ML20133J605

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Responds to Request for Addl Info Re 850115 Application to Amend License DPR-28 Concerning Calculation of Offsite Dose from Radioactivity Released Prior to Purge Valve Closure During LOCA
ML20133J605
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/02/1985
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To: Vassallo D
Office of Nuclear Reactor Regulation
References
FVY-85-70, NUDOCS 8508120075
Download: ML20133J605 (2)


Text

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VERMONT YANKEE NUCLEAR POWER CORPORATION RD 5. Box 169, Ferry Road. Brattleboro, VT 05301

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. y ENGINEERING OFFICE 1871 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701 TELEPHONE 617-672-6100 August 2, 1985 FVY 85-70 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Office of Nuclear Reactor Regulation Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter, VYNPC to USNRC, FVY 85-05, dated January 15, 1985,

" Request for License Amendment-Operation of Purge and Vent Valves"

Subject:

Response to Request for Additional Information Concerning Operation of Purge and Vent Valve License Amendment Request

Dear Sir:

By letter dated January 15, 1985 [ Reference (b)], Vermont Yankee submitted a license amendment request in response to the NRC's request to provide an iodine peak or spike limit for the reactor coolant concentration to assure that the radiological consequences of a postulated loss-of-coolant accident, while purging, are within 10CFR Part 100 dose guidelines. In response to the recent request by Mr. Larry Bell of your staff for information concerning the major assumptions used by Vermont Yankee in calculating the off-site dose from radioactivity released prior to purge valve closure during a loss-of-coolant accident, we provide the following:

1.

The iodine coolant concentration is equal to 4.0 pCi/ gram 2.

A factor of 0.5 was used for iodine removal; 3.

The mass of primary coolant (steam) released through the 18" purge valve is equal to 2,400 lbm, and assumes critical (choked) flow at maximum LOCA pressure and full-open flow area until the valve is completely closed (valve clasure time is 10.5 seconds);

4.

Cround level release with no filtration (assumes that a rapid pressure surgo destroys piping downstream of the safety isolation valve).

8508120075 G50002 0

PDR ADOCK 05000271 1

P PDR l

e' United States Nuclear Regulatory Consission Au5ust 2, 1985 Attention:

Mr. Domenic B. Vassnllo Page 2 We trust that this information is sufficient to allow for the completion of your review and subsequent issuance of the subject license amendment; however, should you have further questions or require additional information, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION d

R. W. Capstick Licensing Engineer RWC/nat

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