IR 05000289/1973008
| ML19256D533 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/22/1973 |
| From: | Knapp P, Mann J, Meyer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D530 | List: |
| References | |
| 50-289-73-08, 50-289-73-8, NUDOCS 7910180842 | |
| Download: ML19256D533 (9) | |
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U. S. ATOMIC ENERGY COSD11SSION DIRECTORATE OF REGULATORY OPERATIONS
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REGION I
RO Inspection Report No.:
50-289/73-08 Docket No.:50-289 Licensee:
Metropolitan Edison Company License No.: CPPR-40 Three Mile Is1 snd - Unit 1 Priority:
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Middletown, Pennsylvanir-Category:
B1 i
i Location:..
Type of Licensee: PWR 831 MWe (B&W)
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Type of Inspection:
Announced, Routine Radiological Protection j
Dates of Inspection:
August 6 and 7 1973 Dates of Previous Inspection: July 23-25,1973 c.
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dd[dhld/th,/ Inspector
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R. J. Meyer, Radiation S ?ecinlist DATE'
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Accompanying Inspectors:
P.
J. Knapp, Senior, Radiological DATE
& Environmental Protection Branch
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J.
n. Mann, Kadiatun specialist DATE
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Other Acccapanying Personnel:
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Reviewed By:%%. - -
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/ DATE P. J. Knapp, Senior, Radiological and Environmental
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Protection Branch
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SUMMARY OF FINDINGS l
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i Enforcement Action p
A.
Violations None B.
Safety Items
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None Licensee Action on Previousiv Identified Enforcement Items i~
None (Radiological Protection)
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Unusual Occurrences
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l None l
Othe-Significant Findings
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A.
Current Findines
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j The inspection was limited to these areas oriented toward radiation protection and chemistry functions of plant operation.
Inspection findings showed that program development is continuing with priority attention directed to procedure formulation. Training of personnel
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assigned to the Radiation Protection and Chemistry functions is (
continuing.
B.
Status of Previously Reported. Unresolved Items
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None (Radiological Protection)
Management Interview The following individuals attended the management interview at the conclusion of the inspection on August 7,1973.
l J. Herbein, Assistant Plant Superintendent i
J. Colitz, Station Engineer
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K. Frederick, Staff Chemist R. Deakin, Radiation Protection Supervisor R. Summers, Staff Engineer
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i The following subj ects were discussed:
A.
General - The inspector discussed, in general, his area of interest and inspection findings and stated that no violations had been noted in the areas inspected.
(Details, Paragraphs 2-11)
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B.
Training - The inspector stated th?t he was unable to determine at Q; ~
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The licensee stated that this would be reviewed. (Details,
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Paragraphs 3a-b)
C.
Radiation Protection Manual - The inspector discussed his review
of the subject manual. The licensee stated that changes would be reviewed or made as discussed.
(Details, Paragraphs 4a-d)
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Procedures - In response to the inspector's questions on procedure completions the licensee stated that they would be complete prior to fuel load date.
(Details, Paragraphs Sa-b)
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Liquid Waste Monitor - In response to questions on the location of
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the subject monitor the licensee stated that they are aware of the potential problem.
(Details, Paragraph 86)
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Gaseous Effluent Sampline Sys tems - In response to questions on isokinatic sampling capabilities and line loss de*.erminations,
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the licensee stated that they were being evaluated (Details,
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Paragraph 9a)
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Filter Testing - With respect to filter testing the licensee s tated that the area would be reviewed. (Details, Paragraphs 10a-b)
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DETAILS
1.
Persons Contacted pq a.
R. Klingaman, Plant Superintendent.
J. Herbein, Assistant Plant Superintendent J. Colitz, Station Engineer R. Deakin, Radiation Protection Supervisor G. Reed, Chemical Supervisor K. Frederick, Staff Chemist i
R. Summers, Staff Engineer 2.
Organization
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Inspection findings showed that the organization relative to
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the Radiation Prote-tion and Chemistry functions were as described in Sectiot. 12 and Figure 12-1 of the Final Safety I
Analysis Report (FSAR).
Line organization cot =tand and re-i sponsibilities remain as noted during the previous inspection *.
I Two personnel changes in supervisory positions have occurred.
The previously designated Supervisor of Operations has assumed
the position of Station Engineer.
The previously designated
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Chemical Supervisor has moved to the position of Staff
t Chemist, being replaced by, an individual with a nuclear i
reactor background.
I b.
According to licensee representatives, staffing is complete,
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with the exception of a contenplated addition of one Radiation Protection Technician.
Currently four technicians are on
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staff. With respect to the chemistry group, inspection
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finding showed that one Setdor Chemical Analyst and four Cldinical Analysts are currentl on staff.
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c.
As described by licensee representatives both staffs have
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capabilities to supplement and complement one another.
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ditionally, the Nuclear Auxiliary Operators have capabilities to supplement the Radiation Protection function, particularly during backshif t periods, when technician coverage is not normally provided.
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3.
Training a.
The inspectors review of training records showed that training has been provided as described in Section 12 of the FSAR and consistent with that described in ANSI N-18.1-1971.
According to licensee representatives, a retraining program is currently
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g-being formulated for the radiation protection technicians.
Na A two week retraining course for the auxiliary operators
\\. J is scheduled to begin August 27, 1973 b.
The inspector's review showed that all plant personnel receive training relative to the radiological aspects of plant operations consistent with their positions or job classifications. Training requirements and subject material are described in the Three
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tule Island Nuclear Station, Radiation Protection Manual.
The inspector noted that retraining frequencies were not defir.ed.
Licensee representatives stated that this would be reviewed.
4.
Radiation Protection Manual
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The subject manual which describes the standards, policies, a.
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and general instructions for providing radiation protection at the Three Mile Island Nuclear Station was reviewed in detail by the inspector.
In general the manual was consistent with regulatory requirements and accepted radiation safety practices.
Several minor deficiencies, iden.tified by the inspector, will
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be corrected as evidenced by licensee response.
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b.
With respect to a whole body counting program which is not identified in the manual, the licensee stated that a program
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count for those personnel who will work in radiation areas, j
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routine follow-up counts and counting as necessary to ap-t t.
propriately. evaluate internal exposures.
Definition will be provided by Health Physics Procedure 1628.
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In response to the inspector's questions about the licensee 's
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required internal reporting, documentation, and investigation
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of personnel contamination events described in the manual, the licensee stated that it would be reviewed, based on the inspector's
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comments.
d.
Relative to the respiratory protection program defined in the manual, the licensee stated that procedures to implement the program are being formulated. The inspector suggested that the licensee review ANSI Z88.2, " Practices for Respiratory Protection" before finalizing their program.
Licensee re-presentatives stated that the subject document would be reviewed.
5.
Procedures (H.P. & Chemis trv)
The inspector's review of procedure status showed that master a.
indices have been prepared and were available. As evidenced by licensee records and statements approximately 70,'; of the procedures have been written and are in the review, approval, or typing process.
As evidenced by licensee statements all s
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[~~D procedures will *oe completed prior to fuel load.
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b.
The inspector reviewed the below listed procedures:
H.P.P. 1602 - Radiation Dose Rate Surveys H.P.P. 1603 - Neutron Surveys H.P.P.1604 - Alpha Surveys H.P.P.1608 - Air Sampling for Tritium
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H.P.P.1609 - Surface contamination Surveys H.P.P.1610 - Establishing and Posting Areas H.P.P. 1613 - Radiation Work Permits H.P.P.1615 - Use of Personnel Monitoring Devices H.P.P.1701 - Background Determination for G.M. Scalers
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H.P.P.1706 - Efficiency Determination for Beckman Wide Beta II H.P.P.1740 - Instrument Operation Hewlett Packard M.C.A.
l H.P.P.1750 - Operation and Calibration of GSM-5
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Survey Instrument H.P.P. 1770 - Film Badge and TLD Badge Record Keeping
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H.P.P.1741 - Instrument Operation of Internal Liquid
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Scintillation Counter i
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Facilities & Equipment
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Health Physics and Chemistry facilities located adjacent to
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the Control Point are nearing completion.
Equipment instal-(_j lation has not yet started.
Counting equipment remains at l
the tempora'ry facility. According to the licensee counting equipment will be installed and recalibrated when a regulated i
voltage supply is available. Portable instrument procurement continues and according to the licensee will include those described in the Radiation Protection Manual.
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7.
Area Radiation Monitors
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a.
Inspection findings showed that the subject system was in agreement with that described in Section 11 of the FSAR.
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The system as noted was installed and awaiting system checkout and calibration. Detector locations, observed by the inspector, were in agreement with FSAR described locations,
b.
The insperior reviewed the calibration procedure for the subject system, e:ititled, " Area Radiation Monitoring Calibration and Functional Test, Number TP360/2".
Calibration will be accomplished with a Victoreen, Model 848-8 Field Calibrator Kit, employing cesium-137 as the radioactive source.
The procedure provides for calibration to instrument ranges beyond the normally established high alarm trip points.
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8.
Process Monitors (Liouid-Gaseous)
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Inspection findings showed that the subject monitoring systems were as described in Section 11 of the FSAR.
Installation of the monitors was essentially complete.
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The units were at locations to monitor the liquid and
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gaseous streams as described in the FSAR.
Sampling systems for the gaseous monitors were not yet complete.
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The inspector noted that the Liquid Waste Discharge Monitor
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RM-L6 was located in close proximity to the condensate l
storage tank.
In response to questions relative to back-ground radiation levels and sensitivity of the monitor, j
licensee representatives stated that they were aware that
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this could be a problem after some period of operation.
I They stated that additional shielding would be added with background buildup or the monitor would be relocated, if
neces s ary.
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c.
Calibration verification procedures for the subject monitors l
are detailed in the " Process Radiation Monitor Calibration and Functional Tests" identified below:
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Portable Atmospheric Monitors - Number TP 360/lA
i Fixed Atmospheric Monitors
- Number TP 360/lB (_ f Liquid Monitors
- Number TP 360/lc
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j d.
As. evidenced by a review of reports and manufacturers manuals supplied with the systems, initial calibration is accomplished
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at the manufacturing site. V rification of that calibration is accomplished after installation at the use site. For these units tnat monitor effluent streams, licensee represen-tatives participated in the initial calibration with the manufacturer.
The inspector reviewed the details and calibration data documented in the "Fincl Test Report on Effluent Monitoring Channels RM-AS, A8, A9, L6, L7 and L8 For Metropolitan Edison Company".
Calibration was accomplished i
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using varying known concentrations of radioactive liquids, l
gases and deposited particulates. Calib r. tion curves,
sensitivities, and linearities have been determined.
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The inspectors review of the test procedures (para e above)
showed that they were consistent with the need to verify the initial calibrations emploving reference sources. The sources employed in the initial calibrations and verification are traceable to N.B.S. Standards.
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9.
Plant Vent Samoling System
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As evidenced by licensee statenents the subject system, not yet installed, will provide for isokinetic sampling.
The
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licensee stated the.fstem would be reviewed af ter installation and capabilities con 'irmed.
With respect to sample line loss determinations the licensee stated that they are evaluating
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methods to make determinations and that some equipment has been purchased to that end.
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10.
Filter Systems As noted during the inspection HEPA and charcoal filters are
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i not yeat installed. As evidenced by licensee s tatements, in place leak testing of the filters will be accomplished.
Ac-cording to the licensee, leak testing will be performed by the supplier of the filters and will include the standard aerosol DOP test for the particular (HEPA) filters and
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Freon-112 method for the charcoal filters.
The licensee
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stated that the method and procedures for the HEPA testing would be reviewed against the requirments of ANSI N101.1-1972.
b.
With respect to testing of the charcoal filters the licensee
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stated that only in place leak testing was scheduled.
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response to the inspectors questions on iodine removal
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(absorption) ef ficiency determinations the licensee stated that this area would be reviewed.
The licensee was provided (post inspection) with a copy of Regulatory Guide 1.52 which provides guidance relative to. testing methods,
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11.
Radioactive Waste Systens i
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a.
A walk through of the subject systers showed that they appeared to be in agreenent with the description in section 11 of the FSAR.
It was noted that piping and storage tanks were located within Class 1 structures. Major components of the systems were further located within shielded cubicles. Test procedures for functional testing of the system will be reviewed during a subsequent inspection.
12.
Biological Shield Survsy The inspector reviewed Test #24, " Biological Shield Survey a.
Power Escalation Functional Requirement", further identified as TP/5/1/800-3.
The subject test procedure establishes survey points and frequencies at which survey measurements will be made during reactor pcwer escalation.
The procedure includes background level determinations prior to startup.
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l MEMO ROUTE SUP Form Arc.9s an. M.y i4. io47: Atc.u o24o N.,..
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{-d D. Thornburg, w.,n..no. io immALS aEMAna$
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RO Inspection Report 50-289
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Chief, FS&EB
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cart Metropolitan Edisca Company Three Mile Island To (Norme and unst)
RO:HQ (5)
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The subject inspection report is forvarded for R0 Files
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your information.
Distribution will be made by DR Central FilesqfArt th.a of fice to the PDR, LPDR, NSIC, DTIE and State Central Mial & F les representatives af ter review by the licensee for proprietarv in formation To (Name and unit)
18e TIALS REMAAKS
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Director of Licensing (13)
Reg Standards (3)
un i' rom (Name and umt)
REMARKS PAUL R. NELSON
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j(m OATUG 2 31973 PHONE 800,
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USE OTHEA SIDE FOR ADDITICM AL REMAAKS CPo i loin 0 - 445 459
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