OPEN PAS-20.

Appendix C OP 3533 Rev. 6 Page 3 of 5

APPENDIX C (Continued)

EE. THROTTLE PAS-7 as needed to maintain 25 gph on FI-109-36.

FF. After 5 minutes, CLOSE valves PAS-4, PAS-5, PAS-6 and PAS-7.

GG. OPEN PAS-26 to blow water out of the grab sample assembly.

HH. After approximately 30 seconds, CLOSE valves PAS-26, PAS-19, PAS-20 and PAS-8.

II. CLOSE SW-4.

JJ. OPEN valves PAS-1 1, PAS-12, PAS-13, PAS-14 and PAS-15.

KK. Turn SW-5 ON to start vacuum pump to evacuate Cylinders B and C.

LL. Remove gas septum port, OPEN valve PAS-39 and allow air to enter the evacuated systems for 1 minute as vacuum pump is running.

MM. Turn SW-5 OFF to stop vacuum pump.

NN. CLOSE valve PAS-39 and reinstall gas septum cover.

00. CLOSE valves PAS-11, PAS-12, PAS-13, PAS-14 and PAS-15.

PP. OPEN valve PAS-27 to allow bath water to gravity drain.

QQ. CLOSE PAS-110.

RR. OPEN PAS-1 12.

Appendix C OP 3533 Rev. 6 Page 4 of 5

APPENDIX C (Continued)

NOTE The Reactor Coolant Sampling Panel is now lined up to repeat sampling procedure as necessary.

WARNING ENSURE THAT RADIATION LEVELS ALLOW FOR PERSONNEL ACCESS BEHIND THE PASS PANEL AND LIQUID RADIATION LEVELS ALLOW FOR PERFORMING THE NEXT STEP. MONITOR DOSE RATES DURING MOISTURE SEPARATOR DRAINING.

SS. OPEN valve PAS-38 and drain water from the vacuum pump moisture separator into a suitable container.

TT. CLOSE PAS-38.

UU. Request the OSC to OPEN Breaker 11 on AC-DP-5.

VV. CLOSE argon tank valve.

Appendix C OP 3533 Rev. 6 Page 5 of 5

APPENDIX D PASS SAMPLE ANALYSIS I NOTES Although this procedure is Continuous Use, each Appendix may be used individually and the entire procedure Does Not need to be in hand.

• Utilize VYOPF 3533.02 to track samples and any aliquots made for analysis.

A. Gas samples NOTE Perform hydrogen and oxygen analysis on the gas chromatograph according to DP 0647.

I

1. Adjust vial pressure to zero by injecting approximately 13 ml of the appropriate GC carrier gas into each vial collected.

I

2. Hydrogen and oxygen analyses will be performed as requested by following the gas chromatograph procedure in DP 0647.

a. Complete VYOPF 3533.01, Section .13 and I.C.

3. Isotopic analysis

a. Obtain 1 ml of sample from a gas sample vial from A. 1. above I

and inject into an evacuated 14 ml vial.

b. Analyze gas vial as a general sample using DP 2631 or steps outlined in Section C (High Activity) using sample volume from VYOPF 3533.01, Step I.D. Up to 20% dead time is allowed.

Appendix D OP 3533 Rev. 6 Page 1 of 5

APPENDIX D (Continued)

B. Liquid samples

1. Chloride analysis

a. Analyze sample for chloride content per OP 0634.

b. Complete VYOPF 3533.01,Section II.B.

2. Boron analysis

a. Analyze sample for Boron using the Lab ICP using the "50B" method file per OP 2630 or by titration per DP 0630.

I

b. Complete VYOPF 3533.01,Section II.C.

3. Isotopic analysis

a. Using a syringe (shielded if high dose rates exist), obtain 1 ml of sample (more may be used if dose rates allow) and inject into a known geometry container. Fill container with DI water. Record aliquot volume on VYOPF 3533.01,Section II.

b. Analyze liquid sample as a general sample per DP 2631 or steps outlined in Section C to obtain activity in iiCi/ml using corrected sample volume from VYOPF 3533.01, Step II.D. Up to 20% dead time is allowed.

c. Complete VYOPF 3533.01,Section II.D.

Appendix D OP 3533 Rev. 6 Page 2 of 5

APPENDIX D (Continued)

C. Counting Techniques for Highly Radioactive Samples NOTE If sample size or dilutions can be used to pennit a sample to be counted by conventional techniques, this should be done. If this is not possible, the following techniques can be used.

1. Use of the MCA at extended distances.

NOTE If general area dose rate in the Counting Room exceeds 5 mR/hr, the use of the MCA at extended distance with shield top removed is prohibited (LAI-417B).

a. Open the shield top from the 10% germanium detector.

b. Using rod and holder, suspend the sample above the detector at a distance that will give a dead time of <20% (must be >1 ft.).

c. Measure the distance from the sample to the top of the detector.

d. Count the sample using a 2" filter paper geometry efficiency.

NOTE Step e. or f. below may be used to calculate elevated sample activity.

e. Analyze the sample using the MCA selection for "PASS Elevated Samples" OR

f. Calculate the sample activity as follows:

piCi/ml = (X) (d2 ) (17)

Appendix D OP 3533 Rev. 6 Page 3 of 5

APPENDIX D (Continued)

NOTE The below correction factor must be re-evaluated if the detector geometry for the filter paper with a 2" shelf is modified at the time the

-efficiency calibration (DP 2631) is performed.

where: X = g.Ci/ml from isotopic printout d = distance in ft. measured in B.l.c above 17 = correction factor gCi/ml Verified by:

2. Use of portable instruments.

NOTE If neither conventional methods or those in Step C.1 can be used, a portable gamma survey meter can be used to determine sample activities.

a. If the MCA is available, it can be used to give a qualitative measure of major isotopes. If it is not available, an assumption must be made based on what is known about the sample at the time.

b. Measure the radiation level of the sample at 1 meter.

Appendix D OP 3533 Rev. 6 Page 4 of 5

APPENDIX D (Continued)

c. Calculate the sample activity as follows:

6

.Ci/ml = (R/hr at I meter)(10 )

(T) (V)

Verified by:

where: 106 = gCi/Ci V = sample volume (milliliters)

T = R/hr @ 1 meter/Ci Values for T (R/hr @ 1 meter/Ci)

Time Degassed Liquid* Containment Air**

1 hr 0.60 0.41 4 hr 0.43 0.28 8 hr 0.35 0.22 12 hr 0.31 0.18 24 hr 0.26 0.14 Assumed mix of 0% of core noble gas inventory, 50% of core halogen inventory and 1% of core solids inventory. For convenience, the mix ratio is expressed as 00/50/1 (% NOBLE GAS/% HALOGENS/% SOLIDS)

• • Assumed mix of 100/50/1.

-- 1 Appendix D OP 3533 Rev. 6 Page 5 of 5

TABLE 1 VY - RADIOACTIVITY CONCENTRATION ([tCi/g) IN REACTOR COOLANT BASED ON DESIGN BASIS SOURCE TERM (100/50/1)

Nuclide 1 Hour 8 Hours 24 Hours Kr-85m 6.5E+04 2.2E+04 1.8E+03 Kr-85 2.5E+03 2.5E+03 2.5E+03 Kr-87 8.5E+04 1.9E+03 3.1E-01 Kr-88 1.6E+05 2.9E+04 5.8E+02 Xe-133 5.3E+05 5.3E+05 5.1E+05 Xe-135m 7.5E+04 3.5E+04 6.6E+03 Xe-135 1.9E+05 2.4E+05 1.3E+05 1-131 1.3E+05 1.3E+05 1.2E+05 1-132 1.9E+05 1.8E+05 1.6E+05 1-133 2.7E+05 2.1E+05 1.3E+05 1-134 2.1E+05 1.8E+03 6.9E-03 1-135 2.3E+05 1.1E+05 2.1E+04 Sr-90 1.9E+02 1.9E+02 1.9E+02 Sr-91 3.2E+03 1.9E+03 5.9E+02 Sr-92 2.8E+03 4.7E+02 7.9E+00 Y-91 3.5E+03 3.5E+03 3.5E+03 Y-93 4.OE+03 2.5E+03 8.2E+02 Zr-95 4.6E+03 4.5E+03 4.5E+03 Nb-97 4.5E+03 3.5E+03 1.7E+03 Ru-103 3.9E+03 3.8E+03 3.8E+03 Cs-134 2.6E+02 2.6E+02 2.6E+02 Cs-136 9.3E+01 9.1E+01 8.8E+01 Cs-137 2.6E+02 2.6E+02 2.6E+02 Ba-140 4.7E+03 4.7E+03 4.5E+03 La-140 4.9E+03 4.9E+03 4.8E+03 Ce-141 4.5E+03 4.5E+03 4.4E+03 Ce-143 4.1E+03 3.6E+03 2.6E+03 Eu-156 2.4E+02 2.4E+02 2.3E+02 Table 1 OP 3533 Rev. 6 Page 1 of 2

TABLE 1 (Continued)

Nuclide 1 Hour 8 Hours 24 Hours 4.1E+02 3.7E+02 3.OE+02

,* Np-238

5. 1E+04 4.7E+04 3.9E+04 Np-239 2.2E+06 1.6E+06 1.1E+06 TOTAL (above) 2.4E+06 1.6E+06 1.2E+06 TOTAL (including others)

Assumptions and

References:

1. Design Basis Source Term 100% NG, 50% lodines and 1% Solids.

2. ORIGEN2 Calculation (VY Core Damage Assessment Methodology).

3. NSSS isolated liquid mass = 1.615E+08 g (VY Core Damage Assessment Methodology).

Table 1 OP 3533 Rev. 6 Page 2 of 2

- 1 TABLE 2 3

VY - RADIOACTIVITY CONCENTRATION ([tCi/cim ) IN CONTAINMENT ATMOSPHERE AFTER SHUTDOWN BASED ON DESIGN BASIS SOURCE TERM (100/25/0)

Nuclide 1 Hour 8 Hours 24 Hours Kr-85m 1.6E+03 5.3E+02 4.4E+01 Kr-85 5.9E+01 5.9E+01 5.9E+01 Kr-87 2.OE+03 4.5E+01 7.3E-03 Kr-88 3.8E+03 6.9E+02 1.4E+01 Xe-133 1.3E+04 1.3E+04 1.2E+04 1.8E+03 8.4E+02 1.6E+02 Xe-135m Xe-135 4.5E+03 5.7E+03 3.2E+03 1-131 1.6E+03 1.5E+03 1.5E+03 1-132 2.3E+03 2.2E+03 1.9E+03 1-133 3.2E+03 2.6E+03 1.5E+03 1-134 2.5E+03 2.2E+01 8.2E-05 1-135 2.7E+03 1.3E+03 2.5E+02 3.9E+04 2.8E+04 2.1E+04 TOTAL (above)

Assumptions and

References:

1. ORIGEN2 Calculation (Core Damage Assessment Methodology).

2. Containment Air Volume = 6.742E+09cm 3 (Core Damage Assessment Methodology).

3. Design Basis Source Term: 100% NG and 25% Iodines.

Table 2 OP 3533 Rev. 6 Page 1 of 1

TABLE 3 VY - DOSE RATES (R/hr) AT DIFFERENT SAMPLING STATIONS AT DIFFERENT TIMES AFTER SHUTDOWNc Post-Accident Containment Air Vent Stack Sampling Station Sampling Station Sampling Room Time (hr) 4.5E-1a 6.OE+Oa I.0E+0b 1

1.9E-1 2.6E+0 5.1E-1 3

5.4E-02 1.1E+0 2.2E-1 8

6.8E-03 4.7E-1 5.8E-02 24 4.1E-03 3.1E-1 1.8E-02 72 NOTES:

a Per Calculation VYC-70.

b Per Calculation VYC-83, Vent Stack Only.

C Dose Rates at other decay times are based on Table 11 of EDS Nuclear, Report No. 02-0180-1126, December 29, 1979.

Table 3 OP 3533 Rev. 6 Page 1 of 1

TABLE 4 VY - REACTOR c(bLANT AND CONTAINMENT AIR SAMPLES AT DIFFERENT TIMES AFTER SHUTDOWNa DOSE RATES (R/hr) lcm3 Dissolved Gas From lcm lcm3 Undiluted lcm3 Undiluted Degassed Pressurized Reactor Coolant Containment Air Sample Time (hr) Reactor Coolant 8.9E-1b 1.6E-02b 1 2 .0E+0b 3.9E-1 7.OE-03 3 1.2E+O 1.6E-1 2.9E-03 8 6.4E-1 6.9E-02 1.3E-03 24 3.2E-1 4.6E-02 8.3E-04 72 1.5E-1 NOTES:

a All dose rates are calculated at lm away from the source. Dose rates at other decay times are based on Table 11 of EDS Nuclear, Report No. 02-0180-1026, December 29, 1979.

b Per VYC-70, no shielding, no dilution.

Table 4 OP 3533 Rev. 6 Page 1 of 1

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

I I - '

A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibilities YES (N (2) Assignment of on-shift Emergency Response Organization personnel/5-:

YES (QW (3) Arrangements for Emergency Response Support and Resources YES 0 (4) Emergency Classification and Action levels, including facility system and effluent parameters YES (5) Notification Methods and Procedures YES (6) Emergency Communications among principal response organizations the public YESN (7) Public Education and Information YES (8) Adequacy of Emergency Facilities and Equipment methods, systems and equipmYES (9) Adequacy of Accident Assessment YE NO actions 74 NO (10) Plume exposure pathway EPZ protective YES (11) Emergency Worker Radiological Exposure Control injured individuals (12) Medical Services for contaminated YES (13) Recovery and Reentry Plans YES NO (14) Emergency response periodic drills and exercises YES 0 (15) Radiological Emergency Response Training YES 0 (16) Plan development, review and distribution YES VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. 10.E06.171

10 CFR 50.54(q) Evaluation Checklist (Continued)

2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization Y NO (2) Section IV. B - Assessment Actions of Emergency Organizations (3) Section IV. C - Activation YES YES (4) Section IV. D - Notification Procedures and Equipment (5) Section IV. E - Emergency Facilities YES f0O (6) Section IV. F - Training YES (7) Section IV. G - Maintaining Emergency Preparedness YES (

(8) Section IV. H - Recovery YES 0 B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For applicable item 10 CFR 50, qe'on above, this change (DOES/DOES NOT) decrease the effectiveness of the Emergency Plan and (DOES/DOES NOT) continue to meet the stated applicable standard or requirement.

BASIS FOR ANSWER:UCAYW

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d1%hchnCD~q -Q~ ULQN4W00 LA VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54 (q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

G The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

[o The changes made do decrease the effectiveness of the Emdrgency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

O Revise proposed changes to meet applicable standards and requirements.

EO Cancel the proposed changes.

o Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search:_

lThis change does not affect any other documents.

[o This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search:

Additional Comments:

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Prepared By: ,f~Oa MI(rsint/*ign) , ate: 2/O2 Reviewed By: (Printl i -4 Date: qj D (Emergency Plan Coo inator)(Print/ gn)

VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3