IR 05000397/1989032
| ML17285A897 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/30/1989 |
| From: | Cicotte G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17285A896 | List: |
| References | |
| 50-397-89-32, NUDOCS 8912200214 | |
| Download: ML17285A897 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
Docket No.
License No.
50-397/89-32 50-397 NPF-21 Licensee:
washington Public Power Supply System P.
0.
Box 968 Richland, washington 99352 Facility Name:
Mashington Nuclear Project No.
Inspection at:
MNP-2 Site, Benton County, Mashington Inspection Conducted:
November 13-17 198 Inspected by:
>co e,
a
>a >on pec>a Approved by:
ens aws
>,
>e Facilities Radiological Protection Section
~Summer:
Ins ection durin the eriod of November 13-17 1989 Re ort No.
I t- >0-~9 a
e cygne
// 3o e
>gne Areas Ins ected:
Routine unannounced inspection by a regionally based snspec or o ontrol of Radioactive Material, Contamination, Surveys, and Monitoring; tours of the facility; and follow-up.
Inspection procedures 30703, 83726; and 92701 were addressed.
'esults:
. No violations were identified in the three areas addressed.
The T>censee's radioactive material control had improved since the last inspection of this program area.
Overall, the licensee's programs appeared fully capable of meeting their safety objectives.
8912200214 8911~0 PDR ADOCK 05000397 A'NU
DETAILS l.
Persons Contacted
- C
- J
- J
"R.
- D
- R.
%D-R.
- D AR NRC M. Powers, Plant Manager A. Baker, Assistant Plant Manager R. Allen, Health Physics (HP) Craft Supervisor D. Arbuckle, Compliance Engineer G. Graybeal, HP/Chemistry (HP/C) Manager A. Kerlee, Principal Quality Assurance (QA) Engineer-R.
Kobus, Plant QA Manager L. Koenigs, Technical Manager E.
Larson, Radiological Programs and Instrument Calibrations (RPIC)
Manager F. Patch, ALARA Coordinator J. Pisarcik, HP Support Supervisor A. Pritchard, HP Craft Supervisor L. Mardlow, Radiological Services Supervisor
- G C
- J R.
R.
F.
+C. J.
Bosted, Senior Resident NRC Inspector Cicotte, Radiation Specialist Sorensen, Resident NRC Inspector Burdoin, Reactor Projects Inspector
"Denotes those present at the exit interview held on November 17, 1989.
In addition to the individuals identified above, the inspector met and held discussions with other members of the licensee's staff.
2.
Control of Radioactive Material Contamination Surve s
an A.
onitorin Audits and A
raisals B.
The findings of the licensee's corporate licensing and assurance audit 89-500, "Radioactive Process Control Program",
dated October 26, 1989, was reviewed.
The audit had been completed, but not yet issued for distribution, at the time of the inspection.
The licensee had included among the auditors individuals who were knowledgeable in the areas audited.
The audit appeared to be thorough and required responses to significant problem areas.
The inspector noted, however, that some of the findings were of long-standing problems which had not been corrected, such as the procedural deficiencies regarding recirculation times for some liquid waste tanks, first identified.in 1988.
Surve s and Monitorin Representative surveys of the licensee's facility from November, 1989, were reviewed.
Few examples of surveys not performed at the
C.
periodicity of the licensee s schedule were observed.
All field instruments in use were observed to be in current calibration and were being properly response checked prior to use.
Calibration and response capabilities were discussed with licensee-
, HP personnel, who were familiar with the equipment available to them for performance of surveys of equipment and personnel.
Calibration of dosimeters was observed to be in accordance with the licensee's Radiological Programs Instruction (RPI) 7. 13,
"Calibration of Xetex Model 415A/B Audible Alarm Dosimeters,"
Revision 4, dated October 20, 1989.
The Eberline 1000B Calibrator was being used to irradiate the dosimeters to specified doses.
RPI 7. 19, "Operation of Eberline 10008 Multiple Source Gamma Calibrator," Revision 0, dated April 8, 1983, stated in part that if the "safe" indicator light is not on when the source is retracted, the operator is to: "notify the ILC Technician and the Radiological Services Supervisor."
The operator was not aware of the requirement, and did not recall how long the "safe," "exposed,"
and
"power" lights had been missing, when observed by the inspector.
The technician immediately informed the RSS and lights were installed soon thereafter.
The inspector noted also that RPI 7. 19 allows use of an uncalibrated ratemeter to verify retraction of the source prior to reaching into the calibrator.
The technician, however, was using a calibrated instrument.
The HP8C Manager stated that the procedure would be revised to disallow the practice of using an uncalibrated instrument.
Radioactive Materials and Contamination Controls The licensee's methods of trending personnel contaminations was reviewed, including procedures for recording contaminations and representative records of contamination incidents.
Contamination control techniques were observed in use in the Radwaste Building (RMB).
Activities to prepare a radioactive waste shipment were observed and the associated records were reviewed.
The licensee's efforts to minimize waste, in the form of instructions to workers to take only necessary materials into the Radiologically Controlled Area (RCA), were also observed.
Surveys of potentially contaminated personnel ahd materials were observed to be consistent with licensee procedures and good practices, though some HPTs appeared to scan materials very quickly.
See paragraph 3, below, for.discussion of tours of the licensee's facility.
The licensee's program appeared fully capable of meeting its safety objectives.
No violations or deviations were identified.
3.
Tours of the Facilit Tours of the Radwaste Building (RMB), Reactor Building (RB), and Turbine Building (TB), were conducted.
Independent radiation surveys were performed with NRC ion chamber survey instrument model 8R0-2, serial
¹015844, due for calibration on December 27, 1989, and NRC micro-R meter model
¹PRM-7, serial
¹008596, due for calibration on April 17, 1990.
Radiological postings, contamination control stepoff pads, and other access controls which were observed appeared to have improved over
~ previous inspections-and were consistent with the licensee's procedures and TS requirements.
Housekeeping appeared adequate.
Only one area, on the 522'levation of the RB, was observed to have significant accumulation of used contamination control materials left on the floor.
However, some contaminated areas appeared to have increased in size.
The traversing in-core probe (TIP) drive machine area appeared much improved, although the size of the contaminated area was unchanged.
Overall, the licensee's program appeared fully capable of meeting its safety objectives.
No violations or deviations were identified.
4.
~Fo11ow-u A.
Follow-u on Ins ector Identified Problems While touring the 572'levation of the RB, one of the Standby Gas Treatment System filtration units, SGT-FU-lA, was observed to have what appeared to be improper flange alignment between the last two modular filtration components in the train, such that the tops of the flanges were approximately 4 cm apart, while the flanges converged approximately
cm down from the top.
Bolts and nuts on the flange in the misaligned area had various amounts of thread engagement.
Further examination by the inspector.
and by the Senior Resident Inspector (SRI) found several of the access door retaining devices,
"dogs," loose.
Both SGT-FU-1A and SGT-FU-1B had loose dogs.
One dog on SGT-FU-1B was out of position such that it was not providing sealing pressure on the door.
Additionally, the last access door in the train for SGT-FU-lA had a piece of a cleaning cloth caught in the sealing area.
The observations were brought to the attention of the licensee, who sent an Equipment Operator to the area to correct the dogs and the foreign material in the seal area.
Mhen the matter was later discussed with the licensee, they stated that the units had been satisfactorily'modified to meet the leakage criteria.
The inspector verified that the filtration housings had been leak tested in 1983.
The resident inspectors will follow up on other issues related to the condition of the SGTS.
B.
50-397/85-20-04(Unresolved):
This refers to iodine plateout in e
uen samp e
~nes using an accident (see Inspection Report 50-397/85-20).
The licensee had received the formal, results of the initial tests performed during the refueling outage.
The licensee stated that laboratory testing was in the final approval process, and provided a copy of the initial test results to the inspector.
This matter will remain unresolved pending review of laboratory tests and rational An unresolved item is one about which more information is required in order to determine if it is an acceptable item, a violation, or a deviation.
No specific violations or deviations were identified by the inspector.
5.
Exit Interview The inspector met with those individuals, denoted in paragraph j., at the conclusion of the inspection on November 17, 1989.
The scope and findings of the inspection were summarized.
The licensee was informed that the resident NRC inspectors would follow up on the status of the SGTS, as described in paragraph 4, abov '