ML19309G408
| ML19309G408 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/01/1980 |
| From: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 WYR-80-47, NUDOCS 8005060260 | |
| Download: ML19309G408 (3) | |
Text
's sou oso MC s
Telephone 617 366-90\\1 t
760-390 0739 YANKEE ATOMIC ELECTRIC COMPANY B.3.2.1 WYR 80-47 W,
20 Turnpuke Road Westborough, Massachusetts 01581
.YAN KEE May 1, 1980 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Division of Licensing Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5
Reference:
(a) License No. JPR-3 (Docket No. 50-29)
(b) YAEC Letter to USNRC, dated April 9, 1980, WYR 80-43 (c) USNRC Letter to YAEC dated April 18, 1980
Subject:
TMI Category "A" Item 2.1.8a - Post-Accident Sampling
Dear Sir:
In Reference (b), we committed to provide a conceptual design description for reactor coolant and containment atmosphere monitoring in order to meet the Category "B" requirements for this item. The attached descriptions and sketch provide that information.
We trust this information is satisfactory, however, if you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY J
J. A. Kay Senior Engineer - Licensing JAK/kaf Attachment i
T 8
Attachment 2.1.8.a.
Post-Accident Sampling Capability A.
Containment Atmosphere Sample The containment air sampling station is at the hydrogen analyzer which is located in the switch gear room.
A sampling device is installed at the containment air sampling station.
Procedures for obtaining and analyzing containment air samples have been revised to include instructions for a sample of high activity concentration.
No further modifications are necessary.
B.
Reactor Coolant Sample A proposed reactor coolant sampling system, a dilution unit, has been developed by Yankee staff engineers.
The proposed system will provide the following capabilities:
(1)
Manual operation from the front side of a shield wall with the unit on the back side (2)
Obtaining a pressurized or unpressurized reactor coolant sample at reactor coolant pressure and temperature (3)
Depressurizing the reactor coolant sample (4)
Diluting the dissolved gas sample and degassed liquid sample (5)
Obtaining dissolved gas sample and liquid sample with syringe Af ter the samples are taken from the sampling system, samples would be transported to the on-site Laboratory for the following analyses:
isotopic ano boron analysis on the liquid sample; isotopic and total dissolved gas concentration analysis on the dissolved gas sample.
A diagram of the proposed dilution unit is attached.
Additional modifications could be required as a result of prototype testing.
The plant shielding review in Section 2.1.6b of Reference (b) concluded that most on-site tsiidings would be uninhabitable for several days after the accident. The overall plant shielding requirements have not been determined and will depend on the results of further review and/or analysis which has been deferred to the SEP per Reference (c). The installation of the reactor coolant sampling system will depend on these results and therefore will be included in the SEP review.
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