ML18152A921
| ML18152A921 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/26/1988 |
| From: | Bermudez H, Kahle J, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A920 | List: |
| References | |
| 50-280-88-13, 50-281-88-13, NUDOCS 8806070242 | |
| Download: ML18152A921 (12) | |
See also: IR 05000280/1988013
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION 11
101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30323
Report Nos.:
50-280/88-13 and 50-281/88-13
Licensee:
Virginia Electric and Power Company
Richmond, VA
23261
Docket Nos.:
50-280 and 50-281
Facility Name:
Surry 1 and 2
.. ermu ez
Approved by,(, ~i}_,/(c.J,L,
License Nos.: DPR-32 and DPR-37
J/a:e,ict ion Chief
,~7on of Radiation Safety and Safeguards
SUMMARY
Scope:
This routine, unannounced inspection was conducted in the areas of
radiological environmental monitoring, liquid and gaseous effluent processing,
liquid and gaseous effluent monitoring and confirmatory measurements.
Results:
No violations or deviations were identified .
8806070242 880526
ADOCK 05000~80
r
REPORT DETAILS
1.
Persons Contacted
Licensee Employees
- D. L. Benson, Station Manager
- P. F. Blount, Assistant Health Physics Supervisor
- B. A. Garber, Health Physics Supervisor
- E. S. Grecheck, Plant Manager
- G. D. Miller Licensing Coordinator
- S. P. Sarver, Health Physics Superintendent
Other licensee employees contacted included engineers, technicians, and
office personnel.
NRC Resident Inspector
- W. E. Ho 11 and
- Attended exit interview
2.
Exit Interview
3.
The inspection scope and findings were summarized on April 29, 1988, with
those persons indicated in Paragraph 1 above.
The inspectors described the
areas inspected and discussed in detail the inspection findings.
No
dissenting comments were received from the licensee.
Semi-annual effluent reports for January-June and July-December 1987 were
reviewed and found to be adequate.
Tests of the HEPA and charcoal ESF
filter systems were reviewed and found to be adequate.
The radiological
environmental air sampling program was reviewed and found to be adequate.
Radioactive effluent monitoring, samp 1 i ng and analysis programs were
reviewed.
Containment particulate and iodine monitor channels were
out-of-service for Unit 2 to a result of mechanical problems with the
filter tape drive; resolution of the problem was being actively pursued by
station personnel.
A total of 14 outstanding items were closed.
The licensee did not identify as proprietary any of the materials provided
to or reviewed by the inspectors during this inspection.
Licensee Action on Previous Enforcement Matters
(Closed) 50-280,281/87-22-0l (SL-4) Inability to Perform Source Check On
1-RM-LA-108 Liquid Radwaste Monitor in Accordance with Table 4.1-l(A) of
the Technical Speci fi cat ion.
The inspectors observed a control room
operator perform a source check on 1-RM-LA-108 liquid radwaste monitor.
The meter needle was observed to move from a reading of approximately
2
500 cpm to a reading of approximately 3,000 cpm upon source actuation.
There were two major factors which made the source check successful.
The
first was the system decontamination effort noted in the closure of
IFI 50-280,281/87-02-02 (see Paragraph 11 of this inspection report).
The
second was installation of a 22 uCi Cs-137 source in place of the original
8 uCi Cs-137 source.
The combined effects of 1 ower background through
decontamination and higher count rate through provision of a larger source
produced a positive source check instead of the imperceptible movement of
the meter needle observed in earlier source checks.
This matter is
considered closed.
(Closed) 50-280,281/87-22-02 (URI):
Perform An Evaluation to Determine If
Slightly Contaminated Sludge Was Shipped to the Surry County Landfil 1.
The licensee performed the requested evaluation.
The licensee was unable
to identify any specific source for the low level sludge contamination
referenced in Inspection Report 50-280, 281/87-22.
In the evaluation the
licensee conceded that it was possible that shipments to the Surry county
1 andfi 11 of sanitary s 1 udge, at radioactivity 1 eve 1 s undetectab 1 e by
normal survey methods, but detectable by laboratory analysis, could have
been made on an approximately twice-annual basis in volumes of 10 to 20
cubic feet of material for each shipment and at radioactivity
concentrations of Cs-137 and Co-60 on the order of 2-3 pCi/gram.
At the
levels of activity seen in sludge samples to date, the licensee considered
that it was possible that previous shipments to the Surry County landfill
had contained radioactive materials at levels within an order of magnitude
higher or lower than the levels reported in Inspection Report
Nos. 50-280, 281/87-22.
It was a 1 so cone 1 uded that extern a 1 radiation
levels from packages of dried sludge, as shipped, were such as to be
undetectable with portable survey instrumentation, and it was therefore
highly unlikely that previous shipments could be located
11 in-situ
11 at the
Surry County 1 andfil 1.
The inspectors' review concluded that the
evaluation was adequate.
The licensee had adopted procedure revisions to
prevent future shipments of potentially radioactive materials to the Surry
County landfill.
The inspectors agreed with the licensee's position that
attempts to locate and retrieve past shipments of dried sanitary waste
treatment sludge would be unproductive.
This matter is considered closed.
(Closed) 50-280,281/87-22-03 (SL-4):
Failure to Conduct An Evaluation and
To Determine The Concentrations of Radioactive Materials Contained in the
Sanitary Sewage Sludge.
The licensee conducted an evaluation which
acknowledged the presence of radioactivity at low concentrations in dried
s 1 udge raked from the sand fi 1 ter drying bed.
Efforts to 1 ocate the
source of the contamination were not successful.
Licensee representatives
stated that the source was considered likely to have been concentration
within the sewage digester from low-level or undetectable levels of
contamination as no apparent radioactive inputs could be i dent ifi ed.
Procedure CAP-53.0 was issued March 11, 1988, and incorporated periodic
sampling of dried sludge, and sampling, analysis and sign-off by the
Supervisor of Health Physics Technical Services before future sludge
quantities can be disposed of.
The licensee's response to this matter was
considered adequate and this matter is considered closed.
3
4.
Semi-Annual Radioactive Effluent Release Reports (84723, 84724)
5.
The inspectors reviewed the the 1 icensee' s Semi-Annua 1 Radio 1 ogica 1
Effluent Release Reports for the first half of CY 1987 (January-June 1987)
and for the second half of CY 1987 (July-December 1987).
The reports
appeared to be complete and to contain the information specified in
A summary of the releases for the year (1987) is
shown below.
Gases
'FTssTon and Activation Products
Iodine - 131
Particulates (>8 day Half-Life)
Liquids
Fission and Activation Products
Dissolved Gases
Alpha Emitters
Volume of Liquid Released (liters)
Volume of Dilution Water (liters)
~uantitb (Curies)
.08 E+ 2
1. 81 E-02
2.84 E-03
3.04 E+Ol
5.17 E+OO
8.15 E+02
2.65 E+OO
3.91 E-05
2.96 E+08 liters
2.21 E+12 liters
Gaseous releasas of fission and activation products were lower than the
average annual releases of 22 operating PWRs in NRC RII (4,400 Ci/yr/unit
in CY 1986).
On the other hand, 1 i quid re 1 eases of fission and
activation products, per operating unit, were 225% of the average releases
of 22 operating*PWRs in RII for the CY 1986 (last year for which all data
was available at the time of inspection).
It should be noted, however,
that the licensee's CY 1987 releases were lower than in previous years.
Fission And Activation Products In Plant Effluents
(Surry, Units 1 and 2, Combined Releases)
Year
Liquids
Gases
1987
5.1 Ci
308 Ci
1986
8.77 Ci
1,990 Ci
1985
8.50 Ci
2,070 Ci
1984
9.73 Ci
6,960 Ci
1983
14.5 Ci
5,490 Ci
1982
6.7 Ci
21,100 Ci
1981
6.11 Ci
14,100 Ci
No violations or deviations were identified.
Radioactive Effluent Monitoring, Sampling and Analysis (84723, 84724)
The inspectors, accompanied by a licensee representative, inspected the
plant gaseous and liquid radioactive effluent monitors and samplers.
4
The liquid radwaste monitor, RM-108, appeared to be operating
satisfactorily.
The licensee had experienced a number of problems with
this monitor, principally the result of buildup of contamination over
extended periods of time, the resultant high background count rate, and a
check source which was too small to provide a measurable increase in
metered countrate when the check source was actuated.
Remedial actions
taken by the licensee to correct these conditions inc 1 uded the
modification of piping to incorporate spool piece connections instead of
an all-welded configuration to facilitate access to the monitor's internal
chamber, providing a new electro-polished samp 1 e chamber for ease of
decontamination, revision of procedures to provide for system flushing
with uncontaminated water to minimize contamination plateout on sample
chamber surfaces, and a 1 arger check source to provide an increased
countrate upon check source actuation.
The inspectors observed that the
system's normal background (at the time of this inspection) was about
500 cpm and that check source actuation resulted in a visible meter
deflection to about 3,000 cpm.
Containment particulate and iodine monitoring channels RM-159, -160, -259,
and -260 were inspected at the request of the senior resident inspector.
In discussion with licensee representatives, the inspectors were informed
that the two monitoring systems concerned (i.e., RM-159/160 and RM-259/260)
were Victoreen noble gas, particulate aerosol, and iodine aerosol monitors
of a new type installed April 1987.
These monitors incorporated a new type
of filter paper drive.
The vendor apparently encountered a number of
mechanical breakdowns of the tape drive mechanism in the production models
of the new monitors.
The breakdowns began on a generic basis shortly after
the licensee received and installed the units (about April 1987).
When the
licensee encountered failure of the tape drives and ordered spare parts for
repair purposes, the vendor notified the licensee that repair parts could
not be provided because of a "design change hold.
11
In early March 1988,
vendor factory representatives came to the licensee's facility and
installed new components in the licensee's monitors.
Both monitors worked
we 11 until the night of April 23, 1988, when the filter tape drive
mechanism on the Unit 2 monitor RM-259/260 jammed again and the iodine and
particulate channels were declared inoperable.
As of the end date of this
inspection, licensee electronics maintenance personnel had been unable to
resolve the jamming problem and the licensee was considering bringing in
vendor personne 1 to correct the prob 1 em.
With the Unit 2 monitor
RM-259/260 inoperable, the licensee met Technical Specification
requirements by sampling and analysis of the containment atmosphere.
This matter was further discussed with the Senior Resident Inspector.
The inspectors noted that the Unit 1 component cooling water system (CCWS)
monitors RM-105/106 were reading at levels of approximately 1 E+OS cpm at
both the local and control room panel readouts.
A licensee representative
stated that these levels were the result of system contamination which
occurred prior to 1983 .
5
The process monitor (RM-107) for the component cooling service water
system (CCSWS) was noted to have been out-of-service for over a year.
A
licensee representative stated that this monitor detector was located in a
well inside a pipe of the CCSWS and had been contaminated sometime prior
to 1983, under the same circumstances which contaminated the CCWS and
resulted in high readings on RM-105/106.
The high radiation background
resulting from the contamination made the monitor incapable of performing
its intended function of responding to small intersystem leaks from the
CCWS into the CCSWS.
For this reason, the monitor had been declared
out-of-service and the sampling and analysis program required by the
Technical Specifications had been implemented.
The licensee has discussed
proposing a Technical Specification change removing RM-107 from the
Technical Specification and adding sampling and analysis of water from the
CCWS to the routine sampling and analysis table of the Technical
Specification. In the cases of all three monitors (RM-105/106/107), the
detectors are located in wells which are not accessible for
decontamination.
In discussions between the inspectors and licensee personnel, it was noted
that the licensee did not do regular correlations between sample analyses
of * 1 i quids and gases from tanks to be discharged and corresponding
effluent monitor readings as the tank are discharged to the atmosphere.
The inspectors noted that many licensees follow the correlation practice
and consider it to be an important tool in verifying the validity of
discharge permits, calculations of total releases and effluent monitor
operability.
During the above discussion, it was also noted that the licensee did not
calculate a new effluent monitor alarm setpoint for each release of
liquids, preferring instead to base alarm levels on the offsite MPC for
iodine-131, assuming minimum dilution.
Such a value was lower than any
that would be calculated on the basis of sample analysis results.
Such
. alarm settings were conservative and placed more restrictive bounds on
licensee operation than using setpoints established separately for each
use and based on both 10 CFR Part 20, Appendix 8, and 10 CFR Part 50,
Appendix I, as implemented by the Offsite Dose Calculation Manual (ODCM).
No violations or deviations were identified.
6 .. Environmental Radiological Monitoring (8072)
The inspectors accompanied licensee representatives during regular
collection of week-long air samples from the eight environmental
monitoring air sampling stations established for the Surry site.
The
eight designated stations were:
Surry Station; Hog Island; Bacon
1s
Castle; Alliance; Colonial Parkway; Dow Chemical; Fort Eustis; and Newport
News.
The inspectors observed sample change methods and noted that good
sampling handling practice was used.
The licensee representatives knew
the sample route and locations and performed their tasks in a competent
and professional manner.
6
All sampling equipment was functioning properly and appeared to be
well-maintained.
Sample enclosures were clean and free of debris and
extraneous material. Collected samples were clearly labelled as to sample
location, sample on and off times, air flow rate, and sample volume.
Samples were to be shipped to the vendor laberatory for analysis.
No violations or deviations were identified.
7.
Radioactive Gaseous Effluent Treatment System (84724)
The inspectors reviewed the licensee's system maintenance, leak testing,
and charcoal iodine retention for the safety-related HEPA - charcoal
gaseous filtration and adsorption systems.
requires, in part, that safety-related filtration and adsorption systems
undergo the following operational testing:
0
0
0
0
0
0
0
0
Each redundant train to be operated monthly for a period of at least
15 minutes if it has not already been in operation during the month.
Once per refueling cycle, the operability of the entire
safety-related portion of the auxiliary ventilation system is to be
demonstrated.
The fan fl ow rate is to be determined once per refueling eye le
(approximately 18 months) or after each partial or complete high
efficiency particulate air (HEPA) filter or charcoal adsorber change.
A visual inspection to be made prior to air flow distribution tests,
HEPA filter leak tests, or adsorber freon (halogenated hydrocarbon)
leak tests; in accordance with ANSI NSl0-1975.
Cold dioctylphthalate (DOP) leak test to be made initially, once per
refueling cycle (approximately 18 months), after partial or complete
high efficiency particulate air (HEPA) filter or charcoal adsorber
change.
A visual inspection is to be made prior to air flow distribution
tests, HEPA filter leak tests, or adsorber freon (halogenated
hydrocarbon) leak tests, in accordance with ANSI NSl0-1975.
Cold dioctylphthalate (DOP) leak test to be made initially, once per
refueling cycle (approximately 18 months), after partial or complete
replacement of HEPA filters or charcoal adsorbers, or after any
structural maintenance, per ANSI N510-1975.
Freon (halogenated hydrocarbon) leak test to be made initially, once
per refueling cycle, after partial or complete replacement of HEPA
filters or charcoal adsorbers, or after any structural maintenance,
per ANSE NSl0-1975.
0
7
Laboratory test for re tent ion efficiency of charcoa 1 for methyl
iodide, initially, once per refueling cycle, and after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of
operation, in accordance with ASTM 03803.
The inspectors toured the HEPA filter and charcoal adsorber installations
and reviewed licensee documentation on selected tests performed to meet
the TS requirements.
Items reviewed included .procedure PT-32.9, issued
June 17, 1985, for details on HEPA filter and charcoal adsorber testing.
Test records for 1987, and the first three months of 1988, were reviewed
for the following installations:
1-VS-FL-3A and 38
1/2-VS-FL-8
1/2-VS-FL-9
HEPA filter and charcoal adsorber testing was performed under contract by
qualified personnel of the Charcoal Service Corporation, Bath, North
Carolina, except that charcoal adsorber methyl iodide retention efficiency
1 aboratory tests were subcontracted to Nuclear Containment Systems,
Co 1 umbus, Ohio.
The most recent series of tests was conducted in late
March and early April 1988.
The contractor 1 s test data, test results,
test instrument calibration documentation and quality assurance program
appeared to be satisfactory; in one system tested, charcoal did not meet
the required TS criteria and the charcoa 1 was rep 1 aced with a new
pre-tested module, with required leak testing and fan testing being
repeated fo 11 owing adsorber module changeout, in accordance with TS
requirements.
Operational records of filter and adsorber system operation to meet the TS
requirement for at least 15 minute of operation monthly were reviewed for
the period of March 1, 1987 through March 31, 1988.
The required
operations appeared to have been done in conformance with the
specification.
No violations or deviations were identified.
8.
Audits (84723, 84724, 84725)
The inspectors reviewed licensee audit files for audits concerning matters
within the scope of this inspection and performed or issued since the
previous inspection (50-280,281/87-22, August 3-7, 1987).
Audit 587.17, dated July 29, 1987, but issued subsequent to the inspection
of August 3-7, 1987, was concerned with the Process Control Program (PCP)
and with the Offsite Dose Calculation Manual (ODCM).
The audit documented
two concerns of administrative nature:
(1) Two procedures OP.22.1,
11High
Level Waste Drain System," (January 1979) and OP.22.2,
11 Low Level Drain
System
11 (July 1982) were noted to be obsolete; and (2) Section 12.1 of the
ODCM referenced an incorrect section of the Technical Specification in
reference to the Semi-Annual Effluent Release Report.
The later concern
was a repeat finding, previously noted in a 1984 audit 584-32.
8
The licensee's responses to the audit concerns appeared to be timely and
were considered to be adequate to meet the specified concerns.
The audit
appeared to have been performed in satisfactory depth.
No violations or deviations were identified.
9.
Licensee Quality Assurance for Confirmatory Measurements (84725)
The inspectors requested and were supplied information concerning licensee
internal quality assurance activities, including analyses of cross-check
samples prepared by Virginia Power Company Corporate Health Physics for
analysis in the Surry Count Room.
ln a memorandum dated September 30,
1987, the corporate Health Physics group reported that Surry analyses of
three mixed gamma emitter liquid samples and one tritium liquid sample
were all in agreement.
All three liquid samples were analyzed on all
three Surry intrinsic germanium detectors; the one tritium sample was
analyzed on the one Surry Tritium analyzer.
In a memorandum dated June 15, 1987, from Corporate Health Physics to the
Surry Plant, documentating an earlier cross-check, the memo noted
disagreement on the Ce-144 result for detector No. 1 and agreement for
Cs-134, Cs-137, Mn-54 and Co-60 for detector No. 1.
For detectors No. 3
and No. 4, agreement was noted on all nuclides (Ce-144, Cs-134, Cs-137,
In a Ce-144 re-check on detector No. 1, the re-check
was in agreement.
The inspectors reviewed Corporate HP procedure CHP-9,
11Confi rmatory
Measurements Using Spiked Samples.
11
The criteria for agreement or
disagreement appeared to be the same as that set forth in NRC Inspection
Module 84725.
The inspectors reviewed data provided by the licensee's contract laboratory
concerning the laboratory's participation in the EPA crosscheck program
for the period between January 1, 1987 and December 11, 1987.
The data
consisted of statements of agreement or disagreement of the contractor
laboratory analysis with EPA results on identical samples.
The contractor
laboratory's performance in analyses of some 35 separate samples appeared
to be adequate.
The licensee's quality assurance programs, including those of the
contractor laboratory appeared to be comprehensive and responsive to needs
and were considered to be adequate.
No violations or deviations were identified.
10.
Licensee Event Reports (92700)
(Closed) LER 50-280,281/87-040 (January 29, 1988)
On December 31, 1987, the licensee discovered that two week-1 ong
particulate filters from the effluent sampler servicing the containment
9
vacuum system gaseous discharge had been uni ntent iona lly discarded.
Technical Specification 4.9, table 4.9-2 required that all weekly
particulate samples taken during a calendar quarter be composited
quarterly for analysis of Sr-89 and Sr-90 at an LLD of IE-11 uCi/ml.
The
specification was implemented by Health Physics Procedure HP.3.2.1.
The
analysis of the missing filters for principal gamma emitters had been
accomplished prior to the discarding of the filters; results were typical
of previous analyses for principal gamma emitters.
The releases due to
discharges from the vacuum system for the October-December 1987 calendar
year quarter were estimated by Heal th Physics personnel from previous
data; based on these estimates, the licensee calculated that releases for
the quarter were within established limits for Sr-89 and Sr-90.
Health Physics supervision and management were notified of. the missed
analyses and reviewed the requirements of HP Procedure 3. 2.1 and the
Technical Specification with concerned HP personnel.
HP Procedure 3.2.1
was revised March 31, 1988 to provide better control over retention of
samples where required for compositing for weekly, monthly, and quarterly
periods. Counting room personnel were counseled on the importance of
maintaining strict control and accountability over samples to be analyzed
in accordance with Technical Specification requirements and received
training on the revision to HP Procedure 3.2.1.
Licensee initiatives in resolving the root cause of this event were
considered appropriate and adequate to prevent a recurrence.
This matter
is considered closed.
(Closed) LER 88-004, Issued March 4, 1988,
11 Iodine Spike Due to Defective
Fuel Element.
11
On February 16, 1988, at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, the Unit 1 reactor coolant spiked at
1.17 uCi/ml of dose equivalent iodine-131, which exceeded Technical
Specification (TS) 3.1.2.d (Limit 1.0 uCi/ml).
This followed a reactor
trip.
Corrective action was to implement actions of T.S. Table 4.1.2.8,
calling for four-hour interval sampling until dose equivalent
iodine-131 (DEI) level dropped below 1 uCi/ml.
The next sample, taken at
1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br /> on February 16, 1988, was 0.75 uCi/ml DEI, which was below
1 uCi/ml.
The event duration was considered to be three hours, the
approximate time interval between the two samples.
At the ti me of this inspection, Unit 1 was shutdown for scheduled
refueling.
Prior to defueling, the licensee planned to conduct ultrasonic
testing of each fuel assembly in an effort to locate the defective fuel,
which was believed to be limited to one fuel pin.
If the assembly
containing the defective pin could be identified, it was to be removed
from the core.
If not, the scheduled refueling operation would proceed.
The licensee considered that it was probable that the fuel assembly with
the defective pin would be among those scheduled for removal and
replacement with new fuel during the outage.
10
The event was an iodine spike which exceeded the TS limit of 1 uCi/ml of
dose-equivalent I-131 by a small margin in the period immediately
following a reactor shutdown.
The followup sample, taken three hours
later, was analyzed at 0. 75 uCi/ml.
Such transient conditions are
characteristic of power changes in nuclear power plants and are known to
occur both on startup and shutdown, particularly in plants with known
defective fuel; however, such spikes do not always occur where defective
fuel is known to exist.
The NRC does not consider iodine spiking of the
order of magnitude seen in this event to be a significant safety problem.
The 1 i censee' s proposed actions to 1 ocate the defective fue 1 and the
actions taken upon detection of the iodine spike were considered adequate
and this matter is considered closed.
11.
Inspector Followup Items
(Closed) 50-280/84-02-06, (IFI):
Vendor Calibration of High Range Noble
Gas Monitor (TMI-0737, II.F.l, Attachment 1).
The inspector reviewed the
vendor's Report of Calibration, Model KMG-HRH, High Range Channel," which
described calibration of the high range detector channel at gamma energies
provided by Xe-133 gas and solutions of Ba-133, Cs-137, and Co-60.
Associated gamma energies were 81, 345, 662, and 1,250 KeV.
Reference
point sources of Cs-137, with NBS traceable calibration, were also used.
The principal NRC guidance in the calibration of the high range monitors
responsive to the criteria of NUREG-0737, Item II.F.1, appears in a
memorandum dated August 16, 1982, from D. G. Eisenhut, NRR, to Regional
Administrators, Subject:
"Proposed Guidance for Calibration and
Surveillance Requirements for Equipment Provided to Meet Item II. F.1,
Attachment 1, 2 and 3, NUREG-0737.'
The inspectors' review of the vendor
calibration report concluded that the data provided in the report appeared
to meet the guidance contained in the NRR memorandum of August 6, 1982,
for type calibration and, therefore, were considered adequate.
This
matter is considered closed.
(Closed) 50-280, 281/86-IN-76 (Information Notice):
Control Room
Emergency Ventilation Problems.
The inspectors and a licensee
representative discussed actions taken by the licensee with respect to the
concerns of Information Notice IN-86-76.
The licensee had received the IN
and had initiated several actions responsive to the IN.
At the time of
this inspection, two ventilation engineers were assigned full-time to work
on the plant control room envelope, with assistance also provided from the
Richmond, Virginia, corporate engineering staff.
The North Anna control
room habitability report was being used as a reference for possible
related problems.
This matter is considered closed.
(Closed) 50-280/86-06-XX (IFI):
Review Licensee Action On Submitting
Environmental Technical Specification Changes to Tables 4.9-5 and 4.9-4.
The licensee submitted a proposed Technical Specification revision to the
subject tables on May 14, 1987.
As of the date of this inspection, the
Office of Nuclear Reactor Regulation (NRR) had apparently not taken action
~~~~
-
- - - - - - -
11
on this matter.
For tracking purposes, the inspectors concluded that the
1 i censee had taken appropriate act ion and this matter is considered
closed.
(Closed) 50-280, 281/87-02-01 (IFI) Define Zero In Semi-Annual Effect
Release Reports and Provide LLDs.
The licensee's Semi-Annual Radiological
Effluent Release Report for the period July-December 1987 provided the
requested information.
In discuss ions with 1 i censee representatives, the
inspectors were assured that future reports would be issued in the correct
format.
This matter is considered closed.
(Closed) 50-280, 281/87-02-02 (IFI):
Improve Maintenance Program for
RM-108 Liquid Radwaste monitor background.
The licensee had modified
monitor RM-108 by providing an electropolished sample chamber with access
by removable spool pieces to facilitate decontamination.
Additionally,
operating procedures were revised to provide adequate flushing of lines
with uncontaminated water after each potentially radioactive discharge.
The inspectors observed that the instrument background 1 eve 1 was
approximately a factor of ten lower than had been observed in a previous
inspection. This matter is considered closed.
(Open) 50-280, 281/87-02-03 (IFI) Resolve the Inoperability Problem of
Component Coo 1 i ng Service Water Mani tor RM. SW-107.
The 1 i ne which
RM.SW-107 monitors was contaminated several years ago.
Residual
contamination was such as to produce high background count rates which
kept the monitor continually in alarm status, although a valid alarm
condition did not exist.
The licensee had been performing periodic
sampling and analysis as required by technical specifications. * At the
time of the inspection, the licensee was developing a Technical
Specification change request to delete the monitor from the Technical
Specifications in favor of periodic sampling and analysis.
Since the
licensee had not submitted the requested change, NRR had taken no action.
This item remained open pending licensee and NRR actions.