IR 05000269/1978013
| ML19316A142 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/06/1978 |
| From: | Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19316A138 | List: |
| References | |
| 50-269-78-13, 50-270-7, 50-287-78-12, NUDOCS 7911280683 | |
| Download: ML19316A142 (11) | |
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NUCLEAR REGULATORY COMMISSION REGloN II
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230 PE ACHT RE E sT R E ET, N.W. sutTE 1217
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Report Nos.:
50-269/78-13, 50-270/78-12 and 50-287/78-12 Docket Nos.:
50-269, 50-270 and 50-287 License No.:
DPR-38, DPR-47 and DPR-55 Licensee: Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Oconee Units 1, 2 and 3 Inspection at: Oconee Nuclear Station Inspection conducted: June 13-16, 1978 Inspectors:
F. Jape J. L. Skolds Acccapanying Personnel:
W. T. Cottle
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Approved by:
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W Date R. CY Lewis, Nief/ g Reactor Projects Eection No. 2 Reactor Operations and Nuclear Support, ranch Inspection Summary Inspection on June 13-16, 1978 (Report No. 50-269/78-13, 50-270/78-12 and 50-287/78-12)
Areas Inspected:
Routine, unannounced inspection of licensee event reports, IE Bulletins and Circulars, refueling activities and maintenance activities.
The inspection involved approximately 60 man-hours on site by two NRC inspectors.
Results: Of the four areas inspected, no apparent items of noncompliance were identified in three areas; one apparent item of noncompliance (deficiency - failure to document receipt and storage location of new fuel assemblies (287/78-12-01) - Details I, pargraph 6) was identified in one area.
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. ,. ' ] - .- " - RII Rpt. Nos. 50-269/78-13, . 50-270/78-12 and 50-287/78-12 I-1 , / DETAILS I Prepared by: 4(tA48v _ _ b F. Jape, Reactor inspsetor ' Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: June 13-16, 1978 - w_ Approved by N 7/[ , > qq"' R. C. Lewis, Chief ~Date Reactor Projects Section No. 2 Reactor Operations and Nuclear . Support Branch i i
1.
Persons Contacted J. E. Smith, Station Manager
- R. M. Koehler, Superintendent of Technical Services
_ W. M. McClain, Procedures Engineer
- *a'. M. Harris, Operating Engineer
' J. N. Pope, Superintendent of Operations L. C. Evans, Assistant Shift Supervisor G. K. McAninch, Engineer
- D. J. Vito, Licensing Engiceer
- J. Davis, Superintendent of Maintenance B. C. Moore, Unit 3 Operating Engineer C. Burns, I&E Supervisor
- B. Martin, Planning Engineer
- R. T. Bond, Licensing and Projects Engineer S. DeGange, Engineer G. Evans, Engineer
- Denotes attendance at the Management Exit Meeting.
2.
Licensee Action on Previous Inspection Findings Not inspected.
3.
Unresolved Items
! Unresolved items are matters about which more information is required i in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. Unresolved items disclosed during this inspection are discussed in Details I, paragraph 6 and Details II, paragraph 5.
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\\ . j - ( _ RII Rpt. Nos. 50-269/78-13, 50-270/78-12 and 50-287/78-12 I-2 4.
Exit Interview The inspectors met with R. M. Koehler, Acting Station Manager and those denoted in paragraph 1, on June 16, 1978, to discuss the inspection finding.
The deficiency concerning failure to document receipt inspection of a new fuel assembly and the storage location of another assembly was discussed. Licensee management acknowledged this finding and stated that a review would be conducted. The remaining findings were discussed without significant comment.
5.
Plant Operations - Unit 3 Refueling Outage The inspector reviewed the schedule of actf.vities for the Unit 3 refueling outage and the licensee's provisions to test specific systems which were removed from a cormal ope ating status as a result of refueling activities. The controlling prc.cedures for unit startup, zero power physics testing and power esca:ation testing were also reviewed.
The purpose of these reviews was to ascertain that systems disturbed during the refueling outage would be returned to an operating status prior to plant startup and that plant startup and power escalation procedures require adherence to Technical Specifications.
No items of noncompliance or deviations were identified.
The inspector reviewed the procedure for, and witnessed the pe rfo rmance of, " Reactor Protection Channel 'A' RC Temperature Instrument Calibration", IP/3/A/305/1E.
Specific items verified included: (1) Procedure properly approved.
(2) Procedure consistent with Technical Specification and administrative control requirements.
(3) Test prerequisites completed.
(4) Test equipment required by procedure within calibration interval.
(5) Required data properly recorded.
(6) Procedure in use by test personnel.
(7) Test personnel meet ANSI Standard 18.1 qualification require-ments.
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.) , , [l RII Rpt. Nos. 50-269/78-13, 50-270/78-12 and 50-287/78-12 I-3 No items of noncompliance or deviations were identified.
6.
Plant Operation - Unit 3 Preparation for Refueling The inspector reviewed the licensee's procedures for new fuel receipt and inspection, fuel transfer, core verification, recycled fuel inspections, and fuel sipping. In addition, the inspector reviewed the decumentation for receipt and inspection of thirty-six Unit 3 Cycle 4 fuel assemblies. Of those inspected there were two instances in which the receipt inspection and storage of new fuel assemblies was not locumented as required by OP/0/A/1503/04 "New Fuel Assembly Inspection and Storage."
This finding represents apparent noncompliance (deficiency 287/78-12-01) with Technical Specification 6.4.lb which requires that the station be operated and maintained in accordance with approved procedures ard Section 4.2.6 of the Administrative Policy Manual which requires cat activities be conducted in accordance with the provisions of the app.. able procedure.
la addition, it was observed that for the majority of the receipt and in:pection documentation reviewed that the Fuel Handling Supervisor bek completed the checklist and signed as the activity supervisor.
Ie-re are no controls established to insure that a timely, independent - m. of the receipt and inspection documentation is conducted. This item is designated as unresolved item 78-13-02.
7.
Dyiew of Licensee Event Reports Tl e inspector performed an in-office review of nonroutine event l recorts listed below to verify that the report details met license re.uirements, identified the cause of the event, described corrective actions appropriate for the identified cause, adequately assessed the event and any generic implications.
In addition, for those reports marked with an asterisk, the inspector examined selected operating and l l maintenance logs and records, and internal incident investigation reports.
Personnel were interviewed to verify that the report accurately reflected the circumstances of the event, that the corrective action had been taken or responsibility assigned to assure completion and that the event was reviewed by the licensee as j stipulated in the Technical Specifications.
The following event reports were reviewed:
- RO-269/78-3, Keowee Unit 2 t ield Flashing Breaker Inoperable
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, _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , , . ., , -(,3 . .- RII Rpt. Nos. 50-269/78-13, , ' 50-270/78-12 and 50-287/78-12 I-4
- RO-269/78-6, Keowee Unit 2 Field Flashing Breaker Inoperable
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- RO-269/78-7, Keowee Unit 2 Field Flashing Breaker Inoperable
- RO-269/78-9, Keowee Unit 2 Field Flashing Breaker Inoperable
'20-269/78-10, Failure to Verify Operability of Keowec Unit 2 "-269/78-12, Keowee Unit 2 Inoperable
- R0-269/78-13, Primary-to Secondary Leak in Steam Generator 90-269/78-14, Keowee Unit 2 Field Flashing Breaker Inoperable E-270/78-4, NI out of Calibration
%-270/78-5, RB Narrow Range Pressure Transmitter Out-of-Calibration " -270/78-6, RC Leakage in Excess of GIPM , 270,/78-7, Fuel Movement with SFP Purge Filters Declared Inoperable ^'a-270/78-8, LPI System Cooler A Inoperable 40-287/78-9, 3HP-24 Inoperability R0-287/78-10, LPI System Cooler B Inoperable 8.
IEB 78-05 The licensee's response to IEB 78-05, dated May 25, 1978, was reviewed and found to be responsive to the requested action. No further action is planned for this item.
9.
IEB 78-06 i The licensee's response to IEB 78-06, dated June 7,1978, was reviewed ' and found to be responsive to the requested action.
The completion date for this item is estimated, by the licensee, to be November 30, 1978.
Therefore this item will be inspected during a subsequent inspection.
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) , i - . [) RII Rpt. Nos. 50-269/78-13, - 50-270/78-12 and 50-287/78-12 I-5 10.
IE Circulars The inspector verified that appropriate action had been taken by licensee management on the following IE Circulars: Circular No.
Subject 78-01 Loss of Well Logging Source 78-02 Proper Lubricating Oil for Terry Turbines 78-03 Packaging Greater Than Type A Quantities of Few Specific Activity Radioactive Material for Transport 78-04 Installation Error That Could Prevent Closing of Fire Doors 78-05 Inadvertent Safety Injection During Cooldown 78-06 Potential Common Mode Flooding of ECCS Equipment Rooms at BWR Facilities , 11.
Orifice Rod Assembly (ORA) Examination The latching devices on fuel assemblies with a cast locking cup were examined using an underwater TV camera, prior to the Oconee 3 Cycle 4 refueling. A commitment to examine these componeots was made to the NRC during a meeting on May 24, 1978, by representatives from Babcock and Wilcox (B&W), on each utility with a B&W Nuclear Plant.
The inspector reviewed the procedure for conducting the examination portion of the tape portion of the work.
Also a and witnessed a recording was viewed.
Final results of the examination were not available during the inspection period.
A tentative, preliminary finding indicated that no latching devices exhibited unacceptable Twenty-eight component were examined and of these, twenty-six wear.
contained an ORA and two contained a regenerative source during the preceding cycle.
12.
Viking Electrical Connector Examination The licensee was verbally informed on March 27, 1978, of a potential problem with Viking electrical connectors. The problem was identified at another nuclear facility and involved missing blinding pins in l i x ~> - ... - .. ---.. ~ .. ~,... - -. -. .
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' (m,! RII Rpt. Nos. 50-269/78-13, 50-270/78-12 and 50-287/78-12 I-6 unused conductor holes.
The licensee reviewed the problem as it related to the Oconee Nuclear Station and committed to examining safety related connectors with spare conductors during the Unit 3 Cycle 4 refueling outage.
The inspector reviewed the prepared procedure, T1/3/A/3001/3, Electrical Penetration Blinding Pin Inspection and Verification, provided for this work and had no comment.
The work was on-going during the inspection period and portions of the conductor examination were witnessed by the inspector. Final results were not available by the end of the inspection period. A report is to be provided by the licensee upon completion of this examination.
, 13.
Plant Tour A tour of accessible plant areas, including Unit 3 Reactor Building, was conducted. During the tour, observations were made regarding plant housekeeping, cleanliness, ongoing activities, radiation control practices and security practices. Housekeeping and cleanliness were found to be satisfactory.
Security and radiation control practices - re observed to be adhered to during the tour.
Station Directive 3.11.4 specifies the controls necessary to maintain the appropriate level of cleanliness of open systems. During the tour of Unit 3 Reactor Building the inspector noted that these controls were being observed over and around the open reactor vessel. A log was being maintained of all tools and materials taken in and out of the area.
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. , > , . , I (~) RII Rpt. Nos. 50-269/78-13, 50-270/78-12 and 50-287/78-12 II-1 '7!7!73 DETAILS II Prepared by: ? A , J. L. Skolds, Reactor Inspector Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: }3f6,1978 [7/ Reviewed by: ef-ief Date P./ Q ztIEg W"Section No. 2 Nuclear Support Reactor Operations and Nuclear Support Branch 1.
Persons Contacted Duke Power Company J. E. Smith, Station Manager +R. M. Koehler, Superintendent Technical Services J. N. Pope, Superintendent of Operations
- J. M. Davis, Maintenance Superintendent
- R. T. Bond, Project License Engineer
- W. M. Harris, Operating Engineer
- Bill Martin, Planning Engineer
- D. J. Vito, Associate Engineer / Licensing R. Gillespie, Associate Engineer S. Degange, Assistant Engineer Lanny Wilkie, Assistant Engineer G. P. Edens, Nuclear Station Support Engineer
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings Not inspected.
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. An unresolved item disclosed during the inspection is discussed in paragraph 5.
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'( ') RII Rpt. Nos. 50-269/78-13, 50-270/78-12 and 50-287/78-12 II-2 i l 4.
Exit Interview The inspector met with licensee representatives as indicated in paragraph 1 at the conclusion of the inspection on June 16, 1978. The inspector summarized the scope and findings of the inspection and discussed the unresolved item.
(paragraph 5) The licensee acknowledged the inspectors findings without comment.
5.
Maintenance The inspector conducted a review of the following maintenance: WR Unit Title 23324
Repair Seat Leakage on 3RC-19 24303
Replace "B" RTD 25203
3X10 Transformer Low Gas Pressure 26718
Power Range NI Calibration - 26?J7
Replace 3CF-15 26948
Repair 3CA Battery Charger s 27404
Furmanite FDW-101 27469
Investigate Statalarm 25A-15/15 28071
Repair plug leak on incore monitor 28222
Calibrate NI's 28239
Rx Bldg. Evacuation Alarm 28242
Investigate CRD Breakers 28282
Clean or replace letdown "A" filters 28585
Investigate Statalarm 2SA8 & 24 . 28808
Refurmanite FDW 37 28842
Repair B/B Leak on CA7 l . V" = ,
J - - . -. _ - . _.. _ _ _, _.. _ _ _ _ _ _ _ _ _ _. _. _ _ - l '. - ' . . , - . . a-s RII Rpt. Nos. 50-269/78-13, l \\_' 50-270/78-12 and 50-287/78-12 II-3 ! l 29253
Repack LPSW-21 ! l 29515
Repair leak on North SF filter 29531
Packing Leak LPSW-24 38403
Replacement of seal supply filters , t 53019
Install seal kit in snubber valve i3171
Investigate and Repair BS-2 53641
Doble Test 3X8 Transformer
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Inspect & PM 3TD-10, 3TC-8,
3 BIT-5, 3B2T-1 ~~ S 15
Repair or Replacement of Fire Stops 56386
Rotate Snubbar 180 22:2o
Perform Annual BWST Level Calibration a0857
Repair Tendon Caps on Rx Bldg.
003
Inspect and Test 3B RB Spray Pump 9.251
Vibration on 2A RB Spray Pump Th maintenance was reviewed to verify that: The limiting condition for operation was met while components - or systems were removed from service for maintenance.
The maintenance activities were accomplished using approved - procedures by qualified personnel.
- The maintenance activities were functionally tested or calibrated as necessary prior to returning the components or system to service.
The required administrative approvals were obtained prior - to initiating maintenance activities.
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_.. ._ __.. ,t . ' . -- , RII Rpt. Nos. 50-269/78-13, V] 50-270/78-12 and 50-287/78-12 II-4 The maintenance activities were inspected in accordance - with the licensee's requireaents.
, ' The inspector used one or more of the following acceptance criteria for the above items.
- Final Safety Analysis Report - ANSI 18.7-1972 - Technical Specifications - Nuclear Station Directives 3.3.5 and 3.3.15 - Administrative Policy Manual Section 3.3 and Section 4.7 M adings were acceptable with the exception of the items mted below.
a.
Work Request (WR) 54886 indicates that hydraulic suppressor #1-01A-0-550-R-5 was rotated 180 so that the reservoir is on the top of the suppressor. Conversaticas with plant personnel indicated , that the locking out on the suppressor was apparently loose and ,
vibration had caused the suppressor to turn over. It is not clear to the inspector that while the suppressor was in the inverted position, that it was fully operational.
The installation procedure for suppressors was not reviewed during the inspection however the surveillance procedure was reviewed and the procedure does not directly address the tightening of the locking nut. This item (78-13-03) will remain unresolved pending licensee review of suppressor installation and surveillance procedures and licensee determination of whether the suppressor was fully operational while in the inverted position.
I b.
Work Request (WR) 25203 indicated that the 3X10 Transformer on Unit 3 had a low gas charge.
The transformer was recharged to 9 psig at 75 C using procedure MP/0/A/2000/08. Step 11.4 of the ., l procedure states that the transformer is to be charged to 5 psig with transformer temperature near 25 C or 9 psig with transformer temperature 100 C or above.
Since there is no guidance in the procedure for temperatures between 25 C and 100 C, it is not clear that it was acceptable to charge the transformer to 9 psig at 75 C.
This matter is an open item (78-13-04) pending licensee review of MP/0/A/2000/08.
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