IR 05000269/1987019
| ML16161A833 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/24/1987 |
| From: | Bryant J, Peebles T, Skinner P, Wert L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A832 | List: |
| References | |
| 50-269-87-19, 50-270-87-19, 50-287-87-19, NUDOCS 8707060273 | |
| Download: ML16161A833 (8) | |
Text
-
epgk RECZ UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report Nos:
50-269/87-19, 50-270/87-19, and 50-287/87-19 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name:
Oconee Nuclear Station Docket Nos.:
50-269, 50-270, and 50-287 License Nos.:
DPR-38, DPR-47, and DPR-55 Inspection Conducted: May 12 - June 15, 1987 Inspectors:
Approved by:
T. A. Peebles, Section-ChiefDaeSgd t
C. Beryant oDate Signed H Skinner/
(Date Signed Lnstei the araW oer atosmineaneasteiln e
Sgnerd safety feature lineups, follow-up of events, and participation in a site dril Results:
No violations or deviations were identified in the areas covered in this repor *3707060273 870625 PDR ADDCK 05000269
REPORT DETAILS Licensee Employees Contacted
- M. S. Tuckman, Station Manager T. B. Owen, Maintenance Superintendent
- R. L. Sweigart, Operations Superintendent J. M. Davis, Technical Services Superintendent C. L. Harlin, Compliance Engineer
- F. E. Owens, Assistant Engineer, Compliance T. C. Matthews, Assistant Engineer, Compliance
- B. K. Millsaps, Maintenance Services Engineer
- M. D. Clardy, Planning and Scheduling Engineer Other licensee employees contacted included technicians, operators, mechanics, security force members, and staff engineer Resident Inspectors
- J. C. Bryant P. H. Skinner
- L. D. Wert
- Attended exit intervie.
Exit Interview The inspection scope and findings were summarized on June 15, 1987, with those persons indicated in paragraph 1 abov The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio.
Licensee Action on Previous Enforcement Matters Not Inspecte. Unresolved Items No unresolved items were identified during this inspectio.
Plant Operations The inspectors reviewed plant operations throughout the reporting period to verify conformance with regulatory requirements, technical specifications (TS),
and administrative control Control room logs, shift turnover records, and equipment removal and restoration records were
reviewed routinel Interviews were conducted with plant operations, maintenance, chemistry, health physics and performance personne Activities within the control rooms were monitored on an almost daily basis. Inspections were conducted on day and on night shifts, during week days and on weekends. Some inspections were made during shift change in order to evaluate shift turnover performanc Actions observed were conducted as required by Operations Management Procedure 2-The complement of licensed personnel on each shift inspected met or exceeded the requirements of TS. Operators were responsive to plant annunciator alarms and were cognizant of plant condition Plant tours were taken throughout the reporting period on a routine basi The areas toured included the following:
Turbine Building Auxiliary Building Units 1,2, and 3 Electrical Equipment Rooms Units 1,2, and 3 Cable Spreading Rooms Station Yard Zone within the Protected Area Standby Shutdown Facility Keowee Hydro Station During the plant tours, ongoing activities, housekeeping, security, equipment status, and radiation control practices were observe Unit 1 began the report period at 87% power as limited by RBCU/LPI heat removal capability and continued at that level until May 19 when the unit was taken off line at 11:55 p.m. to repair an oil leak and to degas the main transformer. Unit 1 was held at hot shutdown until it was again placed on line at 7:20 a.m. on May 21 and returned to 87% powe Unit 2 operated at 88% power throughout the report period, as limited by high steam generator level Unit 3 began the report period at 100% power and remained at that power throughout the report perio No violations or deviations were identifie.
Surveillance Testing Surveillance tests were reviewed by the inspector to verify procedural and performance adequac The completed tests reviewed were examined for necessary test prerequisites, instructions, acceptance criteria, technical content, authorization to begin work, data collection, independent verification where required, handling of deficiencies noted, and review of completed wor The tests witnessed, in whole or in part, were inspected to determine that approved procedures were available, test equipment was calibrated, prerequisites were met, tests were conducted according to
procedure, test results were acceptable and systems restoration was complete Surveillances witnessed in whole or in part:
IP/305/3 RPS "C" On-Line (Unit 1)
PT/0/A/1103/15 Reactivity Balance, Estimated Critical Rod Position IP/305/3 RPS "C" On-Line, CRD Breaker Portion (Unit 2)
IP/305/3 RPS "C" On-Line Test (Unit 3)
PT/O/A/0400/4 SSF D/G ASW Performance Test No violations or deviations were identifie. Maintenance Activities Maintenance activities were observed and/or reviewed during the reporting period to verify that work was performed by qualified personnel and that approved procedures in use adequately described work that was not within the skill of the trad Activities, procedures and work requests were examined to verify proper authorization to begin work, provisions for fire, cleanliness, and exposure control, proper return of equipment to service, and that limiting conditions for operation were me *
Maintenance witnessed in whole or in part:
MP/O/A/1210/4 Rev. 7 -
Refurbish Actuator on ICCW-10 Repairs to Unit 1 Condensate Booster Pumps WR 99549 B Replacement of Teledyne Seismic Switch WR 52695 F 1A1 SSRHDT Valve Repair No violations or deviations were identifie.
Unit 3 Failed Fuel On 5 June, the licensee determined, based on increasing levels of Iodine-131 in reactor coolant samples, that Unit 3 has a small amount of failed fue Initial levels of activity (about 0.49uCi/ml dose equivalent 1-131) indicated that about 0.26% of the fuel has failed (approximately 100 pins).
A set of temporary precautionary operating guidelines was issued and operation at 100% power was continue RCS activity decreased to a level of 0.27uCi/ml 1-131 dose equivalent by June 8, which corresponds to about 0.12% of failed fue Along with careful monitoring of primary activities, secondary system activities were closely monitored since the unit has been operating with a very small, steady steam generator tube leak of about 1X10-4 gpm).
Secondary system Iodine-131 activities remained less than MDA with the exception of moisture separator drain tanks where levels of 1.3X10-7 uCi/ml were measure The resident inspectors will continue to stay abreast of development.
Inspection of Open Items The following open items are being closed or will be left open, as indicated below, based on review of licensee reports, inspection, record review, and discussions with licensee personnel, as appropriat (Closed)
LER 269/86-06:
Anticipatory Trip From 48% Power Due to Feedwater Pump Trip Caused by Check Valve Failur The event was initiated by trip of a heater drain pump and failure of its check valve to close completely, leaving a back flow path through the heate This resulted in loss of suction and tripping of a condensate booster pump and subsequent tripping of the feedwater pump on low suction pressure. Only one feedwater pump was in operatio Repairs have been complete (Open)
LER 269/86-13:
Improper Review and Approval of Procedures Due to Management/Quality Assurance Deficiency:
All improperly approved procedures are under review for proper approval signature (Open)
LER 269/87-03:
Inadequate Overpressure Protection For The Auxiliary Steam Header. Temporary corrective actions are complet Awaiting design chang (Open) LER 270/82-10: Stuck Suction Relief Valve On "2B" MFWP After A Reactor Tri This event resulted in plant modifications to establish a feedwater pump recirculation flow path to the condenser hot wells. Unit 3 modification has been completed. All mechanical work has been completed on Units 1 & The electrical work is scheduled for EOC 10 on Unit 1 and EOC 9 on Unit (Closed) LER 270/86-06:
Reactor Trip by Anticipatory Trip Due to Loss of Feedwater Pumps. Apparently the problem was caused by a malfunction of the turbine header pressure Hand/Auto controller in the ICS. Replacement of this component appears to have corrected the proble (Closed)
LER 270/87-04:
Reactor Trip on High Steam Generator Leve This trip, and others in the past, were caused by anomalies in the BTU limit circuitry of the IC The circuitry has now been modified on all three units so that BTU limit inputs are bypassed with the reactors above 25% power. The purpose of the trips is maintain steam quality for turbine protection at low powe (Closed) LER 287/84-01:
Load Shed Source B Fuse Block Discovered Not Installed -
Manually Pulled by Person Unknow Immediate corrective action was to install locks on fuse block panel Locks were verified at the time by resident inspector NSM 1426 has now been completed providing dedicated fuse blocks for each local load shed trip relay, with a local indicating light for position indication and computer alarms for loss of load shed control powe (Open)
LER 287/85-05:
Anticipatory Reactor Trip on Loss of Main Feedwater Due to Failure of Regulating Valve to Operate Properl Unit 3 has been modified by addition of a valve positioner on the regulator valve. Modification is in place and operable but not in final configuration. Units 1 and 2 have not been modifie (Closed)
LER 287/87-01:
Loose Parts and Reduced Reactor Coolant Flow Due to Suspected Equipment Failur Problems with 38 reactor coolant pump were discussed in Report No. 50-287/86-33 and subsequent report (Closed)
LER 287/87-07:
Isolation of all Three Reactor Building Cooling Units During Startup. This event was discussed in detail in Report No. 50-269,270,287/87-1 (Open)
269,270,287P2185-02: Discrepancies in Weights of Limitorque Valve Operator DPC letter of 12/31/86 states that the B&W Owners Group has determined that B&W does not have all the information needed to resolve this issu DPC will pursue acquisition of information from Limitorque directl Schedule for completion has not been determine (Closed)
P2182-01:
Containment Combustible Gas Contro Recommended modifications to the hydrogen recombiner controls were completed in April 198 (Closed)
P2186-09:
Failure of Coils in Certain Class 1E Motor Starters and Contactors Supplied by Westinghous DPC Potentially Reportable Item report of August 25, 1986, states that equipment search revealed none of the identified coils are in use or in stock at Ocone (Closed)
IFI 269,270,287/86-21-01:
Inspection of Wiring on EQ Limitorque Operators. This item is being closed since the same inspection is required by TI 2515/75, Inspection of Limitorque Motor Valve Operators Wiring to Determine if Wiring is Environmentally Qualifie (Closed) IFI 269,270,287/86-24-02:
EQ Documentation of Reactor Building Cooling Units. A DPC letter of May 21, 1987, certifies the qualification of Texaco Premium RB lubricant as environmentally qualified for the RBCU (Closed) IFI 270/85-20-04:
Long Term Temporary Modification The three month review is now in a computer program which, if a response is not received within two weeks, sends a letter to the responsible engineer's section hea If the section head's response is not received in two weeks, a letter is sent to the department superintenden Licensee stated that in almost two years of operation, only one letter has gone to a superintenden (Closed)
IFI 287/84-03-02:
Corrective Actions to Load Shed Circuits. This item is the same as LER 287/84-0.
Semiannual Effluent Release Reports (90713)
Technical Specification 6.6.1.4 requires the licensee to submit within 60 days of January 1 and July 1 of each year, routine radioactive effluent release reports covering the operation of unit during the previous six months of operatio Additionally, the Radioactive Effluent Release Reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the station during each calendar quarter. The assessment of the radiation doses shall be performed in accordance with the Offsite Dose Calculation Manua The inspector reviewed the Semiannual Radiological Effluent Release Report for the period July 1 - December 31, 198 The review included an examination of the liquid and gaseous effluent release data as well as dose estimate data. Selected data from this report and previous reports are presented in Table Although a slight increasing trend for the three unit station was noted for liquid releases containing fission and activation products from 1984 to 1986, the other quantities of radionuclides released and the annual dose estimates did not follow any significant trends from 1984 to 198 The gaseous releases for each unit at Oconee during 1986 were slightly above the 1985 gaseous release average which was based on data collected from 21 operating PWRs in Region I The liquid releases per unit at Oconee did not vary significantly from the 1985 Region II liquid release averag Table 1 Oconee Nuclear Station Semiannual Effluent Release Summary, 1984-1986 Year 1984 1985 1986 No. Abnormal Releases Liquid
2
b. Gaseous
0
Liquid Waste Released (gallons)
1.80 x 10" 1.88 x 10'
1.18 x 10'
Activity Released (Curies) Liquid Fission and Activation Products 1.58 x 100 4.16 x 100 5.85 x 10'
2. Tritium 1.28 x 10'
1.24 x 10'
1.34 x 10'
3. Gross Alpha
0
b. Gaseous 1. Noble Gas 2.28 x 10'
2.35 x 10'
2.43 x 10'
2. Halogens 1.33 x 10-1 4.95 x 10-'
3.39 x 10-2 3. Tritium 4.17 x 102 4.28 x 10'
4.31 x 101 4. Gross Alpha
0
Dose Estimate (mrem) Liquid Whole-body (adult)
2.81 x 10-'
1.84 x 10*
1.40 x 100 b. Gaseous 1. Whole-body 9.73 x 10-2 7.11 x 10-1 8.73 x 10-2 2. Skin 2.25 x 10-'
2.08 x 1-'
2.51 x 10-'