IR 05000010/1976012
| ML19340A755 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/07/1976 |
| From: | Essig T, Fisher W, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A749 | List: |
| References | |
| 50-010-76-12, 50-10-76-12, 50-237-76-15, 50-249-76-13, NUDOCS 8009030780 | |
| Download: ML19340A755 (15) | |
Text
,-
,
(,l
.
UNITED STATUS NUCLEAR RECULATORY C05011SSION OFFICE OF INSPECTION AND ENFORCEMENT (
REGION III
.
Report of Operational Rar'
te Inspection IE Inspection Report No. 050-010/76-12 IE Inspection Report No. 050-237/76-15 IE Inspection Report No. 050-249/76-13 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-2 Units 1, 2 and 3 License No. DPR-19 Morris, Illinois License !o. DPR-25 Category:
C Type of Licensee:
GE BWR 210 and 810 (Units 2 and 3)
Type of Inspection:
Routine, Unannounced
,
Dates of Inspection:
June 7-17, 1976
'
,y, c ym <d.y
^
Principa; Inspector:
M. C. Schumacher
'
i
..
"*
'(Date)
_ s, [. "
,1 * s t.0C v'
,s
'
Accompanying Inspettor:
T. II. Essig
,e c L
, ' ' ' '
- ,
- ~
'(Date)
Other Accompanying Personnel: None Reviewed By:
W. L. Fisher, Chief 7/'/ 'f Fuel Facility Projects and
["'
'(Dti t e )
Radiation Support Section 8009030 7CPO
- - - - - -
.
SUMMARY OF FINDINGS k
Inspection Summary
-
.
Operational Radwaste Inspection for Units 1, 2, and 3 conducted June 7 through 17, 1976, (Unit 1, 76-12), (Unit 2, 76-15), and (Unit - 3, 76-13): Reviewed procedures and records relating to radioactive effluents, shipments, process monitor calibrations and licensee followup to previously made commitments and to previously identified enforcement items. Reviewed radiological aspects of apparent off-gas explosion on Unit 2 that occurred during the inspection.
Four items of noncompliance related to inadequate calibration of continuous air monitors (Unit 1), inadequate calibration of liquid radwaste monitor (Units 2 and 3), inadequate calibration of chimney monitor (Units 2 and 3), and late notificatign of incoming cask with contamination greater than 22,000 d/m/100 cm (Units 2 and 3).
Enforcement Items A.
Infractions 1.
Contrary to Technical Specification 4.8.A.1, an adequate calibration of Units 2/3 chimney monitor was not done
-
during the first quarter of 1976.
(Paragraph 4, Report Details)
,
2.
Contrary to Technical Specification 4.6.D.2, celibration of Unit I continuous air monitors was inadequate during the first quarter of 1976.
(Paragraph 4, Report Details)
3.
Contrary to Technical Specification 4.8.C.1, calibration of the Units 2/3 liquid waste monitor was inadequate during the period reviewed.
(Paragraph 4, Report Details)
B.
Deficiency Contrary to 10 CFR 20.205(b), the licensee failed to immediately notify IE:1II of the arrival of an empty fuel cask
showing contamination greater than 22,000 dpm/100 cm.
(Paragraph 9, Report Details)
Licensee Action on Previvusly Identified Enforceme,t Itenz
,
Calibration of neutron monitors referenced in the enforcement item in the IE:III letter of April 23, 1976, was verified. This item remains open pending approval of a procedure specifying calibration frequency.
(Paragraph 14, Report Details)
l j
'
-2-l l
l
!
-
.
Other Significant Items A.
Systems and Components k.
Unit 2 experienced an apparent off-gas explosion on June 7, 1976, while operating with the rechar system. No releaca
-
limits were exceeded.
(Paragraph 10, kaport Details)
B.
Facility Items The licensee is planning to build new waste solidification f acilities at Unit 1 and at Units 2/3.
(Paragraph 8.c, Report Details)
C.
Managerial Items None.
D.
Noncompliance Identified and Corrected by Licensee 1.
Contrary to Technical Specification 3.8.A.1, the Units 2/3 chimney monitor was inoperable between 1600 on May 24, and 0830 on May 26,1976.
(Paragraph 2.b, Report Details)
2.
Contrary to Technical Specification 4.6.D.1.A, air samples were not taken in the east and west pipeways of Unit 1 during the week of March 21-27, 1976.
(Paragraph 11,
,
Report Details)
.
<
E.
Deviations None.
F.
Status of Previously Reported Unresolved Items None reviewed.
Management Interview A management interview was held at the close of the inspection with Iessrs. Stephenson, Watts, Adam, Testa and Willaford.
A.
The inspectors identified the following items of noncompliance:
1.
Inadequate calibration cf the Units 2/3 chimney monitor.
(Paragraph 4, Report Details)
-3-
,
o
.
f 2.
Inadequate calibration of the Unit I continuous air monitors.
(Paragraph 4, Report Details)
-
3.
Inadequate calibration of the Units 2/3 liquid waste
-
monitor.
(Paragrajn 4, Report Details)
4.
Delay in notification af receipt of spent fuel cask yith surface contamination greater than 22,000 d/m/100 cm'.
(Paragraph 9, Report Details)
Item 4 was noted to have been adequctely corrected by the licensee and that no.further response would be required.
o B.
The inspectors noted that the following noncompliance items had been identified and corrected by the licensee.
1.
Failure to sample Unit 1 east and west pipe ways during the week of March 21-27, 1976.
(Paragraph 11, Report Details)
2.
Inoperable Units 2/3 chimney moritor May 24-26, 1976.
(Paragraph 2.b, Report Details)
C.
The inspectors noted that airborne effluent _ appeared to be within limits throughout the period reviewed, but noted the lack of a formal program to insure that the daily grab samples are representative.
.
-
The licensee stated this surveillance would be improved.
(Paragraph 2.b, Report Details)
D.
The inspectors stated that liquid releases appeared to be within limits, but noted that there were discrepancies in tank purp out tL=es between the release permits and the tank level ci. arts that would af fect the calculation of maximum release concentration.
The licensee stated that the operators would be instructed to record the actual duration of releases on the permits.
(Paragraph 2.a, Report Details)
E.
The inspectors reviewed the Unit 2 off-gas explosion, noting that appropriate grab sampics taken during the release would have permitted a more accurate quantification.
- t, -
.
-
e
-
The licensee acknowledged this comment.
(Paragraphs 4 and 10,
'
('..
Report Details)
F.
The inspectors discussed operation of the ARM multipoint
.
recorders.
The licensee stated that routine surveillance of radiation monitors and equipment in the control room would be assigned to the unit health physicists and t..at the repair of the Unit 2 ARM recorder would be made a priority item.
(Paragraph 12, Report Dets11s)
G.
The inspector acknowledged that calibration of the neutron monitors had been achieved but stated that the item would remain open until the calibration procedure had been completed.
(Paragraph 14, Report Details)
H.
The inspector stated that surveillance of radioactivity in reactor coolant appeared satisfactory.
(Paragraph 7, Report Details)
I.
The inspector noted satisfactory surveillance of the standby gas treatment system charcoal and HEPA filters. He furcher noted that when test charcoal cartridges are installed, they j
should be representative of all the charcoal in the train.
'
(Paragraph 6 Report Details)
,
J.
Inspectors acknowledged fulfillment of the following commitments previously made by the licensee:
1.
Revised procedure for tracking individuals who do not achieve respirator fitting during training.
(Paragraph 13, Report Details)
2.
Additional shielding of the Unit I waste holdup tank.
(Paragraph 12, Report Details)
i I-5-
.-
F
, -. -,
._
.
REPORT DETAILS
'
('
l.
rersons Contacted
,
B. Stephenson, Plant Superintendent N. Scott, Operating Engineer R. Regan, Operating Engineer E. Budzichowski, Operating Engineer T. Watts, Technical Staf f Supervisor J. Testa, Radwaste Supervisor D. Adam, Radiation Chemistry Supervisor J. Parry, Health Physicist D. Simpson, Health Physicist G. Bergan, Chemist T. Schnieder, Chemist D. Egget, Chemist C. Sargent, Unit 3, Lead Engineer G. Romba, Unit Engineer V. Chaney, Radiation Protection Foreman R. Schumacher, Radiation Protection Foreman D. O'Keefe, Radiation Protection Foreman R. Campbell, Instrument Maintenance F. Willaford Quality Assurance Engineer F. Miller, ANEFC0
-
2.
Radioactive Effluent Releases
-
a.
Liquid Releases Records of liquid radwaste releases were reviewed for th.
period June 1975 through May 1976. The review included selective examination of discharge permits, valve lineup sheets and tank level records. No instances of noncompli-ance with regulatory requirements for releases were noted.
Differences observed several times between the duration of discharge noted on the permits and that shown on tank level charts resulted from the operator logging the time when the pump was shutoff rather than the time the tank reached
,
empty. The licensee's calculation of discharge concentration was therefore affected; however, examination of such cases revealed no concentration in excess of limits.
For the 11 month period covered by this review liquid releases totaled approximately 1.5 curies in approximately 1E + 07 liters of discharged wastes. Discharges
'aring the month of May, when an unusually large volume of-6-
I l
-
t
_,
--
,. -
',
water was processed to remove boron from the Unit 2 coolant, accounted for e.lwost half of the activity discharged. The
..
max recycle system, made operational late in 1974, continues (,'
to be effective in holding down activity discharged as indicated by the following comparison:
-
Activity Discharged Volume Discharged Pe-iod (millicuries)
(liters)
January thru May 1974 1.6E + 04 3.0E + 06 January thru May 1975 7.6E + 02 2.5E + 06 January thru May 1976 8.8E + 02 4.9F + 06 No problems were noted in review of analyses and quantification cf radionuclides discharged.
Records of radioactivity contained in outside tanks were reviewed against the requirements of Technical Specification 3.8.D.
No problems were noted.
b.
Airborne Records of airborne effluents for the period June 1975 to June 1976 were reviewed.
No releases in excess of regulatory requirements were noted.
.
An out of service condition on the Un..tc 2/3 chimney
_
monitor for a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> period during May 24-26, 1976,
,
contrary to Te:hnical Specificgyior 3 8. A.1, was identified and corrected by the licensee.-
The occurrence was caused by failure to follow procedure 37-3-5, "D 2/3 Chinney Sampler Filter Replacement." The individual involved was reprimanded and a minor precedure alteration was made.
Noble gas release rates ere determined from daily grab samples using hold up ti.nes based on fic.w rate.
Units 2/3 samples are normally taken dcwn stream of the charcoal beds.
The Unit I sample is norms 11y collected near the beginning of the holdup pipe but dua to water collecting there (a low point in the system) the :ollection point was moved downstream about 22 feet. The samples are assumed representative of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period unless a system upset occurs and a cor-rected release is calculated. No formal program exists to review the chimney monitor record to verify that the sample is representative although !t is a practice of the unit chemists to frequently review the control room charts.
1/ Reportable Occurrence No. 50-237/76-38, dtd 6/9/75.
-7-
3.
Records and Reports of Radioactive Effluents Effluent releases reported in the licensee's semiannual reports (T for January-June 1975 and July-December 1975 were reviewed for internal consistency and selective comparisons were made with the licensee's diccharge records. No significant problems were
-
nv.
with either the gaseous or liquid release data.
4.
Effluent Control Instrumentation Licensee records of calibrations and functional tests of gaseous and liquid process monitors were examined for the period July 1975 through May 1976.
Several inadequacies were noted:
a.
Lack of flow calibration for Unit I continuous air monitors which monitor for coolant leakage.
b.
Inadequately calibrated Units 2/3 11guld waste discharge monitor.
The monitor appears insensitive to normal discharges and its readings are not correlated with activity in the discharge line. A licensee modification to replace this monit6r, pending since 1974, appears to have been indifferently pursued.
c.
Inadequate calibration of the Units 2/3 chimney monitor.
The response curve for the condition of both units' off-gas
-
belt.g treated by their respective rcchar systems >as not determined during the first quarter of 1976. cloreover, the
-
procedure for determining the curva using ;rab samples appears
'
inadequate because the lowered releases effected by rechar do not give a sufficient range of monitor readings and because the effects of monitor background are apparently unaccounted for. The curves on hand were of little use in making an estimate of release following the June 7 off-gas explosion.
Off-line calibration may be necessary to achieve a suitable range of concentrations and nuclide characteristics, and a system of taking appropriate grab samples during abnormal conditions may be needed to quantify releases.
Calibration problems are further exacerbated by transfer lines in the surrounding max recycle building which at times have an effect on the monitor comparable to that prod.tced by effluents, despite a lead brick shield erected by. > licensee.
-8-
,
5.
Procedures for Controlling Release of Effluents (3 The inspectors reviewed the following newly added or revised
'
procedures related to control of effluent releases:
_
37-1-11 (Rev. 2), February 1976 - Curie Content of Radioactive Shipments.
37-3-3 (Rev. 3), March 1976 - Routine off-gas Sampling and Analysis, Dl/D2/D3.
37-3-8 (Rev. 3), August 1975 - Counting Room Reporting Criteria for Radiation Protection Personnel.
37-3-18 (Rev.
'), March 1976 - DI Chiuncy Filter Sam ue Replacemer.t.
.
37-3-H-7 (Rev. 2), July 1975 - Calculation of Caseous Tritium.
37-3-H-13 (Rev. 3), July 1975 - D1/2/3 Off-gas and Chimney Monitor
,
Response Curves.
'
37-3-H-14 (Rev. O), August 1975 - Calculation of Gaseous Tritium, Unit 1.
37-9-10 (Rev. 2), September 1975 - Radiation Surveys of Spent Fuel Shipping Cask.
-
Only one problem was noted in review. As discusse. in Paragraph
-
"
g 8, a procedure revision is needed to clarify reporting requirements for surveys of incoming spent fuel cask shipments.
Station review and approvals appeared to be in accordance with Dresden procedures.
6.
Testing of Containment Air-Cleaning Svstems Records of part4 : late (DOP) and hailie (Freon) penetration tests of the standby gas treatment system were reviewed for the period July 1975 through May 1976. The records indicate that successful tests on the two trains were conducted in September-October, 1975 and in March 1976. Tests of charcoal samples from both trains done at a vendor's laboratory in April 1976 showed iodine removal efficiencies of 94.46% and 99.19% for Trains A and
,
B respectively. Train A charcoal was replaced on Ag25, 1976.2yil 23 and l
retested successfully with freon on April The licensee has ordered and is awaiting delivery of run-time meters to be installed on both trains in anticipation of a
,
technical specification change tying charcoal testing to usage.
At that time the licensee plans to install cells containing test cartridges for use in determining iodine removal efficiency.
2/ Reportable Occurrence !!o. 50-237/76-30, dtd 5/20/76.
!
-9-
.
.--
_ _ _.
,
7.
Tests of Peactor Coolant Quality Reactor coolant surveillance for radioactivity was reviewed for (N the period July 1975 to June 1976. The licensee appears to have
'
collected and analyzed samples in accordance with Section
,
4.6.C.1 ef the Units 1, 2 and 3 Technicel Specifications.
Technical Specfication 3.6.C.1 requires that the radioactivity concentration in the reactor coolant not exceed 20 uCi/ml. The licensee appears to have complied with this requirement, i.e.,
the maximum gross (beta-gamma) radioactivty concentrations noted were 1.3, 0.51, and 1.5 uCi/mi for Units 1, 2 and 3, respectively.
8.
Solid Radioactive Wastes a.
Shipments Solid radwaste shipment records for the period July 1975 through April 1976 were reviewed. The following data were summarized by the inspector from the licensee's semiannual reports for 1975 and from individual shipment records for 1976.
Period No. of Shipments Curies Shipped Volume (M )
.
January-April 1976 278 365 1400 4.
July-December 1975 475 6700 6700
'
January-June 1975 348 630 2300 The anomalously high activity recorded in the July-December 1975 record is attribut-ale to Unit 2 poison curtains (6300 C1) shipped in August. Most of the volume shipped is contaminated so resulting from the May 1975 spill in the f
ANEFCO compound Examination of selective shipment records for 1975 gave general agreement with semiannual report data.
It was confirmed by observation that the quanitification of shipped activity was being done in accordance with licensee procedure 37-1-11, Revision 2, February 1976, " Curie Content of Radioactive Shipments." An exception was that the activity in contaminated soil being shipped in wooden boxes was being over estimated by the use of a factor appropriate to shipment in concrete tanks. The error is not regarded as significant because the total activity involved is very small compared with normal waste shipments.
3/ IE:III Inspection Rpt No. 050-010/75-10.
- 10 -
-
y v
,
,
. -. -
b.
Leakane f rom a Shipment of Contaminated Soil (*
The' licensee reported to the inspectors that on June 8, 1976, at approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, he was notified by the common carrier that water was leaking from a shipment of
,
solid radwaste (contaminated seil) being transported from the Dresden Station to a licensed burial site near Morehead, Kentucky. At the time the leakage'was noticed, the truck was parked at a service station at the intersection of highways 111-47 and I-80 (about nine miles from the Dresden station) in Morris, Illinois. The shipment consisted of three plywood boxes (4' x 4' x 8'
long) containing soil removed from the Unit I liquid radwaste area. Based on surveys performed prior to the shipment, it was determined that each box contained about 1 mci of activity, consisting primarily of radiocobalt and radiocesium.
Licensee representatives were dispatched immediately to the service station. These individuals learned that small amounts n' water had leaked from the front and rear boxes onto the flat-bed trailer (the middle box exhibited no leakage). The leakage from the front box was confined to a small spot (a few inches in diameter) on the trailer. The rear box, however, was leaking at a sufficient rate to drip
-
from the trailer bed to the ground. Portable instrument
,
surveys indicated that the water appeared to contain no
~
I radioactivity above background. The truck was then ordered to return to the Dresden Station (at approximately 2150
hours).
The inspectors verified, by examination of the shipment on June 9, 1976, after it returned to Dresden, that the leakage rates, contamination levels, and exposure rates were as indicated by the licensee. The inspectors also observed the contents of the boxes when they vere emptied on June 10, 1976, to allow the moist soil to dry out.
The
'nspectors noted that the condition of the soil was as a licensee representative had indicated, not appearing so moist as to preclude shipment, but apparently moist enough to " squeeze" water from itself as it settled dur'ng transit.
(Forty-six boxes, constituting fifteen shipments, had been shipped since June 2, 1976, without any rtported leakage. The subject boxes had been allowed to sat 24-36 hours on site after they were filled with soil and no leakage was noted).
--11 -
I r
i
_ _
. _.
,
_
. ~..
The licensee performed a qualitative analysis of the water which had 1 caked fron the shipment on June 8, 1976. The (!
analysis revealed the presence oi Cs-134 and Cs-137.
Using
~
their own estimates of a sample geometry correction factor
-
together with approximate calibration factors obtained from the licensee, the inspectors estimated that the concentrations of-Cs-134 and Cs-137 were less than their respective MPC (10 CFR 20, Appendix B. Table II Column 2).
This information, together with the knowledge that, based on portable survey instrument measurements, none of the samples (soil and water) contained any activity above background, led the inspectors to conclude that no significant problems related to public health and safety were associated with this event.
c.
Facility Modifications The licensee currently has plans to install new radwaste solidification facilities at Units 1, and 2/3 with completion expected sometime in 1978. The fc 'er will be a system proposed by Dow Chemical involving a po_ymer and will be used for solidification of v...:es generated by the planned decontamination of Unit 1 and thereafter for treatment of
>
Unit I wastes. The Units 2/3 facility will be a concrete
,
system.
.
-
9.
Contaminated Cask Shipment On June 15, 1976, at about 1500, the inspectors were notified that an empty fuel task (1F300 on rail car) was received from General Electric Company, Morris Operation on June 12 with contamination
levels greater than 22,000 dpm/100 cm Seven (7) of 40 cask smears
.
taken at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> post arrival showed levels in excess of the 22,000
dpm/100 cm immediate reporting requirement of 10 CFR 20.205.
It was further learned that this shipment was third in a series begin-ning June 8 which exceeded the reporting requirements. The licensee was informed that he was in noncompliance with 10 CFR 20.205.
This deficiency was attributed by the licensee to inadequate guidance
,
given to the Radmen with regard to timely reporting of such levels.
A memo has been written to the Radmen by the Radiation Chemistry Supervisor to correct the situation.
The licensee further learned that a Ceneral Electric Company petition for a limited exemption to 48 CFR 173.397 for the approxi-mately half mile trip between the Morris Operation and Dresden had been granted by the 6ET cffective June 11, 1976. The exemption for sole use vehicles, permits 10% of the surveys on a cask to reach
- 12 -
_. _._-,
.
~
a maximum of 110,000 dpm/100 eg providing that the average level is less than 22,000 dpni/100 cm This has created the situation
.
wherein the Icvels permitted by the exemption must be reported pursuant to 10 CFR 20.205.
k'
10.
Unit 2 Off gas Explosion,.a' rue 7, 1976
-
An apparent off-gas explosion occurred at about 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on June 7, 1976, while the unit was cperating on the."A" air ejector with recombiner and charcoal adsorbers in service.
- -
Transfer to the "B" ejector was initiated but not completed until about 2200 owing to high water levels in that train. A blown "A" rupture disk was confirmed and subsequently (June 9)
the "B disk was also f ound broken. The off-gas filters were found intact with a DOP cf ficiency of 99Z.
The chimney monitor rose beginning at about 1815 from 60 to 120 cps returning gradually to about 70 cps by 1930. Two sharp spikes to about 190 cps were recorded at about 1840. Accurate quantification using this monitor was not possible because of departure from calibration conditions. However, a reasonable upper limit estimate appeared to be the approximately 50,000 uCi/sec indicated by the Unit 2 off-gas monitor. The Unit 3 release rate was about 130 uCi/sec during the occurrence.
This estimate, well within Technical Specification limits, is regarded as conservative because the charcoal adsorbers were actually in service until about 1940 on June 7.
Recorded
,
flow through the beds increased by a factor of 3 to about 75 :fm
-
g because of air pulled in through the broken rupture disk by cl.e
'
booster air ejector downstream and the reduced residence time of i
noble gases eatrained on the charcoal contributed to the monitor increase. The release rate of iodine plus particelates for the period was in the range observed prior to the occurrence.
Although off-gas was apparently not discharged to the air ejector room owing to the booster, the turbine building did become airborne beginning at about 1900 when particulate icvels on the main turbine floor were noted as SE-10 oCi/cc. This activity is attributed to blown loop seals in the of f-gas system drains which are routed to a drain tank in the radwaste basement and thence via a pump to a waste collector tank in an adjacent tank room. Tank room ventilation enters the turbine building near the Unit 3 moisture separator and the maximum air concentrations (about 3E-08 uCi/cc) were observed in this area. A licensee representative stated that it was believed
- 13 -
.
.
.
.
,
-
that faulty level control on the of f-gas drain tank pump permitted it to continue to operate and thus aggrevate the problem.
Investigation of this problem by the licensec is
,
continuing.
(
11.
Missed Air Samples, March 1976
~
Air sampics in the Unit I cast and west pipeways required weekly by Technical Specification 4.6.D. l.a, were inadvertently missed during the week March 21-27, 1976. The occurrence was identified and corrected by the licensee, and the inspector noted that this lapse has not been repeated.
12.
Inspection of Facilities During the inspection several visits were made by the inspectors to selected areas of the plant, emphasizing mainly radwaste facilities. A licensee furnished portable survey instrument was used to verify radiation levels encountered. All high radiation areas observed were properly posted and controlled.
The Unit I radwaste arca remains a posted and locked high radiation area because of radiation levels (120 mR/hr at 3 feet)
near holdup tanks outside the building. During the inspection the licensee completed a six foot hi shielding for the radwaste building.g!j concrete wall to provide
-
-
Exposure rate reduction by a f actor of about ten was noted. Ground surface conditions in the area were satisfactory, with no contaminated areas noted. The
-
i entire yard had been resurfaced with clean gravel.
Septic tanks awaiting shipment in the ANEFC0 compound were examined. The maximum exposure rate observed at contact with a tank was 60 mR/hr. All other tanks read less than 10 mR/hr.
Exposure rates at the fence near the tanks was about 0.2 mR/hr.
Operations in the Units 2/3 radwaste buildings were observed. Good radiation protection practices were noted in handling and surveying of radwaste drums. Added equipment to reduce exposures included a shielded fork lift truck and a shield for use when attaching grapples to high level drums.
General occupancy exposure rates observed were 1.to 5 mR/hr, with levels between storage bays ranging from 5 to 20 mR/hr.
It was noted that workers involved in wiping down and capping drums wore film badges tapped to a leg, the highest exposure point on the body.
4/ IE:III Inspection Rpt No. 050-010/76-05.
- 14 -
-
.
l
.-
,
Conditions in the Unis7 2/3 radwaste basement remain as
'
i previously described.-
It is posted as airborne based on air
{
i sampics ranging from IE-10 to IE-09 uCi/cc. Exposure rates were generally 25 to 100 mR/hr, with 2.5 R/hr observed in contact (
with a pump. The floor appeared clear of resin and sludges and generally clear of water except near the pump.
.
The Unit 3 ARM multipoint recorder trace in the control was noted to be legible; recovery of data would still be difficult because of the large number of readouts being plotted. No program for improved surveillance of this recorder was noted.
The recorder for Uait 2 was observed to be out of service beginning June 4, 1976. A licensee representative stated that necessary parts were on order.
13.
Respirator Fittings The radiation protection supervisor has issued a memo to his department concerning indyviduals who are unable to achieve a respirator fit in class.
It reiterates the station policy prohibiting beards and requires notation to be made on an individual's training record and pcsting of it at the radiation protection office if a fit is not achieved.
It is also emphasized to the individual that he must achieve a fit before using respira-tors. The system was observed to be in use during this inspection.
14.
Noncompliance Followup (
The licensee's c97rective action regarding use of uncalibrated
-
neutron monitors-was reviewed.
It was observed that the monitorshadbeencalibratedsatisfactorilyonApgp124andMay 6, 1976, as indicated in the licensee's response.- However, the procedure to specify calibration frequency had not been drafted and the item remains open until that is completed.
5/ IE:III Inspection Rpt. No. 050-010/75-14.
6/ IE:III Inspection Rpt. No. 050-010/76-05.
7/ Ibid.
8/
Ltr, Bolger to Keppler, dtd 5/21/76.
i
!
!
- 15 -
!
l l
.