IR 05000220/1982005
| ML20053C964 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/14/1982 |
| From: | Doerflein L, Sharon Hudson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20053C959 | List: |
| References | |
| 50-220-82-05, 50-220-82-5, NUDOCS 8206030227 | |
| Download: ML20053C964 (9) | |
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DCN: 50220-820323 U.S. NUCLEAR REGULATORY COMMISSION Region I Report No.
82-05 Docket No.
50-220 C
License No.
DPR-63 Priority Category
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Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York 13202 Nine Mile Point Nuclear Station, Unit 1 Facility Name:
Inspection at:
Scriba, New York Inspection conducted:
April 4, 1982 to May 2, 1982 Inspectors:
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d. u. Hudson, Resident Inspector date signed dR~NL skhi L. T. DoerfJein, Resident Inspector date signed date signed Approved by:
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fi. B. Kister, Chief, Reactor Projects d' ate / signed Section 1C Inspection Summary:
Inspection on April 4, 1982 to May 2, 1982 (Re) ort No. 50-220/82-05)
Areas Inspected:
Routine, onsite regular and Jackshift insp:ctions by the resident inspectors (94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br />). Areas inspected included:
licer.:n action on previous inspection findings, operational safety verification, physical security, plant tours, surveillance tests, emergency preparedness, plant operatiLns to support repair of reactor vessel safe ends, followup on significant event, and licensee event reports.
Results:
No violations were identified in seven of the eight areas examined. One violation was identified in one area.
(Failure to follow administrative procedures for tagging)
8206030227 820517 gDRADOCK 05000220 PDR Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted J. Aldrich, Supervisor, Operations W. Chambers, Security Investigator K. Dahlberg, Site Maintenance Superintendent W. Drews, Technical Superintendent J. Duell, Supervisor, Chemistry and Radiation Protection F. Hawksley, Supervisor, Mech. Maintenance E. Leach, Superintendent of Chemistry and Radiation Management T. Perkins, General Superintendent, Nuclear Generation R. Raymond, Supervisor, Fire Protection T. Roman, Station Superintendent P. Volza, Emergency Planning Coordinator The inspectors also interviewed and talked with other licensee personnel during the course of the inspection including shift supervisors, administrative, operations, health physics, security, instrument and control and contractor personnel.
2.
Licensee Action on previous Inspection Findings (Closed) VIOLATION (81-17-01): Removal of all automatic isolation protection on both Emergency Cooling Systems. The inspector reviewed Operating Procedure OP-13. " Emergency Cooling System," Revision 10, dated February 16, 1982 to verify that a caution had been added to the operating procedure prohibiting the use of the key lock by-pass switches during maintenance or troubleshooting activities during power operations.
The inspector also examined a copy of the Technical Specification Cross Reference Guide. This was issued to all holders of controlled copies of Technical Specification to assist the user in determining that all applicable Technical Specifications have been considered prior to alternating plant conditions. Training was conducted, including meeting with senior staticn management, to stress the safety significance of instrumentation associated with safety related equipment.
3.
Operation Safety Verification a.
Control Room Observations Routinely throughout the inspection period, the inspector independently verified plant parameters and equipment availability of engineered safeguard features to ensure the following items were observed:
Proper control room manning;
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Availability and proper valve line-up of safety systems;
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Availability and proper alignment of onsite and offsite emergency
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power sources; Reactor control pcnel indications and bypass switches;
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Stack monitor recorder traces, and
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Liquid poison tank level and concentration.
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Selected lit annunciators were discussed with control room operators to verify that the reasons for them were understood and corrective action, if required, was being taken.
Shift turnovers were observed to ensure proper control room and shift manning on both day and backshifts. Shift turnover checklists and log review by the oncoming and off-going shifts were also observed by the inspector.
b.
Review of Logs and Operating Records The inspector reviewed the following logs and instructions for the period April 4, 1982 through May 2, 1982:
Control Room Log Book
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Station Shift Supervisor's Log Book
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Station Shift Supervisor's Instructions
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Licensee Event Report Log
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Reactor Operating Log
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The logs and instructions were reviewed to:
Obtain information on plaint problems and operation;
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Detect changes and trends in performance;
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Detect possible conflicts with technical specifications or
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regulatory requirements; Determine that records are being reviewed as required;
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Assess the effectiveness of the communications provided by the
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logs and instructions, and Determine that the reporting requirements of technical
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specifications are met.
No violations were identified.
4.
Observation of Physical Security The inspector made observations and verified during regular and off-shift hours that selected aspects of the plants physical security system were in accordance with regulatory requirements, physical security plan and approved procedures. The following observations relating to physical security plan were made:
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The security force on both regular and off-shifts were properly
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manned and appeared capable of performing their assigned functions.
Protected area barriers were intact - gates and doors closed and
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locked if not attended.
Comunication checks were conducted. Proper comunication devices
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were available.
Isolation zones were free of visual obstructions and objects that
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could aid an intruder in penetrating the protected area.
Persons and packages were checked prior to entry into the protected
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area.
Vehicles were properly authorized, searched and escorted or controlled
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within the protected area.
Persons within the protected area displayed photo-identification
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badges, persons in vital areas were properly authorized, and persons requiring escort were properly escorted.
The inspector noted that several photo-identification badges had been defaced so severely that proper identification of the individual on the badge was questionable. After the inspector brought this to the licensee's attention, the badges were cleaned and the General Superintendent issued a instruction to all personnel that security badges should not be defaced.
Compensatory measures were implemented during periods of equipment
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failure.
No violations were identified.
5.
Plant Tours During the inspection period, the inspector made multiple tours of plant areas to make a independent assessment of equipment conditions, radiological conditions, safety and adherence to regulatory requirements. The following areas were among those inspected:
Turbine Building
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Auxiliary Control Room
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Vital Switchgear Rooms
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Yard Areas
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Radwaste Area
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Diesel Generator Rooms
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Screen House
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Reactor Building
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Drywell
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The following items were observed or verified:
a.
Radiation Protection:
Personnel monitoring was properly conducted.
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Randomly selected radiation protection instruments were
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calibrated and operable.
Radiation Work Permit requirements were being followed.
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Area surveys were properly conducted and the Radiation Work
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Permits were appropriate for the as-found conditions.
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Fire Protection:
Randomly selected fire extinguishers were accessible and
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inspected on schedule.
Fire doors were unobstructed and in their proper position.
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Ignition sources and combustible materials were controlled in
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accordance with the licensee's approved procedures.
c.
Equipment Controls:
Jumpers and equipment markups did not conflict with Technical
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Specification requirements.
Conditions requiring the use of jumpers received prompt licensee
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attention.
Administrative controls for the use of jumpers and markups
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were followed.
On April 13, 1982, the inspector noticed that RMU 134277 on #12 Emergency Ventilation Fan had not been independently verified by a licensed operator as required by Administrative Procedure APN-7,
" Procedure for Control of Equipment Markups, Etc.," Revision 7, dated January 5, 1982. The failure to follow the requirements of APN-7 is a violation.
(50-220/82-05-01)
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When informed of the violation, the licensee immediately sent a licensed operator to independently verify that the markup was prcperly placed. An entry was made in the Shift Supervisor's
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Instructions reminding all operators of the requirement for independent verification of markups. The inspector has reviewed 10 additional markup sheets since April 13 and noted that independent verification had been completed in each case.
The inspector independently verified that martups #RMU 134275,
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134276, and 134277 had been properly placed.
d.
Radioactive Waste System Controls:
Gaseous waste recorders were operable.
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The radioactive waste system was operated in accordance with
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approved procedures.
The inspector witnessed the survey of radioactive waste shipment #0482-114A prior to its departure from site to verify that applicable Federal limits were not exceeded. The inspector also reviewed the Radioactive Shipment Record to determine that it was properly completed. The inspector verified that the shipment was labelled as " low specific activity."
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Housekeeping:
The inspector noticed a gradual deterioration of general cleanliness in the Reactor Building. After this condition was discussed with the licensee, a marked improvement was noted.
One violation was identified during the plant tours.
6.
Surveillance Testing The inspector witnessed surveillance test ST-M4, " Emergency Diesel Generator Manual Start and 1 Hour Rated Load Test," Revision 8, dated June 26, 1981, performed on April 6, 1982. Observations were made to determine that:
Surveillance procedures conform to technical specification requirements
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and have been properly approved.
Test instrumentation is calibrated.
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Limiting conditions for operations for removing equipment from service
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are met.
Testing is performed by qualified personnel.
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Surveillance schedule is met.
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y Test results met technical specification requirements.
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Equipment is properly restored to service following the test.
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No violations were identified.
7.
Emergency Preparedness On April 29, 1982, the resident inspectors witnessed the semi-annual Health Physics Emergency Plan Training Drill. The scenario was that of a dropped fuel bundle during refueling. Only station personnel were involved; county, state, and NRC officials were notified but their participation was teminated after the initial phone call. The inspectors observed portions of the licensee response from the control room, technical support center, post accident sampling station and with a downwind survey team to detemine that:
The licensec responds in accordance with approved procedures and plans;
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The response seems coordinated, orderly, and timely;
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The licensee is using designated individuals to evaluate its responses;
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A critique is held following the drill, and
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The drill meets the training requirements of the emergency plan
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procedures.
Although some minor shortcomings were noted by the drill observers, the overall performance of the licensee was satisfactory.
On April 5, 1982, the inspector witnessed the quarterly inventory and testing of emergency equipment in the downwind survey kits. The inventory was completed in accordance with Emergency Plan Procedure EPP-10. " Emergency Equipment Inventories and Checklist," Revision 6, dated June 16, 1981.
No violations were identified, i
8.
Plant Operations to Support The Repair of Reactor Vessel Safe Ends l
The inspector examined portions of various plant operations conducted to support the repair of the reactor vessel safe ends. Through direct observation and review of records, he determined that:
Each operation was conducted in accordance with approved procedures.
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Appropriate radiological controls were properly implemented.
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Required administrative approvals and tag outs were obtained prior
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to initiating the work.
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During this inspection period, the following activities were examined:
Removal of control rod blades from the reactor to the spent fuel pool;
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Chemical decontamination of #13 reactor recirculation pump;
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Dye penetrant examination of #15 recirc pump casing to discharge
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piping weld, and Radiographic examination of #15 recirc pump casing to discharge
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piping weld.
No violations were identified.
9.
Followup on Significant Event On April 2, 1982, the licensee performed a ultrasonic (UT) examination on the pump casing to discharge piping weld on all five recirc pumps. Two circular indications were detected on #15 recirc pump discharge piping and one on #13 recirc pump discharge piping. On April 8, radiography was perfomed to verify the UT indications. The results were inconclusive in that they did not show any geometry that could have caused the UT indication nor did they show any linear indications.
Next, the #15 pump was chemically decontaminated and disassembled.
On April 19, dye penetrant (PT) examination on the inside of #15 recirc pump to discharge piping weld showed an intermittent circular indication between the 7 and 9 o' clock position and 2 maller indications at approximately 12 o' clock. A replica of one of these indications was made on April 27.
Preliminary analysis of the replica indicated that the indications are due to intergranular stress corrosion cracking.
Number 13 recirc pump was also decontaminated and disassembled. A partial PT examination performed on April 29 on the inside of the discharge piping to pump casing weld showed a h" transverse indication and a 3" intemittent circular indicatien. These indications are still under review by the licensee at this tiu.
10.
Review of Licensee Event Reports (LER's)
LER's submitted to NRC, Region I were reviewed to verify that the details were clearly reported, including the accuracy of the description of the cause and adequacy of the corrective action. The inspector detemined whether further information was required from the licensee, whether generic implications were indicated, and whether the event warranted onsite followup.
The following LER's were reviewed:
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LER No.
Event Date Subject 82-09 March 23, 1982 Leakage from reactor vessel safe-ends This event is described in detail in IR 82-04.
82-10 March 23, 1982 Failure on analog trip card for D/W high pressure The licensee has not completed troubleshooting the defective analog trip card. The cause of the failure and possible generic implications will be evaluated by the inspector during a future inspection.
(50-220/82-05-02)
11.
Exit Interview At periodic intervals during the course of the inspection, meetings were held with senior facility management to discuss the inspection scope and findings.
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