IR 05000220/1986001
| ML17055B414 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/12/1986 |
| From: | Doerflein L, Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055B413 | List: |
| References | |
| 50-220-86-01, 50-220-86-1, NUDOCS 8603170307 | |
| Download: ML17055B414 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
DCS Nos.
50220-851212 50220-851215 50220-860104 50220-860113 50220-860118 50220-860201 50220-860208 Report No.
50-220/86-01 Docket No.
50-220 License No.
DPR-63 Priority Category C
Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York 13202 Facility Name:
Nine Mile Point Nuclear Station, Unit
I Inspection At:
Scriba, New York Inspection Conducted:
January 1 to February 23, 1986 Inspectors:
S.D.
Hudson, Senior Resident Inspector C.S.
Marschall Resident Inspector Reviewed by:
S il 8'.T.
Doerflei, Project Engineer date Approved by:
D i~
f'i i le, Chic, eactor date Projects Section o.2C, DRP Ins ection Summar
Ins ection on Januar 1 to Februar
1986 Re ort No.
50-220/86-01~: R" '" '" """"
Areas inspected included:
operational safety verification, physical security, plant tours, Licensee Event Reports, Emergency Notification System Reports, preparation for refueling, general employee training, and periodic and special reports.
Results:
No violations were identified.
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DETAILS 1.
Persons Contacted J. Aldrich, Superintendent, Operations T.
Roman, Station Superintendent The inspectors 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.
Summar of Plant Activities During the inspection period the plant coasted down from 87% to 73% power at the end of its fuel cycle.
On January 18, a plant shutdown required by Technical Specifications was conducted.
This event will be described in LER 86-01.
Normal power operation was resumed after startup on January 25',
1986.
3.
0 erational Safet Verification a.
Control Room Observation Routinely throughout, the inspection period, the inspectors indepen-dently verified plant parameters and equipment availability of engineered safeguard features.
The following items were observed:
Proper control room manning and access control; Adherence to approved procedures for ongoing activities; Proper valve and breaker alignment of safety systems and emergency power sources; Reactor control panel instrumentation and recorder traces; Reactor protection system instruments to determine that the required channels are operable; Stack gas monitor recorder traces; Core thermal limits; and Shift turnove b.
Review of Lo s and 0 eratin Records The inspectors reviewed the following logs and instructions:
Control Room Log Book Station Shift Supervisor's Log Book Station Shift Supervisor's Instructions Reactor Operation Log Book The logs and instructions were reviewed to:
Obtain information on plant problems and operation; Detect changes and trends in performance; Detect possible conflicts with Technical Specifications or regulatory requirements; Assess the effectiveness of the communications provided by the logs and instructions; and Determine that the reporting requirements of Technical Specifications are met.
No violations were identified.
4.
Observation of Ph sical Securit The inspector s made observations to verify that selected aspects of the plant's physical security system were in accordance with regulatory requirements, physical security plan and approved procedures.
The follow-ing observations relating to physical security were made:
The security force was properly manned and appeared capable of per-forming their assigned functions'rotected area barriers were intact - gates and doors closed and locked if not attended.
Isolation zones were free of visual obstructions and objects that could aid an intruder in penetrating the protected area.
Persons and packages were checked prior to entry into the protected are Vehicles were properly authorized, searched and escorted or controlled within the protected area.
Persons within the protected area displayed photo badges, persons in vital areas were properly authorized, and persons requiring an escort were properly escorted.
Compensatory measures were implemented during periods of equipment failure.
No violations were identified.
5.
Plant Tours During the inspection period, the inspectors made frequent tours of plant areas to make an independent assessment of equipment conditions, radio-logical conditions, safety and adherence to regulatory requirements'he following areas were among those inspected:
Turbine Building Auxiliary Control Room Vital Switchgear Rooms Cable Spreading Room Diesel Generator Rooms Reactor Building The following items were observed or verified:
a.
Radiation Protection:
Personnel monitoring was properly conducted.
Randomly selected radiation protection instruments were calibrated and operable.
Radiation Work Permit requirements were being followed.
Area surveys were properly conducted and the Radiation Work Permits were appropriate for the as-found conditions.
Fire Protection:
Randomly selected fire extinguishers were accessible and inspected on schedule
Fire doors were unobstructed and in their proper position.
Ignition sources and combustible materials were controlled in accor-
.dance with the licensee's approved procedures.
Appropriate fire watches or fire patrols were stationed when equip-ment was out of service.
c.
E ui ment Controls:
Jumper and equipment mark-ups did not conflict with Technical Specification requi rements.
Administrative controls for the use of electrical jumpers and equip-ment mark-ups were properly implemented.
d.
Vital Instrumentation:
Selected instruments appeared functional and demonstrated parameters within Technical Specification Limiting Conditions for Operation.
e.
Radioactive Waste S stem Controls:
Gaseous releases were monitored and recorded.
No unexpected gaseous releases occurred.
~ll Plant housekeeping and cleanliness were in accordance with approved licensee programs.
No violations were identified.
6.
Review of Licensee Event Re or ts LER'
The LER's submitted to NRC, Region I were reviewed to determine whether the details were clearly reported, including accuracy of the description of the cause and adequacy of the corrective action.
The inspectors also determined whether the assessment of potential safety consequences had been properly evaluated, whether generic implications were indicated, whether the event warranted on site follow-up and whether the reporting requirements of 10 CFR 50.73 had been met.
During this inspection period, the following LER's were reviewed:
LER No.
Event Date Subject 85-24 December 12, 1985 HPCI Initiation Due to High Reactor Water Level
While the plant was shutdown with the mode switch in refuel the control room operator was utilizing GE-MAC level indication to control level.
A turbine trip signal was generated from Yarway level instrumentation causing High Pressure Coolant Injection (HPCI) initiation.
Reactor water level was lowered using the Reactor Water Clean-up System and HPCI was reset.
This event and the difference in level instrument calibration will be reviewed with operators during requalification training'5-25 December 15, 1985 Reactor Power Reduction Due to Failure of Plant Process Computer With the reactor at 85% power a power reduction was initiated as required by Technical Specifications due to a failure of the plant process computer resulting in an inability to monitor core thermal parameters.
After backup core thermal limit calculations were completed which confirmed that all specified values were within prescribed limits reactor power was restored to its original level.
86-01 January 18, 1986 Design Calculations Mere Found Not in Compliance with FSAR During the preliminary engineering for replacement of the Emergency Con-denser steam supply piping and isolation valves the licensee discovered that design calculations were not in compliance with the FSAR.
New calculations for jet impingement loads during a steam supply pipe break inside the guard pipe indicated the actual loading conditions are two times greater than those used in the original design.
Based on the new calculations the plant was shutdown on January 18, 1986 from 82% power.
On January 23, 1986 the licensee presented information to the NRC to support a proposed license ammendment to permit operation until the end of the present cycle with the existing design inconsistencies.
The proposal was based on low probability of pipe rupture, fracture mechanics analysis and leak-before-break detection capability.
The licensee also proposed to issue a standing order which reduces the allowable increase in unidenti-fied coolant leakage into the drywell to 1 gallon per minute (previously
gallons per minute) in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
A waiver of compliance was issued by the NRC on January 24, 1986 and a license ammendment was issued on January 28, 1986 allowing continued operat,ion.
The inspector verified that the licensee had properly issued and implemented the standing order concerning reduced unidentified coolant leakage into the drywell.
No violations were identified.
Review of Emer ency Notification S stem Re orts The inspectors reviewed the following events which were reported to the NRC via the Emergency Notification System as required by
CFR 50.72.
The purpose of this review was to determine if the event was properly reported, if any generic implications exist, and if appropriate corrective
action has or will be taken.
Additionally, the significance of each event was evaluated to determine if on-site followup may be necessary to ensure that the safety significance of each event has been properly determined.
During the current inspection period, the following reports were reviewed:
Event Date Subject January 4,
1986 Automatic Initiation of Control Room Emergency Ventilation System due to radiation monitor spike.
January 13, 1986 Automatic Initiation of Control Room Emergency Ventilation System due to radiation monitor spike.
February 1,
1986
~
Stack gas sample pump trip.
The stack gas sample pump was found tripped by the licensee during a
routine sensor check and immediately restored to service.
The licensee plans to submit a change to Technical Specifications to clarify the allowed out of service time.
February 8, 1986 Stack gas sample pump trip.
No unacceptable reports were noted.
8.
, Safet S stem 0 erabilit Verfication January 18, 1986 Design calculations were found not in compliance with FSAR.
This event was described in LER 86-01, as discussed in the preceding paragraph.
On a sampling basis, the inspectors directly examined selected safety system trains to verify that the systems were properly aligned in the standby mode.
This examination included:
Core Spray Systems 811 and
Standby Liquid Control Sytem 9.
Review of Periodic and S ecial Re orts Upon receipt, the inspectors reviewed periodic and special reports to determine whether the safety significance of each event has been properly evaluated, to monitor plant operations, to determine if appropriate corrective action has been taken, and to ensure compliance with NRC reporting requirements.
During this inspection period, the following report was reviewed:
J
~Te Date Subject Monthly February 7,
1986 Operating Experience for January 1986.
No unacceptable reports were noted.
10.
Pre aration for Refuelin The inspectors witnessed the performance of selected aspects of fuel inspection, assembly, and storage to verify that:
Licensee inspectors were qualified and qualifications were current; Inspection procedures in use were current,and properly approved; Fuel inspection was conducted in accordance with procedure; Radiation protection procedures specific to fuel handling, assembly and inspection were approved, current and properly implemented; No violations were noted.
ll.
General Em loyee Trainin The inspector attended the licensee's requalification program for general employee and radiation protection training to evaluate the adequacy of the training and ensure compliance with NRC requirements.
The training covered administrative controls, industrial safety, security, quality assurance, fire protection, emergency response, and radiation protection.
A written examination must be passed with a minimum grade of 80% to be allowed unescorted access to the site.
The inspector found noticeable improvement in the quality assurance portion of the training.
An instructor was present to discuss those sections of the training which were presented on recorded material.
The licensee's programs were acceptable.
12.
Exit Interview At periodic intervals throughout the reporting period, the inspector met with senior station management to discuss the inspection scope and findings.
Based on the NRC Region I review of this report, it was determined that this report does not contain information subject to
CFR 2.790 restric-tion