IR 05000400/1994004
| ML18011A386 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/23/1994 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18011A385 | List: |
| References | |
| 50-400-94-04, 50-400-94-4, NUDOCS 9403150048 | |
| Download: ML18011A386 (21) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 303234199 KB 25 1994 Report No:
50-400/94-04 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Shearon Harris Nuclear Power Plant License No.:
NPF-63 Date Signed Inspection Conducted:
January 24 - 28, 1994 Inspector:
zs F~
.
P. Carri on, Radi at i on Speci al ist r
Approved by: i v~r..l~
j T.
R. Decker, Chief ate Signed Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, announced inspection was conducted in the areas of organization of the Chemistry Department and Radioactive Waste Shipping Unit; plant water chemistry; the Post Accident Sampling System (PASS); confirmatory measurements; the Semiannual Radioactive Effluent Release Report; Unresolved Item 50-400/92-16-01; contaminated ventilation ductwork; Hicrobiologically-Induced Corrosion (HIC); status of the Spent Fuel Pools (SFPs); notifications to the NRC; and shipping documentation of radwaste and spent fuel.
Results:
The licensee's organization of the Chemistry Department and Radioactive Waste Shipping Unit was stable and satisfied requirements of the Technical Specifications (TSs).
(Paragraph 2)
The licensee's plant water chemistry was maintained well within required TS limits.
(Paragraph 3)
The licensee had made great progress in resolving problems with the PASS.
(Paragraph 4)
9403150048 940225 f PDR ADOCK 05000400 PDR
The licensee demonstrated that a good Counting Room radiochemical analysis program was in place.
(Paragraph 5)
The Semiannual Radioactive Effluent Release Report met the requirements of the TSs.
(Paragraph 6)
The licensee was making satisfactory. progress in the resolution of Unresolved Item 50-400/93-16-01.
(Paragraph 7)
The licensee had satisfactorily resolved the issue of the contaminated ventilation ductwork.
(Paragraph 8)
The licensee had a good program in place to prevent system corrosion and fouling due to microbiological attack.
(Paragraph 9)
The SFPs were being adequately maintained.
(Paragraph 10)
The licensee's
"non-emergency events" resulted in no release of radioactive material to the environment.
(Paragraph 11)
The licensee's shipping documentation was accurate, well-maintained, easily retrievable, and satisfied regulatory requirements.
(Paragraph 12)
REPORT DETAILS.
Persons Contacted Licensee Employees N.
R.
Bach, Senior Specialist H.
E. Barnes, Environmental and Chemistry (E8C) Specialist D. F. Cahill, Radiochemistry Laboratory Supervisor P.
L. Doss, Senior Specialist, Chemistry
= *J.
W. Gurganious, Environmental and Chemistry (E8C) Manager
- W. T. Harris, Acting Spent Nuclear Fuel Manager G. Nathan, Senior E8C Specialist
- W. R. Robinson, Harris Plant General Manager K. B. Rogers, RC Technician I
- M. G. Wallace, Senior Specialist, Regulatory Compliance
- B. C. White, Environmental and Radiation Control (E8,RC)
Manager Other licensee employees contacted during this inspection included engineers, operators, technicians, and,administrative personnel.
North Carolina Department of Environment, Health, and Natural Resources B.
D. Dusenbury, Jr.,
Environmental Radiation Specialist F.
Fong, Chief of Nuc1ear Faci1ities and Environmental Radiation Surveillance Section Nuclear Regulatory Commission
- D. J. Roberts, Reside'nt Inspector
- J.
E, Tedrow, Senior Resident Inspector
- Attended exit interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
Organization (84750 and 86750)
TS 6.2 describes the licensee's organization.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department and Radioactive Waste Shipping Group to verify that the licensee had not made organizational changes which would adversely affect the ability to control radiation exposures or radioactive material.
The structure of the EKRC Organization had remained unchanged since the last inspection.
{Refer to Inspection Report {IR) 50-400/93-16.)
The position of Chemistry Manager had been filled.
The only other personnel change in the E8RC Organization noted by the inspector was a vacancy for the position of Counting Room Supervisor.
A replacement was being
.
sought at the time of the inspection.
There had been no changes in the Radioactive Waste Shipping Group.
The inspector concluded that the licensee's Chemistry Department and the Radwaste Shipping Group satisfied TS requirements and noted that the respective organizations had maintained their ability to function effectively.
No violations or deviations were identified.
Plant Water Chemistry (84750)
During this inspection, the Shearon Harris Nuclear Power Plant (SHNPP)
was in its fifth fuel cycle at 100 percent power.
(The fifth refueling outage is scheduled for Harch 1994.)
The inspector reviewed the plant chemistry controls and operational controls affecting primary water chemistry since the last inspection in this area.
(Refer to Inspection'eport 50-400/93-16.)
TS 3.4.7 specifies that the concentrations of dissolved oxygen (DO),
chloride, and fluoride in the Reactor Coolant System (RCS)
be maintained below 0. 10 parts per million (ppm), 0. 15 ppm, and 0. 15 ppm, respectively.
TS 3.4.8 specifies that the specific activity of the primary coolant be limited to less than or equal to 1.0 microcuries/gram (uCi/g) dose equivalent iodine (DEI).
These parameters are related to corrosion resistance and fuel integrity.
The oxygen parameter is established to maintain levels sufficiently low to prevent general and localized corrosion.
The chloride and fluoride parameters are based on providing protection from halide stress corrosion.
The activity parameter is based on minimizing personnel radiation exposure during operation and maintenance.
Pursuant to these requirements, the inspector reviewed graphical daily summaries and monthly reports which correlated reactor power output to chloride, fluoride, and dissolved oxygen concentrations,.
and specific activity of the reactor coolant for the period of October 1,
1993 through November 30, 1993 and determined that the parameters were maintained well below TS limits.
Typical values for DO, chloride, and fluoride were two parts per billion (ppb), for each of the respective parameters.
DEI values at steady-state conditions ranged from 1;95E-2 uCi/g to 2.46E-2 uCi/g.
The licensee had identified one gross fuel defect in a twice-burned fuel a'ssembly and was tracking it.
The -licensee planned to replace it during the upcoming refueling outage.
The inspector concluded that the primary water chemistry was well-maintained and satisfied TS requirements.
No violations or deviations were identifie Post Accident Sampling System (PASS)
(84750)
TS 6.8.4.e,requires that a program be established, implemented, and maintained to ensure the capability to obtain and analyze, under
. accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples.
The PASS should provide these capabilities and should enable the licensee to obtain information critical to the efforts to assess and control the course and effects of an accident.
The inspector spoke to the cognizant licensee Technical Specialist responsible for the system for a status update of the modifications and upgrades being made to the PASS.
The difficulties with the gas stripper in maintaining a constant pressure or flow had been resolved since the previous review of the PASS.
Equipment-related changes made to the PASS since the last inspection included field revisions which had been added to Plant Change Requests (PCRs)
PCR 6161 incorporated regulator setpoint adjustments identified during system tuning and changes the hydrogen meter scale to provide accurate low-and high-range readings, added valve 1SP-1746 as a pulsation dampening device (to stabilize gas flow indication),
added a demineralized water flush line to improve PASS performance, and added check valves to prevent contamination of clean systems.
PCR 5074 relocated the PASS chiller 2'-4" away from the back wall to allow maintenance personnel access to the rear of the chiller.
This PCR also modified the normally closed status of valves 1SW-673 and 1SW-674 to a normally open status.
PCR 6950 modified control valve 1SP-978 and introduced an analog controller and the 1039N pnuematic actuator to provide better control (to eliminate the "hunting" effect of the valve) at low flow rates.
These PCRs had not been completed as of this inspection.
Operability testing done during the fourth quarter of 1993 showed greatly improved results over those of the fourth quarter of 1992, with all eleven identified parameters satisfying the acceptance criteria.,
(In the fourth quarter. of 1992, four parameters failed to satisfy the acceptance criteria.)
The inspector concluded that the licensee had made great progress in its efforts to upgrade the PASS.
No violations or deviations were identified.'onfirmatory Measurements (84750)
CFR 20.201(b)
requires the licensee t'o perform surveys as necessary to evaluate the extent of radiation hazards.
In an effort to evaluate the licensee's analytical capabilities, the licensee was provided spiked liquid samples for analysis pursuant to the NRC.Confirmatory Neasurements Program.
Specifically, the licensee was requested to analyze samples of beta-emitting radionuclides containing tritium (H-3),
iron-55,.and strontium-90.
The licensee reported th. analytical. results of this batch on September 3,
1993 via the corporate Energy 'and
Environmental (ERE) Center, located at the Shearon Harris Nuclear Power Plant.
As'indicated in Attachment 1, the licensee's analytical results were in agreement with the prepared concentrations for the three isotopes identified.,
Attachment 2 provides the criteria for assessing the agreement between the licensee's analytical results and the prepared concentrations.
The inspector concluded that the licensee maintained a good Counting Room radiochemical analysis program for the detection of beta-emitting radionuclides.
No violations or deviations were identified.
Semiannual Radioactive Effluent Release Report (84750)
TS 6.9. 1.4 requires the licensee,to submit a'Semiannual Radiological Effluent Release Report within the time periods specified in TS 6.9. 1.4 covering the operation of the facility during the previous six months of operation.
The inspector reviewed the semiannual radioactive effluent release report for the first half of 1993.
The results were compared to.those of full years 1991 and 1992.
The data are summarized on the next page.
Harris Radioactive Effluent Release Summary 1991 1992 1993*
Abnormal Releases a.
Liquid b.
Gaseous Activity Released (curies)
a
~
2.
3.
Liquid 1.
Fission and Acti-vation Products Tritium Gross Alpha 6.62E-1 2.92E+2
< LLD 3.14E-1 9.02E+2
< LLD 6.39E-2 8. 36E+1
< LLD b.
Gaseous 1.
Fission and Acti-vation Products 2.
Iodines 3.
Particulates
- 4.
Tritium 0.00E-O 4.71E-5 8.13E-1 7.05E-4 1.90E-4 4.37E-1 9.76E-6 3.62E-S 5.82E+0 8. 63E+2 1.36E+2 2. 19E+2
- First half of 1993 only.
A comparison of the activity released from liquid fission and activation products for 1991, 1992, and the first half of 1993 showed a decreasing
trend.
No significant changes were noted in the other results, except for gaseous tritium releases, which were noted to have increased substantially since the previous reporting period.
Discussions with the Chemistry Manager determined that this phenomenon was due to the licensee's use of fuel with a longer life which required higher levels of boron in the RCS at the beginning of the*fuel cycle to aide in reactivity control.
The boron is converted into tritium in a neutron flux field.
For the first half of 1993, Harris liquid, gaseous, and particulate effluents were maintained well within TS,
CFR 20, and
CFR 50 effluent limitations.
The report also included the results of solid radwaste shipments.
The following table summarizes those shipments for the previous three years.
The shipments typically included spent resins, filter sludge, dry compressible waste, and contaminated equipment.
Harris Solid Radwaste Shipments 1991 1992 1993*
Volume (cubic meters)
Activity (curies)
78.0 301.8 71.2 289.5 21.9 190.0
- First half of 1993 only.
For solid radwaste, the most significant change. noted from the previous years'esults was the reduced volume generated, indicating that the licensee's continued efforts to minimize radwaste were successful.
There was one change to the Process Control Program (PCP),
an administrative change to include the Westinghouse/Scientific Ecology Group (SEG)
PCP as.part of the Harris PCP.
The annual Land Use Census was performed during this period.
As a
result, Table 3.2-2 of the Offsite Dose Calculation Manual (ODCM) was scheduled to be revised during the next reporting period.
Three changes were made to the ODCM during the current period, including:
the incorporation of the 1992 Land Use Census and change of location description for a sample point; revision to reflect the usage of the new terms referenced in the new
CFR 20, especially the use of Effluent Concentrations (ECs) in place of Maximum Permissible Concentrations (MPCs); revision of the definition and value of A, the site-specific factor to account for the mixing effect of the discharge structure (as defined in NUREG-0133, Section 4.3), in the liquid effluent dose equation.
No changes to the Environmental Monitoring Program were made during the current reporting perio No unprotected outdoor tanks and no gas storage tanks exceeded TS limits on radioactivity content during this reporting period. 'urthermore, no major modifications to the Radwaste System were made.
No effluent radiation monitors were addressed in the report as being out of service for thirty days or more.
The inspector concluded that the Semiannual Radioactive Effluent Release Report was complete and satisfied TS requirements.
No violations or deviations were identified.
Status of Unresolved Item 50-400/93-16-01 (84750)
a.
Background During Inspection 93-16 of August 1993, the inspector reviewed the licensee's Radiological Environmental Monitoring Program (REMP),.
which monitors radiation and radionuclides in the environs of the plant, provides representative measurements of radioactivity in the highest potential exposure pathways, and verifies the accuracy of the effluent monitoring program and modeling oF environmental exposure pathways, The Radiochemistry Laboratory at the Harris Energy and Environmental Center in New Hill, North Carolina, provides radioanalytical services for CPL's nuclear plant radiological environmental surveillance programs.
The laboratory is a
participant in the Environmental Protection Agency's (EPA's)
cross-check program and uses its performance in the program as a
major determinant for the accuracy and precision of its own analytical results.
During 1992, a comparison of the laboratory's reported values with those of the EPA's known activity found 98 percent to be within three standard deviations.
The North Carolina Division of Radiation Protection (NCDRP)
independently measures the concentrations of radioactivity in the environs of SHNPP, per a contractual agreement with the NRC, to provide reasonable assurance that environmental measurements made by SHNPP are valid.
Like the Radiochemistry Laboratory at the Harris Energy and Environmental Center, the NCDRP participates in and reports results of the EPA's Intercomparison Studies Program.
During Inspection 93-16, the inspector compared several air particulate and air cartridge results as reported by the licensee to those listed in the "Report On Environmental Radiation Surveillance in North Carolina" for 1992, submitted by the North Carolina Department of Environment, Health and Natural Resources.
The results compared favorably, with the exception of gross beta measurements of the air particulates.
The reported results of both the control and indicator stations showed a bias in that the results of the state were consistently higher than those of the
SHNPP, by a factor of about 1.7, raising a question as to which set of results was most representative.
Discussions at the time about the comparisons with the Acting Radiochemistry Supervisor, members of the staff, and the Environmental Radiation Specialist from the State of North Carolina yielded no definite conclusions.
However, it was noted that air flow characteristics of the air sampling units were sufficiently different to alter the results and that the results would become more consistent when the state placed new air samplers into service.
Another possibility discussed was that the counting techniques were different such that self-absorption of the betas was considered by one party but not the other.
This issue was addressed as Unresolved Item 50-400/93-16-01,
"Air Particulate Beta Result Discrepancy."
Status The licensee had initiated Action Item 93H0833 to review the issue, Four possibilities were postulated as reasons. for the discrepancies, including sample volume measurements, efficiencies of the beta counters, sample decay and self-absorption factors, and weather effects on collected particulates.
Each possibility was discussed, comparing the way each item was addressed by SHNPP versus the NCDRP.
In addition, SKNPP and the NCDRP were coordinating an effort to resolve the source of the differences.
Four SHNPP air filters, two each collected by SHNPP and the NCDRP, were exchanged for beta
. counting, as were eight filters from CP&L's Brunswick plant.
The average discrepancy for the twelve filters was 1.28, which represented an improvement over the previously-reviewed annual results.
However, it.was noted that these activities had been calculated using the air volumes reported by the collecting organization, thereby effectively checking only the relative counter efficiencies.
Both parties had counted an unknown air filter containing Cs-137 prepared by an independent laboratory.
SHNPP had sent its results to the laboratory for comparison.
The NCDRP had not yet sent its results to the laboratory for comparison as of the date of this inspection.
(A direct comparison of the SHNPP and the NCDRP results was not made because SHNPP used a Cs-137 beta efficiency for air particulate filters while NCDRP used a Sr-90/Y-90 beta efficiency for its air particulate filters.)
A comparison of the results would be made upon receipt of the laboratory data.
In addition, the NCDRP had received new air flow meters and had agreed to exchange them with the licensee at a commonly-sited air sampling station in the near future in order to investigate the possibility that the differences in analyses was due to different air flow result This issue will be addressed during a future inspection and will continue to be tracked as Unresolved Item 50-400/93-16-01,
"Air Particulate Beta Result Discrepancy."
The inspector concluded that the licensee was making satisfactory progress in the resolution of this issue.
No violations or deviations were identified.
Ventilation Ductwork Contamination (92700)
IR 50-400/92-08 identified a condition in which contaminated water had collected in ventilation ductwork.
The inspector reviewed the condition, with a special interest in determining if an unmonitored release pathway existed.
(Refer to Paragraph 7 of IR 50-400/92-12 and Paragraph 7 of IR 50-400/93-02.)
A valve leakoff header, designed to collect and separate the liquid and gaseous components of valve leakoff had been improperly installed and, therefore, did not function as designed.
As originally installed, the header permitted liquid to enter the ventilation ductwork rather than directing it into the equipment drain, as designed.
The liquid which entered the header was traced to its source, the packing gland valve leakoff line from Valve 1SI-327.
The ductwork had been internally contaminated.
The valve stem had been repaired during the last refueling outage.
The leakoff line had been reworked and restored it to its original design configuration.
Since the previous review of this issue, Work Ticket 92-ASZXI, written to decontaminate and/or replace the ductwork, had been completed.
The inspector walked down-,the ductwork in the field to verify the documented activities.
The inspector observed that while the vertical run of ductwork had been successfully decontaminated, the horizontal run had been replaced.
The inspector concluded that the licensee had satisfactorily resolved the condition.
No violations or deviations were identified.
Nicrobiologically-Induced Corrosion (NIC) and Biofouling (92700)
The inspector interviewed cognizant licensee personnel about HIC and was told that it had not been a problem at SHNPP.
During the fourth refueling outage (in late 1992) the licensee had performed extensive inspections of plant's cooling water systems, including Circulating Water System, Service Water System, Emergency Diesel Generator Jacket Cooling Water System, Essential Services Chilled Mater System, Component Cooling Water System, and Fire Protection System.
Minor fouling and corro'sion was observed, attributed to silt and organic materials in low flow areas.
(Nore frequent system flushing was considered to mitigate this condition.)
However, there had been no evidence of MIC in any of the closed-loop systems.
The licensee had used a coupon rack in the Service Water System since 1987 to monitor the corrosion status of
components in the system.
The inspector walked down the coupon rack.
After a period of exposure, the coupons were removed, visually inspected, cleaned, weighed, and re-examined.
Corrosion rates were calculated and trended.
Depending upon the results, adjustments to the chemical treatment program were made.
Four coupons were used, one each of mild (carbon)
steel,,
304 stainless steel, admiralty brass, and a 90-10 copper-nickel alloy.
Corrosion rates for the carbon steel had been less than 2.0 millimeters per year and less than 0.2 millimeters per year for the admiralty brass and 90-10 copper-nickel alloy.
The inspector also discussed the methods used by the licensee to control the microbes responsible for MIC and other deleterious, conditions.
The licensee explained that control was maintained through the injection of chlorine compounds (as a biocide), tolyltriazole (TTA) (to inhibit corrosion of copper alloys),. zinc and phosphate compounds (to inhibit the corrosion of iron alloys),
and polyacrylate (to minimize the deposition of suspended solids and mineral scale, as well as to control the solubility of the zinc and phosphate)
at, the suction of the Service Water (SW)
Pumps.
The inspector walked down the SW pumping station to observe its physical condition.
No irregularities were noted and it was well-maintained.
The inspector reviewed Chemistry and Radiochemistry Procedure CRC-159, Rev.
1, "Corrosion Coupon Testing for Service and Circulating Water Systems,"
which defined the purpose, prerequisites, precautions and limitations, etc. of the coupon testing program.
The inspector also reviewed Chemistry and Radiochemistry Procedure CRC-155, Rev.
7, Chemistry Control of Circulating Water, Service Water, and Cooling Tower Basin," which established the sampling locations and grab sampling method for those systems, including sampling and analyses requirements.
Although biofouling has not been a 'major problem for the licensee, bryozoa plugging of SW strainers had been experienced in the 1992 timeframe.
The licensee continued to monitor and evaluate methods to effectively control the situation.
The inspector concluded that the licensee had a good program in place and was taking positive actions to maintain its various cooling water systems within their design bases and to prevent system corrosion and fouling due to microbiological attack.
No violations or deviations were identified.
Spent Fuel Pool (SFP) Facility (92700)
The inspector met with cognizant licensee representatives to discuss the status of the SFPs, especially as related to the receipt of BWR spent fuel from CPSL's Brunswick plant and potential problems associated with crud, Pool A was used for storage of new fuel as well as some spent fuel while Pool 8 was used exclusively for the storage of spent fuel from all three CPL nuclear facilities.
Pools C and D had been used for temporary storage of contaminated filters, scaffolding, et Ten shipments of spent fuel from Brunswick had been made in 1993.
To date in 1994, one shipment had been made.
Each shipment was made by rail and included two casks, each of which contained seventeen bundles of channeled fuel.
Discussions with the Spent Nuclear Fuel Hanager found that, while movement of the spent fuel assemblies sometimes caused the crud to swirl and "cloud up" the SFP (thereby reducing visibility),
there had been no effects on those operations.
The Spent Nuclear Fuel Hanager also had noted that the older spent fuel from Brunswick had exhibited higher levels of crud than recently-burned fuel and that the spent fuel shipments were now being configured to include a mixture of old and recently-burned fuel to minimize the impact from crud associated with the spent fuel from Brunswick.
The status of Pool C had changed since the last inspection in that the water level had been allowed to drop (via natural evaporation)
and was about six feet lower than the level of the Transfer Canal.
This was done to reduce the amount of water to be processed by th'e demineralizers in the future.
Otherwise, the pool was unchanged from the previous inspection, i.e., it was empty of contaminated equipment and debris.
Likewise, Pool D was unchanged from the previous inspection, i.e., it was filled with borated water and contained some remaining miscellaneous items.
The PCR originally initiated by the 1'licensee to provide a permanent vacuum pump system to pump out the spent fuel shipping casks to better control any crud which may be shed from the spent fuel assemblies during their transportation to SHNPP and to install permanent electrical and mechanical services on the "island" between Pools C and D had been reviewed by management and viewed as an enhancement because there were no safety or production concerns at is'sue.
The original cost estimate was thought to be too high and it had been returned for a review of the scope of the proposed work, with the idea of reducing it to its bare essentials.
The PCR had been reviewed and scaled back to include electrical improvements only.
Additional 120-and 480-volt receptacles were to be installed to provide additional light in the decontamination pit, thereby eliminating the need for "drop cords" and their potential safety and contamination hazards.
Engineering had begun and implementation was expected in 1995.
An additional PCR, for the installation of permanent enclosures to the SFP cooling lines, was in Engineering.
The inspector reviewed the SFPs'ater chemistry records for months of October and November 1993.
Chloride and fluoride concentrations were less than ten ppb; boron concentrations remained steady at approximately 2150 ppm (well above the 2000 ppm lower administrative limit); silica concentrations rose gradually from an average 2580 ppm to 2600 ppm (possibly due to a leaching of the silica used in the Boriflex material of the spent fuel storage ra'cks);
and sulfate concentrations averaged approximately 30 ppb for the period (decreasing in October from those of the previous month and rising to previous levels in November).
The licensee could not explain these observations but planned to investigate the source of the high sulfate concentrations, including a soak test of a gate seal specimen (due to its elastomer composition of sulfur-cured rubber).
The inspector toured the Spent Fuel Pools and observed that the area was clean and that.good housekeeping and Health Physics practices were being followed.
The inspector concluded that the Spent Fuel Pools were being adequately maintained.
No violations or deviations were identified.
11.
Notifications to the NRC (92700)
The inspector reviewed two events reported to the NRC in December 1993 and January 1994 per
CFR 50.72(b) to confirm that they were
"non-emergency events."
a
~
b.
Sulfuric Acid Addition Point Discharge Flange Leakage
/
On December 31, 1993, a leak of approximately 20 gallons per minute (gpm)
was found at the discharge flange of Sulfuric Acid Addition Point for the Circulating Water System.
(The leak was identified as Circulating Water because sulfuric acid had never been added to the system.)
The leak was secured by the insertion of a teflon disk into the flange.
An estimated 1200 gallons of water was discharged during the incident.
The Circulating Water had been treated with TTA, zinc phosphate, and a polymer (for corrosion control),
as well as sodium hypochlorite and proprietary biocides.
The water was sampled and found to contain a free available chlorine and total residual 'chlorine concentrations of 0.2 ppm and 0.8 ppm, respectively.
No radioactivity was detected in the sample.
The inspector walked down the site of the flange failure, discussed the event with plant personnel, and reviewed the drainage path of the leaked water to a nearby storm drain.
On January 16, 1994, the Normal Service Water screen washing basin was found to be overflowing to an adjacent storm drain and was immediately secured.
The cause of the event was determined to be frozen equipment (a pressure indicator) which caused the backwash strainer to cycle continuously, resulting in the overflow.
An estimated 18000 gallons was discharged during the event.
The Normal Service Water System had been treated with TTA, zinc phosphate, and a polymer (for corrosion control),
and found to be within limits of the licensee's NPDES Permit.
No radioactivity was detected.
The inspector concluded that no release of radioactive material to the environment had taken place and that these were "non-emergency events."
No violations or deviations were identifie Radwaste Processing and Transportation (86750)
CFR 71.5 (a) requires that each licensee who transfers licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation (DOT) in 49 CFR, Parts 170 through 189.
Pursuant to these requirements, the inspector reviewed the licensee's activities affiliated with these requirements, to determine whether the licensee effectively processes, packages, stores, and ships radioactive
'solid materials.
The licensee's program for the packaging and transportation of radioactive materials, including solid radwaste, was conducted by the Radioactive Waste Group within the Health Physics Department.
Radwaste was processed and packaged by the Radwaste Group, including compacting contaminated material, loading shipments, and preparing shipping documentation.
The inspector reviewed shipping logs for 1993.
The logs -showed that fourteen disposal shipments and eighty-six special, non-burial shipments were made for the year.
The non-burial shipments included a wide variety of items, from empty spent fuel shipping casks to samples to be counted at the Energy and Environmental (E&E) Center.
The inspector reviewed three disposal shipment packages, including D-08-93, D-10-93, and D-13-93 as well as three non-burial shipments, including S-69-93, S-78-93, and S-81-93 for completeness and compliance with the regulations.
The packages documented the shipments and included items such as unique shipment and shipping container numbers, waste content and volume, total activity, analytical summary and breakdown of isotopes with a half-life greater than five years.
The radiation and contamination survey results were within the limits specified and the shipping documents were being maintained as required.
The inspector concluded that the shipping documentation was accurate, well-maintained, easily retrievable, and satisfied regulatory requirements, No violations or deviations were identified.
Exit Interview The inspection scope and results were summarized on January 28, 1994, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection.
The licensee did not identify any such documents or processes as proprietary.
Dissenting comments were not received from the license Acronyms and Initialisms CFR Ci
'P&L DEI DO DOT E&C E&E E&RC EC EPA g
IR pCi HIC HPC NCDRP No.
NPDES NRC ODCH PASS PCP PCR" ppb ppm RCS Rev.
- Code of Federal Regulations
- curie
- Carolina Power and Light
- Dose Equivalent Iodine
- Dissolved Oxygen
- Department of Transportation
- Environmental and Chemistry
- Energy and'nvironmental
- Environmental and Radiation Control
- Effluent Concentration
- Environmental Protection Agency
- gram
- Inspection Report
- micro-Cutie (1.0E-6 Ci)
- Hicrobiologically Induced Corrosion
- Haximum Permissible Concentration
- North Carolina Division of Radiatio
- Number
- National Pollutant Discharge Elimin
- Nuclear Regulatory Commission
- Off-site Dose Calculation Hanual
- Post Accident Sampling System
- Plant Change Request
- parts per billion
- parts per million
- Revision
- Radiological Environmental Honitori
- Spent Fuel Pool
- Shearon Harris Nuclear Power Plant
- Technical Specification
- Tolyltriazole
- Unresolved Item n Protection ation System ng Program
'
ATTACHMENT 1 COMPARISON OF NRC AND CPKL ANALYTICALRESULTS REPORTED SEPTEMBER 3, 1993 Type of Sample:
Unknown NRC Spikes Units:
Ci/ml Radio-nuclide H-3 Fe-55 Sr-90 Licensee's Value Ci ml 1.30 E-4 1.35 E-5 2,30 E-5 NRC Value Ci ml (1.29 +/- 0.06)E-4 (1.23 +/- 0.06)E-5 (2. 33 +/- 0. 12) E-5 Reso-lution Ratio
1.01
1.10
0.99 Compar-ison Agree Agree Agree
'
ATTACHMENT 2 CRITERIA FOR COMPARISONS OF ANALYTICALMEASUREMENTS This attachment provides criteria for the comparison of results of analytical radioactivity measurements.
These criteria are based on empirical relationships which combine prior experience in comparing radioactivity emission, and the accuracy needs of this program.
In these criteria, the "Comparison Ratio Limits"'enoting agreement or disagreement between licensee and NRC results are variable.
This variability is a function of the ratio of the NRC's analytical value relative to its associated statistical and analytical uncertainty, referred to in this program as
"Resolution".'or comparison purposes, a ratio between the licensee's analytical value and the NRC's analytical value is computed for each radionuclide present in a" given sample.
The computed ratios are 'then evaluated for agreement or disagreement based on "Resolution."
The corresponding values for "Resolution" and the "Comparison Ratio Limits" are listed in the Table below.
Ratio values which are either above or below the "Comparison Ratio Limits" are considered to be in disagreement, while ratio values within or encompassed by the
"Comparison Ratio Limits" are considered to be in agreement.
TABLE NRC Confirmatory Measurements Acceptance Criteria Resolution vs.
Comparison Ratio Limits Resolution Comparison Ratio Limits for A reement
< 4 4-7 8-15 16 - 50 51 - 200 200 0.4 - 2.5 0."5 - 2.0 0.6 - 1.66 0.75
- 1.33 0.80 - 1.25 0.85
- 1.18
'Comparison Ratio
= Licensee Value NRC Reference Value
'Resolution
=
NRC Reference Value
'Associated Uncertainty