IR 05000010/1976005
| ML20037B404 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/16/1976 |
| From: | Essig T, Fisher W, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20037B403 | List: |
| References | |
| 50-010-76-05, 50-10-76-5, 50-237-76-05, 50-237-76-5, 50-299-76-04, NUDOCS 8009250548 | |
| Download: ML20037B404 (18) | |
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UNITED STATES NUCLEAR RECULATORY C0dD!ISS10N OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report of Operational Radiological Inspection IE Inspection Report No. 050-010/76-05 IE Inspection Report No. 050-237/76-05 IE Inspection Report No. 050-249/76-04
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Licensee: Commonwealth Edison Company
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P.O. Box 767 Chicago, Illinois 60690 Dresden Nuclear Power-Station Licenses No. DPR-2 Units 1, 2 and 3 No. DPR-19 Morris, Illinois and No. DPR-25 Category:
C Type of Licensee:
BWR, GE 210, 810 and 810 Mwe Type of Inspection:
_ Routine, Unnannounced
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Dates of Inspection: Mar::h 15-19, 31 and April 1, 1976 W. Yutnb sli'
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Principal Inspector:
M. $chumacher (Date)
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.k h'. D Accompanying Inspector:
T. Essig l
(Date)
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Other Accompanying Personnel: None
l Reviewed By:
W. L. Fisher, Chief dhG Fuel Facility Projects and (Date)
Radiation Support Section
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SUMNARY OF FINDINGS
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Inspection Summary
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Operational Radiological Protection Inspection for Units 1. 2, and 3 on March 15-19, March 31 and. April 1 (Unit 1, 76-05), (Unit 2, 76-05), and (Unit 3, 76-04): Inspectien-included review of abnormal occurrences, noncompliance'and commitment followups, review of selected records and procedures related to the radiation protection program, observation of radiation protection _ work in progress and independent measurements of radiation fields at selected locations.-
One noncompliance item concerning inadequate evaluation of neutron dose equivalent rates because of questionable instrument calibration was identified for Unit 1.
Enforcement Item Infraction s
Contrary to 20.201(b), surveys of neutron dose equivalent rates in Unit 1 on February 17, 19 and 25 and March 31, 1976, were inadequate to ensure compliance with 10 CFR 20.101.
(Paragraph 6.d, Report Details)....,
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Licensee Action en Previously Identified Enforcement Items
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A.
Licensee corrective actions with respect to enforcement item A.2 identified in the IE:III letter of August 11, 1975, were reviewed. We have no further questions at this time.
(Para-graph 12.c, Report Details)
B.
Licensee corrective actions with respect to Enforcement Items A.1 and A.2, identified in the IE:III letter of December 15, 1975, vere reviewed. We have no further questions at this time.
(Paragraphs 12.a and' 12.b, Report Details)
Other Significant Items A.
Systems and Components
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None.
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B.
Facility Items (Plans and Procedures)
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Unresolved item: The licensee's program for bioassay of con-i
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tractor personnel needs improvement.
(Paragraph 6.c,. Report Details)
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C.
Managerial Items Radiatior.chbmistrydepartmentchangesincludetheaddition of a third health physicist and the appointment of a third radiation protection foreman. '(Paragraph 2, Report Details)
D.
Noncompliance Identified and Corrected by Licensee Three instances of apparent noncompliance with 10 CFR 20.203 involving unlocked and unattended high radiation area doors at Unit 2 were identified and corrected by the licensee on January 28,. February 4 and March 28, 1976.
(Paragraph 12.a, Report Details)
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Deviations
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None.
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F.
Status of Previously Reported Unresolved Items The licensee is in the process of converting his filter
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respirators to NIOSH 1 approved devices.
If and when the vendor succeeds in obtaining approval of the currently used
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cartridge, the licensee will return to it.
This item, identified-
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in IE:III Inspection Report No. 050-010/75-06, remains open.
Management Interview l
A management interview was conducted on April 1, 1976, with Messrs.
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Stephenson, Abel, Watts, Adam, Maney and Legner.
The inspector stated that this inspection completed the annual radiation protection inspection which was begun in November 1975.
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A.
The inspector stated that neutron dose equivalent rate surveys made with uncalibrated neutron mo.a.' tors were regarded as an instance of noncompliance with respect to the requirements of 10 CFR 20. (Paragraph 6.d, Report Details)
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B.
The inspector discussed the problem of unlocked high radiation area doors noting that thd licensec's corrective action
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appeared to be having some effect. Ihr observed that the
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licensce had identified and corrected three such occurrences since November 1975.
(Paragraph 12.a. Report Details)
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C.
The inspector noted the licensce's corrective actio'n regarding-the iodine air sampling infraction and stated that he had no further questions.
(Paragraph 12.b, Report Details)
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D.
'The inspector stated that he had no further question regarding evaluation of events leading to surface contamination cast of the Unit I radwaste building, but' emphasized a continuing interest in the surveillance program being conducted there.
(Paragraph 12.c, Report. Details)
E.
The inspector noted the fulfillment of the following commitments previously made by the licensee:
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1.
Remo"al of surface contamination east of radwaste.
(Paragraph 12.c, Report Details)
2.
Removal of solids from the floor.of the radwaste vault.
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(Paragraph-13.b, Report Details)
3.
Visual inspection for cracks and monitoring for vault
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in-leakage.
(Paragraph 13.b, Report Details)
4.
Revision of Unit I chimney sample procedure to improve surveillance of sampler flow rates.
(Paragraph'13.a, Report Details)
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F.
The inspector stated that his review of station exposures for l
1975 indicated that stronger efforts were needed with respect to maintaining exposures as low as reasonably achievable.
i The importance of health physics review, rehearsal and use of
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mockups and, above all, management commitment were discussed.
(Paragraphs 6.b and 10.b, Report Details)
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The inspector discussed the increase in the percentage of
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people showing detectable body burdens and stated that he
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considered the question of contractor bioassays an unresolved item.
(Paragraph 6.c, Report Details)
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The inspector stated - that surveillance of direct radiation, 11.
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except neutron, contaminat' Ion, and airborne radioactivity.
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appeared to be satisfactory.
(Paragraphsi6.a and16.d,
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Ecport Details)
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The' inspector noted the following with regard to training:
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1.
The discussion of risk from radiation dwelled mainly on acute exposures and did not adequately treat the linear assumption of risk as the basis for maintaining exposures as low as reasonably achievable. -
The licensee stated that this aspect of radiation protection training would be reviewed.
(Paragraph 4.a, Report
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Details)
2.
Respirator training class recorda do not permit the licensee to confirm that an attendee.who was unable to achieve a fit in class because of a beard was subsequently able to achieve a fit after shaving.
The licensee agreed to revise this procedure.
(Paragraph
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4.b, Report Detials)
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The inspector stated that he had reviewed the radiological
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aspects of four licensee reported occurrences. No problems
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were noted except with respect to the TIP overdrive occurrence of January 9, 1976, where the illegibility of printed symbols prevented the retrieval of data from the ARM multiprint recorder.
The licensee stated that maintenance of the recorder would be improved.
(Paragraph 11, Report Details)
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The licensee discussed planned changes in the respiratory protection program. The inspector stated that this item remains unresolved. (Paragraph 7 Report Details)
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The inspectors discussed observations made during tours of the plant, including need for additional shielding at the
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Unit I waste holdup tanks.
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The licensee stated that additional shielding would be provided.
(Paragraph 10, Report Details)
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t REPORT DETAILS
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Tecsons Contacted B. Stephenson.. Station Superintendent.
A. Roberts,-Assistant Station Superintendent J. Abel, Administrative Assistant T. Watts, Technical Staff Supervisor
E. Budzichowski, Operating Engineer D. Adam, Radiation Chemistry Supervisor
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D. Simpson, Health Physicist.
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- J. Parry, llealth Physicist j
G. Bergan, Chemist T. Schneider, Chemist R. Schumacher, Radiation Protection Foreman
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V. Chaney, Radiation Protection Foreman D. O'Keefe, Radiation Protection Foreman i
~ R. Tromp, Engineering Assistant'
C. Rapp, Engineering Assistant J. Testa, Radwaste Supervisor I
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R. Legner, Quality Assurance Engicer
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C. Mancy, Engineering Assistant
- E. Saunders, Phillips-Get. chow
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F. Miller, ANEFC0
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2.
Radiation Protection Organization - Staff Changes The following radiation chemistry department changes have been made:
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Addition of a third health physicist on to fill a vacancy-created by a resignation during fourth quarter of 1975.
b.
Addition of a new chemist in mid March 1976 to replace
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the chemist who will be transferring to the La Salle
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County-station. Qualifications include a'B.S. in Chemistry and 6 years of nuclear navy experience.
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Addition of an engineering assistant to replace man 1.
transferring to Collins Station.
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A third radiation protection foreman position created
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and filled by promotion of a radman.
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Complement of radmen increased from 23 to 28 in February and then reduced to 27 with promotion to foreman.
3.
Licensee-Conducted Audits A review was made of the radiation protection aspects of the onsite and offsite audits conducted by the licensee during the year ending March, 1976. Onsite audits were conducted quarterly by station personnel and offsite audits were conducted semiannually, as required by Technical Specification 6.1.
The program was found to be satisfactory in that for several items of radiation protection interest, appropriate corrective action was taken.
4.
Training The review of radiation protection and respiratory equipment training consisted of one of the inspectors attending a regulatory scheduled training class and reviewing the relevant procedures.
a.
Radiation Protection Training
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The inspectors found that both procedure and the actual conduct of the class were satisfactory except for the lack of discussing risk associated with radiation exposure.
The licensce's representative mentioned the fact that radiation can be lethal if the level is high enough, but no mention was made of the risk (albeit relarively small) associated with exposures within the limits of 10 CFR Part 20.
Such a discussion would help serve as an impetus for an individual to maintain his radiation exposure as low as is reasonably achievable (ALARA).
b.
Respiratory Protection Equipment Training The inspectors found that both the procedure and the actual conduct of the class were satisfact6ry, with a possible exception related to individuals wearing beards.
During the portion of the class related to actually donning respiratory protection equipment for the purpose of determining whether a proper facial fitting
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could be achieved for each individual, it was pointed
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out to the individuals in the class who were wearing
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beards that a proper fitting could not be performed
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because of the beard.
It was further indicated by the licensee representative instructing the class that each individual wou'd have to shave his beard prior to any work which would require the use of respirrtory protection equipment. However, no indication was made on the check-off sheet (given to everyone in tFe class)
regarding those individuals with beards. Hence, it did not appear that there was any way for the licenoee to take any followup action, such as assuring that the bearded individuals eventually received a proper fitting to the equipment.
5.
Radiological Protection Procedures The inspectors reviewed the following newly added or revised procedures related to radiological protection:
37-1-22 (Rev. O), January 1976
- Whole Body Counter.
37-1-E5 (Rev. 0), October 1975
- Rescue of Personnel in Iligh Radiation Areas.
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37-2-6 (Rev. 2), January 1976
- Description of the Dresden Calibration Facility.
37-2-10 (Rev. 0), January 1976
- Calibration of the Cutie-Pie Survey Meter.
37-2-13 (Rev. 0), March 1976
- Calibration of the R0-3, Ion Chamber Survey Meter.
37-3-3 (Rev. 2), November 1975
- Routine Off-Gas Sampling and Analysis - Dl/D2/D3.
37-3-19 (Rev. O), January 1976
- Routine Laboratary Analyses.
37-3-23 (Rev. O), January 1976
- Sampling and Analysis of Rad-waste Tanks.
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37-3-24 (Rev. 0), December 1975
- Operation of the RADcCO Air Sampler.
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'37-3-H-2 (Rev. 1), April 1975
- Radiation Protection Orientation.
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37-3-H-3 (Rev. 2),' January 1970
- Initial Drywell Entry Following
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37-3-H-18 (Rev. 0), December 1975 - Preparation of Termination.
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Letters.
37-9-4 (Rev. O), January 1976 D2/3 Incore Sipping with Sipping Cart.
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37-9-31 (Rev. 1), January 1976
- Calculation of Radioactivity in Liquid Samples for Discharge
Permits.
37-9-33 (Rev. 0), December 1975
- Transfers of Co-60 and Cs-137 Radiation Sources.
f 37-9-34 (Rev. O), February 1976
- Radiation Protection Procedure
for Dresden Units 2 and 3 Spent Fuel Pool Modifications.
i No problems were noted in review. Station review cnd approvals-
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appeared to be in'accordance with Dresden procedures.
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6.
_ Radiation Protection Records Evaluation
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In-Plant Air Sampling
I A review of air sampling records-for the period November 1975 through March 1976 indicated a satisfactory sampling'
program. Program deficiencies relating to-iodine sampling
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I appear to have been corrected.
(Paragraph 12.b. Report Details) The Unit I sphere was frequently posted as an
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airborne radioactivity area during the period, based on
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beta-gammi1particulateactiv$tylevelswhichrangedfrom
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toabout_}3x 10 sygi/cc. Alpha activity j
ranged from about 10 to 10 uci/cc (4 to 6 hr s
decay). A spot check of records back to 1959 indicated no apparent change in levels.
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b.
Personal Monitoring
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Personal monitoring records for November 1975 through
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March 1976 were examined. No exposures in excess of NRC
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limits were found.
Indicated overexposures ( > 3 rem)
on the microfiche record for the second quarter of 1975 were demonstrated to be a result of the same badge and dosimeter results being entered twice.
Comparison of this record with the daily dosimeter logs and the film badge vendor's report was satisfactory. A spot. check of NRC-4's for contractor personnel revealed no problems.
Examination of the cumulative records for 1975 indicated approximately 53 individuals ~with exposures greater.than
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5 rcm, including 40 contractor employees.
The licensee reported a total station dose of about 3100 man-rem fore the year, with about 70% being incurred by contractor employees.
The inspector noted that the licensee maintains plots of the vendor's performance on spiked film badges which are routinely submitted. Discrepancies noted for spikes submitted in June and October 1975 were attributed by the licensee to errors he made in positioning-and timing
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at his calibration facility. The most recent spikes
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were done with a newly installed and calibrated cesium-
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137 source which permitted exposure at greater distances, (
thus reducing positioning errors.
The ratios of reported to reference value for the period ranged from 0.9 to 1.3
'for gamma and mixed beta-gammc exposures. A licensee representative stated that errors greater than about 15%
are discussed with the vendor.
c.
Bioassay
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The inspectors reviewed records of approximately 240 whole body counts done between October 1975 and March 1976. The frequency of observed radionuclides was
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cobalt-58 (16%), cobalt-60 (92%), cesium-134 (60%),
cesium-137 (100%) and iodine-131 (4.6%). Three individuals showed cobalt-60 body burdens in excess of 10% of MPBB (Based on the lung).
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The observed frequency of cobalt-60 in whole hc ly counting indicates the need for improvement of the contractor bioassay program beyond the termination urine samples e
which are currently being taken. A detailed check of
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personnel _ records indicated that many contractors who
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continue co' work at the station have still not had a bioassay.
d.
Radiation Surveys and Exposure Control Selected survey records for the period November 1975 through_ March 1976-were reviewed.. Surveillance remains generally satisfactory. However, evaluation of neutron dose equivalent rates made February 17 and 19 and March 31, in the secondary steam generator rooms of Unit 1 and February 25, 1976,-on the 584' level of Unit I were inadequate by virtue of being made with inadequately calibrated' instruments. The licensee's records showed that the two neutron survey instruments had last been calibrated in January 1975 and May 1973.
7.
Respiratory Protection Equipment A review of respiratory protection equipment indicated that a'
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major change was in progress. The change consisted of the licensee having ordered (September 4,1975) conversion kits
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which allow the existing half-and full-face masks to accept
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larger diameter, N10SH-approved cartridgas. The licensee f
also placed an order (February 27, 1976) with the same' vendor
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for the larger diameter MSA, Type 11, Ultra Filters- (NIOSH Approval No. TC21C-135).
Until all of the new equipment arrives and the conversion is made, the licensee plans to use his present egoipment, which includes MSA GMA-H combination cartridges (Type H Ultra Filter plus charcoal). These cartridges have neither USBM nor NIOSil approval, however, the Type H ultra filter above
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has been approved (BM 21B-90) for protection against radio-nuclides in particulate form. The combination cartridge has not been approved for protection against halogens, however, the licensee is not taking credit for such protection.
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It is the licensec's understanding that the vendor has been pursuing'N10S!! approval of the combination cartrjdge for use
againut particulates.
If and when this approval is granted, f,
the licensee intends to resume using it.
The inspectors also
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reviewed the mask laundry, inspection and storage facility
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and found conditions to be satisfactory.,
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8.
Materials Inventory j-A review was made of the licensec's program for scaled source
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s inventory and leak testing. The license conducted a quarterly inventory and semiannual leak test as required. All of.the approximately 30 sources were at:ounted for and none were found to be leaking. One of the inspectors physically verifice the location of 16 of the sources on the inventory. The program was found to be satisfactory.
9.
Receipt and Transter of Materials Records _of incoming radioactive shipments for the period May-
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1975 through March 1976. Most of the shipments involved slightly contaminated tools, parts and other materials carried on sole use vehicles. The records indicated that receipt surveys are generally satisfactory although on two occasions,
drums containing pump and valve parts were taken to the job
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area before survcy.
The inspectors observed the loading of a shipment of 18 drums
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of solid radwaste bound for offsite burial. The-drums read 1
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to 4 R/hr at 2" with a working exposure rate averaging about 30 mR/hr. The work was efficiently donc, with remote handling by
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fork lift truck, overhead cranc, and long handled tools being j
used when possible.
Continuous coverage'was provided by radiation protection.
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The inspectors measured exposure rates of 65 mR/hr at 2 inches from the side of the truck, 15 mR/hr at 3 feet, and 5 to 9 l
mR/hr at 6 feet. The exposure rate in the cab was 0.3 mR/hr.
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10.
Facilities and Equipment I
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a.
Changes in Facilitics No significant changes in radiation chemistry department facilitics were noted. The supply of portable survey L
meters appeared improved with'the requisition of several new ionization chambers.
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Inspection of Facilitics
fN The inspectors made several tours of the plant to observe
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radiological conditions and ongoing radiation protection
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work. Licensec-furnished portable survey instruments
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were used to independently verify radiation levels.
l Housekccping in the arcas visitcd was generally good.
i All high radiation area doors encountered were found to be locked or properly attended. Access controls for restricted and radiation areas appeared satisfactory.
Hand and foot counters and portal monitors were found-to
be operable, but many suffered from reduced sensitivitics
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because of background conditions.
For example, the
monitor in the Unit 1 trackway was affected by accumulated trash in an adjacent crash collection point.
The inspectors observed work in the Unit 2 drywell associated
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with control rod drives, 4" bypass lines, MSIV's and
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safety valves. Exposure rates were variable, ranging from l
1 mR/hr at the change area to 350 mR/hr i foot away from the B recirculation line. Crowded conditions hampered i
movement throughout much of the drywell. and exposure rates
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along routes to some of the work areas exceeded 100 mR/hr because of the close p roximity of piping and equipment.
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The use of preformed or ficxible shielding was not observed.
It appeared that a more thorough management review of the work should be made to determine if substantial dose
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reduction is possible. The work of the radiation protection
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men covering the jobs appeared satisfactory and discussions with them indicated they had a good awareness of radiological j
conditions at the work locations.
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The inspectors observed the installation of a manifold-sampling system in the Unit 1 off-gas treatment building
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i which is under construction.
It is to be used for
following air activity trends in rooms which will be closed during. operation. The sampling lines were unneces-
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l sarily long, of small (1/4" OD) diameter and had many
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sharp bends which uill probably make them unsuitable for l
particulate or iodine sampling.
No problems were noted.in the Units 2 and 3 radwaste drumming' area. Exposure rates observed in the general working areas ranged from about 1 mR/hr near the door, to
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about 10 mR/hr near the drum enpping station, to about 40 mR/hr between the storage baya. A license representative
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stated that a shielded fork lif t truck for handling filled
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drums had just arrived and would be put into service soon.
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Operation of a new liquid waste discharge monitor was awaiting testing and calibration by'the licensee's consultant.
The Unit I radwaste area remains a posted and ' ocked l
high radiation area because of radiation fields from the holdup tanks outside the building. The exposure rate en the sidewalk passing by the C holdup tank was noted to be 150 mR/hr. A 3' high shielding wall has been erected between these tanks and the radwaste building.
The exposure rate measured at the operator's console in the building was SmR/hr. Radiation levels cast of the building where new gravel had been laid were 3 to 5 mR/hr.
Levels in the room housing the pump used for moving resin and sludge to the ANEFCO building reached 40 mR/hr at the block shield wall around the valves.
It was observed that pump lockout procedures were apparently still being folloued.
The inspectors observed control room readouts of area and process radiation monitors. High alarm indications were showing for the Unit 3 air ejector ARM and the maximum recycle station (No. 34) ARM, owing to readings at or slightly above their respective setpoints of 1.2
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and 15 millirem per hour. The Units 2 and 3 chimney monitor was noted to have experienced an increase from
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about 70 to 200 cps.
A licensee representative stated this monitor is sometimes affected by nearby transfer lines between the floor drain collector tank and the floor drain neutralizer tank in the maximum recycle building. He stated that he had seen it on one other occasion about 6 weeks earlier.
Discrepancies were noted between recorder and meter readings for two Unit I turbine and auxiliary building ARM's.
At the same time, instrument mechanics were working on the multipoint recorder for the Unit I sphere ARM's, which had been printing fullscale for all monitors.
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11.
Unusual occurrences The inspector reviewed the radiological aspects of the following
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licensee identified and reported events.
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a.
Overflow of Unit J, B lloldup Tank, December 11, 1975 and January 2, 1976 'i'
i Faulty performance of level-indicating equipment resulted in overflow of the Unit 1, "B" lloldup Tank on two occasions.
Activity spilled onto the ground was estimated at less than 5 microcuries. A new level transmitter was installed.
b.
Unplanned Release,co Unit 1 Circulating Water Canal, November 30, 1975d/
A break in a fire main traversing an excavation made for the purpose of connecting the Unit 1 off-gas holdup line to the new off-gas treatment system caused the ditch to fillup and overflow to the intake water canal for a period of about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Gross activity concentration in the overflow (estimated at 100 gallons per minute)
was about 2000 pC1/1.
Isotopic analysis indicated mangenese-54 ( < 500 pCi/1), cesium-134 ( < 300 pCi/1),
cesium-137 ( <C 200 pCi/1), strontium-89 ( < 200 pCi/1),
and strontium-90 (.( 20 pCi/1) in the discharge.
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Circulating water flow of 128,000 gallons per minute resulted in dilution of this overflow to less than 2% of permissible limits.
c.
Traversing In-Core Probe (TIP) Overdrive, January 9, 19764/
Instrument mechanics working on the Unit 2 TIP console in the control roon found that the "B" TIP had been retracted approximately 90 inches beyond the in-shield l
position.
It was verified that the probe had remained l
within the locked TIP room.
The TIP was restored to its
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normal inshield position and a misaligned limit switch j
was fixed.
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This information was developed by discussion with l
involved maintenance and~ radiation protection personnel.
l A review of the 40-point recorder trace to obtain relevant l
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RO No. 010-75-16, dtd 1/6/76.
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RO No. 010/76-1, dtd 1/29/76.
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A0 Rpt No. 010/75-15, dtd 12/10/75.
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RO No. 237/76-3, dtd 1/26/76.
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ARM data failed because the different points could not be distinguished from one another.
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d.
Unit 3 Off-cas Increann, November 25, 1975 The licensee reported that the Unit 3 air ejector off-gas increased from about 200 to 500 millicuries per second on November 25, 1975. The RECIIAR system with.12 charcoal beds in series had been operating since mid-October and was experiencing small leaks such that the release rate measured downstream of the beds was about 0.7 millieuries per second. On November 26, this increased to about 2 millicuries per second, decreased to about 1 millicuries per second the day after, and remained there until shutdown on December 4.
Work was done on RECllAR system valves, and following startup on December 9, the release rate established at about 0.08 millicuries per second, indicating that the leaks were no longer present.
The release has remained at approximately the same level since. The radiological consequences of the off-gas increase were minimal. Prior to operation of the RECHAR system in mid-October 1975, the release rate was in the neighborhood of 20 millicuries per second, about 3% of the technical specification limit for a single unit.
12.
Noncompliance Followup
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Corrective actions taken by the licensee in response to the following previously identified enforcement items were reviewed, b
a.
Unlocked High Radiation Area Doors, November 18, 1975 The licensee is making special efforts to reduce the incidence of unlocked high radiation areas.
The importance of this effort was emphasized in the December 1975 safety cor nittee meeting and in a memo addressed to all station supervisors from the assistent station superintendent.
Signs have been posted in strategic locations to remind personnel to relock high radiation area doors, and evidence of increased surveillance was noted.
Identi-ficd violators are to meet with the assistant station superintendent and repeat violations will be cause for suspension. The licensee has identified and corrected three instances of unlocked doors occurring on January 28, February 4 and March 28, 1976. The inspectors observed no such occurrences during visits made throughout the plant during this inspection.
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A0 Rpt No. 249/75-44, dtd 12/11/75.
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IE:III Inspection Rpt No. 237/75-25.
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b.
Inadequate Evali;ation of Airborne Iodine Concentration, September 1975 '
The requirements for air sampling for radioiodine were
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outlined in a memo to the radiation chemistry department from the radiation chemistry supervisor, and a routine surveillance program has been established, using constant air monitors and other air samplers having iodine collection capability. The acquisition of additional portable air samplers for iodine is being considered. The inspector's review of the program indicated no problems.
c.
Ground Contamination at Unit 1 Radwaste The inspectors observed that the licensee had completed the removal of contaminated soil from the area east and south of the Unit I radwaste building and had placed it in containers for shipment to an offsite burial site.
A new gravel surface had bcea laid down in the area.
A small area of contamination observed at the south edge of the concrete pad was the result of decontamination of the A centrifuge. A licensee representative stated that this would be removed and a new surface laid down.
Routine sampling of radioactivity in witer taken frcm a surveillance well in the backfill is continuing.
Radio-
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nuclides identified were ecsium-134, cesium-137, manganese-54, cobalt-58 and cobalt-60.
Almost all of the activity was associated with the filterable fraction.
The maximum concentration noted in any one sample was less than 20%
of the MPC for unrestricted areas.
No anomalies were
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observed in relevant environmental samples.
13.
Licensee Commitment Followup Actions by the licensee with respect to commitments in the
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following areas were reviewed.
a.
Reporting Unit 1 Chimney Flow Ancmalies /
The licensee has made a change to procedure 37-3-18,
"D/l Chimney Filter Sample Replacament" that requires reporting to the shift engineer it proper chimney sampic flow cennot be obtained.
Il lbid-8/
IE:III Inspection Rpt No. 010/75-14.
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b.
Unit 1 Radwante Spill p May 102
Removal of approximately 100,000 ft of contaminated
soil from the vicinity of the ANEFC0 building has been
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completed. Approximately 35% of the material in contained in tanks awaiting shipment to a burial facility offsite.
Removal of resin and sludge from the Unit I radwaste vault was achieved in February 1976. A licensco repre-sentative stated that remote visual inspections of the vault and the tanks are being made cach shift by a radwaste foreman, that no wall cra'cks have been observed, and that no evidence of scepage into the vault from outside has been seen.
Biweekly observations of the water level in the surveillance nell in the back fill show a fluctuation between 506' and 509' MSL. The vault floor is at approximately 490' MSL.
A contract has been awarded to INEFC0 for the removal of material from the resin and sludge tanks in the vault. Vault entry, detailed inspection, decontamination and and installation of pumps and level instrumentation is expected to follow.
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IE:III Inspection Rpt No. 010/75-10.
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