IR 05000335/1979003
| ML17206A749 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/08/1979 |
| From: | Gibson A, Zavadoski R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A747 | List: |
| References | |
| 50-335-79-03, 50-335-79-3, NUDOCS 7904260100 | |
| Download: ML17206A749 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 RePort NOs I 50-335/79-3 Licensee:
Florida Power and Light Company Post Office Box 529100 Miami, Florida 33152 Facility Name:
St. Lucie
DOCket NOsI
. 50-335 License NoeI DPR-67 Inspection at St. pucie Site near Hutchinso~ Island, Florida Inspector:
d ski Date Signed Approved by:
A. F. Gibson, ection Chief, FFSMSB Date Signed SUMMARY Inspection on January 15-19, 1979 This routine, unannounced inspection involved 44 inspector-hours on-site in the areas of external exposure control, notices to workers, posting, labelling and control, neutron surveys, ALARA considerations, RPM training, respiratory protection program and surveys.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Licensee Em lo ees
- C. M. Wethy, Plant Manager
+J.
H. Barrow, Operations Superintendent
+H. F. Buchanan, HP Supervisor
+R. J. Frechette, Chemistry Supervisor
- H. M. Mercer, Health Physics
+N.
G. Roos, QC Supervisor
- G ~
MD Green, HP Shift Supervisor-J. E. Bowers, Maintenance Superintendent
- G. Longhouser, Security
>A.
W. Bailey, QA Operations Supervising Engineer
- J. J. Walls, Quality Control
- B. W. Mikell, Planning Other licensee employees contacted during this inspection included eight technicians, four operators, six mechanics and four security force members.
+Attended exit interview.
Exit Interview The inspectio'n scope and findings were summarized on January 19, 1979 with those persons indicated in Paragraph 1 above.
Licensee Action on Previous Ins ection Findin s Not inspected.
Unresolved Items Unresolved items were not identified during this inspection.
Licensee Event Re ort (Closed) Ler No. 78-41.
This event involved the inadvertent actuation of the reactor building spray system during an outage and resulted in contaminating personnel and the containment floor. All told, fifteen individuals were initially contaminated and subsequently decontaminated.
Four individuals showed internal contamination, the highest initially showing ten percent of the maximum permissible body burden for cobalt-60.
After a few days, no evidence of internal
-2-contamination could be found.
The containment floor was also decontaminated.
The inspector discussed the event with licensee representatives and had no further questions with respect to their actions in the radiological area.
6.
External E
osure Control The inspector reviewed the licensee's program for external exposure control, including review of selected procedures and records, discussions with personnel and observation and partici-pation in work practices.
Specific areas inspected were:
I (1)
Personnel monitoring required by 10 CFR 20.202(a)
(2)
Permissible doses of 10 CRR 20.101(a)
and (3)
Exposure records required by 10 CFR 20.401(a).
The inspector had no further questions on the licensee's program in these areas.
b.
CFR 20.101(b) permits an individual to receive extended doses provided an NRC-4 Form is completed and an exposure history is obtained.
An inspector reviewed selected personnel exposure records for individuals who had received extended doses and verified that a completed NRC-4 form was on file.
An inspector also verified that there were no unreported cases of personnel exposure above the limits of 10 CFR 20.101(b).
The inspector had no further questions on the licensee's program in these areas.
c ~
An inspector discussed the employment of minors at the facility with licensee representatives.
The licensee representative informed the inspector that company policy prohibits the employment of minors at generating facilities.
The inspector had no further questions in this area.
7.
Notices to Workers
'10 CFR 19.11 requires that Form NRC-3 and certain documents be posted or that a notice be posted stating where the documents may be examined.
Such documents shall be posted where they can be observed on the way to or from any licensed activity location.
The inspector observed that Form NRC-3 and the notice were posted at the entrance to the radiation controlled area and that Form NRC-3 was also posted at various locations around the facility.
The inspector had no further question.
Postin Labellin and Control a
~
The inspector reviewed the licensee's posting for radiation areas (10 CFR 20.203(b)), high radiation areas (10 CFR 20.203(c)),
airborne radioactivity areas (10 CFR 20.203(e))
and container labelling (10 CFR 20.203(f)).
Accompanied by a licensee's representative, the inspector randomly surveyed several areas for radiation levels in the radiation controlled area.
No items of noncompliance or deviations were observed by the inspector.
b.
The inspector reviewed with licensee representatives, the controls as required by 10 CFR 20.203(c) for high radiation areas, and
CFR 20.207 for storage areas.
An inspector also reviewed the use of Radiological Work Permits (RWP's)
and the control measures for radioactive or contaminated areas and equipment as required by procedures.
No items of noncompliance or deviations were observed by the inspector.
On January 18, 1979, the inspector accompanied licensee representa-tives on a tour of the containment with the reactor at 100 percent power.
During the tour of all three elevations of the containment, the inspector noted a high degree of cleanliness at each elevation.
The inspector observed the licensee's representative perform a
neutron survey on each elevation.
At the lowest elevation, neutron levels ranged from 5 to 50 mrem/hr.
and gamma levels ranged from 7 mrem/hr near the personnel lock, about 20 mrem/hr general area, to 1.5 Rem/hr inside the regenerative heat exchanger cubicle.
At the intermediate elevation, neutron levels ranged from 4 mrem/hr to 30 mrem/hr and gamma levels ranged from 8 mrem/hr to 36 mrem/hr.
Entry was not made beyond the biological shield wall.
On the operating deck, neutron levels ranged from 100 to 200 mrem/hr, general area, to 2 to 3.5 Rem/hr near the refueling cavity.
Gamma levels ranged from 25 mrem/hr in the pressurizer cavity to 450 mrem/hr over the refueling cavity.
Prior to containment entry, the inspec-tor observed the preparation of the RWP for the containment entry including a prior determination of the airborne activity level in the containment.
During the containment tour, the inspector observed the conformance by all individuals involved to the conditions stipulated on the RWP.
The inspector also observed that all the verbal instructions of the RPM were obeyed.
No items of noncompli-ance or deviations were observed by the inspecto.
ALARA Considerations a.
Licensee representatives stated that written guidelines were being developed for the use of anti-contamination clothing and respirators.
Apparently, during the November 1978 outage, some confusion arose over the use of respirators.
Workers on one shift at a particular job wore respirators, while at the next shift, on the same job, they did not.
The inspector reviewed the MPC-hour log for the job and ascertained that the use of respirators for the job in question was precautionary.
b.
The inspector requested surveys for removable contamination be made by the licensee for several pieces of equipment that had been in the RCA during the November 1978. outage but was now outside the RCA.
The inspector accompanied the licensee's representative during the surveys and subsequent counting.
No removable contamination was found and the inspector had no further questions.
c ~
Licensee representatives pointed out to the inspector full scale mock ups of the critical parts of the steam generators which are to be used for training prior to the next refueling (approximately April 1978).
The inspector noted that the use of such mock ups was in keeping with the philosophy of Regulatory Guide 8.8.
d.
Licensee representatives stated that during the January 1,
1978 to December 31, 1978 year, the total radiological exposure at the site was 295 man-rem.
The highest exposure received, by any one individual was only 2.6 Rem.
The year 1978 included one refueling in April and one ten-day outage in November.
11.
Res irato Protection Pro ram By review of records, observations, and discussions with licensee representatives, and actual fitting and use of a respirator, the inspector evaluated the program for air sampling, bioassay, engineering controls, MPC-hour controls, respirator medical evaluation, training, fitting, operational testing, maintenance, and issuance controls, and determined that the respiratory protection program appeared to be in. full compliance with 10 CFR 20.103.
Further, the inspector accompanied licensee representatives on an RWP, which required the use of respirators and observed first-hand the field use of respirators and had no questions on the progra w5 12.
~Surve s
I a.
The inspector reviewed the licensee's program for surveys of contaminated and radiation areas, including review of selected procedures and records, discussion with personnel and observa-tion of work practices.
Specific areas inspected were:
(1)
Surveys discussed in 10 CFR 20.201(b),
and (2)
Records of surveys discussed in 10 CFR 20.401(b).
No items of noncompliance were identified and the inspector had no further questions on the licensee's program in these areas.
b.
The inspector toured the plant, and requested an RPM in order to take smears for removable contamination in various locations and on selected pieces of equipment, The inspector examined records of contamination surveys posted in areas of the plant.
The inspector examined the wrapping and tagging of potentially contaminated items in the RCA.
The inspector observed potentially contaminated and contaminated materials wrapped and sealed, tagged, and in specified storage locations.
The inspector had no further questions.
.The inspector reviewed the training records of the health physics staff.
In addition, the projected training schedule was reviewed.
The programs appears to meet the requirements of ANSI N18.1-1971,
"Standard for Selection and Training of Personnel for Nuclear Power Plants",
and the inspector had no further questions.