IR 05000324/1987032
| ML20235V006 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/27/1987 |
| From: | Gloersen W, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235V000 | List: |
| References | |
| TASK-2.F.1, TASK-TM 50-324-87-32, 50-325-87-33, NUDOCS 8710140389 | |
| Download: ML20235V006 (10) | |
Text
UNITED STATES
[parou NUCLEAR REGULATORY COMMISSION o
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~ ,$
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REGION ll y
j 101 MARIETTA STREET, N.W.
g ATLANTA, GEORGI A 30323
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OCT 011987 Report No.:
50-325/87-33 and 50-324/87-32 Licensee:
Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Docket Nos.:
50 325 and 50-324 License Nos. DPR-71 and DPR-62 Facility Name:
Brunswick Inspection Conducted:
September 14-18, 1987 Inspector k. Ab43h/ 4 9/.> 7/r 7
[h+W.G.G ersen Date' Signed Accompanying personnel:
C. Hughey Approved by:
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- A3)(;_ /1 /,
947/y 7 J. 8. Kgale, Section Chief Date' Signed Division of Radiation Safety and Safeguards SUMMARY scope:
This routine, unannounced inspection involved an examination onsite in the areas of liquid and gaseous radwaste management, radiological effluent monitoring instrumentation, TMI action items, and inspector followup items.
Results:
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- P. W. Howe, Vice President
- C R. Dietz, General Manager
- C. F. Blackman, Supervisor, Radwaste
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- J. A. Smith, Director, Administrative Support i
- E. R. Eckstein, Manager, Technical Support
- J. O'Sullivan, Manager, Maintenance
- C E. Robertson, Supervisor, Environmental and Radiochemistry (E&RC)
- J. W. Davis, Project Specialist, E&RC M. L. Milliner, Foreman, E&RC S. L. Watson, Senior Specialist, E&RC J. Kaham, Senior Specialist, E&RC
- L E. Jones, Director, QA/QC
- K. E. Enzor, Director, Regulatory Compliance R. M. Paulk, Senior Specialist, Regulatory Compliance Other licensee employees contacted included engineers, technicians, operators, and office personnel.
- NRC Resident Inspector
- L. Garner
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 18, 1987, with those persons indicated in Paragraph 1 above.
The inspector described the areas examined and discussed in detail the inspection findings listed below.
During the exit meeting, the inspector discussed the inoperability of the effluent monitoring instrumentation described in the semiannual radiological ef fluent release report.
The inspector expressed concern as to the length of time the effluent monitoring instrumentation had been inoperable.
During a telephone conversation on September 23, 1987, the licensee made a commitment to have the Reactor Building and Turbine Building ventilation flowrate measurement devices operational on both units by January 13, 1989. This item was identified as an inspector followup 4 tem (see Paragraph 8).
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspectio ___-.
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3.
Audits and Appraisals (84723, 84724, 80721)
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Technical Specifications 6.5.5.1 and 6.5.5.2 require the licensee's
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Performance Evaluation Unit (PEU) of the Corporate Quality Assurance Department to perform periodic audits including:
The Environmental
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Monitoring Program and results (once per 12 months); the Offsite Dose Calculation Manual (once per 24 months); the Process Control Program (once
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per 24 months); and the Quality Assurance Program to meet the provisions i
of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, l
Revision 1, April 1975 at least once per 12 months.
The inspectors reviewed the following audits:
QAA/0021-87-01, conducted January 12-16, 1987 QAA/0021-87-06, conducted July 20-24, 1987 These audits appeared to satisfy the Technical Specification requirements and licensee identified findings had been resolved or were being tracked until final resolution.
The inspector also reviewed the following surveillance reports conducted by the Brunswick QA organization:
- QASR No.86-026, Reactor Coolant Chemistry, conducted March 13-17, 1986
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QASR No.86-039, Prestartup/Startup Chemi st.ry,
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May 22-June 15, 1986 QASR No.87-050, Unit 1 Prestartup/Startup Chemistry, conducted May 28-June 15, 1987 These surveillance appeared satisfactory and corrective actions had been taken or were being taken to resolve items of concern.
No violations or deviations were identified.
4.
Procedures (84723, 84724)
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Technical specification 6.8.1 requires the licensee to establish, implement, and maintain procedures covering areas such as liquid and
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gaseous radwaste management, radiological process and effluent instrumentation, the Offsite Dose Calculation Manual, ana the Process Control Program.
The inspectors reviewed selected portions of the following procedures:
E&RC-1214, Monthly Source Check of Process Radiation Monitors,
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Rev. 3, February 15, 1985
E&RC-1503, Emergency Sampling of Wide Range Gaseous Monitor (WRGM),
Rev. 2, July 17, 1986
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'E&RC-200'3, EReporting of Radioactive ~ Effluent Releases, Rev.~ 2, May 30, 1985.
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PT-93.0, EOF /TSC Building Emergency System Test, Rev. O,, July 17,
1987-The inspector. reviewed E&RC-2003 and noted' that ' the licensee' quantified
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radioactive gaseous releases by. obtaining the weekly integrated. gross count ~ data from the wide range noble monitor and a_ weekly grab sample
'which.was' analyzed on the. licensee's gamma ray spectroscopy system. The
- weekly grab sample' provided information on the isotopic distribution of
.the: gaseous ' releases and-was used in conjunction ' with~ the weekly
, integrated gross count data to determine.the quantities of various
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isotopes released.
No violations or deviations were identified.
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Changes to.the. Plant Radwaste Treatment Systems (84723, 84724)
In discussions with licensee ~ representatives and from a review of the January 1
. June 30, 1987, Semiannual Radiological Effluent Release
' Report, the inspector determined that' no major changes had been made to
- the Radioactive Waste Treatment Systems which required ' a 10 CFR 50.59 safety evaluation since.the last inspection.
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No violations or deviation: were identified.
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Reactor Coolant System (84723)
i Technical Specification Table 3.4.4-1 specifies the maximum limits for chloride and conductivities.
The inspectors reviewed selected plant
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chemistry records for the period January 1987 - September 1987 and found that these chemistry parameters had been maintained well below Technical-Specification limits in both units. During power operations RCS chlorides
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were normally maintained below 5 ppb and RCS specific conductivities t
normally varied between 0.12 pS and 0.18pS in Units 1 and 2.
Additionally, Technical Specific'ation 3.4.5 specifies the limits' for specific activity the reactor coolant systems.
Technical Specification Table 4.4.5-1 also specifies the sampling and analysis frequencies for
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isotopic analysis for dose equivalent iodine-131, isotopic analysis for iodine including I-131, I-133, and I-135, gross activity determination, and the radiochemical determination for E-bar.
The inspector reviewed selected plant chemistry records for the period January 1987 - September 1987 ;and verified that these various reactor coolant system parameters L
were well within Technical Specification limits.
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. In January.1987, Brunswick Unit 2 conducted a 69 hour7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> hydrogen water chemistry mini-test.
Installation of permanent equipment (liquid
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hydrogen, liquid oxygen and gaseous hydrogen storage and injection
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L facilities) was underway. The licensee plans to complete the installation l
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by April 1988. At that time permanent hydrogen water chemistry controls will begin with an H injection rate of about 10 SCFM via the condensate
booster pump suction.
Hydrogen water chemistry along with high quality reactor coolant water has demonstrated that intergranular stress corrosion cracking can be mitigated and possibly completely suppressed. Inspection of recirculation piping welds at Brunswick has indicated cracking.
Hydrogen water chemistry will be closely followed in subsequent inspections.
No violations or deviations were identified.
7.
Nuclear Air Cleaning Systems (84724)
Technical Specifications 3/4.6.6.1 and 3/4.7.2 define the operating and surveillance requirements for the Engineered-safety Feature (ESF) high efficiency particulate air (HEPA) filter and charcoal adsorber systems.
The inspector reviewed selected records of in place 00P leak tests of HEPA
' filter banks, in place leak tests of charcoal adsorber banks, and methyl iodide retention effir mcy laboratory tests of filtration system charcoal for the control room s,. tem dated November 25, 1986. The inspectors also noted that the licensee routinely performs HEPA filter and charcoal adsorber in place leak tests associated with the Technical Support Center and Emergency Operations Facility Ventilation systems.
The inspectors reviewed the records of these in place leak tests which were conducted on i
July 23, 1987.
No violations or deviations were identified.
8.
Radiological Effluents (84723, 84724)
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Reports Technical Specification 6.9.1.8 requires the licensee to submit, within 60 days of January 1 and July 1 of each year, routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation. The reports shall include a summary of the quantities of radioactive materials released from the unit as outlined in Regulatory Guide 1.21.
Additionally, the reports that are submitted 60 days after January 1 of each year shall include an assessment of radiation doses from primary effluent pathways.
The inspectors reviewed the Semiannual Radiological Effluent Release Report for the period January 1 - June 30,1987. The review included an examination of the liquid and gaseous effluent release data and an examination of unplanned releases selected data from this report and previous reports are presented in Attachment 1.
The inspectors noted that quantities of radionuclides released did not follow any significant trends from 1985 to the first six months of 1987. Three abnormal liquid releases were noted in the Semiannual Ef fl uent Report.
These liquid releases are discussed in Paragraph 10.
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Additionally, the' report indicated that no revisions were made to the Offsite ' Dos, Calculation Manual- (0DCM) or to the Process Control r
Program (PCF) during the reporting period. In-summary, the inspector noted that the -reporting requirements for the Semiannual Effluent Release Report as specified by the Technical Specifications and the applicable portions of Regulatory Guide 1.21 were met.
-In addition,' the inspector reviewed monthly Environmental and Radiochemistry (E&RC) reports that were distributed to plant Lmanagement.
The reports ' included summaries of offsite radiological
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' doses, gaseous and liquid effluent data, contaminated areas, personnel exposure data, radwaste status, radiation safety
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violations, internal contamination, and ALARA suggestions.
b; Effluent Monitoring Instrumentation The~ inspector discussed with the licensee, the inoperable gaseous and liquid effluent monitoring instrumentation as reported in the Semiannual Radiological Effluent Release Report.
The following instruments were inoperable for greater than a 30 day period between January 1 - June =30, 1987: '(1) Unit.1 main service water effluent radioactivity monitor; (2) Unit 1 Turbine Building ventilation noble gas monitor; (3) Units 1 and 2 main condenser off gas treatment.
system ' explosive ' gas. mcnitors; and' (4) Units 1 and 2 Reactor and Turbine Building roof vent monitor' flow elements.
The Unit 1 main
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service water ef fluent radioactivity monitor was out of service for approximately 31 days due to maintenance activities and the time involved to perform a plant modification to connect the monitor to the Emergency Response Facility Information System (ERFIS)..The Unit 2 main service' water monitor had been previously connected to ERFIS.
The Unit 1 Turbine Building ventilation noble gas monitor was not returned to service -within a 30 day period due to the time involved in resolving maintenance problems and performing a plant modification e
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for system connection to the ERFIS.
The Unit 2 Turbine Building noble gas monitor ERFIS modifications were completed previously. The Unit 1 Turbine Building noble gas monitor was returned to service in-August 1987.
The Units 1 and 2 - main condenser offgas treatment system explosive gas ' monitors are discussed in Paragraph 10. These monitors have been inoperable for over two years mainly due to design problems.
l Additionally, the Units 1 and 2 Reactor and Turbine Building roof vent flow elements have been inoperable for approximately two years due to design problems.
The inspectors noted that the licensee satisfied the ACTION statement in Technical Specification 3.3.5.9 for system effluent flow rate measurement device by estimating the flow rate at least once per eight hours.
The Control Room operators conservatively estimated the flow rate twice per twelve hour shift by using the ventilation system's maximum design flow rate.
In the semiannual radioactive effluent release report for the period covering January 1 - December 31, 1986, it was observed that the air
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dose estimates to the skin at 0.5 miles from the plant in the SSE l
quadrant was 15.9 mrem. This calculated dose. was based on estimatea flow rates (maximum design flow rates) which resulted in apparently higher radiological release calculations and higher dose estimates.
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Compared to the years before 1986, these air doses appeared much lower since the calculations were based actual ventilation flow rate measurements.
The inspector and licensee representatives discussed the length of time that the flow rate measurement devices had been inoperable.
The licensee indicated that Unit.1 modifications were initiated in November 1986.
The modifications involved the replacement of the flow transducer and removal of obstructions in the duct. work.
However, the acceptance test on Unit 1 failed.
The licensee'was examining the duct work to check for holes and/or gaps
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that could have caused the acceptance test failure. At the time of this inspection the maintenance work had not been completed.
The licensee was planning to complete the Unit 1 maintenance work by the end of 1987.
The maintenance work on Unit 2 had been delayed until the Unit 1 maintenance work had been completed.
The licensee was planning to initiate the Unit 2 modifications at the end of the Unit 2 refueling outage (April 1988).
It did not appear that the needed repairs in order to get the ventilation flow rate measurement devices in an operable condition had been given much priority. In a telephone conversation on September 23, 1987, the licensee made a.
commitment to have the Reactor Building and Turbine Building ventilation flow rate measurement devices operational on both Units 1 and 2 by January 13, 1989. This commitment date was tied in with the licensee's control room habitability design review commitment to the Commission. This item was identified as an inspector followup item-(50-324/87-32-01 and 50-325/87-33-01).
9.
TMI/NUREG-0737 Items (25544)
NUREG-0737 Item II.F.1, Attachment 2 describes the sampling and analysis requirements of high-range radiciodine and particulate effluents in gaseous ef fluent streams. The purpose for this capability is to determine the quantitative release of radiciodines and particulate for dose calculation and assessment. NUREG-0737, II.F.1, Attachment 2, states that the licensee shall provide continuous sampling of plant gaseous effluent for post-accident releases of radioactive iodines and particulate to meet the requirements of Table II.F.1-2.
The inspector reviewed the licensee's system for sampling and analysis or measurement of high-range radiciodine and particulate effluents against the sampling requirements outlined in Table II.F.1-2 of NUREG-0737.
The sampling requirements are as follows:
(1) representative sampling per ANSI N13.1-1969; (2) entrained moisture in effluent stream should not degrade the adsorber; (3) continuous collection j
of the sample whenever exhaust flow occurs; and (4) provisions for j
limiting occupational dose to personnel incorporated in sampling systems, I
in samrale handling and transport, and in analysis of samples.
The inspector examined the particulate and iodine sampling apparatus used during normal operations and accident situations for the plant's three gaseous release points, namely:
the plant stack and the Units 1 and 2
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Turbine Building Exhaust System. The inspector noted that the particulate and iodine sampling system was part of the General Atomics Wide Range Gas Monitor System. _ All three accident sample collection skids consisted of three shielded particulate and iodine sampling assemblies in parallel controlled by three solenoid-isolation valves. -This system could allow for the continuous sampling of stack effluents while one of the sampling assemblies was exchanged 'and replaced with a new assembly.
The licensee y
t used Procedure E&RC-1503, Emergency Sampling of Wide Range Gaseous Monitor (WRGM), Revision 2, July 17, 1986, for the post-accident sampling and collecting of radiciodines and particulate.
The particulate and iodine
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grab samples would be transported in shielded containers to the licensee's counting room for analysis. Based on the examination of the equipment and
applicable procedures, it appeared that non-real-time system for l
quantifying radiciodines and particulate met the II.F.1 criteria of NUREG-0737 for the sampling and analysis of radiciodines and particulate.
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No violations or deviations were identified.
t 10.
Licensee Action on Previously Identified Inspector Followup Items (92701)
(Closed) IFI 50-325/81-26-15:
Improvements for liquid radwaste/ effluent sampling capability-section 4.1.1.8.
This item pertained to the interim post-accident liquid sampling system (PALSS) utilized by the licensee i
until the permanent system 'was. installed.
The interim PALSS was the licensee's. normal sampling station. The licensee performed an evaluation
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to determine the need for special sampling equipment and sample station
shielding for the interim PALSS.
The permanent post-accident sampling
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system was installed during the middle of 1983 thus eliminating the need for the interim PALSS.
This item is considered closed.
(0 pen) IFI 50-324/85-12-01 and 50-325/85-12-01:
Inoperable condition of the hydrogen ' gas monitoring instruments in the augmented offgas (A0G)
system to be corrected and instruments returned to service. At the time of this inspection, the inspectors observed that the main condenser offgas hydrogen analyzers were still inoperable.
These analyzers had been inoperable for over two years.
The ACTION statement of Technical
Specification 3.3.5.9 states that the licensee may continue to operate the A0G system provided that grab samples are collected at least once per
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24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and proper functioning of the recombiner is assured by monitoring temperature in accordance with approved procedures. The inspectors reviewed selected analytical logs and records and determined that grab samples had been taken and analyzed in accordance with the ACTION statement and that approved procedures had been followed.
The inspectors noted that the Unit 1 main condenser offgas
hydrogen analyzers were scheduled for modification (modification Number 86-080) to begin on September 28, 1987.
The modification plans
called for rerouting the sample tubing and installing new filters to l
minimize the water moisture in the system which had resulted in plugging the flow switch. The licensee estimated the time required to modify each train to be 21 days.
Similar modifications had been made on Unit 2, however, the licensee was not planning to declare this system operational
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since a new. hydrogen analyzing system based on gas chromatography principles was scheduled for installation during the Unit 2 refueling outage (January 2, 1988 - April 22, 1988).
The installation of this
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monitoring system was associated with the licensee's hydrogen water chemistry program.
According to licensee personnel, the new bydrogen
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analyzer system (Applied Automation System) would have the capability to
obtain a 0.16 ml sample volume.
The sample analysis time would take
approximately 180 seconds.
Installation of a similar system was planned l
for Unit I during the 1988/1989 refueling outage.
The new hydrogen l
analyzer system will be located outside the Steam Jet Air Ejector rooms, in the Turbine Building Breezeway in order to minimize the radiation dose to personnel associated with system maintenance.
This item remains open.
(Closed) IFI 50-325/87-11-03:
Abnormal radiation effluent release from j
1B RHR Hx.
On April 26, 1987, 3 abnormal releases of radioactivity
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occurred immediately after the start of the IB RHR service water booster i
pump.
The service water radiation monitors on both units spiked.
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contaminated water entered the service water side of the 1B RHR heat exchanger through the equalizing valve of a differential pressure instrument thad was inadvertently left open. This event was described in detail in IE Report Nos. 50-325/87-11 and 50-324/87-11 dated June 1, 1987, and was identified r s an Unresolved Item (325/87-11-02).
In that report the Resident Insputors requested that the Region II Radiological
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Effluents and Chemistry Section followup on the licensee's
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characterizations and calculations of the releases.
As a result of that request the inspectors discased the release characterizations and calculations with the licensee and also reviewed the licensee's documented characterization.
(E&RC Experience Report
No. 87-04, " Assessment of Radioactive Release through Unit 1 and Unit 2
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Service Water on April 26, 1987," approved May 19, 1987). The inspector j
reviewed the licensee's assessment and noted that the release did not
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violate Technical Specification 3.11.1.1 (10 CFR 20) and 3.11.1.2 c
(10 CFR 50). Based on nominal flow rate of the service water, the service
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water radiation monitors chart recordings, and a conservative assumption j
of a 1 minute release period the licensee calculated a total release of
7.20 E-2 curies to the environment.
The radioactivity was assumed to be
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from Mn-54 and Co-60 based on an RHR grab sample analyzed after the release.
The assessment claims that, based on 7.20 E-2 curies, the releases did not exceed one times the Maximum Permissible Concentration (MPC) in the discharge canal.
This release represented 0.086% of the yearly limit (20 mrem) for the worst organ (GE-LLI).
This release was also properly included in the Brunswick Semiannual Radioactive Effluent Report for the period January 1, 1987 - June 30, 1987.
(Closed) P21-86-04: Anacon chlorine probes had blue tips vs. white and
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were insensitive to chlorine. After discussions with the licensee, the inspectors determined that anacon chlorine probes were not installed at I
the plant.
This item is, therefore, considered closed.
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l ATTACHMENT 1 Brunswick Nuclear Station Semiannual Effluent Release Summary l
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First Half l
No. Abnormal Releases Year 1985 1986 1987-a.
Liquid
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b.
Gaseous
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i Liquid Waste Released (gallons)
8.74 E+6 4.97 E+6 6.82 E+6 Activity Released (Curies)
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a.
Liquid 1.
Fission and Activation 1.51 E-1 1.26 E-1 2.37 E-1 Products -
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Tritium 9.88 E+0 5.78 E+0 7.34 E+0
3.
Gross Alpha 4.97 E-3 2.70 E-3
b.
Gaseous q
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Noble Gas 1.75 E+4 4.51 E+4 1.42 E+4 2.
Halogens 4.01 E-2 1.46 E-2 1.07 E-2 3.
3.82 E+0 7.07 E+0 1.58 E+0 4.
Gross Alpha 2.61 E-4 2.72 E-4 4.75 E-5 5.
Particulate (gross beta /
gamma)
2.32 E-2 3.23 E-2 2,68 E-2
Dose' Estimates (mrem)
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Liquid (Fish Consumption)
GI-LLI (Adult)
4.68 E-6 2.22 E-5 b.
Gaseous (Noble Gas Releases, 0.5 mi, SSE)
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Whole body 1.24 E+0 5.90 E+0
2.
Skin 3.41 E+0 1.59 E+1 i
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