ML19320C410

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Provides Addl Info Per Commission Request Re Proposed Interim Hydrogen Control Requirements.Forwards Eight Listed Documents
ML19320C410
Person / Time
Issue date: 04/22/1980
From: Harold Denton
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19320C411 List:
References
TASK-IR, TASK-SE SECY-80-107A, NUDOCS 8007160786
Download: ML19320C410 (3)


Text

{{#Wiki_filter:y f~r (QE" g J fE* W UNITED STATES j F NUCLEAR REGULATORY COMMISSION j _ g April 22, 1980 WASHINGTON, D. C. 20555 SECY-80-107A 6 ,cb INFORMATION REPORT $n FOR: The Comissioners FROM: H. Denton, Director, Office of Nuclear Reactor Regulation M THRU: W. Dircks, Acting Executive Director for Operations

SUBJECT:

ADDITIONAL INFORMATION RE: PROPOSED INTERIM HYDROGEN CONTROL REQUIREMENTS l l

Purpose:

To provide the additional information requested by the Comission regarding the Proposed Interim Hydrogen Con-trol Requirements for Small Containments (SECY-80-107). Discussion: In SECY-80-107, Proposed Interim Hydrogen Control Require-ments for Small Containments, dated February 22, 1980, the staff reported its recommendation for certain interim hy-drogen control requirements for small containments on the basis of a review of the TMI-2 experience. Specifically, the staff recomended inerting of all Mark I and Mark II containments for boiling water reactors as an interim meas-ure pending a rulemaking proceeding on the subject of de-graded cores and hydrogen management. As a result of the March 19, 1980 meeting in the Comis-sion's Conference Room to discuss SECY-80-107, a memoran-dum was sent from S. Chilk to W. Dircks requesting that certain additional supporting information be provided to the Comission. The documents identified below are hereby provided in response to the Comissioners' request: (The numbering corresponds to that used in the Chilk memorandum.) 1.a The identity of the contractor who performed the calculations of containment capability to accomo-date hydrogen generation from metal-water reaction and a copy of the contractor's analisis. contains this information. Distribution: L

Contact:

W.~ Butler, CSB/ DSS Comissioners \\ 29499 Comission Staff Offices O 8 007160 -J'N8 C ^ $/$ c

= , ). g.= f ~ W-v '= r J9 The Comissioners The analysis was performed by Dr. L. F. 6-eimann of Ames Laboratory. A copy of the contrac.b.r'r analysis is enclosed. It is to be noted that the enclosed analysis is a preliminary one in a program designed to refine the ultimate strength characteristics of the Sequoyah/ McGuire type of containment. 1.b A list of all plants whose containment types fall within the Ollowing categories: Mark I, Mark II, Ic'e Condenser, Mark III, Subatmospheric, and Dry Containment. contains this information. 1.c A comparison of the experience with drywell en-tries for inerted Mark I plants with the informa-tion provided by representatives of the Vermont Yankee Nuclear Station, which is a non-inerted Mark I plant. contains this information. 2. The Comission also requested that the views of the General Electric Company on the utility of inerting, including any calculations which differ from those provided by the NRC staff, be provided in writing. is a copy of the April 8,1980 letter from Richard P. Denise to A. Phillip Bray of General Electric. This letter advises General Electric of the Comission's request and of the staff's planned response. It also acknowledges that General Electric is planning to submit its own letter to the Comission on this subject. Enclosures 5 through 8 contain the following docu-ments which the staft believes to represent the General Electric views on the subject of inerting. , contains copies of the vu-graphs used in the General Electric presentation on October 12, 1979 to Dr. Mattson on the. subject of "TMI Evalu-ation Effort-Review of BWR Hyr~rogen. Accomodation ~ Capability;"

Q'"$5,' f.: .~ w- = .) I h 3-The Comissioners Id - contains copies of the vu-graphs used in the General Electric presentation to the Comission on March 19, 1980 entitled, "The BWR Perspective on Interim Hydrogen Control Measures;" ' is a copy of the 3eneral Electric letter of August 3,1979 from Mr. Sherwood to Mr. Denton, "Inerting Mark I and II Containment;" and is a copy of the General Electric letter of March 7,1980 from Mr. Bray to Chairman Ahearne, "BWR Mark I and II Containment Inerting." The other items requested by the commission (Items 1.d and 1.e in the Chilk memoran'dum) are being prepared and will be e provided in about two weeks. 4f k e i'arold R. Denton, Director

  1. /d' Office of Nuclear Reactor Regulation I

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/ UNITED sTAOS 8-NUCLEAR REGULATORY COMMISSION o gg j: ; wAsamcToN, c. c.20ssa Q..O R. f APR 8 1980 A. Phillip Bray Vice President and General Manager General Electric Company Nuclear Power Systems Division 175 Curtner Avenue San Jose, CA 95125

Dear Sir:

The Comission has requested that the views of the General Electric Company (GE) on the utility of inerting, including any calculations which differ from those provided by the NRC staff, in staff memo SECY-80-107 " Proposed Interim Hydrogen Control Requirements for Sciall Containments" - February 22, 1980, be provided in writing. As our response to this request, we plan to provide the Comission with: a) copies of the vu-graphs used in the GE pre-sentation on October 12, 1979 to Dr. Mattson on the subject of "TMI Evalua-tion Effort-Review of BWR Hydrogen Accomodation Capability;" b) copies of the vu-graphs used in the GE presentation to the Comission on March 19, 1980 entitled, "The BWR Perspective on Interim Hydrogen Control Measures;" c) a copy of Mr. Sherwood's letter of August 3,1979 to Mr. Denton, - Sub-ject "Inerting Mark I and II Containment;" and d) a copy of your letter of March 7,1980 to Chainnan Ahearne, Subject "BWR Mark I and II Contain-ment Inerting." We are not aware of any fundamental disagreement between the results of your calculations of hydrogen concentrations and the results of hydrogen combus-tion in an uninerted BWR containment building, although there are some minor differences in calculated values which reflect minor differences in input as-sumptions. Ve expect to transmit this information to the Comission on or about April 8,1980. We understand that you are currently preparing a document that articulate the GE views on this subject and that you plan to transmit it to the Comissior, on or about April 11, 1980. Should you wish to discuss this further with members of the staff, please con-ttct Dr. Walter Butler, Chief of the Containment Systems Branch. His phone number is 301-492-9412. Thank you for your cooperation. Sincerely, 7 1 e M b\\ Richard P. enise, Acting Assistant Director for Reactor Safety Division of Systems Safety [I Y EHCLOSLRE 4 ._}}