ML20148J684
| ML20148J684 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/08/1988 |
| From: | Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Head G GEORGIA POWER CO. |
| Shared Package | |
| ML20148J689 | List: |
| References | |
| TAC-45950, TAC-45951, TAC-46021, TAC-46022, TAC-46093, TAC-46094, TAC-46309, TAC-46310, NUDOCS 8803300348 | |
| Download: ML20148J684 (3) | |
See also: IR 05000321/1987032
Text
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MAR.0 81988
Docket Hos. 50-321,'50-366
Geprgia Power Company
LATTN: Mr. George F. Head
Senior Vice President-
-P. 0. Box 4545
Atlanta, GA 30302
Gentlemen:
SUBJECT: HRC INSPECTION REPORT N0S. 50-321/87-32 AND 50-366/87-32
This refers to che Nuclear Regulatory Commission (NRC) inspection conducted by
A. Gooden on December 7-10, 1987. The inspection included an evaluation of the
Emergency Response Facilities (ERFs) at Plant Hatch, to determine'if the ERFs
meet the requirements of'10 CFR 50.47(b), Paragraph IV.E.8 of 10 CFR Part 50,
Appendix E, and Orders issued to implement Supplement 1 to NUREG-0737.. At the
conclusion of the inspection, the findings were discussed with those members of
your staff identified in the enclosed inspection report.
Areas examined during the inspection are identified in the report.
Within
these areas, the inspection consisted of selective examination of procedures
and representative records, ERFs and related equipment, interviews with
personnel, and observation of the 1987 emergency exercise.
Within the scope of the inspection, no violations or -deviations were
identified.
However, there were areas identified as requiring further review
and evaluation.
These items are identified as Inspector Followup Items in
Appendix A to this letter, and are also discussed in the enclosed appraisal
report.
The findings also indicate that there are items in your Emergency Preparedness
Program which need improvement.
These items are identified in the text of the
enclosed Appraisal Report.
Accordingly, you are requested to submit a written statement within 45 days of
the date of this letter, which details the action you plan to take,' and the
estimated date of completion with regard to the findings identified in
Appendix A.
1
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosures
will be placed in the NRC Public Document Room.
8803300348 880309
ADOCK 05000321
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Georgia Power Company
2-
The responses directed by this letter and its enclosures are-not subject to the
clearance procedures of the Office of Management and Budget as required by the
Paperwork Reduction Act of 1980, Pub. L. No.~96-511.
Should you have any questions concerning this letter, please contact us.
'
Sincerely,
ORIGNM. SIGNED BY
DOUGLAS M. COLUNS
J. Philip Stohr, Director
,
Division of-Radiation Safety
and Safeguards
Enclosures:
1.
Appendix A, Inspector Followup
Items
2.
Inspection Report
cc w/encis:
kWT.Beckham,VicePresident,PlantHatch
M C. Nix, Plant Manager
10f M. Fraser, Site Quality Assurance (QA)
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Sypervisor
V. Gucwa, Manager, Nuclear Safety
and Licensing
bcc w/encis:
[J4RC Resident Inspector
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DRS Technical Assistant
L M gh S. Jordan Executive Secretary
Document Control Desk
State of Georgia
W C Heard, FEMA, RIV
LEM B. Matthews, EPB/NRR
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APPENDIX A
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Appraisal Open Items
1.
Review the primary dose assessment code (DOSE) to assure .that its use of
atmospheric
transport
and diffusion models is appropriatt,
that
corrections are made for radioactive decay and radionuclide mix . af ter
reactor shutdown, and that it can adequately track the release during
changes in wind direction (50-321/87-32-01, 50-366/87-32-01).
2.
Review the equipment and procedures used for the collection of
meteorological data used in dose assessment to assure it is in accordance
with Regulatory Guide 1.23 (50-321/87-32-02, 50-366/87-32-02).
3.
Verify that the completion of data acquisition system . program upgrade
(Software Modification Request No. 45) includes the capability to produce
,
full data file recovery following computer _ failures (50-321/87-32-03,
1
50-366/87-32-03).
4.
Verify that the plans and/or procedures for the backup EOF adequately
address staffing, equipment, and other logistical requirements to accept
the transfer of the EOF functions in the event the primary EOF must be
,
evacuated (50-321/87-32-04, 50-366/87-32-04).
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