IR 05000245/1989006

Insp Repts 50-245/89-06,50-336/89-09 & 50-423/89-06 on 890306-10.No Violations Noted.Major Areas Inspected:Review of Implementation of Radiation Protection Program at Unit 2 During Refueling Outage & Preparation of Outages for Units

ML20244B569
Person / Time
Site:	Millstone
Issue date:	04/07/1989
From:	Shanbaky M, Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20244B565	List: IR 05000245/1989006 ML20244B563
References
50-245-89-06, 50-245-89-6, 50-336-89-09, 50-336-89-9, 50-423-89-06, 50-423-89-6, NUDOCS 8904190274
Download: ML20244B569 (4)

Text

_ - - _ . ._______ _ - ____ _-___

.. .

. .. . .)

!.

-

. .

,

t

'

U.S. NUCLEAR REGULATORY COMMISSION

,

REGION I

50-245/89-06 50-336/89-09 Report No /89-06 50-245 50-336 Docket Nos. 50-423  :

uPR-21 DPR-65 License Nos.- NPF-49 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: March 6-10, 1989 Inspectors: M a ,. e 3/b ,9 f W. ' Thomas,'Radiatioh/SpecihH1lt. TRRS) FRSSB / date Approved by: /V, 7 7 M.Sha6baki, Chief,Facp1tiesRadiation date Protection Section, Facilites Radiological

_

Safety and Safeguards Branch  !

Inspection Summary: Inspection on March 6-10, 1989, (Report Nos. 50-245/89-06, 50-336/89-09, 50-423/89-06)

Areas Inspected: Routine unannounced inspection to continue review of the ,

implementation of the Radiation Protection Program at Unit 2 during the refueling outage, and preparation for the refueling outages at Units 1 and Results: No violations were identified. The Radiation Protection program was being properly implemented, and preparations for the refueling outages at Units I and 3 were proceeding adequatel '

j PDR ADOCK 05000336 G PDC i

'

i

.

-__ _ ___ _ _ _ __ _ _ _ _ _. _ _ - _ . _ __

. _ _ .

. .

.

.' 't DETAILS 1.0 Persons Contacted 1.1 Licensee Personnel i

• M. Brennan, Radiation Protection Supervisor (RPS) Unit 1 '

R. Doherty, ALARA Coordinator, Unit 1

• H. Haynes, Station Services Superintendent

• 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 Services

• Smith, Assistant RPS, Unit 1

• J. Sullivan, H.P. Supervisor, Operations

• S. Torf, ALARA Coordinator, Unit 2 1.2 NRC Personnel P. Habighorst, Unit 2 Resident Inspector W. Thomas, Radiation Specialist, Region 1

• Attended the exit meeting on March 10, 19E9 Other licensee personnel were also contacted during the course of this inspectio .0 Purpose The purpose of this routine, unannounced inspection was to review the '

implementation of the radiation protection program during the Unit 2 refueling outage, and the preparation for the refueling outages at Units 1 and 3. The following areas were included in this review ,

)

-External Exposure Controls,

-Internal Exposure Control A LARA ,

-Control of Radioactive Materials and Contamination  !

-Units 1 and 3 Outage Planning and Preparation l

3.0 External Exposure Control The external exposure control program conducted by the licensee continues to be a very strong program and was discussed in detail in the previous inspection report (50-245/89-03, and 50-336/89-04). The only major change anticipated in the program will be in the changeover of the present Thermoluminescent Dosimeter (TLD) badge syste The present badge system 1 1

_-____ I

_ _ _ _ -

. . . .

-

. .

is a calcium sulphate system which will be changed to lithium flouride in January 1990. The purpose of the change is to alleviate the fading problems with calcium sulphate TLDs and to improve the overall energy response characteristics of the badge system. The inspector indicated that the TLD badge system change will be closely reviewed during subsequent inspection .0 Internal Exposure Control The licensee's internal exposure control program consists of process and engineering controls, the use of respiratory protective equipment, the use

! of whole body counters for in-vivo measurements, and the use of off-site laboratory facilities for in-vitro measurements. The use of respiratory protective equipment at the Millstone site was reviewed during the previous inspection (50-245/89-03, and 50-336/89-04). During this inspection, tours of the whole body counting facilities were conducted by the inspector and licensee personnel. Two shielded whole body cour. ting chairs are located onsite near the Units 1 and 2 health physics of fices. A third whole body counter is located in warehouse No.1 adjacent to the badge processing unit, procedures for the operation of the counting units are contained at each locatio Source checks and background checks are performed each day the counters are in use. During this inspection re-calibration of chair No.2 was in progress and completed prior to the end of the inspection. A review of the calibration data logs indicates the re-calibration was done properl Normally, each whole body counter is calibrated annually with NBS traceable sources. Calibration records are mairtained for review at the counting laboratory adjacent to the Unit 2 health physics office Review of the records of results of whole body counts for the previous two outages'at each unit indicated no one had exceeded the licensee's action levels for investigation (greater than 20 nanocuries of Cobalt-60),

5.0 Maintaining Occupational Exposures ALARA ALARA goals based on exposure estimates for both the refueling outages at Unit I and Unit 2 and the year have been set. The outage goal for Unit I has been set at 353 man-rem and 494 man-rem for the entire year. The initial outage goal of 560 man-rem for Unit 2 has been decreased to 475 man-rem. The entire year goal was set at 750 man-rem. Although this goal constitutes a noticeable improvement over previous years performance, further improvement is warranted to achieve parity with other operating PWRs. An action plan to minimize exposure and achieve the reduced goal ,

was developed by Unit 2 management and forwarded to Unit 2 staff. The j action plan included: )

• Avoiding unnecessary work (add-ons)

• Completion of all jobs on original schedule which are not affected by steam generators or operational considerations, l

e _ - - _ - _- ]

. _ _ _ _ _ _ _ _ - _ . _ _ _ __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

_ _ - _ _

( . .

-

..

l

!

Continue a daily review of ALARA goals and statu Long term plans to further reduce collective personnel radiation exposure at Unit 2 will continue to be reviewed during future inspection .0 Control of Radioactive Materials and Contamination J The health physics corridor traverses the lower floor of the Unit 2 turbine building and contains the entrance and exit door to '.he Unit 2 auxiliary buildin The licensee, when informed of the inspector's concern that there was the ,

possibility of mixing potentially contaminated and non-contaminated i personnel at the radiological controlled area exit from the Unit 2 auxiliary building immediately installed temporary stanchions and roped ,

down the center of the corridor to delineate and separate the traffic flow 1 patterns. A permanent pedestrian traffic flow control system has been .;

ordered to separate routine traffic in the hallway from potentially '

contaminated individuals exiting the auxiliary building. This system will be installed during the month of Apri .0 Unit 1 and Unit 3 Outage Planning and Preparation  !

The Unit 1 refueling outage has been delayed a week to April 8, 1989 due to the receipt of out-of-specification fuel from the fuel supplie However, the training and qualification program for new personnel for the Unit 1 outage is proceeding on schedule. Preparations for the Unit 3 outage have begun. The outage, which is scheduled to start on May 15, 1989 is on schedule, but health physics personnel availability may be affected by the Unit 1 outage dela .0 Exit Meeting The inspector met with the licensee personnel listed in Section 1.0 of this report on March 10, 1989. At that time, the inspector summarized the purpose, scope and findings of this inspectio l

i

_ - - - - _