ML19323C552

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Forwards Conceptual Design Description of Reactor Coolant & Containment Atmosphere Monitoring Per NUREG-0578,Category a, Item 2.1.8a Requirements Re post-accident Sampling
ML19323C552
Person / Time
Site: Maine Yankee
Issue date: 05/07/1980
From: Groce R
Maine Yankee
To: Clark R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 WMY-80-74, NUDOCS 8005160314
Download: ML19323C552 (3)


Text

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so05100 3/9 MAIRE HARHEE

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ENGINEERING OFFICE WESTBOR O, MASSACHUS ETTS 01501 f

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617-366-9011 B.3.2.1 May 7, 1980 hNY 80-74 United States Muclear Regulatory Commission Washington, D.C.

20555 Attention: Division of Licensing Mr. Robert A. Clark Operating Projects Branch 83

Reference:

(a) License No. DPR-36 (Docket No. 50-309)

(b) MYAPC Letter to USNRC, dated March 5, 1980, WMY 80-39 (c) USNRC Letter to MYAPC, dated April 28, 1980

Subject:

TMI Category "A" Item 2.1.8a rost-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.

4 Very truly yours, MAINE YANKES A'IOMIC POWER COMPANY Robert H. Groce Senior Engineer - Licensing RHG/kaf Attachment i

e MY--NUREG,578 2.1.8a.

Post-Accident Sampling Capability A.

Containment Atmosphere Sample The containment air sempling station is at the hydrogen analyzer which is located in the Primary luxiliary Building at Elevation-21'. A sampling device has been installed at the containment air sampling station.

Pro-cedures of obtaining and analyzing containment air sample were revised to include instructiona for a sample of high activity concentration.

B.

Reactor Coolant Sample A proposed reactor coolant sampling system, a dilution unit, has been developed by Yankee staff engineers. The proposed system would provide the following capabilities:

(1) Manual operation from the front side of a shield wall with unit on the back side (2) Obtaining a pressurized or unpressurized r'eactor coolant sample at the 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 After the samples are taken from the sampling system, samples would be transported to the on-site Laboratory for the following analyses:

isotopic i

and 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. The dilution unit is subject to modification during the testing of the prototype unit. The modified sampling system will be installed and operational by January 1, 1981.

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