IR 05000333/1988021

Insp Rept 50-333/88-21 on 880919-23.No Violations Noted. Major Areas Inspected:Outage Radiological Controls & Followup on Previously Identified Violations & Open Items

ML20204F382
Person / Time
Site:	FitzPatrick
Issue date:	10/13/1988
From:	Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20204F363	List: IR 05000333/1988021 ML20204F361
References
50-333-88-21, NUDOCS 8810210567
Download: ML20204F382 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /88-21 Docket N License No. OPR-59 Category 1 Licensee: New York State Power Authority P. O. Box 41 Lycoming, New York.13093 Facility Name: James A. FitzPatrick Inspection At: Scriba, New York Inspection Conducted: September 19-23, 1988 ( ] Inspectors:

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W. V. Thoma's,"Radiation Sketridlisy / date-r-Approved by: - 1 7 /. T IM M. Shanbaky, Chief, fac Kities Radiation

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date Protection Section Inspection Summary: Inspection Report No. 50-333/88-16 Areas Inspected: Routine, Unannounced. Outage Radiological Controls Inspection and followup on previously identified violations and open item Results: Within the scope of this inspection, no violations were identifie The radiological controls were adequate to support the refueling outage. One inspector followup item and one previously identified violation were reviewed and update GG10210567 8G1014 PDR ADOCK 05000-333 O PDC

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DETAILS 1.0 Persons Contacted 1.1 Licen,ee Personnel i During the course of this inspection the following personnel were  ! contacted or interviewed:  ; i

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D. Johnson, Operations Waste Management General Superintendent

      *R. Converse, Resident Manager       i
      *W. Fernandez, Superintendent of Power      -

D. Lindsey Operations Superintendent .

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      *J. McCarty, Radiological and Environmental Services Department (RES), P.adiation Protection Supervisor
      *E. Mulcahey, RES, Superintendent R. Patch, QA/QC, Superintendent       '
      *J. Solini, Health Physics, General Supervisor
      *G. Tatick QA/QC Supervisor
      *G. Vargo, RES, Radiological Engineering, General Super,isor K. Szeluga, RES, Radiological Protection Supervisor 1.2 NRC Personnel          !
      *A. Luptak, Sr. Resident Inspector
      *R. R1asse, Resident Inspector
      *W. Thomas, Radiation Specialist, Region I
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      * Denotes attendance at the exit meet.ing held on August 12, 198 .0 , Purpose The purpose of this inspection was to examine the licensee's progress       !

concerning the rsiolution of previously identified items and inspection l of the radiological controls and practices in use during the

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decontamination effort and during the refueling outage, l ( I l

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.'   3 3.r; Status of previously Identified Items 3.1 (Closed) Inspector Followup Item (86-17-03)

Instrument issue return area with administrative controls neede This item included several sub-items. The inspector verified that procedure OPP-10, Operation of the RES Department Issue Room, was upgraded and through implementation of the upgrade, weaknesses which were previously identified in the radiological survey instru-ments issuance and centrols are now corrected. With regard to ' weaknesses related to the adequacy of the instrument calibration facilities and procedures, the inspector noted that upgrades in this area, including the purchase and installation of a new calibrator were completed prior to the refueling outag .2 (Closed) Violation (87-07-01) Failure to control worker extremity exposure to less than 18.75 rem for the first calendar quarter of 1987 constitutes an apparent violation of 10 CFR 20.101(a). l The inspector reviewed the 1!censee's corrective actions provided to the NRC by letter, dated May 21, 1987. The inspector verified that , all short and long term corrective actions have been complete j The review of the cutting tool by the vendor to determine how the ! cutting tool was able to capture a segment of the cut dry tube has i been accomplished by the cuttine tool vendor. Several modifications

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of the cutting tool have subsequently been made, which should improve tool operation and prevent a recurrence of this even _ Refueling Outale 4.1 Decontamination  !

During this refueling outage decontamination of the reactor water ; ' recirculation system piping and reactor vessel was accomplished by a l

decontamination contractor. Tne decontamination effort was begun on

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September 16, 1938 and completed on September 22, 1988. The decon- , J tamination method utilized was the LCMI process and DecorJ. amination , Factors (OFs) ranged from a low of 1.17 to a high of 500. The ! i average DF was 41.3. Overall the decontamination effort has resulted j i in the removri of approximately 60 curies of cobalt-60, which should

!  significant?y reduce the dose rates to personnel working throughout !

the reactor facilitie l e

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, The decontamination solutions were pumped to ion exchange enlumns l n for treatment to remove radioactivit The resins from the ion j exchange columns were subsequently transferred to steei liners within , shipping containers for transfer after solidification to a licensed burial facility. The licensee plans to make three shipments of

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  . 4 solidified resins by September 29, 1988. The resin transfer preparation and setup was observed by the inspector and was completed without incident. Solidification of the resins within the liners was in process by September 23, 1988 and should be completed by September 29, 198 .2 External Exposure Control The licensee uses the Panasonic 812AS2 TLD system for monitoring personnel exposm e. In addition, all personnel who enter the Radiation Controlled Area (RCA) are issued a Direct Reading Dosimeter (ORO). All personnel who quaiify as self neonitors are supplied with "Dositecs' for use while within the Radiation :

Controlled Area (RCA). After completion of work within the RCA all 1 personnel must exit through a protal m,nitor located at the RCA exi The portal Lonitor use is checked by a member of the RES staff stationed at the RCA exi ' TLD badge, are processed twice monthiy and an exposure report is prepared and circulated to all plant supervisory personnel. OR0s are read when exiting the RCA or at Job completion. ORD exposure a cards are collected daily and a daily dosimetry report is prepared

and dist.ributed to all plant depart ments. After each badge period TLD readings are compared to the ORJ readings and the DRO eadings are adjusted. For the refuel outage a cumulative man-rem exposure graph is prepared and distributed tc all departments. As a result of this review it was determined that the licensee's personnel dosimetry for external occupational exposure program is adequate to control exposure during refuel outage operations.

{ 4.3 Internal Exposure Control It was noted during the previous inspection that the licensee had

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undertaken a campaign to reduce the number and size of contaminated areas throughout the facilit This campaign is continuing , throughout the refueling outage. Engineering and process control -

techniques are used as much as possible to limit concentrations of i airborne radioactive materials. During this outage there have been ,

i no personnel uptakes from airborne radioactive materials, and all ' d areas of the facility remain below 15's of 10 CFR 20 Appendix B Limits, i i 4.4 ALARA  ; 1  ;

!    The licensee has continued >n intensive ALARA program ef fort during ,

the refueling outage. Re .e controlled closed circuit television is

   . used as much as possible f or ooservation of high dose activitie In addition the decontamination activity conducted at the beginning j    of the outage has significantly reduced dose rates in the drywell and other plant areas traversed by reactor pipin .

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The man-res projection for the outage has Men reduced to approximately 350 man-rem. The man-rem pris e ction for the year ; remains at 650. This will still constitute an improvement over previous years exposures. However continuing efforts should be : undertaken to further reduce exposure. All personnel are aware of f the ALARA goals and are actively involved in the program. The RES i department reviews the daily exposure report by department as l spccific assignments are completed, and adjusts the projected goals i as necessary throughout the outag l

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5.0 Exit Meeting j The inspector met with licensee management representatives (denoted in ! Section 1) at the conclusion of the inspection on September 23, 198 i The inspector summarized the purpose, scope, and findings of the

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