IR 05000254/1979015
| ML19208D864 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/17/1979 |
| From: | Dubry N, Greger L, Hueter L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19208D863 | List: |
| References | |
| 50-254-79-15, 50-265-79-13, NUDOCS 7910010227 | |
| Download: ML19208D864 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/79-15; 50-265/79-13 Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee: ommonwealth Edison Co.
P.O. Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Plant, Units 1 and 2 Inspection At: Quad Cities Site, Cordova, IL Inspection Conducted: July 10-13, 1979 c?.}J.Hueter. k%)Y L'.
I-/f 7f Inspectors:
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Approved By:
L. R.
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Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on July 10-13, 1979 (Report No. 50-254/79-15; 50-265/79-13)
Areas Inspected: Routine, unannounced inspection of radioactive waste systems, including: effluent releases; records and reports of effluents; effluent control instrumentation; procedures for controlling releases; containment air-cleaning systems; reactor coolant water quality; solid radioactive waste processing and shipments; posting; review of an LER with the licensee; and licensee actions on previous inspection findings.
The inspection involved 61 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance or deviations were identified in the ten areas inspected.
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am 7910010
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DETAILS 1.
Persons Contacted
- K. Graesser, Assistant Superintendent, Adminsitrative and Support Services
- T. Tamlyn, Assistant Superintendent, Operations
- L.
Gerner, Technical Staff Supervisor
- J. Heilman, Quality Assurance Engineer
- R. Flesner, Rad-Chem Supervisor
- W. Walschot, Lead Chemist
- T. Kovach, Lead Health Physicist D. Anderson, Staff Assistant J. Forest, Staff Assistant-Radwaste G. Tietz, Thermal Engineer M. Whitemore, Chemistry Laboratory Foreman P. Shafer, Health Physicist W. Munyon, Health Physicist J. Markwalter, Chemist G. Sikkema, Chemist
- Denotes those present at the exit interview.
2.
General This unannounced inspection began at about 10:30 a.m. on July 10, 1979. On that date a tour of the plant with emphasis on the areas involving the radwaste systems was made. Housekeeping was generally satisfactory in the areas toured.
Some loose trash was noted in the area of the trash compactor. The licensee is modifying an inoperable urea formaldehyde solidification system to the DOW (Dow Chemical Company) process. The licensee has experienced continuing problems in meeting the design objective release rate for airborne radioiodine and radioactive particulate effluents. The release rate in early July was below the reporting level but above the design objective release rate.
3.
Radiation Protection Organization TheplannedpersonnelchangeinthepositionofRadiapponChemistry Supervisor referenced in a previous inspection report-took place early this calendar year.
Some changes in organizational structure have recently occurred which also affect the radiation protection organization. Fo rmerly, the radiation chemistry supervisor reported to the technical staff supervisor who in turn reported to the assistant plant superintendent 1/
I.E. Inspection Report No. 50-254/79-04.
-2-1058 303
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and he in turn to the plant superintendent. Under the new organization, the assistant plant superintendent position has been replaced by three assistant superintendents representing administrative and support services, operations, and maintenance. The radiation chemistry supervisor position has been elevated to a department head reporting directly to the administrative and support services assistant superintendent.
Directly under the radiation chemistry supervisor, the lead health physicist and the lead chemist positions have been elevated to group leaders. Six new radiation chemistry technicians are to begin the formal training course on July 16, 1979.
4.
Liquid Effluents Licensee records of liquid releases were reviewed in detail for the fourth quarter of 1978 and selectively for the third quarter of 1978 and the first and second quarters of 1979. T.he inspector _ identified a problem regarding volume of dilution flow.
It was traced by the licensee and verified by the inspectors to be an error in a new program initiated in August 1978, when a new calculator was obtained.
A final zero had been omitted in the program for both the lift pump and the circulating water flow rates resulting in these flow rates both being low by a factor of ten.
The net effect was a conservative error by a factor of 2 to 3 in the volume of dilution flow. This in turu led to conservative errors in five other items reported for liquid effluents in Table 2A of the semiannual effluent report for the last half of 1978. The semiannual report for the first half of 1979 has not yet been issued. These errors included the average diluted concentration for (1) fission and activation products, (2)
tritium, and (3) gross alpha radioactivity; and the percent of applicable release limit for (1) fission and activation products and (2) tritium. The licensee developed a corrected program before completion of the inspection. No other problems were identified in review of liquid effluents. All releases appear to have been made in accordance with regulatory requirements.
No items of noncompliance or deviations were identified.
5.
Airborne Radioactive Effluents Airborne release records were reviewed in detail for the first quarter of 1979 and selectively for the third and fourth quarters of 1978 and the second quarter of 1979. No calculational errors or problems in computational methods were identified.
Release quantification continues to be based on daily grab samples from the chimney (noble gas), gas activity detected by the reactor building vent CAM, and daily integrated charcoal (iodine) and filter (particulate) samples from the chimney and reactor building vents.
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During a previous inspection,2/ the licensee was noted to have exceeded the design objective release rate for iodine-131 and radio-active materials in particulate form with half-lives greater than eight days. These releases have exceede.1 the design objective contained in the technical specifications in the past but did not exceed the reporting level (twice the design objective) until the third quarter of 1978. A corrected * iodine and particulate release summary for 1978 follows:
1978 Calendar Quarter Multiple of Design Objective 1st 1.9 2nd 1.8 3rd 4.0 4th 3.2 Several fluid leaks were identified and repaired effecting some reduction in effluent releases; leaking fuel from Unit I was believed to be a significant contributor to the releases. The Unit I refueling in January-February 1979 included removal of leaking fuel identified by fuel sipping but did not provide the anticipated improvement.
With renewed operation of Unit 1 in March it was apparent that these releases were still more than twice the design objective.
Concentrated efforts were then made to identify system leaks and to make repairs.
Work orders show that over sixty repairs of leaks were performed in the first half of 1979.
Significant radiation exposure to operators has resulted from these efforts. According to licensee personnel, one operator is approaching 5 rem dose for 1979 due primarily to these repair efforts.
The release rate for the first quarter of 1979 was about 4.4 times the design objective for iodine-131 and particulates based on gross beta analysis of daily samples. Although final results for the second quarter of 1979 were not available at tne time of the inspection, licensee personnel stated it would be similar to first quarter results.
Efforts at reducing leaks in the reactor buildings have been successful in lowering the release rate from these buildings via the common vent stack to a combined total of about one third of the design objective.
Efforts were less effective in eliminating leaks in the turbine building which exhausts via the chimney. At the time of this inspection, two leaks had been identified in the turbine building which had not been fixed. One was a small leak in the Unit I high pressure turbine which would require a shut down to repair. The
- This data corrects a nonconservative error of two which appeared in IE Inspection Report No. 50-254/79-04.
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IE Inspection Report No. 50-254/79-04.
-4-1058 305
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other was a larrer leak at a flange on a line to the HP heaters. A
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clamp which is expected shortly can be installed while the unit is operating.
Near the er.d of June, a conservative sampling error was discovered and corrected. A filter housing on the chimney samp1'ng system was found to be loose and leaking air. This leak was located between the charcoal / particulate filters and the flow meter, hence more air was being sampled than indicated by the flow meter.
The indicated release rate of iodine-131 and particulates via the chimney dropped by a factor of two when the leak was corrected.
In the first half of July the release rate of these nuclides by all gaseous paths (based on gross beta analysis) has dropped to about twice the design objective.
The licensee has completed an evaluation, since the previous inspection, that indicates an inherent conservatism in the technique for quantifying particulate releases based on gross beta analyses. The conservatism equals about 38%. The licensee is considering performing a more accurate gamma isotopic analysis instead of the gross beta analysis.
Licensee studies indicate the major remaining contributor to the chimney release rate is the gland seal steam which has a relatively short hold-up time and no clean-up system.
Its activity probably increases approximately proportionally to the air activity at the steam jet air ejectors. The full power off gas release rate has increased in the past year from about 40,000 to 110,000 microcuries per second for Unit 1 and from about 90,000 to 130, 000 microcuries per second for Unit 2.
The increases are attributable to fuel cladding deterioration. Resin * usage and procedures for clean-up of the primary water have not changed according to licensee personnel.
Timely reports notifying the Commission of exceeding one half the design objective annual quantity during a calendar quarter and the corrective measures being taken have been submitted as required by Technical Specification 3.8.B.3.b.
No items of noncompliance or deviations were identified.
6.
Records and Reports of Effluents Refer to Paragraphs 4 and 5 regarding inspection of licensee records and reports of gaseous and liquid radioactive effluents.
7.
Effluent Control Instrumentation The inspector reviewed the effluent monitor functional test and calibration records for the period from July 1978 through June 1979.
The technical specification requirements for the functional tests and calibrations, including the required alarm and trip levels,
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appear to have been met.
Current calibration curves for the offgas, reactor vents, and chimney monitors were posted in the control room.
At the time of a previous inspection ! the licensee was working on S
an improved chimney gas monitor calibration procedure utilizing stronger sources of gas obtained at the steam jet air ejector instead of the relatively low level activity obtained at the stack. The work to provide better calibrations and more meaningful alarm set points has been completed.
At the time of a previous inspection reportSI the licensee had agreed to review the continuing problem of high backgrounds at the liquid radwaste monitor.
Piping and shielding modifications were made which reduced the background count rate from about 3500 cps to about 1700 cps currently. A background count rate of about 1200-1300 cps had been obtained immediately after the modification.
This reduction represents a significant improvement.
No items of noncompliance or deviations were identified.
8.
Solid Radioactive Waste Solidified waste consists of spent powdered and bead type resins and filter sludge. The licensee has no installed radwate evaporator.
Waste solidification improvements made during the past year include:
a.
The mixer blade was lowered farther into the drums for more ccaplete mixing.
b.
A small amount of dry cement is preloaded in the drums to promote more complete solidification.
The mixer blade configuration was changed for a more thorough c.
mixing of waste and cement.
d.
The mixing time has been increased to provide a more uniform mixture of waste throughout the drum.
The above changes were a result of studies performed following the discovery of three damaged drums in June 1979.
On March 19, 1979, the licensee was notified that a shipment of solidified, potentially contaminated waste oil was found leaking at a terminal in Joplin, Missouri. The Lead HP and Radwaste Engineer were dispatched to the site. They discovered the drums had been 3/
IE Inspection Report No. 50-254/78-20.
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Ibid.
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incorrectly loaded with rags and plastic at the bottom of the container.
Analyses of samples indicated that no significant radioactive material was released. The contents were repacked correctly and a Deviation Report, D-4-1-79-40, was filed. The licensee has since instructed personnel on proper loading techniques. No other problems were noted.
ThelicenseeisstillintheprocessofmodificationsgfthePPI system to use the DOW cethod of waste solidification.
The licensee has had Chem Nuclear process reactor water cleanup system spent resins with their mobile urea formaldehyde solidification system. This resulted in a substantial reduction in site personal exposures. The inspector reviewed Temporary Change Nos. 1216 and 1218 to the operating procedures and found they had been reviewed and incorporated into the QC program. No problems were noted.
9.
Shipments Solid waste shipment records were reviewed for the period July 1978 through June 1979. Waste, normally solidified with concrete in 55 gallon DOT Specification 17H drums, is shipped in " sole use" trucks to licensed burial sites. Overpacks provide additional shieldiig and approved containment, when needed, for individual packages containing greater than Type A quantities of radioactive material. The licensee maintains records as required by 10 CFR 71.12(b).
Approximately 120 radwaste shipments totaling 1100 curies and 110 shipments totaling 1700 curies were shipped in the second half of 1978 and first half of 1979, respectively. The review of shipping documentation included:
the cover record description sheet, a shipment record item breakdown, a radioactive waste worksheet, the vehicle survey sheet, a QA manual checklist and instruction in accordance with 10 CFR 71 and an isotopic analysis of solidified contents for shipment. The licensee's records appear complete.
The licensee expressed concern with planned shipping of greater than Type A quantities in a Chem Nuclear cask due to wording on the Certificate of Compliance No. 9113. The matter was discussed with Chief Transportation Branch, NMSs, U.S. NRC on July 10, 1979.
It was confirmed that Certificate of Compliance No. 9113 contained a wording omission and that shipments of greater than Type A quantities of LSA material are authorized in this cask. This information was relayed to the licensee.
No items of noncompliance or deviations were identified.
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IE Report No. 50-254/78-20 and No. 50-265/78-21.
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10.
Containment Air Cleaning and Offgas System Licensee records of standby gas system in place penetration tests for HEPA and charcoal filters and laboratory tests of charcoal filter samples were reviewed for the period January 1978 to July 1979. Periodic tests are being done with satisfactory results in accordance with Technical Specifications. The offgas air cleaning system filter trains do not have routine technical specification surveillance requirements. The licensee said that the last efficiency tests were conducted in late 1974 following an October 1974 offgas explosion.
No problems were identified.
11.
Reactor Coolant Water Quality Records of primary coolant surveillance for radioactivity were reviewed for the period August 1978 through July 1979. No discrepancies from the technical specification requirements for iodine and isotopic analyses were identified.
No items of noncompliance or deviations were identified.
12.
Radwaste Control Procedurr_s The following radwaste c~ntrol proctdures were reviewed:
160-1 Revision 4, 4/16/79
" Standby Gas Treatment System In-Place D0P Leak Test of HEPA Filters" 160-2 Revision 2, 4/16/79
" Standby Gas Treatment In-Place Charcoal Absorber Leak Rate Test" 160-3 Revision 1, 1/9/79
" Standby Gas Treatment System HEPA Fi. 'er
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Flow Distribution Test" 160-4 Revision 1, 3/9/79
" Standby Gas Treatment System Removal of Charcoal Absorber Test Cannister" 160-S1 Revision 3, 3/9/79
"DOP Test Data Sheet" 160-S2 Revision 1, 3/9/79
"SBGTS from Filter In-Place Test" 160-S3 Revision 1, 3/9/79
" Checklist for QTS 160-3" 160-S4 Revision 1, 3/9/79
" Charcoal Absorber Test Cannister Analysis Checklist for QTP-160-4" No problems were noted in the review.
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13.
Posting The inspector gave the licensee current copies of NRC-3 forms to replace the licensee's outdated forms and will be looking into posting updates during a subsequent radiation protection inspection.
No items of noncompliance were identified.
14.
Review of LER/R0 79-10/03L The 2A fuel pool radiation monitor failed upscale on May 14, June 1, and June 2, 1979. The reactor building ventilation system isolated and the standby gas treatment system started as designed. Final repair was completed on June 2, 1979, and the monitor was returned to service. The 2B monitor was operable at all times and the require-ments of TS 3.2.F.2 were met.
The inspector reviewed, from a radiation protection consideration, the licensee's evaluation of the consequences, cause, and corrective action associated with the occurrence and has no further questions concerning this matter.
15.
Bulletins IEBu11eting8-08,FuelElementTransferTube,wasreviewedbythe inspectors No problems were identified.
16.
Exit Interview The inspectors met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on July 13, 1979.
The inspectors discussed the scope and findings of the inspection.
The following matters were specifically discussed:
The inspector noted that posting was antiquated.
(Paragraph 13)
a.
The licensee was given more current copies which were posted prior to the end of the inspection.
b.
The inspectors noted the improvements made to the radwaste solidification process.
(Paragraph 8)
c.
The inspectors discussed certification for the Chem Nuclear Cask No. 7-100 (Certificate of Compliance 9113) and passed on information obtained from the Department of Transportation, NMSS, and NRC.
(Paragraph 9)
d.
The inspector discussed the erroneous calculator program identified during the inspection involving conservative errors in reported 6/
IE Inspection Report No. 50-254/79-05.
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liquid effluent releases since August 1978. The inspector stressed the need to check and verify accuracy of programs.
The licensee agreed to submit an errata sheet to correct the erroneous data contained in the semiannual effluent report fcr the last half of 1978.
(Paragraph 4)
e.
The significance of continuing to exceed the design objective release rate for iodine and particulates with greater than eight day half lives was discussed by the inspector. The licensee noted the many efforts they have made at reducing the rates and the dose received by personnel in making these efforts.
The licensee noted recent indications that release rates now appear to be down to about twice design objectives compared to about four times the design objective for the first and secor.d quarters of this year. The licensee agreed to continue pursuing the matter and to keep the regional office informed of the status of the releases.
(Paragraph 5)
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