IR 05000280/1995013
| ML18153A719 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/27/1995 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153A718 | List: |
| References | |
| 50-280-95-13, 50-281-95-13, NUDOCS 9508020092 | |
| Download: ML18153A719 (18) | |
Text
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Report Nos.:
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W., SUITE 2900 ATLANTA, GEORGIA 30323-0199 July 27 t 1995 50-280/95-13 and 50-281/95-13 Licensee:
Virginia Electric and Power Company Docket Nos.:
50-280, 50-281 Facility Name:
Surry 1 and 2 License Nos.:
DPR-32, DPR-37 Inspection Conducted:
June 26-30, Inspector: J /ilc/~ ~
R. P. Carrion, R~n 1995 Specialist Approved Scope:
by: Jdici-L
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T. R. Decker, Chief Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Division of Radiation Safety and Safeguards SUMMARY
~7/9s-Date Signed 027/90 Date Signed Branch This routine, announced inspection was conducted in the areas of the organization of the Chemistry Department and Radwaste Group, audits, primary and secondary water chemistry, the Annual Radioactive Effluent Release Report, the Radiological Environmental Monitoring Program (REMP), macrofouling in the Circulating Water and Service Water Systems, radioactive waste shipping operations and transportation documentation, and Information Notice ( IN) 94-8 Results:
The licensee's organization of its Chemistry Department and Radwaste Group satisfied Technical Specification (TS) requirement (Paragraph 2)
The licensee's audit process was capable of identifying programmatic weaknesses and making recommendations for corrective actio (Paragraph 3)
The licensee's plant water chemistry program continued to be effectively implemente {Paragraph 4)
9508020092 950727 PDR ADOCK 05000280
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The Annual Radioactive Effluent Release Report indicated that doses to the public due to licensee operations were minima (Paragraph 5)
The licensee had an effective program in place to analyze radiological effluents, direct radiation, etc. due to plant operation (Paragraph 6)
The licensee was taking proactive measures to mitigate the effects of macrofouling in its Circulating Water and Service Water System (Paragraph 7)
The licensee's radwaste processing and shipping was conducted in a competent, professional manner and the radwaste shipping documentation was thorough and in compliance with the applicable regulation (Paragraph 8)
The concerns presented in IN 94-81 were not an issue at the Surry Nuclear Station (SNS).
(Paragraph 9)
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REPORT DETAILS Persons Contacted
- W. Benthall, Supervisor, Licensing
- M. Biron, Supervisor, Radiological Engineering
- B. Blackwell, NSS
- R. Blount, Superintendent, Maintenance D. Boone, Quality Assurance (QA)
D. Bostic, Senior Chemist D. Brock, Assistant Supervisor, Chemistry
- A. Davis, Assistant Supervisor, Chemistry D. Erickson, Superintendent, Radiation Protection (R~)
B. Garber, Engineer, Licensing
- J. McCarthy, Assistant Station Manager
- M. Olin, Supervisor, Health Physics (HP) Technical Services E. Swindell, Supervisor, Chemistry
- J. Swientoniewski, Supervisor, Station Nuclear Safety
- F. Thomasson, Corporate Health Physics E. Topping, Supervisor, Radioactive Material Control M. Wilda, System Engineer (Service Water)
Other licensee employees contacted during this inspection included:
engineers, operators, and administrative per~onne Nuclear Regulatory Commission (NRC)
- M. Branch, Senior Resident Inspector D. Kern, Resident Inspector
- Attended Exit Interview Acronyms and Initialisms used throughout this report are listed in the last paragrap.
Organization (84750 and 86750)
TS 6.1.A describes the licensee's onsite and offsite organization The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department and the Radioactive Material Control Unit to verify compliance with the TS and to assure that adequate control of radioactive material to prevent/mitigate radiation exposures to the general public and plant personnel was maintaine The inspector interviewed the Superintendent of Radiological Protection about his organizatio The inspector was shown the organization char There had been no changes to the Radiological Protection Organization since the last inspection in this area (IR 50-280, 281/94-23).
It continued to be structured into five departments:
HP Operations; HP Technical Services; Nuclear Chemistry; Radwaste; and Radiological *
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Engineerin The unit responsible for the handling and shipping of radiological materials was located within the HP Technical Services Department and had a staff of four. Assistance from other parts of the Radiological Protection Unit was utilized for such activities as sorting and packing of radiologically-contaminated material The Nuclear Chemistry Department was composed of a staff of twenty-five, including the supervisor, an assistant supervisor, six senior chemistry technicians, fourteen chemistry technicians, a senior technician, a senior chemist, and a senior office associat In addition, two vacancies were noted; for a senior chemistry technician and a chemistry technicia The inspector concluded that the TS requirements had been satisfie No violations or deviations were identifie Audits (84750)
TS 6.1.C.2.h specifies the types and frequencies of audits to be conducted under the cognizance of the licensee's QA Departmen The inspector reviewed audits conducted by the QA Department within the scope of this inspectio In order to evaluate compliance with the TS and assess quality of the licensee's programs, the inspector reviewed the following audits:
Chemistry, 93-09, dated August 25, 1993 Radiological Environmental Monitoring Program/Environmental Protection Plan, S94-0l, dated February 3, 1994 ODCM/PCP, S94-02, dated February 17, 1994 Radiological *Protection Program, S94-07, dated July 27, 1994 The audits were found to be well-planned and documented, aided by the licensee's Miscellaneous Data Tracking Report, a continuous internally-generated report by the QA Department compiled as it reviewed various plant activities throughout the year. The audits addressed findings, enhancements, strengths, documentation and records, and actions taken to correct and/or prevent recurrence of previously-identified finding Audit conclusions presented an overall status of the program being reviewe The inspector noted that the comments and recommendations were detailed and would aid the implementation of adequate corrective action The inspector verified that the audit program was conducted in accordance with the TS The inspector concluded that the audit process was capable of identifying programmatic weaknesses and making recommendations for corrective action.
No violations or deviations were identifie **
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Plant Water Chemistry (84750)
During the inspection, both units were operating at one hundred percent power, except Unit 1 which had been reduced to 90% for a few hours on June 30 to clean condenser water boxes of macrofouling material. Unit 1 was in its thirteenth fuel cycle, with its next refueling outage scheduled for September 1995, and Unit 2 was in its thirteenth fuel cycle, having completed its refueling outage in February 199 Primary Water Chemistry TS-Required Parameters The inspector reviewed the plant chemistry controls and operational controls affecting primary plant water chemistry since the last inspection in this are TS 3.1. specifies that the concentrations of DO, chloride, and fluoride in the RCS be maintained below 0.10 ppm, 0.15 ppm, and 0.15 ppm, respectivel TS 3.1.D specifies that the specific activity of the primary coolant be limited to less than or equal to 1.0 µCi/g DEi whenever the reactor is critical or the average temperature is greater than 500° 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 corrosio 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 emergency operation and maintenanc Pursuant to these requirements, the inspector reviewed daily summaries for both units which correlated reactor power output to *chloride, fluoride, and dissolved oxygen concentrations, and specific activity of the reactor coolan For Unit 1, the arbitrarily-chosen period of January 1, 1995 through February 28, 1995, was reviewed, while for Unit 2, the arbitrarily-chosen period of December 1, 1994 through January 31, 1995, was reviewe The parameters were determined to have been maintained well below TS limits. Typical values for DO, chloride, and fluoride were less than five ppb, less than five ppb, and less than two ppb, respectively, for Unit 1 and less than five ppb, less than two ppb, and less than one ppb, respectively, for Unit 2. Typical DEi values at steady-state conditions were 4.6E-3 µCi/g for Unit 1 and 9.5E-4
µCi/g for Unit Neither unit had shown any evidence of leaking fuel.
The inspector concluded that the Primary Water Chemistry was maintained well within the TS requirement *
- Early Boration The licensee typically uses early boration (acid-reducing chemistry) combined with hydrogen peroxide injection (acid-oxidizing chemistry) during unit shutdown and cooldown at refueling to reduce the source ter The inspectors reviewed reports/evaluations of the most recent early boration results (Unit 2 refueling outage 12).
The process solubilized 338 curies of Co-58 and 23 curies of Co-60, as well as 669 grams of nickel (which can be activated during power operation to produce Co-58). These materials were removed via the demineralizers. Values of Co-SB/Nickel specific activities were relatively low, although they increased to between 0.4 to 0.6 Ci/g after the peroxide injectio (Values of between 0.1 to 0.2 Ci/g indicate that ex-core material is solubilized, while values approximating 1.0 Ci/g indicate that in-core material is solubilized.) Therefore, these results indicate that while the Co-58 removed was predominantly ex-core material, a small amount of in-core material was also remove A calculated ex-core dose reduction in the steam generator (SG) channel heads of approximately 7.5% was realized due to the removal of Co-58 and Co-6 Based on the results of these reports, the inspector concluded that the licensee was proactive in trying to reduce dose rates by removing significant quantities of activity via its early boration/hydrogen peroxide shutdown progra Secondary Water Chemistry Licensing Condition 3.K requires the licensee to establish, implement, maintain, and audit a Secondary Water Chemistry Program to inhibit steam generator tube degradatio The inspector discussed the impact of the licensee's program on the condition of the SG The Unit 2 SGs had developed deposits of iron and copper near the upper portion of the tube bundles (due to the higher temperatures associated with the region).
The Unit 1 SGs also had experienced similar deposits. The deposits of the Unit 2 SGs had accumulated to the point where they had significantly affected the stability of the water level, thereby forcing reduced reactor power operatio To rectify this condition, the licensee undertook a three-part chemical cleaning of the Unit 2 SGs in June 1994 and the Unit 1 SGs in December 199 To eliminate future copper deposits in Unit 2, the remaining copper components in the feedwater system, particularly the first and second point feedwater heaters, were replaced with stainless steel heaters during the Unit 2 refueling outage of February 199 The licensee was using an ETA regimen
(injection into the feedwater/condensate systems) on the SGs of both units to enhance pH control and thereby reduce the corrosion rate of the feedwater piping. The final estimates of the quantities (in lbs.) of material removed from the respective SGs are as follows:
Steam Generator Coi;rner Iron Sludge Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2
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SG A 610 345 3993 2500 880 1258 SG B 499 470 3609 3050 1248 984 SG C 429 510 3860 3900 995 610 Totals 1538 1325 11462 9450 3123 2852 The inspector also reviewed the history of plugged tubes in the SGs. To date, the number of plugged tubes was 2, 6, and 4 for -
Unit 1 SG A, SG B, and SG C, respectively. Similarly, the number of plugged tubes was 6, 0, and O for Unit 2 SG A, SG B, and SG C, respectivel Based on this review, the inspector concluded that the licensee had taken proactive steps to preserve/protect its SGs through effective implementation of its Secondary Water Chemistry Program and special chemical cleaning evolutions, as require Based on these findings, the inspector concluded that the licensee had implemented an effective over-all chemistry program to not only maintain the components of both the primary and secondary systems, but to reduce the potential dose to its personne No violations or deviations were identifie.
Annual Radioactive Effluent Release Report (84750)
TS 6.4.N requires the licensee to establish a program for the control of radioactive effluents and for maintaining resultant doses to members of the public ALAR Furthermore, TS 6.6.B.3 and 10 CFR 50.36a(a)(2)
require the licensee to submit an Annual Radiological Effluent Release Report before May 1 covering the operation of the facility during the previous year of operatio The TS also states the requirements for the content and format of the repor The inspector reviewed the Annual Radiological Effluent Release Report for 1994 and compared its results to those of 1991, 1992, and 199 The data for those years are summarized belo ' '. -. ~ -*,_.-..,._-..... *:t-,. -~.,u_..... ----
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Surry Power Station Radioactive Effluent Release Summary 1991 1992 1993 1994 Unplanned Releases Liquid
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0 Activity Released (curies) Liquid Fission and Acti-2.85E+O 8.23E-2 2.0BE-2 6.48E-2 vation Products Tritium 9.13E+2 9.74E+2 1.32E+3 9.79E+2 Gross Alpha l.06E-5 O.OOE+O O.OOE+O O.OOE+O Volume of Waste Liquid 3.91E+8 1.52E+8 1.11E+8 6.78E+8 Released (liters) Gaseous Fission and Acti-3.54E+l 1.06E+l 4.lSE+l 2.75E+2 vation Gases Iodines 5.16E-4 4.97E-4 6.llE-4 4.0SE-3 Particulates 6.68E-4 3.06E-4 1. 74E-4 3.lSE-4 Tritium 2.55E+l 2.37E+l 2.31E+l 1.51E+l A comparison of the activity released from liquid and gaseous effluents for 1991, 1992, 1993, and 1994 found no significant changes, except for liquid fission and activation products, which showed a dramatic decrease after 199 The inspector discussed this item with cognizant members of the Chemistry staff and found that this improvement was the result of radwaste facility going online in September of 199 For 1994, Surry liquid, gaseous, and particulate effluents were maintained well within TS, 10 CFR 20, and 10 CFR 50 effluent 1 imitation VPAP-2103, "Offsite Dose Calculation Manual," Rev. 5, dated June 10, 1994, specifies the method to calculate the annual maximum individual total dose from radioactive effluents and all other nearby uranium fuel cycle sources. Sections 6.2.3 and 6.3.3 specify the quarterly and annual dose limits for liquid effluent and gaseous effluents, respectively. Section 6.5 specifies the total dose limit to the public from uranium fuel cycle source The inspector reviewed the licensee's assessment of radiation doses to the maximum-exposed member of the public from radioactive materials in gaseous and liquid effluents released during 1994 as reported in the Annual Radioactive Effluent Release Repor The table below includes the annual dose assessments due to gaseous and liquid effluents for 1991, 1992, 1993, and 1994 for compariso '
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Surr~ Power Station Cumulative Estimated Doses from Effluents Annual Dose Pathway 1991 1992 1993 1994 Limit Airborne Gamma Air Dose l.37E-l 5.65E-3 3.13E-2 l.lOE-1
(mrad)
Beta Air Dose 8.07E-2 I. 26E-2 6.74E-2 3.47E-l
(mrad)
Max Organ Dose I. 04E-2 l.05E-2 I. 27E-2 8.20E-2
(Thyroid) (mrem)
Liquid Total Body Dose I. 52E-2 6.95E-4 I.07E-3 5.99E-4
(mrem)
Max Organ Dose 7.97E-2 5.60E-4 5.05E-4 7.89E-4
(GI-LLI) (mrem)
The release of radioactive material to the environment from Surry for the year was a small fraction of the 10 CFR 20, Appendix Band 10 CFR 50, Appendix I limits. As can be seen from the data presented above, the annual dose contributions to the maximum-exposed individual from the radionuclides in liquid and gaseous effluent released to unrestricted areas were all less than one per cent of the limits specified in the ODC These results were attributed to significantly improved fuel integrity and the new SRF, which processes all liquid radwast The SRF used an improved technology for more efficient treatment and cleanup of radioactive material released in the liquid effluent strea *
Based on the data, the inspector concluded that the licensee's radwaste systems were effectively utilized and operating within their design criteria to make effluent releases that were ALAR Revisions 5 and 6 were made to the ODCM during 1994 to implement changes resulting from the revision of 10 CFR Part 20 and to implement changes to the radiological environmental monitoring program based upon various sample location changes, the elimination of sample locations, changes in sample collection frequency, modification of classification for unplanned liquid and gaseous effluent releases, and miscellaneous editorial change No major changes were made to the Radwaste Treatment System during the reviewed reporting period The report also included the results of solid radwaste shipment The following table summarizes solid radwaste shipments for burial or disposal for the previous four years. These shipments typically include spent resins, filter sludge, dry compressible waste, and contaminated equipmen Surry Power Station Solid Radwaste Shipments 1991 1992 1993 1994 Number of Waste
43
54 Disposal Shipments Volume (cubic meters)
17.1 21.2 Activity (curies)
81.7 56.5 For solid radwaste, the inspector noted that the number and volume of the shipments had remained relatively constant for the period reviewe The inspector concluded that the Radioactive Effluent Release Reports were complete and satisfied TS requirement No violations or deviations were identifie.
Radiological Environmental Monitoring Program (84750)
TS 6.4.0 specifies that the licensee shall conduct a REMP to monitor radiation and radionuclides in the environs of the plant and defines how the program shall be conducte The REMP shall provide representative measurements of radioactivity in the highest potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathway Accumulation of radioactivity in the environment can thereby be measured and trends assessed; to determine whether the radioactivity resulted from plant operations, to project the potential dose to off-site populations based on the cumulative measurements of any plant-originated radioactivity, and to detect unanticipated pathways for the transport of radionuclides through the environmen Annual Radiological Environmental Operating Report TS 6.6.B.2 requires that the Annual Radiological Environmental Operating Report be submitted prior to May 1 of the following year. It also includes format and content requirements for the repor The inspector reviewed the report for calendar year 1994 to verify compliance with the TSs. * The report had been submitted in compliance with TS 6.6.8.2 on April 27, 1995, and the format and contents were as prescribed by the T The inspector determined that the report was in compliance with the TS The inspector reviewed the Radiological Environmental Operating Report for 1994. Analytical results were divided into five
categories based on exposure pathways: Airborne, waterborne, aquatic, ingestion, and direct radiation. The pathways were described as follows:
The airborne exposure included airborne iodine and airborne particulat No fission products or other man-made isotopes in the airborne particulate media were detected in 199 Overall 1994 airborne results were very similar to those of previous years and preoperational level The waterborne exposure pathway included well water and river water sample No man~made isotopes were detected in the river water, except for tritium. The average tritium activity in 1994 was approximately two pe*rcent of the NRC reporting limi No man-made isotopes were detected in the well wate The aquatic exposure pathway included silt and shoreline sediment sample During the preoperational period, no man-made isotopes were detected in the silt pathwa However, man-made isotopes (Co-60 and Cs-137) have accumulated, although their 1994 concentrations indicated a decreasing trend compared to the previous eight-year perio The concentration of man-made isotopes was projected to continue to decrease due to the radioactive waste treatment facility which uses state-of-the-art technologies to reduce the volume and activity of liquid effluent In 1994, Cs-137 was detected in ten (of ten) samples collected at a maximum concentration of 493 pCi/kg (dry). Also in 1994, Co-60 was identified at a maximum concentration of 232 pCi/kg (dry) in nine (of the ten) sample The shoreline samples contained no detectable concentrations of isotopes attributable to plant operation The ingestion exposure pathway included milk, aquatic biota, and food product sample lodine-131 was not detected in any 1994 milk sampl Sr-90 was detected at concentrations comparable to those of the previous years. Naturally-occurring K-40 was detected at normal environmental levels in the milk sample Each aquatic biota sample contained K-40 at average environmental concentrations. Vegetation samples yielded concentrations of naturally-occurring radioisotopes (K-40 and Be-7) at concentrations which were similar to those of the previous five year The direct radiation exposure pathway measured environmental exposure by use of TLD TLD results for 1994 remained consistent with those of the previous five year The radiological environmental data indicated that plant operations had no significant impact on the environment or public health and safet.. ~*"** -::-... -.**,* *. --~..... - -::--*.* ***- -.., --~.* *'.**-* --.
10 Comparison of Results of Commonwealth of Virginia vs. Surry The Virginia Department of Health entered into a contractual agreement with the NRC to perform independent environmental sampling and radiological analyses of samples at designated locations around nuclear facilities licensed by the NRC within the state, including Surr The principal objective of the contract is to provide reasonable assurance that environmental measurements made by NRC licensees are vali To this end, the Commonwealth of Virginia:
Detects and measures radioactive releases during routine plant operatio Detects and measures radioactive releases during abnormal operation event Measures reconcentration of radioactive effluents in the environment, especially in human exposure pathway Provides an independent means of verification of release report These objectives are achieved through continuous sampling of air and ambient radiation, as well as, periodic sampling of water, milk, vegetation, fish, et The inspector compared several air particulate, air cartridge, milk, shellfish, surface water, and vegetation results, as reported by the licensee, to those listed in the 11 1994 Environmental Radiation Program Comparative Report," submitted by the Virginia Department of Health, Bureau of Radiological Health for tritium and beta and gamma isotopics). The results compared favorabl The inspectors discussed the comparison with the Superintendent of Radiological Protectio Observation of Sample Collection The inspector accompanied a HPT on his normal weekly sample collection rounds to observe collection technique and to check the physical condition and operability of the sampling stations. The collection of air samples was observed at three locations, including:
SS, HIR, and B In addition, the collection of a water sample was observed at the discharge cana The inspector also noted that TLDs were located at or nearby the air sampling location Except for Location SS, the air sampling stations were located in areas generally free of tall weeds/vegetation which might interfere with obtaining representative sample At Location SS, the inspector noted that it was located in a low-lying area surrounded by trees. The inspector commented about his observations to the licensee, which said that the location of the sampling station would be reviewed in the futur The inspector
noted that all of the air sampling units were within calibration and were well-maintaine The inspector noted that it was not necessary for the technician to review the procedure (HP-3051.010, Rev. 0, "Radiological Environmental Monitoring Program") due to his familiarity with the station locations and the media to be collected. The inspector also noted that the licensee used a quick disconnect assembly containing the charcoal canister and particulate filter, which allowed easy retrieval of the samples and installation of the new assembly, even in adverse weather condition The inspector concluded that the technician was knowledgeable, well-trained, and conducted his activities in a professional manne From a review of the licensee's environmental report, observation of the technician in the field, and a review of the State's report, the inspector concluded that the licensee had an effective program in place to monitor radiological effluents, direct radiation, etc. due to plant operations and that the Report was in compliance with the TS In 1994, plant operations had negligible impact on the surrounding environmen Furthermore, any activity which may have been present as a result of plant operations caused minimal impact to the environment and virtually no dose to members of the general publi The inspector concluded that the licensee had effective programs in place to monitor releases of radiological effluents. Plant operations caused minimum impact to the environment and virtually no dose to the general public from those effluent No violations or deviations were identifie.
Macrofouling of the Circulating Water and Service Water Systems (84750) Background The plant's Circulating Water System provides cooling water for the condensers and the Service Water Systems of both units. It operates primarily as a gravity-flow siphon syste The water is pumped from the James River to an upper (higher elevation) intake canal from which it flows via gravity through four 96-inch diameter buried parallel pipes to each main condenser and then through four separate lines to a concrete tunnel for each unit, which terminate at seal pits at the edge of the low-level discharge cana The four 96-inch diameter lines connecting the condenser and the high-level intake structure are constructed of reinforced concrete in the station _yard and welded steel encased in concrete under the station. The taps for the 48-inch diameter Service Water System lines are made in the welded steel portion of these lines. Service Water is supplied from the Circulating Water
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System via gravity flow between the high-level intake canal and the seal pits and supplies the bearing cooling water heat exchangers, the component cooling heat exchangers, and the recirculation spray heat exchanger The plant has experienced significant macrofouling problems in its Circulating Water and Service Water Systems since start up, the major contributors being hydroids during the spring, summer, and autumn months and eels during the winter month Lesser contributors include crabs, barnacles, and bryozoan The two major fouling problems of the Circulating Water System have been:
(1) reduced traveling screen life caused by hydroid growth on screen surfaces and (2) fouling of condenser inlet water boxes, primarily by hydroids in the spring, summer, and autumn and by eels in the winter. The major fouling problems experienced by the Service Water System have been:
(1)
colonization of hydroids on the inside surface of the 48-inch Service Water supply headers which branch off the Circulating Water inlet lines, (2) colonization of hydroids in the headers to the CCWHXs, (3) fouling of the Recirculation Spray Heat Exchangers by hydroids and other debris, and (4) fouling of the CCWHX Past efforts by the licensee to mitigate this problem in the Service Water System include chlorine injection and stagnation. Stagnation was done by alternating flow in the two supply headers once per week, depleting the food and oxygen supply for the hydroids and thereby killing the Discussions with the licensee determined that an epoxy-based
"Chesterton" coating had been applied to approximately 90% of the Circulating Water lines (from the high-level intake structure to the condenser inlet motor-operated valves) and Service Water lines (from the Circulating Water lines to the Service Water motor-operated valves).
The remaining work was expected to be completed during the Unit 1 outage in September 199 The licensee had been physically removing the macrofouling material during each outage for the past several years and has found that the best method to remove the material from the epoxy-coated piping was with a high-pressure was Hoes and shovels were commonly used on the concrete-lined pipin Future plans included the installation of a chemical injection system in the Service Water Syste The inspector concluded that the licensee was taking proactive measures to mitigate the effects of macrofouling in its Circulating Water and Service Water System No violations or deviations were identifie *
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13 Radwaste Processing and Transportation (86750)
10 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 DOT in 49 CFR, Parts 170 through 18 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 material The licensee's program for the shipping of radioactive materials, including solid radwaste, was conducted by a staff of four within the HP Technical Services Departmen Personnel from other parts of the Radiological Protection Unit were responsible for such activities as the sorting and packing of radiologically-contaminated material Radwaste Shipments The inspector observed the activities involved in the preparation of Shipment SH-1995-041 to evaluate the effectiveness of training, activities of personnel, procedures, et The shipment was four empty new fuel casks destined for a fuel fabricator in South Carolina. The inspector observed part of the work evolution of loading the shipping casks onto a flatbed truc The work was performed per procedure (Operating Procedure O-OP-4.2, "Receipt and Storage of New Fuel," Rev. 4) and proceeded smoothly, with the crew members handling their assignments professionally. Before the shipment left the site, the inspector reviewed the final survey records of the shipment and conducted a
"spot check" of several of the survey point The inspector found that the survey points checked were in agreemen The inspector concluded that the survey was properly done and well-documente In addition, placarding of the vehicle and the general condition of the tractor/trailer were reviewed by the inspecto No irregularities were identifie Radiological Materials Shipping Documentation The inspector reviewed shipping logs for 199 The licensee classified shipments into three categories: Radiological Material Receipts; Radiological Material Shipments; and Radwaste Shipment Radiological Material Receipts included items such as decontaminated outage and refueling equipment, empty Seavan containers, and laundered protective clothing and modesty garment Radiological Material Shipments included items such as contaminated outage equipment, radioactive material samples, and laundr Radwaste shipments included radioactive material ultimately destined for disposa The inspector reviewed shipment
documentation packages for three radwaste shipments and two radioactive material shipments for completeness and compliance with the regulations. The three radwaste shipments included 895-3 (drums of LSA material for disposal), 895-8 (drums of LSA material for disposal), and 895-10 (a cask filled with DAW).
The radioactive material shipments included SH-1995-025 (four boxes of outage equipment) and SH-1995-032 (a power air purification respirator motor and batteries to the North Anna Power Station).
The packages documented the respective shipment and included items such as unique shipment and shipping container numbers, content and volume, total activity, analytical summary and breakdown of isotopes with a half-life greater than five year The radiation and contamination survey results were within the limits specifie The inspector concluded that the licensee's staff was competent to effectively implement the radiological materials shipping progra Volume Reduction The licensee continued to focus attention on reducing the volume of radwaste generated through increased vigilance/awareness, restrictive practices, innovative practices (such as replacing plastic bags and disposable protective clothing with ones of washable cloth and limiting the use (and encouraging the reuse) of plastic sheeting and Herculite). The general goal of the program was to make all generators more sensitive to the issue and to make the radwaste volume reduction goal a mindset for all plant employee The Supervisor of Radioactive Material Control said that a significant volume reduction was expected in 1995 due to these efforts. The results of these efforts had been obscured in the 1994 data because of the licensee's emphasis on disposing of as much as possible of the previously-generated radioactive material which had accumulated onsit The inspector concluded that the licensee was making a determined effort to further reduce its volume of radwast The inspector concluded that the licensee had an effective program in place to make radioactive materials shipments and that the staff responsible for this work was dedicated and professiona No violations or deviations were identifie.
Information Notice (IN) 94-81: Accuracy of 8ioassay and Environmental Sampling Results (84750)
IN 94-81 raises questions about the reliability of sample results and analyses performed by a bioassay and environmental contracto The IN urges licensees who may have used the services of the identified contractor within the last few years to consider how the results were
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used and whether potentially-inaccurate results would have any safety significanc Furthermore, if inaccurate results could cause significant safety concerns, the licensee is urged to consider what actions would be appropriate to confirm their sample result The inspector discussed the IN with the RP Superintenden The licensee had not used the services of the identified contractor. The Superintendent stated that the quarterly analysis of beta-emitting radioisotopes, specifically Fe-55, Sr-89, and Sr-90 (and Y-90) were done by a different contractor, whose performance was satisfactor The inspector concluded that the concerns presented in the IN were not an issue at the SN No violations or deviations were identifie.
Exit Interview (84750)
The inspection scope and results were summarized on June 30, 1995, with those persons indicated in Paragraph 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 ALARA CCWHX CFR Ci OF DAW DEi DO DOT ETA g
GI HIC HP HPT IN IR kg lb LLI LSA
µCi mrad mrem
- As Low As Reasonably Achievable
- Component Cooling Water Heat Exchanger
- Code of Federal Regulations
- curie
- degrees Fahrenheit
- Dry Active Waste
- Dose Equivalent Iodine
- Dissolved Oxygen
- Department of Transportation
- Ethanolamine
- gram
- Gastrointestinal
- High Integrity Container
- Health Physics
- Health Physics Technician
- Information Notice
- Inspection Report
- ki 1 ogram
- pound
- Lower Large Intestine
- Low Specific Activity
- micro-Curie (1.0E-6 Ci)
- milli-rad
- milli-rem
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NRC
- Nuclear Regulatory Commission ODCM
- Off-Site Dose Calculation Manual ppb
- parts per billion ppm parts per million QA
- Quality Assurance RCS
- Radiological Environmental Monitoring Program Rev
- Revision RP
- Radiation Protection SG
- Steam Generator SNS
- Surry Nuclear Station SRF
- Surry Radwaste Facility TLD Thermoluminescent Dosimetry TS
- Technical Specification