IR 05000483/1990002
| ML20011E128 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/30/1990 |
| From: | Grant W, Snell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20011E127 | List: |
| References | |
| 50-483-90-02, 50-483-90-2, NUDOCS 9002080095 | |
| Download: ML20011E128 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
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Report No. 50-483/90002(DRSS)
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-Docket No. 50-483 License No. NPF-30 Licensee: Union Electric Company i
E Post Office Box 149 St. Louis, MO 63166 Facility Name:
Callaway County Nuclear Station Inspection At: Callaway Site, Callaway County, Missouri Inspection Conducted: January 8-12, 1990 M L O ["
Inspector:
. Grant
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Date Approved By: William Snell, Chief
'h a />e Radiological Controls and Date
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Emergency Preparedness Section Inspection Summary Inspection on January 8-12, 1990 tReport No. 50-483/90002(0RSS))
Areas Inspected:
Routine, unannounced inspection of the radiological protection program during power operation including: organization and management controls (IP 83722); sudits and surveillances (IP 83750); external exposure control (IP 83724); internal exposure control (IP 83725); control of radiological material (IP 83726); maintaining occupational exposure ALARA (IP 83728); a review of open and unresolved items (IP 92701); and a review of a licensee event report (IP 92702).
Results: The licensee's radiation protection progrem is very good and continues to be effective in protecting the health and safety of workers and the public. No violations or deviations were identified.
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DETAILS 1.
Persons Contacted L. Beaty, Instrument and Controls
'J. Blosser, Manager, Callaway Plant
- F. Eggers, Supervisory Engineer, QA
- C, Graham, Supervisor, Health Physics Technical Support
- G. Hamilton, Supervisor, Radwaste
'J. Laux, Manager, QA
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- J. Neudecker, Supervisor, Health Physics Operations
'J. Peevy, Assistant Manager, Operations and Maintenance
- J. Polchow, Superintendent, Chemistry /Radwaste
- G. Randolph, General Manager, Nuclear Operations
- R. Roselius, Superintendent, Health Physics G. Spires, ALARA Coordinator, R/C Foreman
- B. Little, NRC Senior Resident Inspector
- C, Brown, NRC Resident Inspector The inspector also contacted other licensee representatives.
- Present at the January 12, 1990 exit meeting.
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2.
General This inspection was conducted to review the radiation protection program during power operation including organization and management control, audits, exposure control, control of radioactive material and ALARA.
During plant tours, the inspector noted that area posting, access control, and housekeeping were very good.
3.
Licensee Action on previous Inspection Findings (IP 92701)
[ Closed)UnresolvedItem(483/88018-04)):
Resolution of variance requests by NRR for-TMI action items, a.
NUREG 0737,Section II.F.1, Attachment'2, Clarification 3, regarding the wide range gas monitor (WRGM) isokinetic sampling method was accepted by NRR on July 26, 1989.
This item is closed.
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b.
NUREG 0737. Item II.F.1-13, concerning calibration of containment nigh range radiation monitors.
The licensee's method and schedule for performing the calibration was accepted by NRR by letter dated October 16, 1989. This item is closed.
4.
Organization and Management Controls (IP 83722)
The inspector reviewed the licensee's organization and management controls for the radiation protection and radwaste programs including changes in the organizational structure and staffing, effectiveness of l
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procedures and other management techniques used to impir%nt these
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programs, experience concerning self-identification and correction of
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program implementation weaknesses, and effectiveness of audits of these
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programs. Audits are discussed in Section 5.
The Health Physics and the chemistry /radwaste groups (R/C) reorganized on 1'
January 1,1990. The following organizational and personnel changes were
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implemented.
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The Health Physics Operations group has responsibility for all medical
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emergency response and radiological emergency response duties on all shifts.
The Rad / Chem helpers, a group of 18 workers who are responsible for
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decon, painting, laundry, trash sorting, and radwaste compacting were
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assigned to the Health Physics Operations group.
Three Radwaste foreman positions were transferred to HP Operations
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resulting in eight HP Operations foreman positions.
The reorganization appears to be functioning with only a few minor difficulties.
The licensee believes the new organization will improve the effectiveness, efficiency and operation of the R/C group.
The Assistant Manager, Technical Services was transferred to the position
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of Assistant Manager, Operations and Maintenance while that individual is in license training for 13 months.
In the interim the Superintendent of Health Physics and the Superintendent of Chemistry /Radwaste, who formerly reported to the Assistant Manager, Technical Services, will report directly to the Plant Manager.
No violations or deviations were identified.
5.
Audits and Surveillances (IP 83750)
The inspector selectively reviewed the results of onsite and offsite quality assurance (QA) audits and surveillances conducted since the last
. inspection of radiation protection activities. Also, reviewed were the extent of the audits and surveillances, their thoroughness, and the qualifications of the auditors.
One onsite and one offsite audit of the radiation protection program were conducted during this period. The onsite audit was completed August 25, 1989; no major findings resulted.
The audit assessed programmatic and implementation effectiveness of the respiratory protection program, the radioactive material control program, the administrative program for TLD
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processing, and implementation of health physics operations activities.
The offsite audit had minor findings for which necessary corrective action was timely and technically sound.
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Surveillance reports reviewed appeared thorough and any corrective actions veguired appeared to be adequate and timely.
The extent of the audits and 4he surveillances and the qualification of the auditors appeared adeouate.
No vielations or deviations were identified.
6.
External Exposure Control and Personal Dosimetry (IP 83724)
The inspector reviewed the licensee's external exposure control and
personal dosimetry programs, including:
changes in facilities, equipment, personnel, and procedures; adequacy of the dosimetry program to meet routine and emergency needs; planning and preparation for maintenance and refueling tasks including ALARA considerations; required records, reports, and notifications; effectiveness of management techniques used to implement these programs and experience concerning self-identification and correction of program implementation weaknesses.
The licensee's personnel dosimetry program remains essentially as described in Inspection Report No. 50-483/89010.
Exposure records of plant and contractor personnel were selectively reviewed for 1989.
No exposures greater than 10 CFR 20.101 limits were noted.
The licensee is upgrading their TLD processing program. New chips will
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be purchased to replace some of the older chips and a new TLD reader will be purchased.
In addition, a hard copy of glow curve data will be made and stored. The system upgrades should be completed by the September 1990 refueling outage.
Posting and labeling in the RCA were observed during plant tours; no problems were noted. Housekeeping appeared to be very good.
No violations or deviations were identified.
7.
Internal Exposure Control and Assessment (IP 83750)
The inspector reviewed the licensee's internal exposure control and assessment programs, including:
changes in facilities, equipment, personnel, respiratory protection training, and procedures affecting internal exposure control and personal assessment; determination whether engineering controls, resotratory equipment, and assessment of individual intakes meet regulatory requirements; planning and preparation for o
maintenance and refueling tasks including ALARA considerations; required records, reports, and notifications, and effectiveness of management techniques used to implement these programs and experience concerning self-identification and correction of program implementation weaknesses.
The licensee has two chair type whole body counters (WBC) one located in I
the service building and one used as a backup located in the Central
Processing Facility (CPF). The WBC located in the Service Building is
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currently being refurbished and upgraded. The WBCs are used for baseline l
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. counting of incoming' personnel, routine annual counting of_ station l
personnel,_and random counting of workers on active RWPs involving possible airborne contamination. All non station workers who have been in the controlled-area are whole body counted when their work at the station is completed. All whole body counts performed during 1969 were less than 1% of the Annual Limit of Intake (ALI).
No violations or deviations were identified.-
8.
Control _ of Rad _ioactive Materials and Contamination, Surveys and Monitoring (If 83725)
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The inspector reviewed the licensee's programs for control of radioactive materials and contamination, surveys and monitoring, including:
adequacy of supply, maintenance and calibration of contamination survey and monitoring equipment; effectiveness of survey methods, practices, equipmenty and procedures; adequacy of review and dissemination of survey data; effectiveness of methods of control of radioactive and contaminated'
materials.
The inspector observed the pre-job briefing of divers, th? set up of the hot particle control areas and the entry and removal of the divers from the refueling canal prior to and during the replacement of the inflatable seals on the spent fuel pool doors. No problems were nnted; the diving / repair operation went smoothly.
The licensee's reporting criterion for a personnel contamination incident (PCI) is 100 cpm above background on skin or clothing.
In 1989, 225 PCIs were identified.
Significant resources have been spent to reduce the contaminated arees within the radiologically controlled area (RCA). As of December 31, 1989 less than 2% of the RCA, excluding the Reactor Building, was contaufnated (greaterthan1000dpm/100cm2),
No violations or deviations were identified.
9.
Maintaining Occupational Exposures ALARA (IP 83728)
The inspector reviewed the licensees program for maintaining occupational exposure ALARA, including: changes in ALARA policy and procedures; ALARA considerations for the maintenance and refueling outage; worker awareness -
and involvement in the ALARA program; establishment of and effectiveness in meeting goals and objectives.
Also, reviewed were management techniques used to implement the program and experience concerning self-identification and correction of implementation weaknesses.
The 1989 total radiation dose was approximately 282 person-rem of which about 250 person-rem was attributed to the 55-day maintenance / refueling outage.
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The licensee has implemented several innovative source term reduction and ALARA techniques including:
a reactor coolant letdown filter mesh size
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reduction program which was developed to reduce the amount of corrosion
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products in the reactor coolant system; and use of a reactor vessel-water
shield plug to. reduce dose rates at the reactor vessel flange. The shield plug provided about seven feet of water shielding oetween the lower
internals and the reactor vessel flange when the reactor coolant level was below the hot and cold legs; ALARA pre-job and post-job briefings are conducted using actual job site video tapes and plant system viewgraphs.
In addition, ALARA briefing details are entered in the computer which is
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available throughout the plant including the reactor building during
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This provides effective and consistent ALARA briefings.
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No violations or deviations were id' ntified.
e 10.
Licensee Event I:eport (LER) No. 89-014-00 (IP 92702)
I On December 9,1989 at 0900, Engineered Safety Features (ESF) Control Room Ventilation Isolation (CRVIS) and Fuel Building Ventilation Isolation o
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(FBIS) actuated during a filter replacement on Fuel Building Exhaust
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Radiation Monitor GG-RE-27. On December 9, 1989 at 1302, during.the
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subsequent investigation a second spurious CRVIS and FBIS occurred.
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t Event 1
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The first event occurred when a Health Physic's (HP) technician shut off sample flow to the Fuel Building Exhaust Radiation Monitor GG-RE-27 as-part of a routine, sample flow filter replacement. This requires placing the skid mounted sample pump switch from AUTO to 0FF.
Concurrent with this action, unexpected FBIS and CRVIS ESF actuations occurred. The utility operators verified proper. operation of ventilation dampers and-t fans as a result of the'FBIS and CRVIS.
The ESF actuations were determined to be spurious and not the result of abnormal radiation
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The ESF actuation signals were reset at 0936 and the ventilation systems were restored to their normal, standby lineup.
Since the ESF actuations occurred when the sample pump switch was moved, it was tagged-to prevent its operation.
The utility Event Review Team was activated to investigate the event.
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Event 2 At 1302, with the Event Review Team and the involved HP technician at the
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e radiation monitor skid for GS-RE-27, a second FBIS and CRVIS signal was received. The monitor was not being manipulated when these second ESF actuaticas occurred.
No apparent cause was evident to personnel at the skid or in the Control Room. The operators verified the proper operation of the FBIS and CRVIS equipment as before. Radiation monitor GG-RE-27 was declared inoperable and placed in bypass. The Emergency Exhaust System lineup was initiated to maintain the Fuel Building at a negative pressure to satisfy Technical Specification (T/S) 3.3.3.1 Action 30.
This lineup precluded subsequent spurious ESF actuations while troubleshooting continued. At 1400 the Control Room emergency ventilation system was restored to its normal standby lineup.
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Root Cause Although a, loose terminal block connection was found on the radiation monitor skid motor controller, no positive direct cause for the spurious ESF actuations could be determined.
Corrective Actions The. loose terminal connection was tightened and the connection was
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tested. Troubleshooting included numerous manipulations of the sample pump switch and wire connections in order to recreate the event but-there were no recurrences through January 12,,1990. The radiation monitor was then de-energized to perform a previously scheduled design modification. This modification involved extensive determinations and redeterminations=plus power supply checks. Additional visual inspections were made. These checks and inspections yielded no additional-insight _ to the cause of the spurious signals. The T/S surveillance was performed as a retest. At 1513 on December 12, 1989, GG-RE-27 was returned to service and the Emergency Exhaust System was restored to its normal standby lineup.
11.
Exit Meeting (IP 30703)
The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on January 12, 1990. The inspection
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summarized the scope and finding of this inspection. The inspector also discussed the likely informational. content of the inspection report with regard to document and processes reviewed by the inspector. The licensee did not identify any such document as proprietary.
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