IR 05000289/1977007
| ML19261E844 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1977 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261E842 | List: |
| References | |
| 50-289-77-07, 50-289-77-7, NUDOCS 7910170886 | |
| Download: ML19261E844 (9) | |
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IE:I Form 12 (Jar 75) (Rev)
U. S. NUCLEAR REGUIATORY CC20tISSION OFFICE OF INSPECTION AND ENFORCrMEhT
REGION I
IE Inspection Reoort No:
50-289/77-07 Docket No:
50-289 Licensee:
Metropolitan Edison Company License No:
000 50 P. O. Box 542 Priority:
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Reading, Pennsylvania 19603 Category:
C Safeguards Three Mile Island I Group:
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kca tion:
Middletown, Pennsylvania Type of Licensee:
Typ<
f Inspeccion:
Routine, Unannounced
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Dates of inspection:
March 9-11,1977 Dates of Previous Inspection:
March 4,1977 b'
Reporting Inspector:
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DATE
'K.#E. Plumlee, Radiation Specialist Accompanying Inspectors:
None DATE DATE DATE Other Accompanying Perscnnel:
None DATE Reviewed By:
G OW-
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DATE P. Knapp, Section Chief, R'adiation Support Section, Fuel Facility and Materials Safety Branch g4 7910179
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SUMMARY OF FINDINGS Enforcenent Action A.
Violations
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None.
B.
Infractions
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None.
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C.
Deficiencies j
None.
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Licensee Action on Previously Identified Enforcement Action 76-26-01 - Failure to Post a Radiation Area.
'l A review of posting indicated that the corrective action on this item 1s complete.
(Details,4)
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Design Changes Plans to pipe the Borated Water Storage Tank (BWST) area sump directly
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to the radwaste system.
(Detail s, 8)
Licensee Events
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None.
Other Significant Findings A.
Current Findings 1.
Acceptable Areas No inadequacies were identified during inspection of the following areas.
(Details, 3 or as shown below)
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a.
Qualification of personnel.
b.
Radiation protection training.
(Details, 3 and 5)
c.
Upkeep of instruments and equipment.
d.
Posting, labeling, and control.
(Details,4)
e.
Surveys.
f.
Personnel exposure control.
g.
Licensee audits.
2.
Unresolved Items i
None.
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3.
Items Requiring Further Review I
77-07-01 - Unit 1 and 2 Radiation Protection Organization,
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Staffing, and Resumes.
(Details,6)
4.
Deviations None.
B.
Status of Previously Identified Unresolved Items None.
Management Interview A management interview was conducted at the Three Mile Island Facility on March 11, 1977.
A.
Persons Present
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Mr. J. Colitz, Unit l Superintendent Mr. W. Cotter, Supervisor of Quality Control Mr. R. Dubiel, Acting Supervisor of Radiation Protection and Chemistry
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B.
Items Discussed 1.
Purpose of the Inspection This was a routine unannounced inspection of the radiation protection program, preparations for the forthcoming refuel-ing outage, and corrective actions on previously identified pro bl ems.
2.
Acceptable Areas The items discussed are as identified under "Other Significant Findings" section of this report.
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3.
Work Force for the Refueling Outage
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The licensee plans for radiation protection, training, and for monitoring the exposures to the contractor personnel were reviewed.
(Details, 5.a)
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ALARA Program
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The licensee plans for controlling exposures to personnel
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during the outage were reviewad.
(Detail s, 5.b)
5.
Information on Organization and Resumes The licensee representative stated that updated information was being prepared by Met-Ed management for transmittal to NRC.
(Details,6)
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DETAILS 1.
Persons Contacted
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Ms. R. Brown, Technical Analyst III Mr. N. Derks, Administrator, Technical Training, Nuclear Mr. R. Dubiel, Acting Supervisor of Radiation Protection and Chemistry Mr. K. Frederick, Staff Chemist Mr. E. Gee, Safety Supervisor Mr. W. Herman, Associate Engineer II - Nuclear Mr. J. Heverle, Security Supervisor Mr. F. Huwe, Radiation Protection Foreman Mr. R. McCann, Radiation Protection Foreman Ms. C. Nixdorf, Office Supervisor Mr. D. Weaver, Instruments and Controls Foreman
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2.
Scope of the Inspection This was an inspection of radiation protection practices during
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normal operation of the facility.
Inspection effort included
observation of work performance, review of procedures, sampling of records, and review of corrective actions on previously identified
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pro bl ems.
3.
Plant Records The inspector reviewed selected samples of the following records for the periods indicated and found that they appeared to be acceptabl e.
Record title or subject Acceptance criteria Qualifications of radiation TS 6.2.2.d & 6.3.1 protection personnel (current)
ANSI N18.1-1971 FSAR Section 11.6.3 Radiation protection training, 10 CFR 19.12 January and February, 1977 TS 6.4 and 6.10.2.g ANSI N18.1-1971 Procedure HPP 1690 1482 328
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Instrument and equipment calibrations TS Ta bl e 4.1-1 (28 & 35)
and tests, July 1,1976, to March 1, Procedure HPP 1749 1977 FSAR Sections 11.4, 11.5.6 and 11.6.2 Surveys, January and February,1977 10 CFR 20.201(b)
10 CFR 20.401(b)
TS 6.10.2.c Procedures HPP 1602 to 1609 License Condition 2.b.(2)
to (4)
Personnel exposure control, 10 CFR 20.101(a) and (b)
December 1976, and January and 10 CFR 20.102
February, 1977 10 CFR 20.103
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10 CFR 20.104(a) and (b)
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Procedures HPP 1615, 1616, l
and 1628 n
Audits, September 1976, to TS 6.5.2.A.2.k (5)
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March 10, 1977 TS 6.5.2.B 8 Procedure HPP 1685 4.
Control of Access to Restricted, Radiation, and High Radiation Areas Regulatory requirements include posting of information, signs and notices, and the control of au ess to restricted, radiation, and high radiation areas.
In addition, the licensee recently completed a review of access controls pursuant to IE Circular 76-03.
Inspection 50-289/76-26 identified a problem with the posting of a radiation area.
Part of the inspection effort was to tour the facility and to observe the posted. information, signs and notices, and the access controls.
The inspector observed confirmatory measurements of radiation levels.
The inspector observed the work being performed under radiation work permits and the RWP conditions.
The inspector observed the status of some padlocked temporary doors and reviewed the licensee's plans for installing lockable sermanent doors at those locations, which control the access *., high radiation areas.
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The above items appeared to be acceptable and the inspector has no further questions on these items at this time.
5.
Planned Radiation Pretection Training and Monitoring of Personnel during the Spring 1977 Refueling Outage a.
Temporary (contract) work force.
The licensee representative stated that in addition to the TMI employees the following personnel will be present during the outage.
(1)
100 workers in the steam turbine area.
(2)
100 workers in the controlled area.
(see next paragraph)
(3)
25 workers performing inservice inspection and nondestructive testing.
5 (per day) specialists and consultants.
(4)
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(5) 8 con?.ract health physics personnel.
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Forecast of exposures during the outage.
The licensee representative estimated that the total exposure during the outage would reach 120 man rem, with the major jobs being as follows:
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(1) Replacement of letdown heat exchanger "A."
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(2) Hydrotest and possible replacement of letdown heat exchanger "B."
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(3)
Inservice inspection and nondestructive testing.
(4) Safety valve servicing.
(5)
Refueling operations.
The licensee representatives stated that these jobs had been preplanned and then reviewed by a committee and that the day to day control of radiation expos"res is maintained by the radiation work permits issued for eacn job.
The control of radiation exposures will include monitoring, the use of shield-ing and protective equipment, careful preparation, and adequate supervision to expedite each job.
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c.
Training and monitoring of person,cl.
The licensee representative stated that each individual
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will be trained in TMI radiation protection procedures, in-cluding respiratory protection as appropriate, prior to per-forming radiation work on site.
Monitoring will include the use of self reading dosimeters, thermoluminescent dosimeter
(TLD) badges for whole body, head and hand monitoring, and frisking.
Nasal swipe counts will be required when the inhal-ation of airborne contamination is suspected.
The licensee
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routinely processes the TLD dosimeters on site.
The licensee representative stated that whole body counts will be taken of all personnel who are exposed to airborne contamination during the outage, after the completion of their assignments.
The licensee program for radiation protection, training, and monitoring of personnel appears to be acceptable and the inspector has no further questions on this item at this time.
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6.
Review of Radiation Protection Organization, Staffing, and Resumes Reviews on previous inspections identified several vacancies and the lack of current resumes involving the Unit 1 and 2 radiation protection organization.
(Report Nos. 50-289/77-01, January 11 and 12,1977, Management Interview Item E, and 50-320/77-07, February 8-10, 1977, Details,3)
Review on this inspection did not identify any change.
The inspector noted that the Radiation Protection Supervisor has had the additional responsibilities of Acting Supervisor of Radiation Protection and Chemistry since January 1,1977, although the docu-mentdtfon indicated that these were two positions, and not one.
(77-07-01)
The licensee representatives again stated, during this inspection, that the corporate management is reviewir.g the staff requirements and that updated information will be documented with the NRC.
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7.
Contamination of Intermediate Coolina Water System The leakage of the letdown heat exchanger (Details, 5.b.(1))
resulted in contamination of the Intermediate Cooling Water System and this led to the discovery of the leak.
Review of records of the radiation monitor, RM-L9, during this inspection indicated that the Intermediate Cooling Water activity was holding steady at 0.003 uCi/ml.
The licensee representative stated that the planned replacement of the leaking component would alleviate the contamination, and that no problem was foreseen with other equipment that is cooled by the Intermediate Cooling Water System.
The licensee's planned correction on this item appeared to be acceptable and the inspector had no further questions on this item at this time.
8.
Miscellaneous Sump Discharge Monitor RM-L8 The inspector reviewed the status of RM-L8 with the licensee
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representative who stated that because of contamination (crud)
trapping RM-L8 remained continually tripped and this automatically diverted all of the miscellaneous sump discharges to the radwasge collection system.
The indicated level of activity was 3 x 10-uCi/ml at the time of this inspection.
(several times the back-ground count rate on other liquid monitors)
A licensee representative stated that a design change is planned to pipe the BWST area sump directly to the radwaste collection system, and that the change would allow the remainder of the mis-cellaneous sump discharge to go to the storm drain instead of the radwaste drain, after RM-L8 is cleaned up.
The licensee representative stated that the planned change had been reviewed and determined not to affect the safety of the facility.
The licensee's planned design change appeared acceptable, and the inspector had no further questions on this matter at this time.