IR 05000220/1983006
| ML20023D342 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/13/1983 |
| From: | Sharon Hudson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20023D336 | List: |
| References | |
| 50-220-83-06, 50-220-83-6, NUDOCS 8305200392 | |
| Download: ML20023D342 (9) | |
Text
.
-
.
-.
..
.
,
DCN Numbers U. S. NUCLEAR REGULATORY COMMISSION
-
REGION I
50 220 830122 50 220 821018 50 220 821000
'
50 224 830315 Report No.
83-06
.
Docket No.
50-220 License No.
--
Priority Category Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York 13202 Facility Name:
Nine Mile Point Nuclear Station, Unit 1 Inspection At:
Scriba, New York Inspection Conducted:
March 1-31, 1983 Inspectors: Mb.
2.
S. D. Hudson, Senior Resident Inspector date date ate Approved by:
h/3 K
K. B. Kisi;ebChief, Reactor Projects Section 1C dat(e
-
Inspection Summary:
Inspection on March 1-31, 1983 (Report No. 50-220/83-06)
Areas Inspected:
Routine inspection by the resident inspector (82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br />).
Areas inspected included:
licensee action on previous inspection findings, plant tours, observation of physical security, plant maintenance, IE Circulars, Licensee Event Reports, periodic reports, and followup on spill of radioactive water.
Results:
No violations were identified in the areas examined.
Region I Form 12 (Rev. February 1982)
8305200392 830425 PDR ADOCK 05000220 G
_
.
_
.
-
.
.
.. -
.
.
.
_
_ _. _ _.
.
-
,
,
DETAILS
.
1.
Persons Contacted
.
J. Aldrich, Supervisor, Operations T. Breigle, Lead Q. C. Engineer W. Connolly, Supervisor, Q. A. - Operations K. Dahlberg, Site Maintenance Superintendent W. Drews, Technical Superintendent J. Duell, Supervisor, Chemistry and Radiation Protection
!
G. Gresock, Recirc Piping Replacement Project Manager E. Leach, Superintendent of Chemistry and Radiation Management D. Palmer, Manager, Nuclear Quality Assurance
!
T. Perkins, General Superintendent, Nuclear Generation T. Roman, Station Superintendent The inspector also interviewed other licensee personnel during the course of the inspection including shift supervisors, administrative, operations, health physics, security, instrument and control, and contractor personnel.
2.
Sumary of Plant Activities The plant remair.ed out of service throughout the inspection period for the replacement of the recirculation (recirc) system piping.
As of April 3,1983, the recirc piping replacement was reported as 99.9%
complete.
3.
Licensee Action on Previous Inspection Findings (Closed) UNRESOLVED ITEM (79-21-09):
The inspector reviewed ST-M3,
" Suppression Chamber - Drywell Relief Valve Exercising," Revision 5, dated November 11, 1982 and verified that it requires an operator to r
be stationed at the valves to observe the valves' operation.
(Closed) UNRESOLVED ITEM (79-21-01):
(a) The inspector reviewed Chicago Bridge and Iron Inspection Report No. 959 and 964, dated September 13,1979 and vuified that restraint #39-A2 for the Emergency Condenser Return Valves had been tested as required by IE Bulletin 79-02.
(b)TheinspectorvisuallyexcminedtheU-bolts on restraints #60-Rl-A, B, C, D, E, and F for the Emergency Condenser make-up water piping.
All of the bolts were found to be properly installed.
4.
Plant Tours (1) During the inspection period, the inspector made multiple tours of plant areas to make an independent assessment of equipment conditions, radiological conditions, safety, and adherence to regulatory requirements. The following areas were inspected:
__ _. _.,
_
__ _
.
.
.
- _ _ _
.
.
.
,
Control Room
-
--
Turbine Building
--
Auxiliary Control Room
--
Vital Switchgear Rooms
--
Yard Areas
--
Radwaste Area
--
Diesel Generator Rooms
--
Screen House
--
Reactor Building
--
Drywell
--
(2) The following items were observed or verified:
(a)
Radiation Protection:
Personnel monitoring was properly conducted.
--
Randomly selected radiation protection instruments
--
were calibrated and operable.
Area surveys were conducted and the Radiation Work
--
Pemits were appropriate for the as-found conditions.
Routine radiation surveys were conducted in the Drywell.
--
'
Radiation Work Pemit (RWP) requirements were being
--
followed.
On March 21, 1983, the inspector noticed that one individual had not signed out on RWP 8146 after leaving the drywell.
The inspector infomed the contractor drywell radiation i
protection coordinator. He detemined that the individual's exposure was 15 mrem, which was then added to the RWP. The
individual was instructed to ensure that exposure data is entered on the RWP when leaving a radiation area.
(b) Fire Protection:
Fire doors were unobstructed and in their proper position.
--
Ignition sources and combustible materials were controlled
--
in accordance with the licensee's approved procedures.
-
-
.,
..
'
Fire watches were posted during periods when smoke
--
detection equipment was out of service.
.
Randomly selected fire extinguishers were accessible
--
and inspected on schedule.
(c) Equipment Controls:
Jumpers and equipment mark-ups did not conflict with
--
Technical Specification requirements.
.
Mark-ups were performed in accordance with approved
--
procedures.
The inspector independently verified that the following
--
mark-ups had been properly conducted by observing the position of breakers and/or valves:
BMU #1289 on #12 Emergency Service Water Pump BMU #1276 on #12 Emergency Ventilation Fan The licensee had recently begun to use a new log sheet for recording the tags associated with each mark-up. This fonn does not provide a separate space for documenting the independent verification of the mark-up. The inspector discussed the requirement for documenting the verification with the Operations Supervisor.
He stated that the space to be initialled by the individual placing the tag would also be initialled by the individual perfonning the independent verification.
Subsequently, the inspector reviewed several current mark-ups.
Each was found to be properly completed, including the independent verification.
(d) Radiation Waste System Controls:
On March 4,1983, the inspector witnessed Radiation Survey
- 75723 perfonned on a shipment of contaminated waste material.
No Federal limits were exceeded.
On March 29, 1983, the inspector examined a shipment of contaminated equipment and determined that it was properly labelled prior to its departure from the site.
The inspector also reviewed Radiation Survey #1WS-002 and the Radioactive Shipment Records.
(e)
Review of Logs and Operating Records:
The inspector reviewed the following logs and instructions l
for the period March 1-31, 1983:
Control Room Log Book
--
.
-
,
-
-
,,
,
-
,a
- -
.
Station Shift Supervisor's Log Book
--
Station Shift Supervisor's Instructions
--
Recirc Piping Replacement Project Log
--
Ncnconfonnity Report #1399-K-241 through K-286
--
The logs and instructions were reviewed to:
Obtain infomation on plant problems and operation;
--
Detect changes and trends in perfomance;
--
Detect possible conflicts with technical specifications
--
or regulatory requirements; Detemine that records are being maintained as required;
--
Detemine that the reporting requirements of technical
--
specifications are met.
No violations were identified.
5.
Plant Maintenance The inspector examined portions of various safety-related maintenance activities. Through direct observation and review of records, he detemined that:
These activities did not violate the limiting conditions for
--
operation.
..
Required adninistrative approvals and tagouts were obtained prior
--
to initiating the work.
Approved procedures were used or th: ac? Nity was within the
--
" skills of the trade."
Appropriate radiological controis were pHoerly implemented.
--
Quality Control hold points were observed.
--
Welders were properly qualified.
--
The proper weld filler wire was used.
--
During this inspection period, the following maintenance activities were examined:
Welding on FW 150-9, FW 15D-19, and FW 150-22
--
. -
_
.
._
._.
.
.
.
,
Replacing rubber goods on CRD scram pilot valves #38-15 and #38-35
--
No violations were identified.
6.
Followup on Spill of Radioactive Water On March 15, 1983, the licensee conducted a flush of the filters in the reactor water cleanup (RWCU) system. The filters were flushed to the RMCU ftlter sludge tank.
Prior to the flushing operation, the tank was pumped down and an operator was stationed locally to observe the tank's level. indication. At an indicated level of 26% full, the tank overflowed to the Reactor Building ventilation duct, causing both channels of the Reactor Building ventilation monitor to alarm.
This monitar also isolated the normal Reactor Building ventilation and initiated the emergency ventilation system.
The licensee evacuated the Reactor Building and the flushing operation was immediately secured. The contaminated water leaked out of the ventilation ducts at several elevations of the Reactor Building. The highest airborne activity detected was 74% of MPC at Reactor Building
elevation 237'.
There were no personnel exposure or contamination as i
a result of the event.
Based on monitoring of the stack effluent, there was no release of radioactive material to the environment.
The resident inspector was on site at the time of the spill and observed the licensee's actions from the Control Room.
He immediately verified that the stack monitor was not increasing, the emergency ventilation system was operating and the normal Reactor Building ventilation was secured.
He independently confirmed'that the event was properly classified as an Operational Event in accordance with the Emergency Action Procedures.
The event was reported by the licensee to the NRC via the Emergency Notification System (red phone) and as Licensee Event Report 83-05.
The cause of the event was the failure of the RWCU filter sludge tank level indicator.
To prevent reoccurrence, the licensee plans to require the tank level indicator to be calibrated prior to adding water to the
,
'
filter sludge tank. The licensee's actions to implement this will be exanined during a future inspection (50-220/83-06-01).
No violations were identified.
7.
Licensee Action in IE Circulars The inspector reviewed the licensee's actions on the IE Circulars listed below to verify that the Circulars were received by licensee management, that a review for applicability was performed, and that appropriate corrective action has been taken.
.
- - - - - --
,
-.m,r,,.
, - -,
,
,. _,, -
.,
.
..
IEC 79-19, " Loose Locking Devices on Ingersoll Rand Pumps"
--
The licensee's review dated February 15, 1983 stated that pumps of this type are not used at the station.
No further action is required.
IEC 79-20, " Failure of GTE Sylvania Relays"
--
The licensee's review dated February 15, 1983 stated that no relays of the specified model are used at the station.
No further action is required.
IEC 79-23, " Motor Starters and Contactors Failed to Operate"
--
The licensee's review dated February 15, 1983 stated that no contactors or starters of the specified model and serial number are used at the station.
No further action is required.
These Circulars are closed.
8.
Review of Licensee Event Reports (LER's)
The LER's submitted to NRC, Region I were reviewed to verify that the details were clearly reported, including accuracy of the description of the cause and adequacy of the corrective action. The inspector detemined whether further infomation was required from the licensee, whether generic implications were indicated, and whether the event warranted onsite followup.
The following LER's were reviewed:
LER No.
Event Date Subject 83-01 January 22, 1983 Wind direction sensor misalignment
,
83-02 October 18, 1982 Tritium found in intake water sample
'
83-03 October 1982 Lower limit of detection sensitivity not met 83-05 March 15, 1983 Spill of radioactive water No violations were identified.
l 9.
Review of Periodic Reoort l
The following report was reviewed to detemine that the reporting requirements of Technical Specifications are being met and that plant l
operations are accurately reported:
l Monthly Operating Report for February 1983
--
No violations were identified, o
... ~ ~
.
THIS PAGE, CONTAINING, NOT FOR PUBLIC DISCL95URE IS INTENTIONALLY LEFT BLANK
!
l
.
$
i a
}
i
,
4 i
!
,
i
!
i e
_
l
!
!I.
l
!
!
!
!
!
i I
...., - - - -,. - - - ~, ~, - - -
.
.
,
11. Exit Interview At periodic intervals during the course of the inspection, meetings were held with senior station management to discuss the inspection scope and findings.
_ _ _, _ _ _ _.
-
-
-
-
-