ML20196E082
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| 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
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O' '4 UNITED STATES
c j ** .j* NUCLEAR REGULATORY COMMISSION !'
g REGION 11
"g ,[ 101 MARIETTA ST., N.W. [
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e',,,e ATLANTA. GEORGIA A323
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NOV 2 5 8 -
Report Nos.: 50-424/88-46 and 50-425/88-61 [
Licensee: Georgia Power Company
P. O. Box 4545 ,
i Atlanta, GA 30302
Docket Nos.: 50-424 and 50-425 License Nos.: HPF-68 and CPPR-109 ,
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Fccility Name: Vogtle 1 and 2 ;
Inspection Conducted: October 17-21, 1988 !
Inspector: [[M
C. A. Hu
8 /4 / ///13/JT
Date Signed
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Approved by: - M_, M_ k kb /l/2 [2 l
H, Section Chief
J. 8./K n of Radiation Safety and Safeguards Datb Signed l
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SUMtARY
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Scope: This routine, unannounced inspection was conducted in the areas of l
radiological effluents and plant chemistry [
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i Results: No violations or deviations were identified, a i
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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
vent noble gas monitor (12444C) had been prev'.ousi f taken out of service
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.
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Because ten minute average readings from channel 12442C were reading
2 "0.00 E + 00" (less than background), the licensee suspected a gain siiift
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.
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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)
i At the time of the inspection there were 24 Georgia Power Company
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
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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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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
in the RCS loops, This pro
Monitoring Program, HP-5234) gram
consisted of directly(EPRI-Westinghouse PWR
monitoring 36 points on Standard Radia
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.
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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.
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? b. Steam Cycle Chemistry
; (1) During the first fuel cycle there was no major in-leakage of
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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.
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Because of hamonic vibratt jn problems within the titanium
l 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.
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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.
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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
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geometry the licensee had discontinued the use of the "one liter"
Marinelli beaker geometry.
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c. Implement a cross-check program between the Chemistry and Health !
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. ,
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This item is considered closed. l
9. Licensee Actions on Previous Inspection Findings (92701)
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(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
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