ML20054K328
| ML20054K328 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/01/1982 |
| From: | Moody D YANKEE ATOMIC ELECTRIC CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20054K318 | List: |
| References | |
| FYR-82-55, NUDOCS 8207010430 | |
| Download: ML20054K328 (3) | |
Text
.
YANKEE ATOMIC ELECTRIC COTPANY
" " ^ " * ' -*'
- _ ~,
yh 1671 Worcester Road, Framingham, Man,<husetts 01701 2 C.2.1
,Yau x.,
rYR 82-55 se June 1, 1982 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Attention:
Mr. Ronald llaynes, Regional Administrator Office of Inspection and Enforcement
References:
(a)
Ilcense No. DPR-3 (Docket No. 50-29)
(b)
USNRC Letter to YAEC, dated February 25, 1982
Subject:
Response to Emergency Preparedness Appraisal Findings
Dear Sir:
Please te informed that the below-listed items [ Items (4), (5), and (8) of Reference (b)) have been completed. Appropriate procedures have been written or revised as necessary. Training in the use of these procedures is expected to be completed July 1, 1982.
Item (4) states:
1 Provide procedures for backup monitoring for the high range PVS noble gas monitor and the main steam line monitors in the event they become inoperable.
Compliance Action:
l Plant procedures, " Measurement of Radioactive Airborne Release Rates Under Accident Conditions," and, " Determination of Noble Gas Release Rates From The Main Steam Lines Under Accident Conditions," have been revised to include backup methods for evaluating noble gas release rates if the high range monitors become inoperable. These methods include the use of off-site survey teams responding to the plant upon notification.
Item (5) states:
Revise procedures containing description of Emergency Action Levels (EALs) to address the requirementsof NUREG-0654, Appendix 1.
Compliance Action:
Appropriate procedures have been revised to meet the requirements of NUREG-0654, Appendix 1 in accordance with NUREG-0818 as specified in the Emergency Preparedness Appraisal Findings.
8207010430 820625
{DRADOCK 05000029 PDR
United States Nuclear Regulatory Commission June 1, 1982 Attention:
Mr. Ronald Haynes Page 2 Item (8) states:
Provide a description of the method to be used for estimating radiofodine releases from the Primary Vent Stack (PVS) under major accident conditions.
Compliance Action:
The plant chemists and Radiation Protection Technicians will be trained to collect and analyze PVS effluent samples using a newly installed radiolodine sample system and the plant laboratory multichannel analyzer. This training is expected to be completed by. July 1, 1982. A description of the system and method of analysis is attached.
If you desire additional information, please contact us.
Very truly yours, YAh E ATOMIC ELECTRIC COMPANY Mit&Y v
rv
/
D
. Moody Manager of Operations DEM: dad Enclosure s
i l
l
\\
l l
l l
l l
l
,e v,.
RADI0 IODINE SAMPLING AND METHOD OF ANALYSIS - YANKEE ATOMIC
SUMMARY
A modular sampler was designed which selectively absorbs gaseous radioiodines in a chemical trapping solution. Aliquots of the solution may be periodically removed with a syringe for laboratory analysis for radiofodine concentration.
The concept of using alkaline sodium thiosulfate solution as an absorber for airborne iodines was developed by Duke Power. Testing by Duke Power has verified essentially 100% retention of volatized iodine in the absorber solution, even at high air flows.
DESCRIPTION:
The high range Primary Vent Stack (PVS) radiolodine sampler extracts an aliquot of air from the PVS normal range sampler sample line. The flow rate is approximately 1E-8 of the PVS flow rate. The air is bubbled through a 200ml solution of sodium thiosulfate, sodium hydroxide, and sodium iodide.
Iodine is converted to soluble, nonvolatile iodide.
Five cc's of trapping solution can be removed from the bubbler at any time by means of a syringe attached to, and an integral part of, the bubbler.
Sample volume is determined using an elapsed time timer and sample flow rate.
INSTALLATION:
The high range iodine sampler for the plant vent stack is located in the stack monitor room, adjacent to the plant vent stack. The sampler, when activated, extracts a slipstream of air form the inlet sample lines to the stack monitors, which operate continuously.
The high range iodine sampler for the reactor containment building atmosphere is. located in the switchgear room, a shielded location directly beneath the main control room.
The sampler draws a slipstream from a two inch pipe of the post-accident hydrogen vent system, which would have to be operated to get a representative sample to the iodine sampler.
METHOD OF ANALYSIS:
Sample analysis is performed in the radiochemistry lab using the lab computerized multichannel analyzer or it may be taken off site and analyzed in i
the Environmental ' Laboratory's mobile van multichannel analyzer.
,m-
,w
.