ML20196E082
| ML20196E082 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/25/1988 |
| From: | Hughey C, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20196E058 | List: |
| References | |
| 50-424-88-46, 50-425-88-61, NUDOCS 8812090268 | |
| Download: ML20196E082 (8) | |
See also: IR 05000424/1988046
Text
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REGION 11 g ,[ 101 MARIETTA ST., N.W. [ "g ',,,e e ATLANTA. GEORGIA A323 , .. - NOV 2 5 8 - Report Nos.: 50-424/88-46 and 50-425/88-61 [ Licensee: Georgia Power Company P. O. Box 4545 , Atlanta, GA 30302 i Docket Nos.: 50-424 and 50-425 License Nos.: HPF-68 and CPPR-109 , 4 ' Fccility Name: Vogtle 1 and 2
Inspection Conducted: October 17-21, 1988 ! Inspector: [[M 8 /4 / ///13/JT C. A. Hu
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Date Signed ! Approved by: M_, M_ k kb /l/2 [2 l - J. 8./K H, Section Chief Datb Signed l Divi n of Radiation Safety and Safeguards , , j < t SUMtARY t Scope: This routine, unannounced inspection was conducted in the areas of l radiological effluents and plant chemistry [ i i Results: No violations or deviations were identified, a i i ! l f i l J I L l
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_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __ ___ _ _ _ _ _ _ _ ' . . . . REPORT DETAILS 1. Persons Contacted Licensee Employees C. Eckert, Manager, Health Physics and Chemistry
- T. Greene, Plant Support Manager
- D. Hallman, Chemistry Supervisor
S. Jackson, Senior Regulatory Specialist
- W. Nicklin, Regulatory Compliance Supervisor
- K. Pointer Senior Plant Engineer
J. Sills, Chemistry Supervisor S. Sundaram, Plant Engineer Other licensee employees contacted during this inspection included engineers, operators, security force members, technicians, and administrative personnel. Nuclear Regulatory Commission
- J. Rogge Senior Resident inspector
- Attended exit intersiew
2. Process and Effluent Radiological Monitoring and Sampling System (PERMSS) (84750) On the evening of October 17, 1988, a noble gas grab sample of the plant vent stack effluent was taken by a shift technician using the process and effluent radiological monitoring and sampling system (PERMSS) and analyzed on the chemsitry gamma spectroscopy system. The noble gas activity was determined to be approximately 4 E-7 uti/cc. When the technician compared the sample results to the reading on the inline PERMSS noble gas channel, a difference was noted. The PERMSS channel (12442C) was indicating approximately 2 E-6 uti/ce, or a factor of five higher than the sample analysis indicated. As a result of this discrepancy, the monitor was taken out of service at S:20 a.m. on October 18, 1988
- redundant plant
taken out of service vent noble gas monitor (12444C) had been prev'.ousif for its 18 month calibration. The calibration had been completed but the monitor (12444C) had not yet been placed back in service. Technical Specification Table 3.3-10, Section 4.a., required the licensee to suspend containment purges via the plant vent when less than one noble gas channel was operable. Because both noble gas channels (channels 12442C and 12444C) were inoperable, the licensee suspended Unit I containment purging as required. Containment was being purged because of refueling operations. J
. _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _____ _ __ ___ __ ____ _ ____ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ ____ ___ . . . 2 . Because ten minute average readings from channel 12442C were reading "0.00 E + 00" (less than background), the licensee suspected a gain siiift 2 in the channel. Ucing grab sample data from the October 17, 1988 sample analysis, a new gain factor was hand calculated and entered in the PERMSS and a new background was determined. Nc51e gas moniter Channel 12442C was subsequently placed back in service at 5:00 p.m. on October 18, 1988. ! Licensee actions appeared to be adequate; however, the root cause of the monitor failure had not been determined by the end of the inspection. No violations or deviations were idenM ried. ! 3. Chemistry Staffing (84750) At the time of the inspection there were 24 Georgia Power Company i chemistry technicians on the chemistry staff, not including supervisory and support staff personnel. Six of these were new hires in initial training at the training center. Seventeen contract chemistry technicians supplemented the permanent chemistry technician staff. During the previous year, a number of chemistry technicians had been promoted into newly created supervisory and support staff positions. This
resulted in an overall decrease in knowledge and experience at the ' technician level. Although an INP0 accredited training program was ', in-place and implemented, the licensee had not been able to recruit new i personnel at the desired proficiency level. To supplerrent the in-house chemistry technician staff, the licensee continued c.v maintain a comparatively large (17) experienced and knowledgeable group of contract . i technicians. l The licensee anticipated having approximately 38 permanent chemistry 1 technicians on the chemistry staff to man both units by the time Unit 2 I would achieve commercial operation. ! The inspector interviewed three chemistry technicians, ranging in nuclear power plant experience from four moaths to 21 years, to obtain a , j subjective evaluation of technician knowledge levels. All had a minimum j of a bachelor of science degree and prior non-nuclear chemistry laboratory experience, and appeared to be knowledgeable within their specific duty , areas. ) No violations or deviations were ioentified. 4. Reactor Ccolant System (84750) At the time of this inspection, Vogtle Unit I was in te r , ,and week of a l planned 45 day refueling outage that began October 8, luo. This was the ! first refueling since going critical in March 1987.
! The licensee had performed a hydrogen peroxide (H 0,) induced midloop crud ! burst of the IJnit I reactor coolant system prfor to beginning refueling
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_ _ _ _ _ _ _ _ _ _ _ . . . 3 ' - , operations. This was intended to significantly reduce radiation fields " and potential exposures to plant workers in and around the stea.n generators and reactor coolant system during the refueling outage. A program had been initiated to monitor long term radioactivity build-up Monitoring Program, HP-5234) gram (EPRI-Westinghouse PWR Standard Radia in the RCS loops, This pro consisted of directly monitoring 36 points on the reactor coolant system loops, 9 on each of four loops, for dose rates. The measurements were to be taken during each refueling outage to monitor the effectiveness of the reactor coolant system chemistry control program for minimiting crud build-up. Measurements were to be taken at least 3 days after plant shutdown to allow the decay of short-lived radioactive isotopes. Vogtle Unit I was also using a coordinated Lithium-Boron reactor coolant chemistry scheme during power operations that resulted in a primary coolant pH higher than previously recommended by the NSSS supplier. Comparison of the initial Vogtle Unit I results to those from plants of similar age indicatad that crud build-up in the loops was significantly lower in plants using the coordinated Lithium-Boron RCS chemistry scheme relative to plants that did not. The inspector reviewed trend plots of various Unit I reactor coolant chemistry parameters for the period May 1988 to October 1988. Chloride was consistently maintained below 10 parts per billion (ppb) and fluoride was maintained below 20 pob, both of which were well below Technical Specifications Limits. During 100% power steady state operations, Unit 1 dose equivalent lodine-131 stayed between 8 to 9 E-04 uCi/ gram and the lodine-131/ lodine-133 ratios averaged about 0.1. This indicated good fuel cladding integrity with very low fission product leakage into the RCS, other than that expected from tran.p uranium, into the reactor coolant. A reduction in start-up rate also contributed to maintaining fuel integrity. Significant iodine spikes were not noted during reactor trips. Reactor coolant gross activity was between 5 to 6 E-01 uti/ gram for the period. No violations or deviations were identified. 5. Count Room (84750) The inspector reviewed quality control charts for the chemistry count room gamma spectroscopy detectors. These charts, for the period April 1988 through October 1988, consisted of daily background, resolution and efficiency checks for each of 4 detectors. A'l plotted data was within t established control limits, implying stable detector phrformance. A t review of the liquid scintillation counter daily background and efficiency checks for the same period also indicated stable instrument performance. As a result of a previous violation (Paragraph 8) all calibrations for the Health Physics and Chemistry count rocms were being perforr.ed by the same staff chemist. No violations or deviations were identified. l _ _ _ _ - _ _ _ _ _ _ _ _ - a
_ - _ _ _ _ _ _ _ _ - __________ _ _____ - ____-_________ _ ._ _-__________________ ________ _ _ __________ _ _ _ _ _ _ - _ _ ' . . . 4 ' . 6. Plant Chemistry (84750) a. Turbine Plant Cooling Water System (TPCWS) Corrosion The inspector accompanied a licensee representative on an inspection of the stator cooling water heat exchangers, TPCWS heat exchanger "A" and the "C" hotwell for corbiculae ( Asiatic clams), biofouling and general conditions. The systems were similar because they all operated in direct contatt with concentrated chlorinated river water. During power operations, circulating water was maintained at S to 6 cycles of concentration. TPCWS water was drawn from and returned to the circulating water system. The systems inspected were similar because all inner carbon steel surfaces were coated with a protective epoxy coating. The inspector noted no signs of microbiologically induced corrosion (MIC), biofouling or significant corrosion in these coated components. However, an inspection of a condenser vacuum pump heat exchanger by the licensee indicated severe general internal corrosion. This component was also cooled by TPCWS but the carbon steel inner surfaces of this heat exchanger were not epoxy coated. The inspector concluded from these observations that severe corrosion problems could exist in all TPCWS piping since it was mainly constructed of carbon steel and was not epoxy coated. The licensee agreed with this conclusion and indicated they were in the early stages of evaluating chemical treatment solutions for this problem. The TPCWS does not cool any safety-related equipment. All safety-related equipment was cooled by the nuclear service cooling water system (NSCW). Makeup to this system was well water, not river water. A licensee inspection of selected components in the NSCW system indicated no significant corrosion or fouling problems. The inspector also observed that there were apparently no corrosion or fouling problems in the "C" waterbox. All inner carbon steel surfaces of the "C" waterbox were epoxy coated. The coating appeared to be in good shape except for minor bubbling which was scheduled to be repaired during the current outage. Corrosion of the tube sheets and water boxes was also retarded by the use of a cathodic protection system. The chemistry department regularly monitored voltage readings on this system when in operation to prevent possible hydriding of the titanium condenser tubes. To prevent corbiculae (clams) intrusion into the circulating water and TPCW systems, the l'censee maintained residual chlorine levels in the water and periodically "shock treated" the system with chlorine during clam breeding and growing seasons. Although these clams are known to live in the Savannah River, the chlorin tion program appeared to be effectivo in preventing clam intrusion. While the chlorine treatment was effective in killing clams, tests by a chemical treatment vendor at Vogtle indicated a dir'it relationship between chlorine levels and accelerated corrosion rates in the circulating water ar.d TPCW systems. . _i
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! ? b. Steam Cycle Chemistry
(1) During the first fuel cycle there was no major in-leakage of circulating water into the hotwell. When minor leaks did occur, ' condensate polishers were effective in preventing contaminants from reaching the steam generators. Hotwell dissolved oxygen concentrations remained below 5 parts per billion Juring power operationt.. ! Circulating water in-leakage was detected by monitoring sodium and silica concentrations in the hotwell. Concentration factors ! of 5 to 6 in the circulating water system pemitted easy detection of in-leakage by detection and measurement of sodium ' i and silica. t l Because of hamonic vibratt jn problems within the titanium condenser tubes during power operations, Unit 1 tubes w1re being i, staked at the time of the inspections. Unit 2 tubes had been I previously staked. ] 1 (2) A review of chemistry data plots for the period May to October 1988 indicated that secondary chemistry, except for minor transients, was maintained within the guidelines recomended by the Steam Generator Owners Group. Steam generator blowdown cation conductivity averaged 0.3 micrombos/cm, well helow the recommended level of 0.8 micrombos/cm. Chloride and sodium concentrations in blowdown were maintained below 20 parts per billion except for a short period in July, August and September 1988. Sulfate levels were normally less than 5 parts per billion indicating low condensate polisher resin intrusion. The licensee also indicated low sulfate levels during limited hideout return studies. (3) During the inspection, the licensee indicated that the planned sludge lancing of the steam generahrs (secondary side) and eddy current testing of sonie steam generator tubes had not been completed. During a phone conversation on November 14, 1988, a licensee representative indicated to the inspector that a total of only 80 pounds of sludge had been removed frcm all 4 sten generators. Test results from the eddy current examination of selected steam generator tubes led to the preventative plugging of only 1 tube. This, along with low sludge removal, was indicative of an effective secondary chemistry control program, ho violations or deviations were identified.
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . . . 6 - . 7. Followup of Information Notices (92701) a. (Closed) Information Notice (IN) 88-22, Disposal of Sludge from Onsite Sewage Treatment Facilities, had been received by the i licensee, reviewed for applicability and distributed to the ' appropriate plant personnel for action. Sewage treatment sludge was being transported by truck to the City of Augusta sewage treatment plant. Each truck load of sludge was being analyzed for radioactivity prior to removal from the site. To date, only one incident, concerning lodine-131 contamination, had occurred i which was ultimately traced to medical radioisotope treatment of an employee. This item is considered closed. ' b. (Closed) IN 88-31, Steam Generator Tube Rupture Analysis Deficiency, had been received by the licensee, reviewed for applicability, and distributed to the appropriate plant personnel for action. A Deficiency Card initiated by the licensee indicated that steam generator tube uncovery was not considered to be a problem at Vogtle on the basis of startup test data. The Westinghouse Owners Group planned to present to the NRC a methodology for resolving the steam generator tube uncovery issue approximately June 1989. Based on these results, required corrective actions would be initiated. This item is considered closed. 8. Licensee Action on Previous Enforcement Matters (92702) (Closed) Violation 50-424/87-64-01, Licensee Failed to Correctly Determine the Volume of a One Liter Gas Marinelli. During inspection 50-424/87-64, a Notice of Violation (NOV) was issued to the licensee for failing to 9rrectly determine tM volume of a Marinelli beaker used to conduct survt for airbone radioactivity within the plant, which resulted in inaccurate lama spectroscopy measurements. In response to the NOV, the licensee co aitted by letter, dated January 7,1988 to certain corrective actions as listed below The inspector verified that appropriate corrective actions had been comp.eted, a. Convert software in the Health Physics Count Room to the same software used in the chemistry count room. Licensee Corrective Action. The Health Physics count room w35 using the same computational software as the chemistry coutit room, b. Obtain a new "one liter" Marinelli beaker and calibrate and implement this geometry. Licensee Corrective Action. A new 1260 cc Marinelli beaker standard had been ordered and received. The licensee had correctly calibrated 6.1d implemented this gaseous geometry. Prior to implementing this s
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, geometry the licensee had discontinued the use of the "one liter" Marinelli beaker geometry. .. Implement a cross-check program between the Chemistry and Health c. Physics Count r50c5. l Licensee Corrective Action. This program had been implemented with a once per quarter cross-check using a one liter liquid and 4.6 liter
gaseous geometries. An agreement criteria of plus or minus 10% was required. , This item is considered closed. l , 9. Licensee Actions on Previous Inspection Findings (92701) (Closed) Inspector Followup Item (IFI) 86-92-01, Review of Chemistry staff ' ) training. Since this IFl was opened in October 1986, a performance-based training I program had been developed, implemented and subsequently accredited by INP0. A number of chemistry technicians had completed the initial phases of this training program and schedules were in place for technicians and supervisory personnel to complete future training. This item is considered closed. l 10. Exit Interview The inspection scope and results were summarized on October 21, 1988, with ) those persons indicated in Paragraph 1. The inspector described the areas
inspected and discussed in detail the inspection results. Proprietary I inforration is not centained in this report. Dissenting comment.s were not ! received from the licensee. l i i ! i t t r i l , - . _ - . - ._ ._ __ . -- }}