IR 05000220/1979004
| ML17053A677 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/14/1979 |
| From: | Crocker H, Thonus L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053A676 | List: |
| References | |
| 50-220-79-04, 50-220-79-4, NUDOCS 7905090140 | |
| Download: ML17053A677 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
0
. ~50-220 29-04 Docket No.
50-220 License No.
DPR-63 Region I Priority Category Licensee:-
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse, New York 13202 Facility Name:
Nine Mile Point Nuclear Station, Unit
Inspection at:
Scriba, New York Inspection conducted:
February 6-9 and 21-23, 1979 Inspectors:
L.
. Thonus, Radiation Specialist date signed date signed Appr oved bv:
H.
W.
ocker, Acting Chief, Radiation Support Section, FF8MS Branch date sig ed date signed Ins ection Summar
Ins ection on Februar 6-9 and 21-23, 1979 Re ort No. 50-220/79-04 Areas Ins ected:
Routine, unannounced inspection by a regional based inspector of Ra coactive Waste Systems and Radiation Protection during Refueling including.
licensee action on previous inspection findings, effluent releases, records and reports, instrumentation, procedures, air cleaning systems, reactor coolant water quality, solid waste, facility tours, and refueling preparations.
Shortly after arrival at 8:30 p.m.
on February 6, 1979, areas where work was in progress were examined to review radiation safety practices.
The inspection involved 44 inspector-hours on site by one NRC regional based inspector.
Results:,
No items of noncompliance were identified.
VBOSOeo ~q~
Region I Form 12 (Rev. April 77)
DETAILS 1.
Persons Contacted Princi al Licensee Em lo ees V. Aublair, Station Shift Supervisor J. Duell, Assistant Supervisor, Radiochemistry and Radiation Protection R.
For tino, Chief Radiochemistry and Radiation Protection Technician
~C. Gerber, Radwaste Operations Supervisor M. Jones, Outage Coordinator
- E. Leach, Supervisor, Radiochemistry and Radiation Protection
- T. Lempges, General Superintendent
- Nuclear Generation J. Pavel, Assistant to the General Superintendent
- Nuclear Generation
- T. Perkins, Station Superintendent
~M: Silliman, Results Superintendent C.. Stuart, Operations Supervisor The inspector also interviewed approximately 15 other individuals including radiation protection technicians, operators, clerical personnel, and members of the security force.
- denotes those present at exit interviews held on February 9 and February 23, 1979.
- denotes those present at February 23, 1979 exit only.
2.
Licensee Action on Previous Ins ection Findin s (Closed)
Noncompliance (50-220/78-12-01):
Technicians with less than 2 years experience utilizied in responsible positions.
The inspector reviewed classifications and job assignments of the
radiation protection technicians.
Those personnel allowed to issue radiation work permits (RWP) without further supervisory review had greater than the required 2 years experience.
The inspector examined approximately 30 RWP's to verify that they were authorized or countersigned by qualified personne (Closed)
Noncompliance (50-220/78-12-02):
Testing of self-reading dosimeters (SRD) and alpha counting of smears.
The inspector reviewed the licensee's revised method of insuring SRD's in use have been calibrated* which utilizies color coding by spray paint after calibration.
Approximatel'y 40 SRD's in use were examined to verify that they had the proper color code.
The licensee's alpha counting equipment was out of service and the inspector reviewed results of contractor alpha counting of plant samples.
(Closed)
Noncompliance (50-220/78-12-03):
Leak testing of sealed sources.
The inspector reviewed results of leak tests of the licensee's PuBe source and several other sources conducted on January 10, 1979.
The tests had been performed within the required interval with the required sensitivity.
(Closed)
Noncompliance (50-220/78-16-02):
The licensee's revised procedures, dated December, 1978 which clarified the "Step Off Pad", posting, and roping requirements for contaminated areas was reviewed.
The inspector examined at least 10 contaminated areas while touring the facility for compliance with procedural require-ments.
Radioactive Effluent'Releases Environmental Technical Specification (ETS) 2.4.l.a-c limits activity discharge in liquid effluents on an instantaneous, quarterly and annual basis.
The licensee had no radioactive liquid effluent releases during 1978 or thru february 9, 1979.
ETS 2.4.3.a-b limits noble gases, iodines and particulates in airborne effluents on an instantaneous, quarterly and annual basis.
Examination of licensee analyses and records of noble gases for the periods March - May and November - December 1978, and analyses and records of iodines and particulates for the periods January - March and October - December 1978 indicated that the releases were within ETS 2.4.3 limits.
ETS 2.4.1.g limits the maximum activity in certain liquid radwaste tanks to 10 Ci.
The inspector reviewed the activity in the concen-trator which indicated that the radwaste tanks held less than 10 Ci (the radwaste tanks are frequently pumped into the concentrator).
e
A licensee representative stated that direct surveillance (rather than indirect via the concentrator)
of these tanks would be per-formed weekly.
No items of noncompliance were identified.
Records and Re orts of Radioactive Effluents The inspector reviewed the licensee's Semi-Annual Effluent Release Report covering the period January through June 1978 against the criteria given in Regulatory Guide 1.21 and Environmental Technical Specification (ETS) 5.6.2..ETS sections 2.4.l.h, 2.4.3.e, 2.4.3.f and 5.6.3.
1 require. additional reports if releases exceed certain values.
These values were not exceeded and additional reports were not required.
No items of noncompliance were identified.
Effl'uent Control Instrumentation Calibration'and Functional Tests Environmental Technical Specification (ETS) 2.4.2.f, requires that all liquid effluent radiation monitors be calibrated at least quarterly by means of a source which has been traceable to a National Bureau of Standards source.
Additionally, ETS 2.4.2.f requires that each liquid effluent monitor shall have a functional test
=
monthly and an instrument check prior to making a release.
ETS 2.4.4.d, requires that all waste gas effluent monitors be calibrated" at least quarterly by means of a known radi'oactive source which has been traceable to a National Bureau of Standards source.
ETS 2.4.4.d also requires that each gaseous effluent monitor shall have a functional test at least monthly and instrument check at least daily.
Calibration of'he stack gas radiation monitor performed using the licensee's procedure Nl-ISP-16-5 "Stack Gas Radiation Monitor
. Instrument Channel Calibration" were reviewed for the four quarters of 1978.
Calibrations of the off-gas radiation monitor performed using the licensee's procedure Nl-ISP-IC-6 "Off-Gas Line Radiation Monitor Instrument Channel Calibration" were also reviewed for the four quarters of 1978.
monthly functional tests performed on the stack gas and.off-gas monitors using procedures Nl-OP-25 and Nl-ST-
- W9 respectively were examined for December 1978 and January 197 Calibration of the liquid radwaste discharge monitor performed using the licensee's procedure Nl-ISP-IC-8 "Radwaste.'Discharge to Tunnel Radiation Monitor Instrument Channel Calibration" were examined. for the four quarters of 1978.
Monthly instrument channel'hecks of the liquid radwaste monitor performed using licensee procedure Nl-OP'-29 were reviewed for December 1978.'nd January 1979.
Alarm and Tri Set pints A monitoring point location, alarm setpoints and automatic isola-.
tion requirements are detailed in ETS 2.4.1.d, 2.4.3.d, table 2.4-3-and, table 2.4-.4.
Alarm and trip setpoints checked during
'he above calibrations and checks of the off-gas monitor; stack monitor and liquid radwaste monitor were found to be set conser-vatively.
Ph sical Installation During one of the facility tours, the inspector examined the liquid discharge monitor and stack monitor'ing system.
.Physical arrange-ment'f equipment,. air flow readings and background radiation levels. were observed.
The inspector noted that the required moni-toring equipment was operable.
No items of noncompliance were identified.
Procedures:
Technical'pecification 6.8.1 requires that written procedures be established, implemented and maintained that meet or exceed section 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of regulatory guide 1.33.
The following licensee procedures were reviewed:
Instrument Surveillance Procedures Nl-IS P-IC-5 Nl-ISP-IC-6 Nl-ISP-IC-8 Operating Procedures Nl-OP-25 Nl-OP-29 No items of noncompliance were identifie Testin of Containment Air Cleanin S stems Technical Specification 4.4.4 requires certain surveillance tests to be. performed on the Emergency Ventilation Systems including DOP tests, halogenated hydrocarbon tests, pressure drop tests and system operability.
The tests were performed at the time of the inspection.,
Preliminary results indicated that all aspects of the Emergency Ventilation System passed.
The surveillance of the Emergency Ventilation System will be reviewed at a subsequent inspection when the final test results and reports are available.
No items of noncompliance were identified.
Reactor Coolant llater ualit Chemical ual it Technical Specification 3.2.3 details the reactor coolant water quality requirements regarding chlorides and conductivity under various =steaming conditions.
Technical Specification 4.3.3 de-tails the reactor coolant monitoring and sampling requirements under various conditions.
Strip charts from the continuous conductivity monitor were examined for the period October 23 through November 10, 1978 and December 24, 1978 through January 13, 1979.
Results of laboratory analyses of reactor coolant for conductivity and chlorides were examined for the period October, 1978 through February,.
1979.
Radioactivit Limitations Technical Specification 3.2.4 limits total iodine activity in primary coolant to 25 microcuries per gram.
Technical Specifi-cation 4.2.4 requires that samples be taken and analysed for gross gamma activity once per 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and that isotopic analyses be performed once per month.
Results of the gross gamma analyses were examined for the period October 1978 through February 1979.
Results of the isotopic analyses, performed weekly by the licensee, were examined for the period October 1978 through February 1979.
No items of noncompliance were identifie Solid Radioactive Iltaste The inspector examined licensee records and shipping documents from 14 shipments of radioactive waste shipped during the period August 14, 1978 through February 14, 1979 (this constituted over 75% of the shipments made during this period).
Estimates of curie content and isotopic composition for the ship-ments were reviewed.
Three:shipments of greater than Type A quantities of material were examined for-compliance with 10 CFR 71.12.
The licensee uses several procedures and checklists as aids in
'aintaining and checking compliance with regulations.
A licensee
.representative stated that the solid waste loading procedures were being updated and would be revised by June, 1979.
No items of noncompliance were identified.
An offshift inspection of areas where work was in progress was conducted shortly after arrival at 8:30 p.m.. on February 6,
1979 to review radiation safety practices.
Several additional tours were conducted to review radiation work permits; work in radio-logically controlled areas; control of contaminated, radiation, and. high radiation areas; and to examine radiation monitoring equip'ment.
No items of noncompliance were identified.
Refuelin Pre arations The inspector reviewed the licensee'.s: radiation protection related plans for the March, 1979 refueling outage.
The licensee plans to augment his radiation protection staff with additional contractor technicians who meet the ANSI N18.1-1971 qualifications criteria.
The training staff has been augmented by contractor personnel to handle the additional workload in radiation worker training.
The licensee's planning and schedule for several of the more radiologically significant tasks were reviewed.
No items of noncompliance were identifie.
Exit Interview The inspector met with licensee management representatives (denoted in paragraph 1) at the conclusions of the sections of the inspection on February 9 and February 23, 1979.
The inspector summarized the purpose and scope of the inspection and the finding