ML20153C612
| ML20153C612 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 08/22/1988 |
| From: | Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Cruden D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20153C615 | List: |
| References | |
| NUDOCS 8809010205 | |
| Download: ML20153C612 (4) | |
See also: IR 05000338/1988014
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AU6 2 21998
Docket Nos. 50-338, 50-339
,VjrginiaElectricandPowerCompany
MTTH:- Mr. D. S. Cruden, Vice President,
Nuclear Operations
P. O. Box 26666
Richmond, VA 23261
Gentlemen:
SUBJECT: NRC INSPECTION REPORT NOS. 50-338/88-14 AND 50-339/88-14
This refers to the Nuclear Regulatory Commission (NRC) inspection conducted by
A. L. Cunningham on June 27-30, 1988. The inspection included an evaluation of
the Emergency Response Facilities (ERFs) at the North Anna Power Station, to
determine if the ERFs meet the requirements of 10 CFR 50.47(b),
Paragraph IV.E.8 of Appendix E to 10 CFR Part 50, and Orders issued to
implement Supplement 1 to NUREG-0737.
At the conclusion of the appraisal, the
findings were discussed with those members of your staff identified in the
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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, assessment of ERFs and related equipment, inter-
views with personnel, and evaluation of the effective use of the response
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facilities and equipment in support of the Emergency Response Organization
during the 1988 Annual Emergency Preparedness Exercise.
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Within the scope of the inspection, no violations or deviations were
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identified.
Other areas were identified, however, that require further action
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for completion.
These areas are identified in Enclosure 1 to this letter as
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Open Items and are discussed in the enclosed Inspection Report.
Open Items
will be tracked as Inspector Followup Items.
The enclosed Inspection Report
documents oral commitments made by licensee representatives and discussed in
the exit interview,
if your understanding of these commitments differs from
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the report statements, please inform this office promptly.
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Additional findings also indicate that there are other items in your Emergency
Preparedness Program which should be considered for program enhancement. These
items are identified in Enclosure 2 for your benefit.
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In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2
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Title 10 Code of Federal Regulations, a copy of this letter and its enclosures
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will be placed in the NRC Public Document Room.
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Virginia Electric and 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,
Orlyin&}l (S/[CCd
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J. Philip Stohr Director
Division of Radiation Safety
and Safeguards
Enclosures:
1.
Emergency Response Facilities
Appraisal Open items
2.
Items Which Should be Considered
for Program Enhancement
3.
NRC Inspection Report
cc w/encls:
- E. Kane, Station Manager
L V E. Hardwick, Manager - Nuclear
Programs and Licensing
bec w/encis:
(JMC Resident inspector
DRS Technical Assistant
Document Control Desk
Comonwealth of Virginia
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ENC'_050RE 1
EMERGENCY RESPONSE FACILITIES APPRAISAL OPEN ITEMS
Completion of resolution of differences in dose calculations between the
RAD / MET Model and manual method defined in the Emergency Plan Implementing
Procedures (338,339/88-14-01).
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Completion of evaluation of validity of use of field monitoring data for
calculating a source term and use of same in the protective action
decision process,
or in determining emergency classifications
(338,339/88-14-02).
Completion of revisions to the EP!Ps addressing dose assessment to include
separate stability classes for vertical and horizontal diffusion
(338,339/88-14-03).
Completion of modification of the RAD / MET Model to provide dose projection
estimates at future plume positions (338,339/88-14-04).
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Completion of revision of TSC ventilation operational procedure
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(1-0P-21-10) to include operator verification of nonnal system damper
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positions to ensure proper system operation (338,339/88-14-05).
Completion of revision of TSC ventilation test procedure (1-PT-77.9) to
test system components including system interlocks (338,339/88-14-06).
Completion of establishment of a mechanism to track all sensor data errors
to help correct
and prevent abnormal
sensor data errors
(338,339/88-14-07).
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E'NCLOSURE 2
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Items Which Should be Considered for Program Enhancement
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Modifying the manual EPIP dose calculation method to. run on a personal
computer or a computer system separate from RAD / MET.
This computerized
EPIP method could be made available in the Control Room TSC, LEOF, and
CEOF.
Conducting a more detailed comparison between RAD / MET and the Comonwealth
of Virginia's dose assessment model following completion of the
Comonwealth's proposed modifications to the model.
Reasons should be
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identified if any comparisons differ by more than a factor of 3.
Developing a verision of the RAD / MET model with a domain that extends
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through the ingestion pathway zone.
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Providing support for a backup method for estimating the vertical
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diffusion coefficient that does not involve sigma theta.
Two possible
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alternatives for this suppurt are an independent, backup delta T system,
and implementation of a procedure to estimate stability class from solar
radiation and wind speed.
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Protecting the meteorological tower instrument power supplies from the
effects of power surges caused by lightning strike,
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Replacing the spot meteorological data values available through the SPDS
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with time-averaged data, except where there is specific need of the spot
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meteorological data.
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Developing a procedure to test the throw-over feature of the UPS buss.
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Developing algorithms to coordinate the SPDS top level display color code
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with the applicable EAL parameter escalation values.
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Providing a preventive maintenance program for key emergency ventilation
system components.
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Revising non-safety preventive maintenance program to ensure periodic
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maintenance of non-safety system and documentation thereof.
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Documenting period testing of non-safety system and the results thereof.
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