ML20004F266
| ML20004F266 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/12/1981 |
| From: | Ball S OAK RIDGE NATIONAL LABORATORY |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20004F267 | List: |
| References | |
| CON-FIN-B-0762, RTR-NUREG-0660, RTR-NUREG-0696, RTR-NUREG-0737, TASK-1.C.1, TASK-1.D.2, TASK-2.B.3, TASK-2.B.4, TASK-2.K.3.17, TASK-3.A.2.1, TASK-3.A.2.2, TASK-TM NUDOCS 8106170143 | |
| Download: ML20004F266 (4) | |
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OAK RIDGE NATIONAL LABORATORY CPERATED SY UNION CARBIDE CORPORATION NUCtEAR 31visiOM
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June 12, 1981 M'
L n causass ua, e usnan ces Mr. Darrel G. Eisenhut, Director
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Division of Licensing, ONRR CM U.S. Nuclear Regulatory Commission N
'4ashington, D.C. 20555
Dear Mr. Eisenhut:
Subject:
Monthly Report
" Applicability of IMI Action Plan Requirements to Fort St. Vrain and HTGas", for Period Ending June 15, 1981 (FIN. NO. 30762)
'Jork Co-leted Durinsr the Reporting Period Action plan ite=s in NURFG-0737 were reviewed, along with letters submitted to NRC by Public Service Co. of Colorado (PSC) to determine areas where some question or disagreement may exist on implementation of particular items at the Fort St. Vrain (FSV) reactor. Our aim was to work on assessing these items first, if possible. Per this review, and discussions with ONRR and PSC personnel, several action items were chosen to receive prompt attention. These are listed in At achment 1.
Four of these items were written up in prelf, b ry draft form for NRC staff comments, and serve as exa=ples of our current interpretation of what is needed.
(Attachment 2).
These items (and authors) are: (1) Item I.D.2, Plant Safety Parameter Display Console (S. J. Ball); (2) Item II.3.3,' Postaccident Sampling Capability (J. C. Conklin); (3) Item II.3.4, Training for Mitigating Core Damage (R. M. Harrington); and (4) Item II.K.3.17, Report on Outages of Emergency Core Cooling Systems - Liceasee Report and Proposed Technical Specification Changes (S. J. Ball).
Other assistance enlisted to evaluate specific NUREG-0737 items include:
J. P. Sanders (I.C.1 - Guidance for Evaluation and Development of Procedures for Transients and Accidents); social scientists from the Resource Analysis and Social Impacts Analysis Groups (ORNL Energy Division) to review appropriate aspects of the evacuation plan and operator training requirements; meteorologists from the Environmental Impact Section to evaluate meteorological requirements for the e=ergency response facilities; and N. E. Clapp to assist on accident analysis and instru=entation-related items.
Funds Scent for Mancover and other Services (It should be noted that expenditures for monthly periods ending the 15th of the month cannot be reported precisely because the ORNL financial reporting system works by the month.)
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Estimated Costs:
Previous Present Period Cumulative Manpower, Task 1:
$2900
$5250
$8150 Manpower, Task 2:
0 0
0 Computer:
0 0
0 Travel:
300 0
300 Problems or Delavs Encountered or Anticipated None.
Plans for the Next Reporting Period
'4ork will continue on specific action item tasks.
Future writeups of task assessments will factor in comments from NRR staff on the attached assessment drafts. Further technical assistance will be enlisted as required.
Yours truly,
.AV S. J. 3all Instrumentation & Controls Division SJ3:rtw Attachments cc:
R. Tedesco, Division of Licensing, NRR
- 3. L. Grenier, NRR James R. Miller, NRR G. Kuzmycz, h2R R. Ireland, NRR R. Foulds, RSR N. E. Clapp J. C. Conklin R. M. Davis R. M. Harrington P. R. Kasten F. C. Kornegay A. L. Lotts J. P. Sanders e
S. J. Ball 6/12/81 NUREG-0737 Action Items Chosen to Receive Prompt Attention Re: Applicability to Fort St. Vrain I.C.1 Guidance for the Evaluation and Development of Procedures for Transients and Accidents I.D.2 Plant Safety Parameter Display Console II.3.3 Postaccident Sampling Capability II.B.4 Training for liitigating Core Damage II.K.3.17 Report on Outages of Emergency Core-Cooling Systems, Licensee Report and Proposed Tech Spec Changes III.A.2 Esproving Licensee Emergency Preparedness --
Long Term (including NUREGs 0654 and 0696)
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4 ATTACHMENT 2 Preliminary Action Item Evaluations for NRC Staff Comment 1.
Item I.D.2 - Plant Safety Parameter Display Console 2.
Item II.B.3 - Postaccident Sampling Capability 3.
Item II.E.4 - Training for Mitigating Care Damage 4.
Item II.K.3.17 - Report on Outages of Emergency. Core Cooling Systems -
Licensee Report and Proposed Technical Specification Changes i
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