IR 05000244/1981023
| ML17258A536 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/18/1982 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17258A535 | List: |
| References | |
| 50-244-81-23, IEB-80-10, IEC-80-14, NUDOCS 8202160659 | |
| Download: ML17258A536 (11) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-244/81-23 Docket No.
50-244 License No.
DPR-18 Pri ority Category C
Licensee:
Rochester Gas and Electric Com an 89 East Avenue Rochester New York 14649 Facility Name:
R.E.
Ginna Nuclear Power Plant Inspection at:
Ontario, New York Inspection conducted:
October 8 L 9, 1981 Inspectors:
.E. Plumlee, Radiation Specialist date signed date signed Approved by: ~
P.J.
Knapp, Chief, Faci ity Radiological Protection Section, Technical Inspection Branch ate signed Ins ection Summar
Ins ection on October 8&9 1981 Re ort No. 50-244/81-23 Areas Ins ected:
Routine unannounced inspection by a regional based inspector of licensee actions on NRC: IE Bulletin No. 80-10,
"Contamination of Nonradio-active Systems and Resulting Potential for Unmonitored, Uncontrolled Release to Environment", including:
documentation, identification of interfaces between nonradioactive and radioactive systems, sampling to identify any unmonitored releases, interim measures or safety evaluations necessary to use nonradioactive systems that have become radioactive, and corrective actions.
This inspection involved ten inspector hours on site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
Region I Form
(Rev. April 77)
82021bOb59 820l 28 PDR ADOCK 05000244
-
DETAILS 1.
Persons Contacted C. Anderson, Manager of guality Assurance
"J. Bodine, guality Control Engineer
- D. Fi lkins, Supervisor of Health Physics and Chemistry P.
Fi lion, Environmental and Radiochemistry Supervisor
"F. Mis, Health Physicist
- K. Nassauer, equality Control Technician
~J.
Noon, Assistant Plant Superintendent
- B. guinn, Health Physicist (Operations Foreman)
"B. Snow, Plant Superintendent R. Watts, Corporate Health Physicist
"Denotes presence at the exit interview on October 9, 1981.
2.
Licensee Action on Bulletins and Circulars (Closed)
IE Bulletin No. 80-10 (80-BU-10):
"Contamination of Nonradioactive Systems -and Resulting Potential for Unmonitored, Uncontrolled Release to Environment."
Review of the licensee's actions is documented in the following paragraphs.
(Closed)
IE Circular No. 80-14 (80-CI-14):
"Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel."
The licensee verified that the existing interfaces between the demineralized water system and the contaminated systems were designed to prevent any spread of contamination.
No contamination of this system was identified.
City water is processed within the demineralized water system to supply demineralized water to the plant.
City water flows through the domestic water system to the kitchens, drinking fountains, showers, and restrooms.
There is no interface with the nuclear steam system or any contaminated or potentially contaminated system.
The licensee prohibits human consumption of plant-supplied demineralized water by posting signs prohibiting eating, smoking, and drinking in the areas where demineralized water is available, such as the chemistry laboratory.
3.
Verification of Licensee Documentation a
~
Re uired ActionsBulletin 80-10 required the following licensee actions within 45 days of the date of the Bulletin (May 6, 1980):
( 1)
Identification of systems that are considered nonradioactive, or are described as nonradioactive in the FSAR, but could possibly become radioactive through interfaces with radioactive systems; (2)
Establishment of a routine sampling/analysis or monitoring program to promptly identify any contaminating events in the above systems which could lead to an unmonitored or uncontrolled liquid or gaseous release; (3)
Restriction of the use of any such system that is or becomes contaminated, until the cause has been identified and corrected and the system has been decontaminated; or if system operation is necessary before these actions are completed, prompt evaluation of the safety of operation in accordance with the requirements of
CFR 50.59; and, (4)
Assurance that any such operation is in compliance with 10 CFR 20.201, General Design Criterion 64 of Appendix A to
CFR 50, Appendix I to 10 CFR 50, and the facility's technical specifications.
b.
Re uired Notification and Documentation Bulletin 80-10 required, within an additional 15 days (of the original 45 days),
a letter from the licensee notifying the Director of NRC Region I of the completion of the required actions and of the availability of documentation for onsite review of the specifics taken to comply with the Bulletin.
The licensee's letter, dated June 24, 1980, stated that the above actions were completed.
Inspection No. 50-244/81-10 indicated a need for additional information on the sampling of the service air and the condensate storage tanks.
The inspector reviewed the following licensee documents and drawings:
Licensee reply to Bulletin 80-10, L.D. White, Jr.,
June 24, 1980 Memo,
"Response to IE Bulletin No. 80-10",
C.H.
Peck, May 29, 1980 Ginna Station Preventive Action Report No. 59-80, May 11, 16 to 29, 1980 FSAR Sections:
9.3 9.4 9.6.2 10.2.1 11.
Auxilia'ry Coolant System Sampling System Plant Fire Protection System, and Service Water System Circulating Water System Waste Disposal and Radiation Protection System
Health Physics 9.1 9.2 9.3 9.4 Other Procedur CP-210. 1, CP-211. 2, CP-212. 2, CP-213.2, CP-214. 2, CP-215. 2, CP-216. 2, CP-217. 2, CP-218.2, CP-219. 2, CP-220.2, CP-221.2, CP-222.2, P-9, Procedures:
Steam Generator Blowdown Activity Primary to Secondary Leakage Detection and Measurement Air Ejector Gas Sampling Actions for an R-21 Alarm (i.e., Retention Tank Monitor Alarm)
es; Calibration of R-10A and R-10B Detectors Calibration of R-11 Detector Calibration of R-12 Detector Calibration of R-13 Detector (Containment Vent)
Calibration of R-14 Detector (Plant Vent)
Calibration of R-15 Detector (Air Ejector)
Calibration of R-16 Detector (Containment Fan Cooling)
Calibration of R-17 Detector (Component Cooling)
Calibration of R-18 Detector (Waste Discharge)
Calibration of R-19 Detector (Steam Generator Blowdown)
Calibration of R-20 Detector (Spent Fuel Pool Cooling)
Calibration of R-21 Detector Calibration of R-22 Detector Radiation Monitoring System Precautions, Limits, and Setpoints.
The inspector also interviewed the Supervisor of Health Physics and Chemistry, and the Environmental and Radiochemistry Supervisor, to obtain further details of the licensee's sampling and monitoring program.
None of the systems were identified to be operating outside of the design limits.
Based on the documents and interviews listed above, the licensee had complied with Bulletin 80-10.
4.
Summar of the Monitorin and Sam lin Pro ram a.
Water Systems The plant draws cooling water through the plant intake and returns the water to the discharge canal, which is routinely sampled under the
environmental program.
The circulating water system and the service water system discharge water continuously during plant operation.
Three loops of the service water system are monitored to detect any
'nleakage at interfaces with radioactive systems.
Miscellaneous drains run into retention tanks, and the retention tanks are discharged periodically into the discharge canal unless the retention tank monitor trips.
I'f the monitor is found to have failed, discharge canal sampling is required by procedure HP-9.4.
Most of the storm and roof drains, and the surface runoff, runs to Deer Creek.
A weekly composite sample is taken from Deer Creek.
The sanitary sewer discharges to an offsite public sewer system.
No sewer samples are analyzed for radioactivity.
The licensee takes a weekly composite sample from the city water works intake, 1.5 miles from the plant, for the State of New York.
In addition, a monthly tap water sample is taken onsi te.
The licensee's program for monitoring and sampling nonradioactive systems is summarized in Table I.
TABLE I Summar of Nonradioactive Water S stems
~Satem Monitored
~Sam lin
~or Sam led FrerrFuenc r
~Sam le Anal si s uCi/ml Circulating Mater System Service Mater System Component Cooling Mater Heat Exchanger Containment Fan Cooling Mater Spent Fuel Pit Heat Exchanger Retention Tank System
"A" Steam Generator Blowdown
"B" Steam Generator Blowdown
"A" Condensate Storage Tank
"B" Condensate Storage Tank
"Outside" Condensate Storage Tank Component Cooling Mater System Demineralized Water Storage Tank House Heating System Discharge Canal Storm Drain System Fire Protection System City Water System Sanitary Sewer System Sampl ed Sampl ed Monitored Monitored Monitored Both Both Both Sampled Sampled Sampled Both Sampled Sampled See Text See Text Neither, Sampled Neither Monthly Monthly Meekly 3X/Week 3X/Meek Meekly Weekly Monthly Monthly 2X/Meek Monthly Monthly
<5E-9"
<5E-9"
<5E-9*
2E-8 5E-8 lE-8 5E-8 6E-9 1. 9E-5
<1. 4E-8*
<6.5E-7"
<5E-9"
<5E-9"
<5E-9" Lower limit of detection as sample The licensee representative stated that the above analyses were repre-sentative of normal operating conditions.
The analyses shown were for the period September 20 to November 13, 1981.
A licensee representative informed the inspector by telephone on November 13, 1981, that the sampling fre-quencies have been incorporated into procedures PC-1.2 and MC-1.
The licensee representative stated that the radiation monitors identified in Table I were operating as described in the FSAR.
The inspector reviewed the background indications, trip settings, and calibration records of the monitors.
The retention tank monitor and service water loop monitor trip points were in uCi/ml:
Retention tanks Component cooling heat exchanger loop Containment fan cooling loop Spent fuel pit cooling heat exchanger loop 6E-6 1.7E-5 1.7E-5 1. 6E-4 The trip points varied because of differences in the background radiation levels where the monitors were located.
No items of noncompliance were identified.
The sampling frequency will be reviewed onsite on a subsequent inspection.
(244/81-23-01).
b.
Ventilation S stems and Com ressed Air S stems The monitoring and sampling of the ventilation systems and compressed air systems are summarized in Table II.
The sample analyses were typical of current operating conditions.
TABLE II Ventilation and Com ressed Air S stems Summar
~Setem Monitored or Sam led Sam le Anal sis uCi/ml Primary Vent Auxiliary Building Exhaust Condenser Air Ejector Instrument Air Supply Breathing Air Supply Service Air Supply Both Noble Gas H-3 Iodines Particulates Monitored Both*
Sampled**
Sampled*~*
Neither lE"7 3E-8 ZE-13
~7E 15****
4E-5 g 1 E 8et**tt 9*tt'st*
Sampled daily.
- "
Sampled monthly.
"** Sampled at each distribution station before use of the station.
- ~~~ Lower limit of detection, as sample Review of the monitoring and sampling of these systems did not identify any changes from the FSAR description and the Technical Specifications bases, which have been evaluated by NRC.
5.
Exit Interview The inspector met with the licensee representatives, denoted in paragraph 1, at the conclusion of the inspection, to review the inspection finding