IR 05000220/1982007
| ML20054J572 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/11/1982 |
| From: | Doerflein L, Doerflin L, Sharon Hudson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20054J568 | List: |
| References | |
| 50-220-82-07, 50-220-82-7, IEB-79-15, IEB-79-18, NUDOCS 8206290265 | |
| Download: ML20054J572 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION Region I Report No.
82-07 Docket No.
50-220
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C License No.
DPR-63 Priority Category
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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 May 3-3, 1982 Inspectors:
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ww-5. D. Hudson, sr / Kesident Inspector defe signed A
8!9R.
L. T. Doerflei Resident Inspector date Isigned date signed (o !//[72.--
Approved by:
H.' B. Kister7 Chief, Reactor Projects dite ' signed
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Section 1C Inspection Summary:
Inspection on May 3-31, 1982 (Report No. 50-220/82-07)
Areas Inspected:
Routine, onsite regular and backshift inspections by the resident inspectors (141 hours0.00163 days <br />0.0392 hours <br />2.331349e-4 weeks <br />5.36505e-5 months <br />). Areas inspected included:
licensee action on previous inspection findings, operational safety verification, physical security, surveillance testing, plant maintenance, licensee action on IE Bulletins and Circulars, and periodic reports.
Results: No violations were identified in the areas inspected.
Region I Form 12 (Rev. April 77)
8206290265 820614 PDR ADOCK 05000220 G
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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 R. Orr, Supervisor, Nuclear Security T. Perkins, General Superintendent, Nuclear Generation 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's Action on Previous Inspection Findings (Closed)
INSPECTOR FOLLOWUP ITEM (76-22-01):
Licensee completion of audit and upgrading of radiation protection procedures. The licensee has issued procedures N1-RTP-38, " Emergency Ventilation and Control Room Air Treatment System HEPA and Charcoal Bed Filter," and S-RTP-2, " Procedure for the fitting of Respirators," and has revised procedure RP-1, " Access and Radiological Control," to include exposure authorization. The inspector also noted that the licensee has issued or revised several procedures involving analysis of samples and calibration of monitors and portable instruments.
(Closed)
INSPECTOR FOLLCWUP ITEM (76-22-04):
Review respiratory protection program. Since inspection 76-22, the licensee has issued a procedure for fitting and testing of face masks. The inspector reviewed procedure no.
S-RTP-2, " Procedure for the Fitting of Respirators," Revision 1, dated April 10,1981, and noted it contained both the qualitative and quantitative methods used to insure adequate individual fit of respirators. The inspector detennined that the licensee's procedure for the fitting of respirators meets the requirements in section 8.5 of NUREG-0041.
(Closed) UNRESOLVED ITEM (77-02-07): Disposition of SRAB audit findings.
The inspector reviewed the 1976 SRAB Emergency Plan audit and noted that the current Emergency Plan either incorporates the audit findings or the findings are no longer applicable. The inspector also reviewed EPP-ll, " Review and Revisions of Site Emergency Plan and Procedures," held discussions with licensee personnel and detennined that the licensee's present procedure for followup of audit findings and recommendations appears adequate.
(Closed) VIOLATION (79-07-03):
Failure to follow Radiation Work Permit (RWP)
Procedures. The inspector verified that the licensee has implemented I i
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appropriate corrective action. A radiation protection technician is now required to check that all high radiation area gates and doors are closed and locked. This check is performed three times a week. The licensee is also conducting audits of RWP's on a daily basis to ensure compliance with the RWP requirements and to issue "on the spot" correction of any deficiencies observed. Approximately 30 RWP's audited were perfomed each week.
Beginning May 24, 1982, the licensee will begin RWP audits on the backshifts also.
The proper use of RWP's is included in the radiation protection training given to all radiation area workers.
(Closed)
INSPECTOR FOLLOW ITEM (80-19-01): On November 12, 1980, the licensee conducted a fire drill with the participation of an off site fire company.
Several minor deficiencies were noted by the drill observers. The inspector reviewed each deficiency listed in the Fire Drill Report dated November 30, 1980 and discussed the corrective action taken with the Emergency Planning Coordinator. Many of the problems were due to poor comunications inside the plant. A new radio base station and antenna system appears to have corrected these problems.
Several key personnel in the emergency organization become overly involved in small details of the response. Their role as supervisors and coordinators appears to have been developed in subsequent drills. The inspector also verified that Emergency Plan Procedures EPP-2, " Fire Fighting,"
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and EPP-5, " Personnel Accountability," has been revised to include recommended l
improvements of the emergency response actions.
(Closed)
INSPECTOR FOLLOW ITEM (80-21-01): On December 21, 1980, the licensee conducted a medical emergency drill with the participation of Oswego Hospital staff. The inspector reviewed each deficiency listed in the Medical Emergency Drill Report dated January 19, 1981 and discussed the corrective action taken with the Emergency Planning Coordinator. The inspector verified that the New York State Nuclear Hotline directly connecting the plant with the State and County Warning Points has been installed, a qualified Emergency Medical Technician has been assigned to each shift, and Emergency Planning Procedure EPP-4, " Personnel Injury or Illness," has been revised to include recommended improvements of the emergency response actions.
(Closed) VIOLATION (81-25-01): A radioactive waste shipment of solidified evaporator bottoms was found to contain free standing liquid. This shipment had been solidified using urea formaldehyde. The inspector verified that the licensee has discontinued the use of urea formaldehyde and is using cement as
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the solidification media for shipments of evaporator bottoms. Resin and
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filter sludge shipments are mechanically de-watered prior to shipping.
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INFRACTION (78-05-01):
Inability to implement downwind surveys.
(Closed)
INFRACTION (78-05-02): Failure to maintain emergency equipment.
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(Closed) DEVIATION (78-05-03):
Failure to have an emergency plan training
and retraining program established in the form of lesson plans and schedules.
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(Closed)
INFRACTION (78-05-04):
Failure to review and update emergency plan and implementing procedures.
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(Closed)
INFRACTION (78-05-05):
Implementation of unreviewed, unapproved procedures.
The licensee has increased management attention towards the emergency planning program by hiring an Emergency Planning Coordinator and an assistant.
In addition, the licensee has rewritten it's emergency plan and procedures, revised procedure APN-10F, " Emergency Preparedness Training,"
and upgraded it's emergency kits. These and other areas were examined during an Emergency Preparedness Appraisal during August 1981, and those areas needing improvement were identified at that time. These items from Inspection 78-05 are closed for administrative purposes as the Emergency Preparedness Appraisal findings represent the deficiencies in emergency preparedness under the new plan.
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; Availability and proper alignment of onsite and offsite emergency
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power sources; Reactor control panel 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 w'.th 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.
No violations were iden?ified.
b.
Review of Logs and Operating Records The inspector reviewed the following logs and instructions for the period May 3-31, 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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Protective Tag Record Log
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Jumper Log
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Stack Weekly Sample Data Log
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The logs and instructions were reviewed to:
Obtain information on plant 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 maintained and reviewed as required;
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Assess the effectiveness of the connunications provided by the logs
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and instructions, and Determine that the reporting requirements of technical
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specifications are met.
No violations were identified.
c.
Plant Tours (1) 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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(2) The following items were observed or verified:
(a) Radiation Protection:
Personnel monitoring was properly conducted.
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Randomly selected radiation protection instruments
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were calibrated and operable.
Radiation Work Permit requirements were being followed.
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Area surveys were properly conducted and the Radiation
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Work Permits were appropriate for the as-found conditions.
(b) 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
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in accordance with the licensee's approved procedures.
(c) Housekeeping / Cleanliness Conditions:
No unacceptable conditions were identified in the area of
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housekeeping and cleanliness.
No violations were identified.
d.
Tagout Verification The inspector independently verified that the following tagouts were properly conducted by observing the position of breakers, switcher and/or valves:
RMU #134295 on No. 102 Emergency Diesel Generator
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RMU #134412 on No. 12 Liquid Poison Pump
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BMU #34862 on the Liquid Poison System
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RMU #134320 on the Shutdown Cooling System
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RMU #134402 on the Containment Spray System
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BMU #69347 on the Emergency Diesel Generator Cardox System
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No violations were identified.
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Occurrence Report Review The inspector reviewed occurrence reports 82-14 to 82-18 to determine that the licensees problem identification system is functioning properly.
No violations were identified.
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Radioactive Waste Systems Controls The inspector witnessed survey #N64076 of radioactive waste shipment
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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 on both regular and off-shifts were properly manned
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and appeared capable of performing their assigned functions.
Protected area barriers were intact - gates and doors closed and locked
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i' not attended.
Communication checks were conducted.
Proper communication devices
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were available.
Isolation zones were free of visual obstructions and objects that could
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aid an intruder in penetrating the protected area.
Persons and packages were checked prior to entry into the protected area.
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Vehicles were properly authorized, searched and escorted or controlled
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within the protected area.
Compensatory measures were implemented during periods of equipment
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failure.
Persons within the protected area displayed photo-identification badges,
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persons in vital areas were properly authorized, and persons requiring a escort were properly escorted.
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During this inspection period it was noted_that personnel donning
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protective clothing, for various tasks, were leaving their photo-
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identificatien badges / key cards on badge racks or attaching them to the Radiatien Work Permit (RWP) prior to entering the work area. The inspector brought this to the licensee's attention, pointing out how the theft of one of these key cards could allow an unauthorized person to gain access to a vital area. The licensee immediately issued a
memorandum to all personnel instructing them, that when donning protective clothing, to wear their photo-identification badge on the inside of the protective clothing. The inspector noted that since this memorandum was issued the badge racks at the drywell entrance and the refuel floor airlock have been removed and that no further instances of attaching photo-identification badges to RWP's have been observed. The inspector will continue to monitor licensee progress in this area during future inspections.
No violations were identified.
5.
Surveillance Testing The inspector witnessed surveillance test N1-ICP-CAM, " Constant Air Monitor Alignment," Revision 1, dated February 22, 1982, performed May 14, 1982 on
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the Reactor Drywell Monitor. 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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Equipment is properly restored to service following the test.
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No violations were identified.
6.
Plant Maintenance i
The inspector examined portions of various safety related maintenance activities. Through direct observation and review of records, he determined that:
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These activities did not violate the limiting conditions for operation.
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Required administrative approvals and tag outs were obtained prior to
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initiating the work.
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g Approved procedures were used or the activity was within the " skills of
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the trade."
Appropriate radiciogical controls were properly implemented.
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Equipment was properly tested prior to returning it to service.
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Quality Control hold points were observed.
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Ignition / fire prevention controls are appropriate.
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During this inspection period, the following maintenance activities were examined:
WR #16272. Replacement of Intermediate Range Monitor No. 16 detector.
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WR #17441, Repair of the air start relay on Emergency Diesel Generator
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No. 102.
WR #17452, Replace oil seal on No. 12 Liquid Poison Pump.
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The inspector also examined portions of various activities conducted to support the repair of the reactor vessel safe ends to verify that each operation was conducted in accordance with approved procedures, appropriate radiological controls were properly implemented and that the required administrative approvals and tagouts were obtained prior to initiating the work. The following activities related.to the safe end repairs were observed:
Draining of the reactor vessel annulus and installation of the vessel
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shield platfonn.
Removal of the reactor vessel head.
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Ultrasonic Testing (straight beam) of fl5 Recirc Pump suction line.
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Chemical decontamination of the recirc pump suction lines.
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In a letter dated May 7, 1982, NRR approved the licensee's chemical decontamination process for the recirculation system piping from the reactor vessel outlet to the recirc pump discharge valve. However, due to problems installing the hot tap connections in the recirc piping and with the vessel outlet. seal plug leaking, decontamination did not being until May 20, 1982. With NRR concurrence, the licensee had to modify the decontamination process, using a stagnant decontamination of the recirc pump suction piping, periodically draining and refilling this piping. The effectiveness of the decontamination as measured by decontamination factors, obtained by comparing the before and after radiation levels on contact with the recirc piping using a directional probe, varied. The decontamination factors for the recirc piping ranged from 1.6 to 77.
No violations were identifie.
7.
Licensee Action on IE Bulletins and Circulars a.
IE Bulletins The inspector reviewed licensee action on the following Bulletins to verify that:
Written response was within the stated time period and contained
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the required infomation.
Written response includes adequate corrective action commitments.
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Licensee management forwarded copies of the written response to
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appropriate onsite management.
Information discussed in the licensee's written response was
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accurate.
Corrective action taken by the licensee was as described in the
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written response.
The following Bulletins are closed:
IEB 79-15, Deep Draft Pump Deficiencies
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In letters dated September 14, 1979 and November 13, 1979, the licensee provided the information on deep draft pumps used at Nine Mile Point Unit 1 as requested by the Bulletin. The inspector reviewed the response and had no additional questions in this area.
IEB 79-18, Audibility Problems Encountered on Evacuation of
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Personnel from High-Noise Areas In it's response dated September 19, 1979, the licensee stated that the paging system, with the exception of those portions located in inaccessible areas, had been tested for proper operation and that the alarm system in the drywell and condenser areas would be tested at the next refueling outage. The inspector reviewed the data from procedure N1-PM-SA4, " Paging System," completed on September 1, 1979 and Work Request No's. 11476, 11488, 11489 and 11490 to verify that the announcement system was tested and that inoperable speakers were repaired. The inspector also reviewed the Station Shift Supervisors log and work request no. 14783 to verify that the announcement system in the condenser area and the drywell was tested, and the necessary repairs were made on May 29, 1981 and July 1, 1981 respectivel _____
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b.
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 performed, and that appropriate corrective actions were taken.
IEC 79-24, Proper Installation and Calibration of Core Spray
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Pipe Break Detection Equipment on BWR's.
The inspector noted that the licensee still sets the Core Spray Sparger Differential Pressure alann trip point at 5 psig increasing. To provide an accurate and reliable Core Spray pipe break detection system the licensee has ordered and received new differential pressure transmitters and trip units to replace the existing ones, however, the engineering design has not been completed. A licensee representative further stated that they are considering a change to the Technical Specifications to delete the surveillance on the Core Spray header differential pressure (A P) instrumentation. This Circular remains open pending installation of the new transmitters and trip units or a revision to the Technical Specificacions deleting the Core Spray header oP instrumentation.
IEC 79-12, Potential Diesel Generator Turbocharger Problem. The
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licensee plans to revise procedures MP-22.1, " Maintenance of Diesel Generators," and MP-22.2, " Maintenance of Diesel Engine and Auxiliaries," to ensure that anytime the lube oil system is refilled, the circulating oil pump is in operation for at least 30 minutes and the strainer box is full before the diesel generator is started. The licensee also plans on revising
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procedure N1-MPM-C6, " Diesel Generators Engine Inspection," to include a visual inspection of the oil cooler for leaks. This Circular remains open pending completion of these proposed changes to the maintenance procedures.
8.
Review of Periodic Reports The following reports were reviewed to detennine that the reporting requirements of Technical Specifications are being met and that plant operations are accurately reported:
Monthly Operating Reports for March and April 1982.
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No violations were identified.
9.
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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