IR 05000335/1991008
| ML17223B191 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/25/1991 |
| From: | Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223B190 | List: |
| References | |
| 50-335-91-08, 50-335-91-8, 50-389-91-08, 50-389-91-8, NUDOCS 9105290269 | |
| Download: ML17223B191 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.IN.
ATLANTA,GEORGIA 30323 APR pg ~
Report Nos.:
50-335/91-08 and 50-389/91-08 Licensee:
Fl ori da Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-335 and 50-389 Facility Name:
St. Lucie 1 and
License Nos.:
DPR-67 and NPF-16 Inspection Conducted:
March 26-29, 1991 jm Inspector:
R.
R. Marston Approved by:
MA L(lc'<4~8~
./p g/
T.
.
ec er, ref Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards y ~/vs Date igned 4 -H ~i/
Date Signed SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of liquid and gaseous effluents, solid radwaste, radiological environmental monitoring, effluent instrumentation and count room, periodic reports, in-place filter testing, and changes to the chemistry program, Offsite Dose Calculation Manual (ODCM), and Process Control Programs (PCP).
Results:
No violations or deviations were identified.
All effluents were within Technical Specification and
CFR 50, Appendix I limits.
The radiological environmental monitoring program was good; no anomalous values were reported.
Effluent monitors were calibrated at required intervals and HEPA and charcoal filters were leak tested and laboratory tested at required intervals.
9105290269 9f0425 PDR ADOCK 05000335
REPORT DETAILS Persons Contacted Licensee Employees
- J. Adams, Independent Safety Evaluation Group Engineer
- A. Bailey, Nuclear Energy Supervisor, Quality Assurance
- G. Boissy, Plant Manager
- J. Brady, Mechanical Maintenance Engineering Supervisor
- H. Buchanan, Health Physics Supervisor
- C. Burton, Operations Superintendent
- R. Cox, Chemistry Effluents Supervisor
- R. Dawson, Maintenance Superintendent
- J. Dyer, Quality Control Supervisor
- R. Englmeier, Site Quality Manager D. Faulkner, Primary Chemistry Supervisor
- R. Frechette, Chemistry Supervisor
- J. Geiger, Vice President Nuclear Assurance
- G. Madden, Plant Supervisory Engineer
- A. Menocal, Assistant Superintendent, Mechanical Maintenance
- D. Oliver, Superintendent, Material Management R. Somers, Radwaste Supervisor
- T. Ware, Technical Training Coordinator
"D. West, Technical Department Supervisor Other licensee employees contacted during this inspection included engineers, operators, security force members, technicians, and administrative personnel.
NRC Resident Inspectors
- S. Elrod, SRI
- M. Scott, RI
- Attended exit interview Audits (84750, 86750)
Technical Specification (TS) 6.5.2.8 requires that audits of unit activities shall be performed under the cognizance of the Company Nuclear Review Board (CNRB),
and specifies the areas that these audits shall encompass and the frequency at which they shall be conducted.
The inspector reviewed the following audit reports to verify TS compliance:
QSL-OPS-90-762, Radioactive Effluents and Radiological Environmental Monitoring, October 20, 1990.
No findings were identifie gSL-OPS-90-732, Process Control Program, April 23, 1990.
Three findings had been identified, responses made, corrective action taken, and findings closed.
gSL-OPS-90-744, Emergency Plan, October 25, 1990.
One finding was identified.
The audit noted. that the Radiological Emergency Plan referenced use of Silver Zeolite cartridges for sampling of airborne iodine.
The audit referenced NRC Information Notice IN 86-43, which identified an explosive hazard in sampling in the presence of hydrogen.
Corrective action was scheduled and page changes to the Plan were submitted, deleting the use of the specified cartridges except for certain uses.
Documentation..accompanying the audit stated that the changes were to be submitted to the Plant Manager March 31, 1991.
Audit checklists were included with each audit package.
The checklists showed the thoroughness and depth of detail which was covered in each audit.
The audits were professionally done and served to demonstrate the auditor's competence as well as the quality of the licensee's program.
No violations or deviations were identified.
'adiological Environmental Monitoring Program (84750)
TS 3/4. 12 states the requirements for the conduct of the radiological environmental monitoring program.
The radiological environmental monitoring program was conducted at the St.
Lucie plant by the Office of Radiological Control, Florida Department of Health and Rehabilitative Services (DHRS).
The inspector reviewed the quarterly Radiological Surveillance Reports for Calendar Year 1990 to verify compliance.
The reports showed results for both required sampling and analyses, and for the supplemental sampling programs.
The Chemistry Effluent Supervisor stated that the 1990 required Annual Land Use Census was conducted in June 1990.
No changes in the program were required as a result of the Census.
The Radiological Environmental Monitoring was conducted in accordance with requirements.
No violations or deviations were identified.
4.
Training (84750, 86750)
TS 6.4.1 states that a retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS-3. 1-1978 and Appendix A of 10 CFR Part 55.
The inspector discussed the Chemistry Technician training program with Chemistry Supervisors, reviewed documentation of the program, and toured the Training Lab to verify compliance
" and to assess quality.
The Chemistry Supervisor stated that a trainee would spend two weeks as a
trainee technician in each of seven areas to complete the required modules to qualify for shift work.
Initial assignment would be to one of
5.
the three less difficult areas-secondaries, environmental, or count room.
Classroom work would cover several modules, primarily those on fundamentals.
The Supervisor stated that the continuing training for qualified technicians had consisted of one four hour class a
month on selected subjects.
During the present year, a
one week DIONEX (ion chromatograph)
course was to be offered, and was to be attended by two personnel at a time.
This was expected to allow for more individual attention to the students by the instructor, and to facilitate learning.
The Chemistry Department had one trainee going through the upgrade program at the time of the inspection.
The inspector reviewed records. showing the individual's progress through the training program.
The records showed module number and name, completion dates, and signoffs.
The Training Lab was equipped with a
NMC PCC-11T Proportional Counter Converter with a
NMC DS-3P Sealer, and a
Gamma Spectroscopic system consisting of a
PGT detector with a
PGT Lab Cooler instead of a liquid nitrogen cooling system.
The detector system was controlled and readout by either a
ND computer or a Canberra Series 85 computer.
The existing and proposed Chemistry Technician Training Program appeared to be good.
No violations or deviations were identified.
Liquid Radwaste (84750)
TS 3. 11. 1 specifies the concentrations and doses authorized for liquid effluent releases, and FSAR Section 11.2 describes the Liquid Waste Systems in the plant.
The inspector and the Chemistry Effluent Supervisor toured the plant, examining Liquid Waste System components.
The Liquid Waste Control Panel was found on the 19.5 foot level of the Auxiliary Building.
The level indicators on the panel showed Aerated Waste Storage Tank level and levels for the 1A and 1B Monitor Tanks, the Laundry Tank, and the Equipment Drain and Chemical Drain Tanks.
Outside the Unit 2 Reactor Auxiliary Building a cask was set up in an inflated berm of a rubbery material.
The Supervisor stated that this was set up for a resin transfer which was to take place later in the week.
The inspector reviewed 28 Liquid Release Permits for the period from August 1990 to December 1990, and the Liquid Waste Management Running Log for May and September 1990.
Analyses were also available for quarterly composites for alpha and tritium analyses.
The permits included required setpoint, release, and dose information.
No limits were exceeded.
No violations or deviations were identified.
6.
Gaseous Radi ol ogi ca 1 Eff1uents (84750)
TS 3.11.2 specifies the concentrations and doses authorized for gaseous effluent releases.
The inspector reviewed 28 Gaseous Release Permits for batch and continuous releases for the period from July 1990 to February 1991.
Gaseous Release Running Logs were also reviewed for the period which also included monthly composite analyses for alpha, and
quarterly composite analyses for strontiums and yttrium.
The permits included required setpoint, release, and dose projection information.
The permits showed that releases were within TS limits.
Ko violations or deviations were identified.
Changes to Programs (84750, 86750)
The inspector discussed status and changes to the Chemistry organization and program with the Chemistry Supervisor, the Chemistry Effluent Supervisor, and the Primary Chemistry Supervisor, to evaluate quality and assess capability.
The organization was fully manned at 25 personnel, and at, least one person was on shift at all times.
The fuel racks in the Unit 1 pool were partially constituted of boraflex.
This metal had been found to suffer from leaching of silicon from its structure when exposed to the environment in Spent Fuel Pools (SFPs).
In some power plants, the silica formed was transferred to the reactor when the design was such that enough mixing could occur.
The St.
Lucie coolant systems were designed such that there was very little mixing between the SFP and the primary system.
The Chemistry Supervisor stated that approximately 2 parts per million (ppm) of silica had been detected in the Refueling Water Storage Tank (RWST).
The Secondary Chemistry and Water Treatment Plant instrumentation had been converted to digital readouts with the exception of the Unit 1 Secondary.
The Unit
Secondary was expected to be converted to digital readout during Summer 1991.
There had been no Offsite Dose Calculation Manual (ODCM)
changes implemented, but a
change which was connected to a proposed TS revision was sent to Onsite Licensing for review.
The Supervisor also stated that the Post Accident Sampling System (PASS) Procedure had been made more user friendly.
The Supervisors stated that the plant had backed off on Lithium-Boron coordination; that Lithium would be held to a
maximum value of 2.2 ppm rather than 3.5 ppm.
The implemented or proposed changes appeared to benefit the plant, or at least not contribute to any degradation of safety.
No violations or deviations were identified.
Semiannual Radioactive Effluent Release Report (84750)
TS 6.9. 1.7 states the requirements for the Semiannual Radioactive Effluent Release Report, including timeliness, content, and format.
The inspector reviewed the Report for the period from July 1 through December 31, 1990, to verify compliance and reviewed several past reports to evaluate effluent trends.
Trend data is presented in the following table:
TABLE Gaseous Effluents Curies)
1988 1989 1990 Fission
& Activation Gas Iodines
& Particulates 1.06E+04 3.49E-02 6.75E+03 1. 41E-02 1.15E+03 1.42E-02 Fission
& Activation Products Tritium 5.50E+02 8.30E+02 5.67E+02 5.73E-01 5.09E-01 1.59E+00 The Chemistry Effluents Supervisor stated that the two refueling outages and the maintenance outage during the year probably were responsible for the changes noted.
The down time would result in less fission and activation gas being produced, and the perturbations in the primary coolant system taking place as a result of outages and associated activity would result in release of some of the fission and activation products which had been plated out on the system surfaces.
There were no unplanned releases during the year.
The report had been submitted within the required time and was formatted and the contents were as specified in the TS.
No violations or deviations were identified.
Confirmatory hteasurements (84750)
Pursuant to
CFR 20.201(b)
this area was inspected to verify the licensee's ability to conduct precise and accurate measurements.
The licensee was asked to analyze liquid samples provided by the NRC containing beta-emitting nuclides.
The results were provided to the NRC and compared to NRC analytical results (Attachment 1).
Agreement was determined using the criteria described in Attachment 2.
The inspector determined that analyses for Iron-55 and Strontium-90 were in disagreement.
The licensee agreed to reanalyze these or replacement samples and provide the results to the NRC.
The inspector stated that these results would be evaluated during a subsequent inspection.
No violations or deviations were identified.
Air Cleaning Systems (84750)
TS 4.6.6.1 specifies in-place HEPA and charcoal filter testing and charcoal sampling and lab testing requirements for the Shield Building Ventilation System, TS 4.7.7. 1 specifies these testing requirements for the Control Room Emergency Ventilation System, TS 4.7.8. I specifies the
testing requirements for the ECCS Area Ventilation System, and TS 4.9.12 specifies the testing requirements for the Fuel Pool Ventilation System.
The inspector reviewed testing records for the specified systems and for several non-TS systems to verify compliance.
The records showed that the systems were tested at the required frequencies and that all tests were passed successfully.
The Unit 1 systems were last tested in Yiarch 1990, and the Unit 2 systems were last tested in September 1990, During the laboratory testing of the Unit 2 charcoal samples, the vendor initially tested all samples with Methyl Iodide.
The licensee realized that with the exception of the charcoal from the Control Room Emergency Ventilation System, the charcoal was required to be tested with elemental Iodine.
The licensee requested that the tests be redone with elemental Iodine.
All samples passed the tests successfully.
No violations or deviations were identified.
11.
Process and Effluent Radiation Monitors (84750)
TS 4.3.3.9 requires that each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check.
channel calibration, and charnel functional test at the frequencies shown in Table 4.3-8.
TS 4.3.3. 10 requires that each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check, channel calibration, and channel functional test at the frequencies shown in Table 4.3-9.
The inspector toured the plant with a cognizant Chemistry Supervisor and examined accessible process and effluent monitors to determine their operability.
The inspector reviewed licensee documentation of the most recent calibration of a
selection of effluent monitors to verify compliance.
The following Unit 1 Monitors were last calibrated:
Plant Vent Low Range Gas Monitor - November 2, 1989 Plant Stack Accident Range Monitor - November 2, 1989 Radwaste Building Exhaust System Plant Vent Monitor - September 19, 1990 Fuel Storage Area Ventilation System - September 25, 1990 Steam Jet Air Ejector Monitor - February 15, 1990 Steam Generator Blowdown Treatment Facility Building Exhaust System (AKB) - October 18, 1990 Steam Dump Monitors - July 23, 1990 ECCS SPING Yionitors, A - December 28, 1990 B - February 21, 1990
I
n Containment Gas and Particulate - February 16, 1990 Liquid Waste Discharge - January 27, 1990 The Following Unit 2 Monitors were last calibrated:
Plant Vent Wide Range Gas Monitor (WRGYi),
Low 5 Nid Range-October 22, 1990 Plant Vent WRGN, High Range - January 23, 1991 Plant Vent Gas - October 19, 1990 ECCS A WRGM - October 11, 1990 B
WRGM - September 7,
1990 Fuel Handling Building Particulate - October 29, 1990 Containment Atmosphere A - October 12, 1990 B - October 17, 1990 Condenser Air Ejector - October 22, 1990 Steam Generator Blowdown A - October 16, 1990 B - October 16, 1990 Main Steam Line Monitor 1 - October 23, 1990 2 - July 25, 1990 All monitors reviewed were calibrated at required frequencies.
No violations or deviations were identified.
12.
Solid Radwaste and Transportation (86750)
The FSAR, Section 11.4 describes the Solid Waste Management System.
The inspector discussed function of the Radwaste organization with the Health Physics Radwaste Supervisor to assess capability.
The Supervisor stated that the Radwaste Coordinator was the only individual reporting directly to him.
Indirect assistance as needed was provided from Radiation Protection personnel, Operations, Mechanical Maintenance Journeymen, and Utility Helpers.
The Supervisor talked through a proposed resin transfer and a proposed Dry Active Waste shipment, discussing how each craft would contribute.
The Supervisor had been in his position for over four years, the Coordinator for slightly less.
The Supervisor stated that he felt that excellent communications existed between his organization, the State of Florida, the Burial Site, and Plant Licensing, and with the Corporate Radiation Protection.
From the above discussion, the inspector concluded that in spite of the diversity of organizations working on the program, good coordination and communication ensured an effective progra ~
'
No violations or deviations were identified.
13.
Exit interview (84750, 86750)
The inspection scope and results were summarized on Yiarch 29, 1991, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results.
No violations
'r deviations were identified.
All effluents were within limits.
The radiological environmental monitoring program was good; no anomalous values were reported.
Effluent monitors were calibrated at required intervals and HEPA and charcoal filters were leak and laboratory tested at required intervals.
Dissenting comments were not received from the licensee.
The licensee did not identify as proprietary any of the information reviewed during this inspectio ATTACHMENT 1 CONFIRMATORY MEASUREMENT COMPARISONS OF H-3, Fe-55, Sr-89, AND Sr-90 ANALYSES FOR ST.
LUCIE NUCLEAR PLANT REPORTED ON DECEMBER 20, 1990
~Isoto e
H"3 Fe-55 Sr-89 Sr-90 NRC (uCi/ml)
6.53+0.26 E-5 Licensee
~(oCi/ml 6.34E-05 3.8520.15 E-5 7.32E-05 1. 01+0. 04 E-4 8. 10E-05 I
2. 67+0. 11 E-6 1. 94E-06 Resolution
25 Ratio Licensee/NRC 0. 97 1. 90 0. 80 0. 73
~Com ari son Agreement Disagreement Agreement Disagreement
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 relation-ships which combine prior experience in comparing radioactivity analyses, the measurement of the statistically random process of radioactive emission, and the accuracy needs of this program.
In these criteria, the
"Comparison Ration Limits"~ denoting 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"~.
For 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 Ration 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 Ration Limits for A reement
<44" 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