ML19211A283

Requests That 791130 Ltr Be Placed on Docket as Response to NRC 791002 & 30 Ltrs Re Acceptance Criteria for Mark I Containment Program

ML19211A283
Person / Time
Site:	Vermont Yankee
Issue date:	12/13/1979
From:	Rich Smith VERMONT YANKEE NUCLEAR POWER CORP.
To:	Office of Nuclear Reactor Regulation
References
WVY-79-141, NUDOCS 7912170310
Download: ML19211A283 (2)

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VERMONT YAN KEE NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET RUTLAND, VERMONT 05701 REPLY TO:

ENGINEERING OFFICE TURNPIKE RO AD WESTDORO. M ASS ACHUSETTS 01581 TELEPHONE 417-366-9011 IMS B.3.2.1 WVY 79 141 December 13, 1979 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Office of Nuclear Reactor Regulation

References:

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

(b) Letter L. J. Sobon (GE) to D. G. Eisenhut (USNRC)

MFN 289-79 dated November 30, 1979.

(c) Letter D. G. Eisenhut (USNRC) to All Boiling Water Reactor Licensees dated October 2, 1979 " Confirmatory Requirements Relating to Condensation Oscillation Loads for the Mark I Containment Long Term Program."

(d) Letter to D. G. Eisenhut (USNRC) to R. H. Groce (YAEC) dated October 31,1979 " Acceptance Criteria for the Mark I Long Term Program."

Subject:

Mark I Containment Program - NRC Acceptance Criteria for the Mark I Program This letter is to request that the Reference (b) letter be placed on the Vermont Yankee docket as the response to References (c) and (d).

Reference (c) asked for additional testing in the Mark I Full Scale Test Facility for " Condensation Oscillation" loads. Vermont Yankee supports the Reference (b) commitment to do additional testing based on a desire to complete the Mark I Long Term Program.

Reference (d) asked for a schedule for the completion of the LTP plant-unique analysis. As Reference (b) states, a schedule cannot be produced until differences in the NRC acceptance criteria are resolved. In areas accepted by the Mark I Owners, analysis is now proceeding and several modifications are planned for the September 1980 outage.

1.592 238 7912170 3/O

United States Nuclear Regulatory Commission December 13, 1979 Attention: Office of Nuclear Reactor Regulation Page Two Additional areas not listed in Reference (b) may require exceptions from the present LDR Load Definitions. These will be discussed at a Mark I/NRC meeting in the future.

We trus t you will find this submittal satisf actory; however, should you desire additional information, feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION R. L. Smith Vermont Yankee Licensing Engineer RLS/nj 1592 239 O

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