IR 05000220/1982021
| ML20028C498 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/27/1982 |
| From: | Sharon Hudson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028C494 | List: |
| References | |
| 50-220-82-21, NUDOCS 8301100277 | |
| Download: ML20028C498 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION Region I 82-21 Report No.
50-220 Docket No.
DPR-63 C
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License No.
Priority Wm 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: November 1-December 4, 1982 Inspectors: M. bb
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S. D. Hudson, Senior Resident Inspector dite signed date signed date signed Approved by:
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H B. Kisteh Chief, Reactor Projects
'dat( signed Section 1C Inspection Summary:
Inspection on November 1-December 4, 1982 (Report No. 50-220/82-21)
Areas Inspected:
Routine, onsite regular and backshift inspections by the resident inspector (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). Areas inspected included:
licensee action on previous inspection findings, plant tours, observation of physical security, plant maintenance, quality assurance, IE Circulars, material procurement and storage and review of periodic reports.
Results: No violations were identified in the areas inspected.
8301100277 821227 PDR ADOCK 05000220
PDR Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted J. Aldrich, Supervisor, Operations T. Breigle, Lead Q. C. Engineer K. Dahlberg, Site Maintenance Superintendent W. Drews, Technical Superintendent J. Duell, Supervisor, Chemistry and Radiation Protection G. Gresock, Safe End Project Manager E. Leach, Superintendent of Chemistry and Radiation Management D. Palmer, Supervisor, 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.
Licensee Action on Previous Inspection Findings (Closed) VIOLATION (81-16-01):
Failure to approve a temporary change to a procedure. The inspector reviewed the minutes of the Site Operations Review Committee Meeting No. 81-67 dated June 8, 1981 and verified that the procedure received the proper review within the seven days allowed by Technical Specification. He also reviewed procedure RPSTP-2, " Full Core Control Rod Scram Timing," Revision 2, dated September 28,1981 and verified that the changes were incorporated as a pemanent revision to the procedure.
(Closed)
INSPECTOR FOLLOWUP ITEM (82-01-01):
Licensee to conduct periodic review of ST-sal. The inspector verified that the licensee had issued FST-sal, " Ionization, Photo-Electric, Infra-red and Heat Detector Test," Revision 0, dated August 17, 1982. This procedure replaces ST-sal, " Smoke and Heat Detector Test" and now includes all of the smoke and heater detectors added as a result of the recent fire protection modifications.
3.
Plant Tours (1) During the inspection period, the inspector made multiple tours of plant areas to make an independent assessment of e'quipment conditions, radiological conditions, safety and adherence to regulatory requirements.
The following areas were inspected:
Control Room
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Turbine Building
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Auxiliary Control Room
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Vital Switchgear Rooms o
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Yard Areas
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Radwaste Area Diesel Generator Rooms
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Screen House
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Reactor Building
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Drywell
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(2) The following items were observed or verified:
(a) Radiation Protection:
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Personnel monitoring was properly conducted.
Randomly selected radiation protection instruments were
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calibrated and operable.
Area surveys were conducted and the Radiation Work Permits
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were appropriate for the as-found conditions.
Routine radiation surveys were conducted in the Drywell.
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Radiation Work Permit requirements were being followed.
Glove bags were installed prior to grinding on highly
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contaminated surfaces.
(b)
Fire Protection:
Fire doors were unobstructed and in their proper position.
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Ignition sources and combustible materials were controlled
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in accordance with the licensee's approved procedures.
Fire watches were posted during periods when smoke detection
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equipment was out of service.
Randomly selected fire extinguishers were accessible and
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inspected on schedule.
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On November 4, 1982, the inspector noticed that the monthly preventative maintenance inspection of C02 fire extinguisher
- 171 located on the refueling floor had not been perfomed for the month of October. All other portable extinguishers on the refueling floor had been checked as required. On September 16, 1982, a new procedure, FPM-M1, " Fire Protection System-Fire Department Monthly Routine," Revision 0, was issued.
CO2 fire extinguisher #171 was inadvertently deleted from the list of portable extinguishers. When informed of the error, the licensee promptly inspected the extinguisher and corrected the procedure. The inspection of the extinguisher found that it was properly charged.
(c) Equipment Controls:
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Jumpers and equipment tagouts did not conflict with Technical Specification requirements.
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The tagouts were perfomed in accordance with approved procedures.
The inspector noticed that the mark-up index sheet showed that BMU# 69423 for the Auxiliary Control Room Halon System was still outstanding when it was in fact cleared. The Chief Shift Operator verified that the mark-up had been cleared on November 9,1982 and corrected the index shect.
The inspector independently verified that the following
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tagouts had been properly conducted by observing the position of breakers and/or valves:
BMU# 135763 on #13 Reactor Building Closed Loop Cooling Pump BMU# 68879 and 68974 on the Fire Detection System (d) Radioactive Waste System Controls:
On November 10, 1982, the inspector witnessed radiation survey
- 70487 of radioactive waste shipment #1182-121-L prior to its departure from the site to verify that applicable Federal limits were not exceeded. The shipment consisted of 7.6 Curies of solidified concentrated waste. The inspector also examined the truck and trailer to verify that they were properly labelled.
(e) Review of Logs and Operating Records:
The inspector reviewed the following logs and instructions for the period November 1,1982 through December 4,1982:
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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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Safe End Project Log
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Task Person-Rem Sumary Report
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Nonconformity Report #1399-K-81 through K-106
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The logs and instructions were reviewed to:
Obtain infomation on plant problems and operation;
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Detect changes and trends in perfomance;
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Detect possible conflicts with technical specifications or regulatory requirements;
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Detemine that records are being maintained and reviewed as required, and Detemine that the reporting requirements of technical
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specifications are met.
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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 the physical security plan were made:
The security force was properly manned and appeared capable of
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perfoming their assigned functions.
Protected area barriers were intact - gates and doors closed and
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locked if not attended.
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 are I l
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Persons within the protected area displayed photo-identification
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badges, persons in vital areas were properly authorized, and persons requiring an escort were properly escorted.
No violations were identified.
5.
Plant Maintenance The inspector examined portions of various safety-related maintenance activities. Through direct observation and review of records, ha detennined that:
These activities did not violate the limiting conditions for operation.
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Required administrative approvals and tagouts were obtained prior to initiating the work.
Approved procedures were used or the activity was within the " skills
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of the trade."
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Appropriate radiological controls were properly implemented.
Quality Control hold points were observed.
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Welders were properly qualified.
The proper weld filler wire was used.
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During this inspection period, the following maintenance activities were examined:
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Dye penetrant examination on #11 recirc pump suction elbow
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Weld crown reduction on FW-13S-7 Welding on FW-13S-4 and FW-llD-SEN
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No violations were identified.
6.
Licensee Action on IE Circulars The inspector reviewed the IE Circulars listed below to verify that the Circulars were received by licensee management, that a review for applicability was perfonned, and that appropriate corrective action has been taken.
IEC 80-03, " Protection from Toxic Gas Hazards"
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The licensee's review indicated that no corrective action was require..
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7 IEC 80-08, "BWR Technical Specification Inconsistency - RPS Response Time"
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The licensee's review indicated that the RPS response time is not addressed in Nine Mile Point's Technical Specifications. No further action is required.
IEC 80-09, " Plant Internal Communications System"
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The licensee's review indicated that the dial telephones and intercom and paging system automatically transfers to emergency power upon loss of normal power.
Pre-operational testing of the portable radio comunication system was perfomed to verify that use of these radios does not cause spurious actuation of electrical relays. No further action is required.
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IEC 80-10. " Failure to Maintain Environmental Qualification of Equipment"
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The licensee's review indicated that the control of replacement parts for safety-related equipment is currently addressed in the station's administrative procedures. No further action fi: required.
IEC 80-14 " Radioactive Contamination of Plant Demineralized Water System"
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The licensee's review indicated that check valves are installed on interconnections with systems that operate at a higher pressure than the demineralized water system to prevent contamination due to back flow.
All demineralized water hose connections are located inside the restricted area where drinking is prohibited. No further action is required.
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IEC 80-18, "10 CFR 50.59, Safety Evaluations for Changes to the Radioactive
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Waste Systems" This Circular required no specific action. A licensee memorandum indicates that it was routed to the members of the corporate Nuclear Licensing group and the Chaiman of the Site Operations Review Committee for infomation.
The above Circulars are closed.
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Implementation of Quality Assurance (Q.A.) Surveillance Program In addition to specific Q. A. hold points in the Controlled Work Instructions governing the replacement of the recirculation system piping, on September 13,
1982 the licensec established a Schedule of Surveillance of Q. A. activities of its prime contractor, Newport News Industrial (NNI). The purpose of these j
surveillances is to provide a programmatic examination of NNI's overall Q. A.
program implementation.
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The inspector reviewed Surveillance Report S.R. 2999-4 perfomed October 26, 1982 on Weld Metal Issue and the Nonconfomance Report NR 82-41 dated -
November 1,1982 to verify that:
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The content of the report clearly defines its scope and the results;
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The frequency was in accordance with established schedule;
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Appropriate followup actions had been taken, and
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The audited organization's response was in writing, timely, and
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adequately addresses the findings.
No violations were identified.
8.
Material Procurement and Storage The inspector examined selected records for pieces of the replacement recirculation systen piping to ensure that safety-related material is procured, inspected and stored in accordance with approved procedures.
For the pieces of piping selected (Tube #9B,10A,10B,14A), the inspector reviewed the records listed below to verify the proper imp 1'ementation of APit-14, " Procedure for Control of Material and Service," Revision 5, dated August 26, 1982, and proper certification of Class 1 piping:
Purchase Order #54236 Material Record of Chemical and Physical Properties Receipt Inspection Reports Certification of Weld Filler Metal Independent Chemical Analysis of Piping Solution Annealing Certification Radiographic and Ultrasonic Test Reports Vendor Certificate of Compliance Conditional Release #82-16 and 82-21 The inspector examined piping stored at the fab shop and in the storeroom to verify that the requirements of ANSI N45.2.2 were met.
The inspector also examined pieces #10A, and 10B in the drywell to verify that the apnropriate Quality Assurance " Hold" tags were attached. The
" Hold" tag was missing from piece #10B.
Q. A. records show that the tag had been attached to the piping and apparently fell off during handling.
The licensee promptly completed its review of the vendors radiographs thereby clearing the condition requiring the use of a " hold" tag.
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At the off-site fab shop, the inspector noted that the serial number and heat number had been destroyed by a 1-inch connection on a piece of recirc piping labelled "#12 discharge elbow." The inspector informed the lic'ensee's Q. A. representative and will examine the licensee's action to permanently mark this piece of piping during a future inspection.
(50-220/82-21-01)
No violations were identified.
9.
Review of periodic Reports The following reports were reviewed to detennine that the reporting requirements of Technical Specifications are being met and that station operations are accurately reported:
Monthly Operating Reports for September and October 1982
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10.
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.
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