ML20052H852
| ML20052H852 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/12/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8205240075 | |
| Download: ML20052H852 (2) | |
Text
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MEMORANDUM TO:
Darrell Eisenhut Director RECEF/ED Division of Licensing kj Mfty J 9 Jggg Q a s:un tsaw % L-THRU:
Thomas M. Novak, Assistant Director 82 *ama C
For Operating Reactors, DL FROM:
Robert A. Clark, Chief Operating Reactors Branch #3, DL
SUBJECT:
CONTRACT EFFORT WITH OAK RIDGE NATIONAL LABORATORY Your note of April 5,1982 casts doubt on the pertinency of work performed /
by ORNL to the TMI Action Plan and the detemination of its applicability to HTGRs. Our March 2,1982 letter to ORNL changed the scope of work in a manner so as to eliminate all reference to HTGRs and, instead focus all effort only on the applicability of the Action Plan to Fort St. Jrain. This was a result of the December 31, 1981 memo from T. F. Englehart on conflict of interest considerations in placing work with ORNL. Our plans for deter '
mining applicability of the Action Plan to large HTGRs include an inhouse review of generic issues stemming from the ORNL effort on FSV supplemented by a contract with LANL or BNL. This effort, however, is not scheduled for FY 82 but instead for FY 83, when several RES contracts will be complete and will help in our determination.
The second part of your memo questions which Action Plan items are addressed.
The submittals by ORNL deal with several Action Plan items identified as follows:
1.
Evaluation of FSV RERP Emergency Categories: Classification and Actions.
Sections III.A.2 of NUREG-0737 deals with long term improvement of Licensee emergency preparedness. Specific criteria to meet this requirement is de-lineated in NUREG-0654 (FEMA-REP-1) " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparation in Support of Nuclear Power Plant."
Section 4 of the FSV RERP presents the classification of emergencies as proposed by PSC. During our review of the RERP we determined that several of the proposed actions by PSC are questionable; these deal with the time required for notifications and the initiating events. ORNL has been asked review this section to eliminate the discrepancies and to propose FSV re-quirements.
2.
HTGR Severe Accident Sequence Analysis:
This analysis by ORNL is a partial prerequisite to resolution of sections I.C.I.2. I.C.I.3. II.B.2 II.B.3. II.B.4 II.F.1. II.F.2, III. A.2 III.D.
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1.1, and III.D.3.3 NUREG-0737. These secticns deal with inadequate core i
cooling, and other accid g.t pe. ue.;
.ent related subjects.
In order to properly deter-
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b 2-for RERP, the maximum credible accident at FSV is analyzed and the doses calculated based on "Best estimate" values not conservative as those in the FSAR. This effort will be used for comparison and determination of the " safety factor" that exists in the PSC FSAR calculations as well as to determine the source teams for the above mentioned NUREG-0737 sections that require them.
We hope that this memo has alleviated any doubts that you may have on the pertinency of ORNL work to the NUREG- 0737 requirements. As ORNL mentioned in their last paragraph, Task 2. NUREG-0660 effort will start this month.
Original signe M Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing I
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