IR 05000320/1978004
| ML19220B381 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/16/1978 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B361 | List: |
| References | |
| 50-320-78-04, 50-320-78-4, NUDOCS 7904250679 | |
| Download: ML19220B381 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No, cn_,?pf7a_nc Docket No.
c;n 7?n License No.
roco u Priority
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Category
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n1 Licensee:
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D. Ony Ra?
n Daadino. Ponnsv1vania 10603 Facility Name:
Thraa Mila Tsland Norlaar Station, Unit 2 Inspection at:
Middletcwn, Pennsylvania Inspection conducted: Jan ry 5-6, and 26-27,1978 Inspectors:
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K. E. Plumlee, Radiation Specialist
'6L-16 - 7 9 date signed date signed
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date signed Approved by:
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u /l P.'J. Knapp, Chief, Radiation Support 9.'Ib-76 Section, FF&MS Branch date signed Insoection Summary:
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Insoe-tion on January 5-6, and 26-27, 1978 (Recort No. 50-320/78-04)
Areas Insoected:
radiation prot ction personnel, radiation protection procedures, i
instrtments anu equipment, respiratory protection program, liquid and gaseou,s waste t ystems, effluent monitors, test of ventilation system filters, preoper-ational testing of instruments, observation of the status of the facility, and intervi tws with personnel.
NRC inspector.
The inspection involved 28.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> onsite by one Resul ts_: No items of noncompliance were identified.
I 3b~233 i
i Region I Form 12 7 9 0 4 2 5 0 67t
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(Rev. April 77)
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DETAILS _
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persons Contacted _
Metrooolitan Edison Company (Met Ed)
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- M. Bezilla, PORC Secretary
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J. Brumer, Instrument and Controls Engineer
- R. Dubiel, Supervisor of Radiation Protection and Chemistry
- L. Fisher, Engineer - Nuclear
- E. Gee, Safety Supervisor F. Huwe, Radiation Protection Foreman t
- G. Miller, Station Superintendent / Unit 2 Superintendent
- T. Mulleavy, Radiation Protection Supervisor
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- J. Seelinger, Unit Superintendent - Technical Support
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- W. Zewe, Shift Supervisor General Public Utilities Service Corocration (GPUSC)_
- M. Nelson, Technical Engineer
- R. Toole, Test Superintendent
- denotes those present at a management interview on January 6, 1978.
27, 1978.
- denotes those present at the exit interview on January Radiation Protection Staff _
2.
The FSAR and the proposed Technical Specifications, indicate that members of the TMI-2 staff will meet or exceed the minimum ifications of ANSI N18.1-1971 ation Protection and Chemistry is to meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975.
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77-31 - Staffing, cualifications, and training of radiation pro-320/77-31:
tection personnel were last reviewed on Inspection No.
The FSAR infomation was subsequently updated and existing openings for a Health Physics Engineer and four technicians were filled.
Further technician openings resulting from terminations and Updated transfers within the Met-Ed organization were also filled.
resumes were provided for the FSAR.
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Review of this inspection showed that these personnel met the qualifications referenced above, and the training provided for the technicians had been completed except that three have a scheduled laboratory chemistry course to attend offsite during the Summer of 1978.
The inspector observed that the responsibilities and authority for radiation protection activities were clearly established and that the Radiation Protection Supervisor, a Radiation Protection Foreman, and a Chemistry Foreman were actively involved in planning and preparations for TMI-2 fuel loading.
Auditing of these activities was conducted by the Supervisor of Radiation Protection and Chemistry.
The inspector found that the staffing, qualifications, training, auditing, and assignment of responsibility for radiation protec-tion and chemistry were in conformance with the applicable docu-
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mentation, and the status appeared to be acceptable for fuel loading operations.
The inspector had no further questions on this item.
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3.
Radiation Protection Procedures The inspector completed a review of the radiation protection pro-cedures. Two of these procedures were being changed:
Prbcedure HP1606, Revision 3, April 15,1977, " Air Sampling for Radioactive Iodine;"
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Deletion:
Cesco Cartridge Filter # 81-70 Insertion: SAI RADECO Filter CP-100 t
Reason:
Better perfonnance using the CP-100 filter.
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Procedure HP1621.2, Revision 1. January 10, 1978, " Releasing Radioactive Liquid Waste from Unit 2," was being retyped. This
. revision appeared to be acceptable.
77-31 - A previous inspection ident.fied three procedures:
HP 1621.2, HP 1622.2, and tiP 1629.2 as still to be issued.
On this inspection these procedures involving waste liquid releases, waste gas releases, and waste liquid disposal, respectively were reviewed and found to be acceptable.
The inspector had no further questions on procedures.
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Facilities, Instruments, and Eouioment a.
Occupancy The inspector observed that during the onsite inspection, the Unit 2 Radiation Protection Office was not occupied and it lacked chairs, desks, and a telephone.
The' licensee representative informed the inspector by tele-phone on February 15, 1978, that the Radiation Protection Office was subsequently occupied and equipped as planned.
This will be reviewed on a subsequent routine inspection (78-04-01).
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Construction and Test Eauioment During the onsite inspection there were nunerous items of
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construction and test equipment in the auxiliary building one of which was a temporary sump pump and hose that discharged the water collected in the Miscellaneous Waste Sump by an unmonitored path.
The licensee representative stated that the sump and the areas draining to the sump were frequently checked and veri-
'fiec to be free of radioactive contamination.
The inspector performed a confirmatory survey and identified no radioactive materials in the Auxiliary Building other than instrument check sources that were secured in the monitoring equipment.
The licensee representative informed the inspector by tele-phone on February 15, 1978,.that the above pump had been
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removed and no further unmonitored discharge will be made from the sump.
He also stated that the remaining scaffolds, tempor-ary electric power cables, and test equipment were being removed.
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c.
Area Radiation Monitors and Licuid and Gas Monitors 77-31 - An outstanding item was to observe preoperational
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tests of these monitors. The licensee representative stated that the monitors needed during fuel loading were being calibrated and checked out, and these were the following:
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Instrument Number Location HP-R-209 Main Fuel Handling Bridge - Reactor Building HP-R-210 Aux. Fuel Handling Bridge - Reactor Building HP-R-214 Reactor Building Dome HP-R-215 Fuel Handling Building - Fuel nandling Bridge HP-P-219 Station Vent HP-R-223 Spent Fuel HP-R-225 Reactor Building Purge Exhaust Duct A HP-R-226 Reactor Building Purge Exhaust Duct B RM-L7 (Recorder Station Effluent Point)
WDL-R-1311 Plant No. 2 Effluent WDG-R-1480 Waste Gas Discharge
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WDG-R-1485 Waste Decay Tank 1A Discharge
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WDG-R-1486 Waste Decay Tank 18 Discharge
_ The inspector observed that acceptable test equipment and pro-cedures were being used and the licensee's progress indicated that these monitors would be in service by the time of fuel loading. The electronic, calibration was incamplete on HP-R-214 and the liquid and gas monitor sampling flows had not been completely checked out on January 26, 1978.
This item was reviawed by telephone and verified to be completed prior to fuel loading.
The inspector wi'41 complete +he review of the test documenta-tion on these monitors on a subsequent inspection, prior to the reactor sta~ tup.
(78-04-02)
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Other Safety Ecuipment The inspector observed that the following items had not been finished at the time of this inspection, but with the continued attention of the licensee, apparently would be finished by the time of the initial fuel loading.
Hood and Sample Sink Ventilation
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Emergency Shower
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Decontamination Room
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Storage and Disposition of Radioactive Samples and Sources The inspector f)und that the designated safety equipment apparently wouli be acceptable on the completion of work observed to be in progress.
The completion of this work will be reviewed on a subsequent inspection.
(78-04-03)
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Personnel Dosimetry Ecuioment The inspector observed the availability and status of per-sonnel dosimetry equipment and he reviewed the TMI-2 dosimetry program.which coincided with the THI-l program.
The TMI-2 program applied to only those individuals involved in fuel movements at this time.
s The inspector found that the licensee's plans, procedures, and arrangements appeared to be acceptable.
.rersonnel dos-imetry equipment will be routinely inspected on subsequent inspections.
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Respiratory protection Procram 77-31 - An outstanding item was to review the respiratory protec-tion program. The inspector reviewed this program for compliance with the requirements of 10 CFR 20.103 and Regulatory Guide 8.15.
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The licensee representative stated that except for the comoletion of each individual's fitness evaluation, the program was imple-He stated that no one who had not completed the recuire-mented.
ments would be allowed to enter an area where respiratory protection He stated equipment is necessary to comply with 10 CFR 20.103.
that a delay had resultad from a failure of x-ray equipment in a service organization's mobile laboratory durino the physical examinations and this was being rescheduled as soon as available.
The inspector found that the written procedures and policies on respiratory protection and as low as reasonably achievable exposures appeared to be acceptable and that the user's training, the fitting and testing of respirators, air samplino, bioassays, avail-abi.ity and upkeep of equipment, and the control of exposures appeared to be adequately addressed.
The implementation of the respiratory protection program will be reviewed on a subsequent routine inspection.
(78-04-04)
Ventilation Systems and Gaseous Waste Systems _
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The inspector toured the facility and also reviewed test records to verify the status of the control building and reactor building ventilation and purge systems.
- The inspector noted that the DOP and charcoal filter test results appeared to meet the removal efficiency specifications of the
" Draft and Review" copy of the Technical Specifications but the licensee's review of these tests were incomplete and had not'
identified any possible exceptions to the test procedures oc problems involved in these tests.
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Tests of gaseous waste systems had not been finished.
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Ventilation systems and gaseous waste systems preoperaticnal tests will be reviewed on a subsequent inspection.
(78-04-05)
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Manacement Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on January 27, 1978.
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The inspector reviewed the scope and findings of the inspection and stated that the licensee's completion of items such as review and acceptance of test results, occupancy of the facility and removal of construction and test equipment would be reviewed on a subsequent inspection.
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The Respiratory Protection Prcgram was reviewed and the inspector stated that its implementation will be reviewed on a subsequent inspection.
The status of procedures was reviewed.
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