IR 05000245/1988013
| ML20154F700 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/08/1988 |
| From: | Shanbaky M, Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20154F663 | List: |
| References | |
| 50-245-88-13, 50-336-88-18, 50-423-88-18, NUDOCS 8809200091 | |
| Download: ML20154F700 (5) | |
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U.S. NVCLEAR REGULATORY COMMISSION
REGION I
Report Nos. 50-245 88-13 50 336 88-18 50-423 88-13 Docket Nos.
50-245 50-336 50 423 License Nos. DPR 21 Category C
DPR-65 DPR-49 Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 0610'
Facility Name: Millstone Nuclear Generating Station
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Inspection At: Waterford, Connecticut
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Inspection Conducted: July 26-29, 1988
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Inspectors:
h M.
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W. Thomas, RadiaNon EpecialisFTRP3 TR55B date
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Approved by:
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I__ M 9h JY.
.ky, cme, acTTitWs Radiation
date
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Protection Section Inspection Summary:
Ins ection on July 26-29 1988 (Report Nos.
50!p!4578973D07-36/88-IB 50N-23788-IIT'-
Areas Inspected:
Routine, unannounced inspection to review Unit 2 radiation protectTon activities. Areas reviewed included status of previously identified
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items, internal and external exposure controls, and station ALARA practices.
Results: No violations were identified, the Unit 2 radiation protection program was being effectively implemented.
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Details 1.0 Persons Contacted
- M. Brennan, Unit 1 Radiation Protection Supervisor (RPS)
- D. Fitts, Unit 2 ALARA Coordinator
- R. Gault, Unit 2 Assistant RPS
- H. Haynes, Station Services Superintendent
- J. Kennan, Unit 2 Superintendent
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- J. Laine, Unit 2 RPS
- R. Sachatello Unit 3 RPS
- P.Simmons,RkS Services UnitiAssistantRPS
- G. Smith,ki
- S. Turows Unit 3 ALARA Coordinator P. Weekly, $ecurity Supervisor
- Attended the exit meeting on July 29, 1988
Other licensee personnel were also contacted during the course of this inspection.
2.0 Pyoose lne purpose of this routine, unannounced inspection was to review the r
implementation of the Radiation Protection Program.
The following areas were included in this review:
Status of Previously Identified Items.
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External Exposure Controls, and
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Internal Exposure Controls.
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3.0 Status of Previously Identified Items I
(closed) Inspector Followu 3.1 50 336/86-29-05 and 50-423/p Item (50 245/86 23-05Improvetralni,gonthe 86-36 05):
of cmergency instrurents during an emergency l
Revised Procedure Number EPIP 4207, "Radiolo ical Sampling During Rev. 4, dated September 8, 19 6, specifies that AnEmergency"In6istobeturnedoffbeforetheairsampleris
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the truck eng turned on.
The portable instrument survey probes, which were i
dangled outside the vehicle window were GM ) robes, which are not
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closed. y affected by cold temperatures.
adversel 111s item is considered l
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3.2 (0 pen) Inspector Followup Item (50 245/87-13-03 and 50-423/87-13-03): Licensee to evaluate the need for respirator training for security guards.
During this inspection additional discussions were held with the Security Supervisor concerning respirator training for security guards. At the present time approximately 75% of the Addition, guard force have been respirator qualified. Inprocedure SEP 50 security force members to be repirator qualified.
The Security Supervisor stated that this requirement will L< implemented by September 1, 1988. This item remains open and will be rettewed during a I
subsequent inspection.
radioac).ivemateria'L50-245/87-1501): Shipping box containing (Closed Violation 3.3 was not labeled as required.
j The inspector reviewed the Licensee's corrective actions provided to the NRC by letter, dated September 18, 1987.
The inspector verified that the actions taken were appropriate, l
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completed in a timely manner, and in accordance with the referenced licensee's letter.
This item is considered closed.
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3.4 (Closed) Inspector Followup Item (245/87-15-02, 336/87-17-01,423/87-14-01): implement a revised HRA key control proced Licensee to develo The licensee has evaluated additional measures to ensure HRA gate integrity and HRA key control.
These measures have been implemented in revised Radiation Key Control", procedure HP 951/2951/3951, "High dated November 27, 1987.
This item is considered c'losed.
(Closed 3.5 procedur)es. Violation (50-245/87-15 03): Failure to follow RWP The impector reviewed the licensee's corrective actions provided i
to tL) NRC by letter, dated September 18, 1987.
The inspector l
'ver.fied that the actions taken were a ppropriate, completed in a
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timely manner and in accordance with tie referenced licensee's letter. This item is closed.
(Closed Inspector Followup Item (50-336/84-22-02): Licensee to 3.6 provide)for periodic verification of the fuel handling bridge gamma radiation monitor operability.
j Rev. 9 of procedure SHP 4905 dated December 1,1987, requires a l
weekl sourcecheckoftheVIctoreenAreaMonitoringPacket l
(VAMP located on the 38'6" elevation of the spent fuel sool.
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Recor s of the source checks for 1987 were reviewed by tie inspector and found to be complete.
This item is considered
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closed.
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4.0 ALARA The inspector )erformed a limited review of the implementation of the licensee's ALA(A Program by the following methods:
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discussion with the Unit 2 aad Unit 3 ALARA Coordinators,
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review of planned job exposure estimates.
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review of ongoing job exposure tracking,
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review of procedure ACP 6.02, "Maintenance of Occupational Radiation
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Exposures ALARA",
Based on this limited review, no deficiencies were identified. This area will be reviewed in depth during a future inspection.
5.0 External Exposuro Controls The licensee's External Occupational Exposure Control Program was reviewed by the following methods:
discussion with licensee personnel,
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review of selected Radiation Work Permits and radiological surveys.
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observation of Unit-2 radiological area postings.
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review of radiological investigation reports associated with Unit 2
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High Radiation Area door control,
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I review of the weekly exposure status report for Units 1 & 2
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The inspector toured the Unit 2 Radiation Controlled Area accompanied by
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the Unit-2 Assistant RPS. During the tour it was noied Liiat, au radiation ar us were properly posted and that all locked high radiation area gates were lecked. Key to dose rate area maps as well as ALARA area maps were located throughout Unit-2.
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1he inspector reviewed Unit-2 area surveys and noted that all required surveys were completed in a timely manner. The inspector also noted that progress has been made in the reduction of the number of locked high radiation areas and in contaminated areas at Unit-2.
Licensee efforts in these areas will continue to be reviewed during subsequent inspections.
I 6.0 'nternaj Exposure Controls (he licensee's program for control of internal exposure was reviewed with respect to criteria contained in the applicable regulatory requirements.
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The licensee's performance with respect to the above criteria was determined by:
observations of work activities esde during the tour of Unit 2
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review of selected records and 'rocedures, and
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discussions with licensee personnel.
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Within the scope of this review, no violations were identified.
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7.0 Exit Meeting The inspector met with the licensee personnel denoted in Section 1.0 of this report on July 29, 1988. At that time, the inspector sunmarized the purpose, scope, and findings of this inspection.
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