IR 05000302/1993026
| ML20059B795 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/15/1993 |
| From: | Decker T, Mcneill N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20059B763 | List: |
| References | |
| 50-302-93-26, NUDOCS 9401040248 | |
| Download: ML20059B795 (12) | |
Text
/oash\\
NUCLEAR REGULATORY COMMISSION
'
UNITED STATES
'!
3 t
REGloN 11
..
$
S 101 MARIETTA STREET, N.W., SUITE 2900 7.
p ATLANTA, GEoPGIA 303no199
%
- %,
- .
'
ggg 151333
.....
,
Report No.:
50-302/93-26 Licensee:
Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733
Docket No.:
50-302 License No.: DPR-72'
,
Facility Name: Crystal River 3 Inspection Conducted:
November 15-19, 1993 N.kM l Z-14-9 Inspector:
N. G. McNeill
_
Date Sigried Approved by: V
- s:1 AW
/2f/S /73
~
T. R. Decker, Chief Date Signed I
Radiological Effluents and Chemistry. Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards
SUMMARY
,
I Scope:
j This routine, announced inspection was conducted in the areas of program organizational changes and restructuring, the Microbiologically Induced Corrosion (MIC) program, semiannual radiological effluent and dose commitment summaries for 1993, the results of Audits, Technical Specification (TS)
chemistry parameters, the procedures involved in a liquid batch release, and
decommissioning records.
.
Results:
The licensee had not made any changes to their organization which would i
adversely affect the ability to control radiation exposures-or radioactive material (Paragraph-2).
The MIC program.had addressed potential pro'ilems with microbiological growth and macrofouling (Paragraph 3).
<
'
The Semiannual Radioactive Effluent Release Report for 1993 was reviewed and.
totals for various parameters were totaled and compared with previous years
'
and found to be similar to previous years (Paragraph 4).
The results of audits performed by the licensee were reviewed and found to be comprehensive and thorough (Paragraph 5).
i 9401040248 931215 PDR ADOCK 05000302 G
,
.. -
-
-
_
..
.
.
.
.
.... _.
.
_
.,. -
_.
,
!
-
TS chemistry parameters were reviewed for the previous six months and all parameters were found to be maintained within requirements and the trends well i
analyzed and documented (Paragraph 6).
i
!
Liquid Batch and Gaseous Release permits were examined for previous releases
'
during 1993 to date, and licensee activities for two liquid releases were
)
observed in depth to assure that these activities were performed in accordance
,
with the limits of 10 CFR 20 (Paragraph 7).
Deccmmissioning records were reviewed and found to meet regulatory requirements (Paragraph 8).
j i
!
i i
,
i
!
l l
e
. -
d v--
.-
r
--, -
-
.-
,, -
.
>
REPORT DETAILS
1.
Persons Contacted
Licensee Employees i
P. Ezell, Environmental Chemistry
- E. Froats, Manager, Nuclear Compliance
.
'
- S. Johnson, Manager, Chemistry and Radiation Protection
- T. Lehman, Manager, Nuclear Chemistry
- D. McCullough, Supervisor, Radiochemistry
.
P. McKee, Director, Quality Programs
!
- B. McLaughlin, Nuclear Regulatory Specialist
'
- W. Rossfield, Manager, Site Nuclear Services
- R. Widell, Director, Nuclear Operations Site Support
- D. Wilder, Manager, Radiation Protection Other licensee employees contacted during this inspection included engineers, technicians, and administrative staff.
- Attended Exit Interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
2.
Organization (8'.750)
i Technical Specification (TS) 6.2.1-describes the licensee's organization.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to radiation protection and radioactive material control to verify that the licensee had not made organizational changes which would adversely affect the ability to j
contrcl radiation exposures or radioactive material.
j The inspector determined that there had been one major change to the organizational structure. Management reassessments of staffing requirements had resulted in the loss of some technical staff positions in the Chemistry and Radiation Control group. The group had lost two technicians and one technical as'sistant. There was also some reorganizing of responsibilities for the remaining managers in the section.
The changes were expected to have minimal impact on the ability of the organization to perform required tasks. The loss of
~
positions was also less than had previously been anticipated.
Responsibilities and training requirements for the technicians had not
changed.
Licensee representatives were advised that the changes in this-area, which had been in effect less than a month at-the time of the inspection, would be reviewed during future inspections to assess the impact on the program.
.l l
.
,
!
l i
Based on this review, the inspector determined that the licensee had not
-
made any changes to the organization which would adversely affect the ability to control radiation exposures or radioactive material.
No violations or deviations were identified.
!
.
3.
Microbiologically Induced Corrosion and Plant Chemistry (84750)
'
Water chemistry can have a major impact on component performance, availability, and expected life. Steam generator material integrity is closely aligned with the control and minimization of several different i
secondary water chemistry parameters as well as biologically influenced corrosion factors. The inspector discussed with cognizant licensee personnel the continuing actions that the plant was taking in order to prevent microbiological attack and macrofouling of cooling water piping
and heat exchangers within the plant service water.
t Protection against ingress of corrodants from the plant cooling system is discussed below.
a.
Main Condenser Water Boxes
[
Metallurgical examinations of the condenser inlet water boxes were conducted as early as 1986. Degradations in the stainless steel
,
welds in both the water boxes and connecting instrument piping were determined to be caused by microbiologically induced corrosion (MIC). Since that time several attempts have been-made to alleviate the effects of MIC. A new condenser tube cleaning system (Amertap) and new circulating water pumps were utilized and
'
are maintained as part of the licensee's program to reduce MIC.
Additional key modifications have included replacement of sacrificial iron gratings in the water boxes. When these gratings were first removed it was determined that this reduction of iron available to the resident bacteria population had driven these
!
microbes to attack E 308 weld fusion zones. This weld attack has resulted in noted stress corrosion cracking (SCC).
The licensee has initiated several actions to remedy past i
corrosion and prevent new attack. The iron gratings were replaced in the system, one half of the condenser tubes were replaced with titanium tubes (with the-remainder scheduled for the next outage-
April 1994), component repair was conducted with nickel base
alloys and weld rods, and a program for sulfate-reducing lacteria (SRB) testing was implemented.
,
b.
Reactor Coolant Bleed Tank During the same 1985-1986 time frame, a red fungal-type bacterial
,
growth was detected in the Reactor Coolant Bleed Tank. The tank was isolated, drained, washed with a hydrogen peroxide solution, i
and refilled with demineralizew treated water. No recurrences of
,
i
4
--
_
_.
i
3 bacterial growth have been noted and the system is tested routinely for the presence of bacteria.
The systems water quality is routinely tested by the following procedure: Chemistry and Radiation Protection Procedure CH-413,
" Reactor Coolant Support System's Chemistry Scheduling Program,"
Revision 13, dated October 14, 1993.
l c.
Closed Cycle Cooling Water l
These water systems also contain demineralized, treated water which is routinely monitored by chemistry personnel by the following procedure: Chemistry and Radiation Protection Procedure CH-418 " Secondary Coolant Support System's Chemistry Scheduling
Program", Revision 12, dated July 8, 1993.
i
.
While no severe MIC problems have been noted on this side of the
!
system, the associated heat exchangers on the closed cycle cooling
-
water have employed zinc anodes as a method of passive protection for piping and welds, d.
Raw Water This side of the system has water which is untreated and for which no routine testing and maintenance of water quality is performed.
!
However, most affected piping has been urethane lined or coated and piping integrity is routinely evaluated.
The inspector found that the licensee had undertaken, and
continues to provide, a program to monitor and evaluate potential i
problems associated with MIC.
,
No violations or deviations were identified.
l 4.
Semiannual Radioactive Effluent Release Report (84750).
TS 6.9.1.5.d requires the submittal of routine Radioactive Effluent Release Reports covering the operation of the unit during the previous i
six months of operation. These reports summarize the amounts of liquid
!
and gaseous effluents released from the site and assess the dose to
-
offsite populations from these effluents.
A summary of the effluent releases for 1991, 1992 and the first half of-l 1993, is presented. The doses to the public due to these effluents
'
were less than two percent of the 25 mrem per year limit for total body or critical organ doses specified in 40 CFR 190.
No adverse trends were-noted.
-
There were no unplanned gaseous or liquid releases for 1993 to the date of the inspection. There were no instances of effluent monitor
inoperability of greater than 30 days in 1993 to date.
!
!
,
-
.
h
,
A summary of the annual releases are as follows:
Crystal River Unit 3 Radioactive Effluent Release Summarv i
First Half
1991 1992 1993
!
No. of Unplanned f
Releases
.
a. Liquid
0
- b. Gas
1
Activity Released (Curies)
a. Gaseous
1. Fission and Activation Gases 1.40E+03 7.86E+02 4.50E+01
.
2. Iodines 2.55E-04 6.32E-04 5.13E-05 3. Particulates 2.80E-04 8.12E-06 3.49E-06
i 4. Tritium 1.35E+01 1.50E+01 9.19E+00 t
b. Liquid 1. Fission and Activation Products 4.64E-02 2.07E+00 3.65E-01
,
t 2. Tritium 4.49E+02 3.64E+02 2.45E+02
-
3. Gross Alpha
<LLD
<LLD 1.29E-04 c. Volume of liquid
,'
Wastes Released 4.34E+07 3.35E+07 1.96E+07 Prior to Dilution
,
(liters)
'
I The above table shows an improved performance (compared with the previous year) for the first half of 1993 in the fuel since Refueling
Outage 8 (RF8) as evidenced by the iodine. levels. The fission and e
activation products for the first half of 1993 indicate that problems-
!
identified as poor demineralizer performance and. Control Rod Drive i
Mechanism (CRDM) leakage had been resolved as well.
l There were no instances of effluent monitor inoperability of greater
than 30 days in 1992.
l t
i l
-
_
.
,
!
i A summary of associated calculated annual radiation doses to the public
'
for 1990,1991, and 1992 are presented in the following table:
v Crystal River Unit 3 Dose Commitments l
Doses to Individuals From Liauid and Gaseous Effluents
,
Annual Dose Totals 1990 1991 1992
I a. Gaseous Effluents 1. Total Body (mrem) 3.67E-01 6.28E-02 1.95E-02 i
2. Critical Organ (mrem)
9.94E-01 2.21E-01 3.87E-01 b. Liquid Effluents i
1. Total Body (mrem)
1.38E-02 6.32E-02 4.50E-02 2. Critical Organ (mrem)
2.43E-01 4.45E-02 6.24E-01 c. Annual Totals.
,
,
1. Total Body (mrem) 3.81E-01 1.26E-01 6.45E-02 2. Critical Organ i
(mrem)
1.24E+00 2.65E-01 1.01E+00 l
In conclusion, the effluent releases and resultant doses were within l
Technical Specifications; 10 CFR 20, Appendix B; and 10 CFR 50, Appendix I limits.
No violations or deviations were identified.
i 5.
Audits (84750 and 86750)
i TS 6.5.2.9 requires audits of facility activities to be performed I
including:
The Radiological Environmental Monitoring program and the results
thereof at least once per 12 months.
The ODCM and implementing nrocedures at least once per 24 months.
-
The Process Control Program and implementing procedures for
solidification of radioactive wastes at least once per 12 months.
The performance of activities required by the Quality Assurance
-
Program for effluent and environmental monitoring at least once per 12 months.
.
i I
. -, -.... ~.
...
- - -
.., -. - - - -
- - + - - - - - - -
'
i
.
i
The purpose of the audits was to ensure that the licensee effectively implemented the programs which controlled these various areas. These programs ensured that the licensee effectively controlled, quantified, and monitored releases of radioactive materials; and that the Environmental Monitoring Program was implemented effectively.
!
Pursuant to these requirements, the inspector reviewed the following Audit Reports:
Audit Report No. 93-005-SSUP, " Nuclear Operations Site Support,"
!
-
June 1993 Audit Report No. 93-03-CREW, " Nuclear Chemistry, Radiation
-
Protection, and Nuclear Waste," April 1993
Audit Report No. 93-05-SSUP was reviewed for site support services provided by the Florida Department of Health and Rehabilitative Services (DHRS) in the environmental monitoring program. DHRS provides for the sampling and analysis of environmental samples as part of the licensees Radiological Environmental Monitoring Program (REMP). The audit team
,
reviewed the Florida DHRS laboratories, equipment, calibrations,
,
procedures, and Land Use Census report. The DHRS facilities and
monitoring capabilities were found to meet all requirements of the
i Technical Specifications and no deficiencies were identified.
Audit Report No. 93-03-CREW was performed in administration, control and implementation of Nuclear Chemistry, Radiation Protection, Rad Waste, and Environmental Monitoring Program; and assessed the effectiveness of
.
the interfaces among the organizations having responsibilities for these l
programs.
The inspector reviewed the audit findings, the Problem Reports (prs)
_
'
associated with the audit findings, and the observations and recommendations associated with the concerns, in the areas pertinent to
>
this inspection and determined tLat the licensee corrective actions were-timely and technically acceptable.
No violations or deviations were identified.
!
6.
Technical Specification Chemistry Parameters (84750)
TS 3.4.8.a requires that the specific activity of the primary reactor r
coolant be less than or equal to 1.0 microcurie per gram (uCi/g) dose
!
equivalent iodine-131 (DEI-131). This ensures that resulting two hour i
doses at the site boundary will not exceed 10 CFR 100 limits following a l
steam generator rupture accident in conjunction with a primary to
!
secondary steam generator leak of 1.0 gallon per minute.
l i
Water chemistry can have a major impact on component performance, I
availability, and expected life.
Steam generator material integrity is
!
closely aligned with the control and minimization of several different
!
secondary water chemistry parameters.
i
1
-
.
The inspector reviewed both primary and secondary parameters. The secondary parameters examined were Feedwater oxygen and sodium as well as Hotwell oxygen and sodium. The primary parameters examined were Reactor Coolant System (RCS) chlorides, fluorides, and DEI-131. Daily chemistry reports as well as monthly summaries were reviewed and trends for the last six months noted. All of the parameters were well within TS guidelines. The DEI-131 values in particular were very low, averaging less than.0030 uti/g. No iodine spikes were noted for the time frame reviewed and were indicative of good fuel performance to date. Chloride concentration was averaging.004 to.006 parts per million (ppm) for the year to date. One instance of elevated chloride concentration was detected after start up and was attributed to welding performed during shutdown. The levels immediately returned to normal concentrations for the rest of the year. Fluorides averaged.004 ppm for the same time frame. The three primary parameters averaged less than one percent of the Technical Specifications requirements. Secondary parameters also averaged less than one percent of administrative limits. The daily chemistry reports were well organized and had the added feature of trending for the last 28 day time frame.
Based on this review, the inspector determined that the licensee was effectively monitoring TS chemistry parameters and results were within established guidelines.
No violations or deviations were identified.
7.
Liquid and Gaseous Releases and Permits (84750)
TS 3.3.3.8 requires that radioactive liquid effluent monitoring instrumentation channels shall be operable with their alarm / trip setpoints set to ensure that the concentrations of radioactive material released to unrestricted areas shall be less than or equal to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. The setpoints shall be determined in accordance with the ODCM.
TS 4.11.2.1.2 details the methods for determining dose rates due to radioactive materials including noble gases which are outlined in Table 4.11-2. The table also lists the sampling and analysis frequencies, and Lower. Limits of Detection (LLD), which are to be used for batch and continuous releases.
The inspector reviewed the sampling and analysis portions of two liquid releases. The batch releases were from the Secondary Drain Tank #1 (SDT-1) and the Laundry and Shower Sump Tank (LSST). The inspector also-reviewed the associated procedures for batch and gaseous releases. The procedures reviewed were as follows:
- Chem / Rad Instruction No. CH-268, " Liquid Radwaste Evaluation,"
Revision 4, Dated March 25, 1993
_ -.
-
.
,
- Chem / Rad Instruction No. CH-269, " Gaseous Radwaste Evaluation,"
Revision 5, dated October 15, 1993 The inspector observed collection and analysis of the samples from the
,
respective tanks. The inspector paid particular attention to the rauiological analyses required for the Release Permit and the nonradiological analyses performed to meet National Pollution Discharge Elimination System (NPDES) requirements. The inspector also reviewed the
-
calculations performed as part of the final Release Permits.
The inspector found that the technicians were competent in the sample collection and analyses and were able to meet all procedural
,
requirements. The inspector found the permits to be thorough and.
accurate and to meet the requirements as outlined in the Technical Specifications.
No violations or deviations were identified.
8.
Decommissioning Records 10 CFR 50.75(g) requires, in part, that licensee's maintain " records of information important to the safe and effective decommissioning of the facility in an identified location until the licensee is terminated by the Commission". Furthermore, information considered important by the
,
Commission for decommissioning is identified as " records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site" aad that the records "must include any known information on identification of involved nuclides, quantities, forms, and concentrations."
The inspector examined the records maintained by the licensee to meet the requirements for decommissioning purposes. The licensee's records consist of a three part notebook. The first part deals with all administrative 1y controlled Radiation Control Areas (RCAs) found i
throughout the plant. The second part of the notebook details the :,.it of spills and contamination events which have occurred since the plant began operations and is continuously updated as conditions warrant. The final portion of the notebook is a list of as-built drawings and modifications to structures which have occurred on site. All portions are maintained current to date and are quite thorough.
,
The inspector found that the records maintained by the licensee were very well maintained and complete and exceeded minimal requirements. It i
was noted in discussions with the licensee that this area revealed a l
very conscientious and proactive approach by the site to meet regulatory standards.
No violations or deviations were identified.
,
l l
-
,
10.
Exit Interview The inspection scope and results were summarized on November 19, 1993, with those persons indicated in Paragraph I above.
Licensee representatives acknowledged the inspector's comments and no dissenting comments were received.
11.
Acronyms and Initialisms ARE0R Annual Radiological Environmental Operating Report CFR Code of Federal Regulations DEI Dose Equivalent Iodine DHRS (Florida) Dept. of Health and Rehabilitative Services LLD Lower Limit of Detection LSST
. Laundry and Shower Sump Tank HIC Microbiological 1y Induced Corrosion mrem millirem NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual PCP Process Control Program PR Problem Report RCS Reactor Coolant System REMP Radiological Environmental Monitoring Program RM Radiation Monitor SCC Stress Corrosion Cracking SDT Secondary Drain Tank SP Surveillance Procedure TS Technical Specification uti Microcurie