IR 05000245/1989009
| ML20247J978 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/18/1989 |
| From: | Shanbaky M, Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20247J963 | List: |
| References | |
| 50-245-89-09, 50-245-89-9, 50-336-89-10, NUDOCS 8906010176 | |
| Download: ML20247J978 (5) | |
Text
b
.;
"'
.
.
,
U..S.' NUCLEAR REGULATORY COMMISSION
REGION I
' Report.Nos..
89-09
- c 89-10
- Docket Nos.
50-245 50-336 License Nos.
DPR-21 Category C
.
Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Generating Station Inspection At: Waterford, Connecticut Inspection Conducted:
. April 17-6,~T98 Inspectors:
%.
/,
SYAT/g9
_.' Tfiomas,' Radiation 5peciallst, RPS, ifRSSB
' ddte W
,.
Approved by:
_
.
.
m_
_q P,D p
/
M. Shanbaky, Chief, Fa esRadifion date Protection.Section, F B, DRSS Inspection Summary: Inspection on April 17-21, 1989 (Report Nos. 50-245/89-09 and 50-336/80-10)
Areas Inspected:
Routine, unannounced inspection to continue the review of radiation protection activities at Unit 2, and the beginning of the refueling outage at Unit 1.
Areas reviewed included the end of the Unit 2 refueling outage activities, and the beginning of the Unit 1 outage activities.
Results: No violations were identified. The Unit 2 refueling outage is complete and the Unit I refueling outage has begun, j
.
)
8906010176 890519
~7 PDR ADOCK 05000245 O
__-_- -__ -____________-__________-___-______-_ - _
_ _ _ _ - _ - _
_ _ _
'
.-
,
V L
l-DETAILS 1.0 Persons Contacted 1.1. Licensee Personnel
'
- M. Brennan, Radiation Protection Supervisor (RPS), Unit 1
- R. Doherty, ALARA Coordinator, Unit 1
- D. Hagan, Assistant RPS, Unit 1
- H. Haynes, Station Services Superintendent
- B.
Kreiling, Health Physicist
,
- J. Laine, RPS, Unit 2
- C. Palmer, Health Physics (HP) Supervisor Support Services
- F. Perry, Assistant RPS, Unit 3
- R. Sachatello, RPS, Unit 3
- P. Simmons, RPS, Support
- J. Stetz, Superintendent, Unit 1
- J. Sullivan, HP Supervisor, Operations
- S. Torf, ALARA Coordinator, Unit 2 1.2 NRC Personnel
- L. Kolonauski, Unit 1, Resident Inspector
- W. Thomas, Radiation Specialist, Region I
- Attended the exit meeting on April 21, 1989.
Other licensee personnel were also contacted during the course of this inspection.
2.0 Purpose The purpose of this routine, unannounced inspection was to complete the review of the implementation of the radiation protection program for the Unit 2 refueling outage, and to begin a review of the radiation i
protection program for the Unit I refueling outage. The following areas were included in this review.
Unit 1 Outage Planning and Preparation,
-
-
External Exposure Controls,
-
Internal Exposure Controls, ALARA,
-
Control of Radioactive Materials and Contamination, Surveys and
-
Monitoring 3.0 Unit'l Outage Planning and Preparation The Unit i refueling outage was delayed a week due to the receipt of out-of-specification fuel from the fuel supplier. The fuel was returned to the supplier and a new shipment of fuel has been received.
During the
!
interim, Unit I has taken full advantage of the delay to assure that l
R
_ - _ -. _
. _ _ _ - - _ _ - - _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ -
, _ - -. _-
L
,
'
s
.
..
proper planninc and preparation for outage activities have taken place.
Approximately 83 vendor senior technicians have been added to the health physics staff for the outage.
Each major radiological area or building to which the vendor technicians are assigned will be supervised by an in-house technician or supervisor, who will be responsible for the radiological controls and vendor technicians in the assigned area.
In addition, 15 vendor control room monitors have been added. Copies of the Unit I health physics department organization chart for the refueling outage were provided to the inspector for review and found to be adequate in that all critical outage positions were staffed properly.
l
,
The inspector determined that management support for and cooperation with radiation protection planning for the outage is adequate.
Needed health physics supplies and materials have been received and are available for l
use.
In addition, six Eberline personnel contamination monitors (PCM-Is)
I have recently been installed at the exits to the Unit 1 Radiological Control Area (RCA). These monitors form the basis for the new contamination monitoring program at Unit 1 and are capable of detecting hot particles, provide better contamination monitoring, and provide more positive control to assure that personnel are properly monitored.
4.0 External Exposure Control, Internal Exposure Control The external and internal exposure control programs conducted by the licensee continue to be ver/ strong programs and were discussed in detail in previous inspection reports (50-245/89-03, 50-336/89-04 and 50-245/89-06,50-336/89-09,50-423/89-06).
5.0 Control of Radioactive Materials and Contamination, Surveys and Monitoring As discussed in Section 3.0 of this report, the PCM-Is installed at the RCA exits at Unit 1 form the basis for the new contamination monitoring program at Unit 1.
PCM-1s have also been installed at the RCA exits from Unit 2.
During a previous inspection at Unit 2, the inspector was concerned that there was the possibility of mixing potentially contami-nated and non-contaminated personnel at the RCA exit from the Unit 2 Auxiliary Building. The licensee replied by promptly installing temporary stanchions and ropes down the center of the health physi:s corridor to delineate and separate the traffic flow patterns. A permanent pedestrian
traffic flow control system was received and installed prior to this
'
inspection.
During tours of Unit 1 and Unit 2 and during discussions with workers, l
aspects of surveys and monitoring were evaluated.
It was determined that adequate surveys necessary to post and control radiation areas and high radiation areas were required and are performed.
Use of the PCM-1s are
monitored by an HP Technician and hot particle surveys are performed
?
daily in those areas where the likelihood of finding hot particles is highest.
It was determined that the survey practices for personnel
'
contamination and hot particles are adequate.
. - - _ _ _ -
- ______________ _ _ ___ _ _ -
_ _ _ __ _____
_ - -. - - - _
-
_
_
,
.
l
'
l-
-
<.
)
- ..
..
,
_
,
Records of surveys and survey results are reviewed by health physics-management on a daily basis and distributed to the health physics staff at each' radiation control point.
Plant conditions and contamination st;ius continue to be reviewed weekly at the outage planning and status meetings for use in work planning and dose control.
It was noted during a tour of Unit-1 that a large area of the facility has been decontaminated and released from contaminated area controls.
This extensive decontamina-tion program at Unit 1 is ongoing.
Extensive housekeeping improvements have also been accomplished outside of Unit 1 in-the radwaste storage areas.
.
6.0 Maintaining Occupational Exposures ALARA The ALARA program was discussed with several workers to determine whether
>
they understood the ALARA program, understood their role in the program, and were actively involved in the program. Most of the workers who were interviewed were aware of the program, were actively involved in the program, and understood their role in the program. ALARA suggestions are actively solicited from all workers and acted upon if judged to be feasible in reducing dose accumulation by workers. ALARA low dose rate areas have been identified throughout Units 1 and 2 and workers have been instructed to use these ALARA areas as waiting areas during slack periods in work activities.
ALARA goals based on exposure estimates for both units for the refueling outages and the year as a whole have been set.
During the outages, the status of the cumulative exposures will be reviewed at each outage meeting. An outage goal of 560 man-rem was adopted for Unit 2, to date the actual exposure has been approximately 715 men-rem due to extensive steam generator work, which was not anticipated prior to the outage.
It is presently estimated that Unit 2 will end 1989 at approximately 760 man-rem. Although this is higher than other facilities that underwent similar outages, it continues to decrease compared to previous outages at this unit.
It is anticipated that replacement of the steam generators in 1992 will result in a further decrease in total annual cumulative dose for Unit 2.
Unit 1 ALARA goals of 494 man-rem for the year and 180 man-rem for the outage have been adopted. To accomplish these goals several ALARA initiatives have been adopted.
These included:
New automatic stud tensioners for the reactor vessel
Purchase of a new control rod drive tool to change out control rod
drives Divers to perform modifications to torus strainers
Aggressive reactor cavity decon
Realignment of the drywell head
Continued reduction of contaminated areas
IGSCC countermeasures
i l
!
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _
__
. _ _ _ _ _
__
.
,
,
.
..
i Inservice inspections of the reactor vessel using underwater camera
'
equipment Zinc injection process to be initiated during 1989
7.0 Exit Meeting The inspector met with the licensee personnel denoted in Section 1.0 of this report on April 21, 1989. At that time, the inspector summarized
.
the purpose, scope and findings of this inspection.
I
- _ _