IR 05000269/1988005

Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes

ML20148E456
Person / Time
Site:	Oconee
Issue date:	03/21/1988
From:	Peebles T, Skinner P, Wert L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148E450	List: IR 05000269/1988005 ML20148E445
References
50-269-88-05, 50-269-88-5, 50-270-88-05, 50-270-88-5, 50-287-88-05, 50-287-88-5, NUDOCS 8803250157
Download: ML20148E456 (8)

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NUCLEAR REGULATORY COMMISSION

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Report Nos:

50-269/88-05, 50-270/88-05, and 50-287/88-05 Licensee:

Duke Power Company 422 South Church Street Charlotte, NC 28242

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Docket Nos.:

50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 Facility Name:

Oconee Nuclear Station Inspection Conducted:

bruary 17 - March 16, 1988 P. H. Ski n~~ 28 /2 c3fd}fW Inspectors-

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, Senio Resident Inspector tam Signed

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L a/DArr Lh'D.~%ert,Residen Inspector Gat ( Sigried Approved by:

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_J /J r [y T. Al Peebles, Section Chief Date' Signed Division of Reactor Projects SUMMARY Scope:

This routine, announced inspection involved resident inspection on-site in the areas of operations, surveillance, maintenance, physical security, engineered safeguards features lineups, nonroutine reporting and design changes.

Results: Of the seven areas inspected, no violations were identified.

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8803250157 880321 PDR ADOCK 05000269 O

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

• M. Tuckman, Station Manager J. Davis, Technical Services Superintendent W. Foster, Maintenance Superintendent T. Glenn, Instrument and Electrical Support Engineer

• C. Harlin, Compliance Engineer J. McIntosh, Administrative Services Superintendent

• F. Owens, Assistant Engineer, Compliance R. Sweigart, Operations Superintendent L. Wilkie, Integrated Scheduling Superintendent Other licensee employees contacted included technicians, operators, mechanics, security force members, and staff engineers.

NRC Resident Inspectors P. H. Skinner

• L. D. Wert

• Attended exit interview.

2.

Exit Interview The inspection scope and findings were summarized on March 16, 1988, with those persons indicated in paragraph 1 above.

The inspectors described the areas inspected and discussed in detail the inspection findings listed below.

Dissenting comments were not received from the licensee.

Proprieta ry information is not contained in this report.

Item Number Status Description / Reference Paragraph 270/87-44-01 Closed Failure to Document Component Verification Actions LER 269/87-05, Rev. 1 Closed Potential Tripping of High Pressure Injection Pumps During Starting LER 270/86-01 Closed Turbine / Reactor Trip Due to Inadequate Communication of a

Relay Design Feature LER 270/87-05 Closed Fire Wall Breached Causing Violation of Technical Specification w

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2.

269,270,287/87-48-01 Closed Correction of Potential Loss of Siphon

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Effect on Emergency Condenser Cooling Water (ECCW) System.

3.

Licensee Action on Previous Enforcement Matters

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(Closed) Violation. 50-270/87-44-01:

Failure to Document Component Verification Actions.

Corrective actions as documented in the licensee's

letter of December 31, 1987, have been reviewed and found acceptable.

The resident inspectors have observed rigid adherence in implementation

and documentation of component verification actions.

4.

Plant Operations (71707)

a.

The inspectors reviewed plant operations throughout the reporting

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period to verify conformance with regulatory requirements, technical

specifications (TS), and administrative controls.

Control room logs, shift turnover records, Unit 2 Refueling log and equipment l

removal and restoration records were reviewed routinely. Discussions were conducted with plant operations, maintenance, chemistry, health physics, instrument & electrical (I&E), and performance personnel.

Activities within the control rooms were monitored on an almott daily basis. Inspections were conducted on day and on night shifts, during week days and on weekends. Some inspections were made during

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shift change in order to evaluate shift turnover performance.

• Actions observed were conducted as required by the Licensees Administrative Procedures. The complement of licensed personnel on i

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each shift inspected met or exceeded the requirements of TS.

Operators were responsive to plant annunciator alarms and were

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cognizant of plant conditions.

Plant tours were taken throughout the reporting period on a routine basis.

The areas toured included the following:

Turbine Building Auxiliary Building

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Units 1,2, and 3 Electrical Equipment Rooms l

Units 1,2, and 3 Cable Spreading Rooms Station Yard Zone within the Protected Area

Standby Shutdown Facility Units 1,2, and 3 Penetration Rooms

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Unit 2 Containment Condenser Circulating Water Intake Structure f

During the plant tours, ongoing activities, housekeeping, security,

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i equipment status, and radiation control practices were observed.

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Unit 1 began the report period at 100% power. On 2/17/88, power was reduced to 65 due to a loss of one main feedwater pump due to a broken jack shaft gear. Af ter repairs, power was increased to 100%

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on 2/25/88 and the unit operated at 100% for the remainder of the report period.

Unit 2 remained in a refueling outtTe.

Startup is currently scheduled for 4/11/88.

Unit 3 operated at 100% power for the entire report period. A small steam generator tube leak remained stable at approximately.025 gpm.

5.

Surveillance Testing (61726)

Surveillance tests were reviewed by the inspectors to verify procedural and performance adequacy. 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 work. 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 completed.

Surveillances reviewed or witnessed in whole or in part:

PT/0/A/0400/05 Standby Shutdown Facility Auxiliary Service Water Pump Performance Test MP/0/B/1300/66 Monthly Inspection of Conderser Circulating Water Pump Flange Boot and Equal.ition Lines.

PT/0/A/0400/04 SSF Diesel Engine Service Water Pump Performance Test No violations or deviations were identified.

6.

Maintenance Activities (62703)

a.

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 trade.

Activities, procedures and work requests were examined to verify proper authorization to begin work, provisie's for fire, cleanliness, and exposure control, proper return of equipment to service, and that limiting conditions for operation were met.

Maintenance reviewed or witnessed in whole or in part:

WR 96164C Temporary Closure, Emergency RB Hatch (TN/2/A/TM0345/0/I Installation of Closure Plate on U-2 RB Emergency Hatch)

WR 99520B TN/2/A/2609/00 Moisture Separator Reheater 2B1 Tube Bundle Replacement and Modification

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WR 14038C Repair SSF-CCW 284 WR 55280A PM on 2KI Inverter per IP/0/A/3C11/01 WR 98344B TN/2/A/2174/00 Installation of Nuclear Station Modification to Emergency Power Switching logic (NSM-2174)

No violations or deviations were identified.

7.

Resident Inspector Safeguards Inspection (71881)

In the course of the monthly activities, the Resident Inspectors included review of portions of the licensee's physical security activities.

The performance of various shifts of the security force was observed in the conduct of daily activities which included; protected and vital areas access controls, searching of personnel, packages and vehicles, badge issuance and retrieval, escorting of visitors, patrols and compensatory posts.

In addition, the inspectors observed protected area lighting and protected and vital areas barrier integrity, and verified interfaces between the security organization and operations or maintenance.

Mo violations or deviations were identified.

8.

Inspection of Open Items (92701)

The following open items are being closed based on review of licensee reports, inspection, record review, and discussions with licensee personnel, as appropriate:

(Closed) LER 269/87-05, Revision 1:

Potential Tripping of High Pressure Injection Pumps During Starting.

This revision provided additional information on the analysis that was performed including graphical results of engineering calculations. There were no changes to the corrective actions as a result of this revision, therefore this item is closed as discussed in IR 269,270,287/87-34.

(Closed) LER 270/86-01:

Turbine / Reactor Trip Due to Inadequate Communication of A Relay Blocking Switch Design Feature.

This turbine / reactor trip occurred as a result of a communication breakdown between transmission personnel and operations.

The corrective action for this event has been performed and reviewed by the inspector.

Based on this review this item is closed.

(Closed) LER 270/87-05:

Fire Wall Breached Causing Violation of Technical Specification.

This LER was concerned with two five inch holes that were cut into the fire wall between the turbine building and the auxiliary building. Due to an interruption of the work, the breach was not recognized for 105 days.

The corrective action was to conduct training of Construction and Maintenance Division personnel that perform this work in administrative controls and work controls on fire barriers.

The inspector reviewed records to

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indicate all training had been completed as of February 10, 1988.

Bated on this review, this item is closed.

(Closed) Inspection Followup Item 50-269,270,287/87-48-01: Correction of potential loss of siphon effect on emergency condenser cooling water (ECCW) system.

The inspector reviewed the corrective actions taken by the licensee for agreement with commitments as documented in Inspection Report 50-269,270,287/87-48; i.

The inspector observed an inspection of the Unit 2 condenser circulating water (CCW) flange rubber boots and drain tubes.

Lake Keowee level was just above the aqualization line quick disconnects (about 790 f t.) and a small inflatable raf t was utilized in each CCW pump bay to inspect the boot and drain tubes.

Maintenance procedure MP/0/B/1300/66 was utilized to complete the inspection.

The inspector feels that this inspection (scheduled monthly) is satisf actory to ensure no lines or couplings are broken or disconnected until the permanent corrective action is completed.

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The inspector observed thi.t on the Unit 2 CCW pumps the licensee has installed flexible connectors from the drain tube couplings, around a lower pump flange and connected to conduit which is attached to the pump's suction line.

This is expected to prevent any future failure of the tubes or couplings in the disconnect area by minimizing any vibration at the coupling due to turbulence in the suction well.

This action is expected to be taken on the other CCW pumps within a few months, iii.

After a close examination of the actions involved, the licensee has decided not to change the Emergency Operating Procedures to require an immediate inspection of the pressure equalization lines in the event of a loss of power to the CCW pumps.

The event which would require the ECCW system siphon effect to be relied upcn is a station blackout. By the time operators could get down to the CCW flange boot and drain tubes to inspect them, air in leakage through any broken or disconnected tubes would have adversely effected the ECCW siphon effect, it should be noted that this er. tire situation is only a possible problem if Keowee lake level is below the equalization line disconnects.

Station procedures require that anytime events occur which require the Safe Shutdown Facility (SSF) to maintain any unit in hot shutdown then actions will be taken to install the SSF dedicated submersible pump to supply water to the Unit 2 CCW inlet piping for extended SSF operation if the ECCW siphon effect fails, iv.

Provisions are on hand at the CCW pump area for rapid sealing or repairs of any broken conduit that is discovered during an inspection.

The inflatable raft, foot air pump and other required material is stored in a box on the CCW pump structure.

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Unit 2 End of Cycle Refueling Outage (71700) (Unit 2)

Unit '2 remained in the refueling outage (which began on February 3)

throughout this report period.

With just over_ half of the scheduled outage days elapsed, the shutdown work war, far enough ahead of schedule

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that the startup date has been moved up three days.

The inspectors i

witnessed portions of a number of jobs in progress including the i

following: Defueling operations, chemical cleaning of steam generators (SG), replacement of :SG feedwater nozzles, cleaning of Low Pressure

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Injection Coolers and Reactor Building Cooling Units, installation of

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Reactor Coolant System cold leg dams, extensive electrical generator

rotor work, rework of valves, feedwater pump rebuilding, replacement of

noisture separator reheater tube bundles, and installation of several

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major nuclear station modifications.

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Chemical cleaning of the SG's has been completed.

Approximately 4700

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pounds of material was removed from the 'B'

SG, about 4100 pounds from the 'A' SG. Sludge lancing is in progress and is expected to remove an additional 500-700 pounds of material from each generator.

10.

Nonroutine Reporting Program (90714)

The inspector reviewed the licensee's administrative control programs for review, evaluation and reporting of nonroutine events or issues.

The Administrative Policy Manual (APM) (Section 2.8) and the Oconee Nuclear

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Station (ONS) Compliance Manual (Sections 4.9, 5.1 and 5.3) outline the key responsibilities and processes of this program.

The Problem Investigation Reporting (PIR) program as described by the APM and ONS

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Station Directive 4.5.5 serves as the basis for the process of i

documenting an evaluation and resolution of any identified problem.

The PIR process includes provisions for recognition and reporting of events covered by 10 CFR Part 21 as well as 10 CFR 50.73 and other reporting i

requirements.

The resident inspectors review PIRs on a daily basis. The i

investigation, resolution and corrective actions of PIRs of interest are

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closely followed by the inspectors.

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l The inspector also reviewed the licensee's administrative controls for i

review, evaluation and resolution of vender bulletins and circulars.

l Duke Power Company's (DPC) Nuclear Production Department Directives

Manual describes the Operating Experience Program carried out primarily I

by DPC Generai Office personnel.

This program includes the review and

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evaluation of Vendor Information Letters, Information Notices (NRC), INP0

Good Practices and Significant Operating Experience Reports. The program i

clearly sets forth the processes to be used and defines implementation j

responsibilities.

l No violations or deviations were noted in this area.

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11.

Design, Design Changes, and Modifications (37700)

The inspectors reviewed various design changes to ascertain that the changes were reviewed and approved in accordance with 10 CFR 50.59, lechnical Specifications and established QA/QC controls, controlled by approved procedures and that changes to the inservice inspection and test program were updated as required by the cnange.

In addition, records were reviewed to assure that the modifications were tested by appropriate procedures and the results of the test reviewed by management personnel.

The inspector also reviewed as-built drawings, operating procedures, surveillance procedures and training associated with the modification.

The specific modifications reviewed were the following:

a.

NSM - ON 12493 - Unit 1 - This modification extended the suction of the Motor Driven Emergency Feedwater Pumps to within 12 inches of the bottom of the hotwell, b.

NSM - ON 22680 - Unit 2 - This modification changed the BTU Limits associated with the Integrated Control Circuits to inactivate the limit if power is greater than 25% and activate the limit if power is less than 25%.

This modification is a B&W Owners Group recommendation as discussed in NUREG 1231, Safety Evaluation Report Related to Babcock & Wilcox Owners Group Plant reassessment Program, c.

NSM - On 1782 - Unit 3 - This med;fication replaced the electro-mechanical operators on valves 2HP-409 and 2HP-410.

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NSM-ON 32460 - Unit 3 - This modification involved a change to the RC Makeup Pump to increase the capacity of the pump.

At the conclusion of this report period, the review of these modifications was still in progress. This review will be concluded during a subsequent reporting period.