IR 05000269/1985034

Insp Repts 50-269/85-34,50-270/85-34 & 50-287/85-34 on 850930-1004.No Violation or Deviation Noted.Major Areas Inspected:Fire Protection/Prevention & Followup on Previously Identified Items

ML20198A779
Person / Time
Site:	Oconee
Issue date:	10/24/1985
From:	Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198A724	List: IR 05000269/1985034 ML20198A719
References
50-269-85-34, 50-270-85-34, 50-287-85-34, NUDOCS 8511060177
Download: ML20198A779 (9)

Text

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Report Nos.: 50-269/85-34, 50-270/85-34, and 50-287/85-34 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-269, 50-270, and 50-287 License Nos.: DPR-38, DPR-47, and DPR-55 Facility Name: Oconee 1, 2, and 3 Inspection _ Conducted: September 30 - October 4, 1985 Inspector:P /~ peo t /4 -JlW-fS'

W. H.' Miller, J & Date Signed Approved by: [

T. E. Conlon, Section Chief

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Date Signed Plant Systems Section, Engineering Branch Division of Reactor Safety SUMMAR,Y Scope: This routine, unannounced inspection involved 38 inspector-hours on site in the areas of fire protection / prevention and followup on previously identified item Results: No violations or deviations were identified.

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REPORT DETAILS Persons Contacted Licensee Employees

• M. Tuckman, Station Manager

• J. T. McIntosh, Superintendent Station Services q * G. Sasser, Safety Supervisor D. Kelly, Training Supervisor

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N. Watson, Mechanical Maintenance R. Sweigart, Operations Engineer l'

E. L. Jackson, Projects

• T. C. Mathews, Compliance - Technical Support

• H. D. Brandes, Design Engineer Other licensee employees contacted included engineers, technicians, operators, mechanics, and office personne NRC Resident Inspectors J. Bryant

• K. Sasser L. King

• Attended exit interview Exit Interview The inspection scope and findings were summarized on October 4,1985, with those persons indicated in paragraph above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license .

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Inspector Followup Item (269, 270, 287/85-34-01), P.ocedures To Be Provided For Periodic Preventative Maintenance of the Reactor Coolant Pump Motor Lube Oil Collection System and Verification That Oil Collection System Drain Tanks Are Empty paragraph The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio ' Licensee Action on Previous Enforcement Matters (Closed) Unresolved Item 269/80-14-02 and 270, 287/80-09-02, Interior Fire Hose Systems Do Not Meet NRC Guideline Following the NRC Staff fire protection review and issuance of the August 11, 1973 Safety Evaluation Report (SER), Duke installed additional fire hose stations throughout the plant supplied by the designated fire protection water i

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system, except the hose stations within containment are supplied by low pressure service water pumps. The water supply available from each hose station will deliver water at a sufficient volume and pressure for fire brigade manual fire fighting operations, except for the reactor buildin The water supply at the top floor level of the reactor building is seriously deficient with only approximately 30 gpm at 8 psig available in lieu of the required 100 gpm at 65 psi This deficiency is somewhat compensated by the protection afforded by the oil collection system provided for each reactor coolant pump motor which is designed to prevent lube oil from the motor being discharged onto any adjacent hot surface This is one of the principle fire hazards within the reactor building when the plant is operatin Additional fire fighting capability from portable fire extinguishers is also availabl Furthermore, the containment spray systemt are available for fire fighting operations in the event of a major fire. This system consists of two electric driven pumps per unit rated at 1500 gpm at 195 psi each. The system is arranged to discharge through separate independent piping systems to 125 nozzles per system. These nozzles are located at the top level of the reactor buildings and are designed to discharge an average of 13.9 gpm per nozzle. The reactor coolant pumps are located below the reactor building operating floor with an open metal floor grating separating the pump areas from the containment spray nozzle This would allow water to be discharged into the pump area from the containment spray system in the event of a major fir As noted in the above referenced SER, the NRC staff did not rely on the ability to promptly detect or suppress fires for Oconee as required at other plants due to the installed dedicated shutdown system. The dedicated shutdown system is available for plant shutdown even if other plant shutdown systems are adversely affected by a fire. Therefore, it appears that even though the installed interior fire hose systems deviate from the NRC guidelines and industry standards, the system provided meets the commitments previously made to the NR Any additional upgrade will not provide a significant improvement in protection afforded for the protection of the health and safety of the publi This item is close (Closed) Unresolved Item 269/80-14-03 and 270, 287/80-09-03, Smoke Detector Systems Do Not Meet NRC Guidelines. Following the NRC staff fire protection review and issuance of the August 11, 1978 SER, Duke installed additional smoke detectors such that areas of the plant containing safe shutdown equipment and combustible materials were provided with smoke detectors. The location and spacing of the smoke detectors in many plant areas do not meet industry standards and NRC guidelines and may not affect early detection and notification in the event of a fire. However, this discrepancy is not considered a serious safety concern since the licensee has provided a dedicated safe shutCown system which would be unaffected by fires involving normal shutdawn systems and can be used for safe plant shutdown in the event

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of a fire in any location of the plant. The NRC staff did not require as heavy a reliance on the ability to detect and suppress fires at Oconee as at other plant due to the installed dedicated shutdown syste Therefore it appears that even though the installed smoke detection system deviates from NRC guidelines and industry standards, the system meets the commitments made to the NRC. Any additional modifications would not provide a significant improvement in the protection afforded for the protection of the health and safety of the publi This item is close (Closed) Unresolved Item 270/80-09-11, Review of Fire Loading for Room 34 Room 347 is the area adjacent to the personnel hatch for the Unit 2 reactor buildin This area contains a high fire loading due to the storage of transient materials prior to, following and during refueling and other major outage The same situation also exists in the areas adjacent to Units 1 and 3 personnel hatches. Therefore, the licensee has installed automatic sprinkler systems to provide fire protection coverage for these area This item is close (Closed) Unresolved Item 269, 270 and 287/83-30-01, Inadequate Procedure for Fire Brigade. Station Directive 4.2.2, Fire Brigade Organization and Training, and Oconee Nuclear Station Fire Plant have been revised to define the duties of the shift supervisors and assistant shift supervisors during fire events. This item is close (Closed) Unresolved Item 269, 270 and 287/83-30-02, Independence of Tri-Annual Audit Consultant. Previously, the consultant who provided input to the original fire protection design of the plant has also conducted the tri-annual fire protection audits required by the Technical Specifications. Subsequent discussions with the NRR staff indicated that this arrangement was satisfactory. Therefore, this item is close . Unresolved Items Unresolved items were not identified during this inspectio . Fire Protection / Prevention Program (64703) Prccedures The inspector reviewed the following procedures from the Station Directives (SD) and the Fire Plan:

N Title Date SD 4. Control of Combustible Materials 7-31-85 SD 4. Fire Brigade Organization and Training 12-1-84 SD 4. Welding and Burning Safety Direction 12-1-84 SD 4. Housekeeping Responsibilities 4-13-85

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N Title Date SD 4. Cleanliness in Safety-Related Areas 12-1-84 SD 4. Waste Oil Management Program 7-29-85 SD 4. Chemistry Approved Chemicals 12-1-84 These procedures comply or meet the intent of the NRC guidelines in the document entitled " Nuclear Plant Fire Protection Functional Responsi-bilities, Administrative Controls and Quality Assurance" of June 1977 and the licensee's commitments in the letter to the NRC dated January 16, 197 Fire Brigade (1) Organization The fire brigade is composed of approximately 144 personnel from the operations group. The brigade leader is normally one of the assistant shift supervisors and the brigade members are composed of nuclear equipment operators. Sufficient personnel are assigned to each shift to meet the minimum operating staffing requirements of the Technical Specification including five qualified personnel for fire brigade dutie The inspector reviewed the shift assignment effective October 1, 1985, and verified that sufficient manpower to meet these requirements were assigned to each shif (2) Training A review was made of the training and drill records for five brigade leaders and ten brigade members for 1984 and the first three quarters of 1985. The records reviewed indicated that each of these leaders and members had received a medical review within the past year, attended the required training and participated in the required number of drills. The inspector also verified that a fire brigade drill had been conducted each quarter for 1984 and the first half of 1985 for each shif (3) Fire Brigade Equipment Fire brigade equipment, consisting of fire hose, nozzles, tools and miscellaneous equipment, is stored on three trailers in the exterior area of the plant and on two roll carts adjacent to the control room A total of 17 sets of turnout gear (coats, helmets, boots, etc.) and ten self-contained breathing apparatus are stored in equipment rooms adjacent to the control room Three portable foam carts are also availabl The brigade equipment appeared adequate, properly stored and satisfactorily maintaine _ _ . . . _ _

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5 Surveillance of Fire Protection Systems The licensee's QA fire protection audit, Audit No. NP-85-10 (ON), of May 13-29, 1985, reviewed the fire protection Technical Specification (TS) requirements and verified that the specified tests and inspections had been correctly translated into station procedure The audit also reviewed completed procedures to verify that the inspections and tests had been performed within the required time frame. The only deficiency identified was the failure to perform the semi-annual surveillance on  ;

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the Keowee CO, system storage tank within the time permitted by the T ! This item wat reported to the NRC by LER No. 269/85-08 and the surveillance was accomplishe The inspector reviewed the following completed surveillance procedures for indicated dates and verified that the procedures had been completed i

within the time permitted by the TS. No discrepancies were identifie z (1) IP/1 and 2/A/250/5A, fire Detection System Accessible Detector Tests (Semi-Annual)

August 18, 1984 through February 18, 198 (2) IP/3/A/250/5A, Fire Detection System Accessible Detector Tests (Semi-Annual)

October 20, 1983 through April 17, 198 (3) PT/0/A/250/5, HPSW Pump and Power Supply (Monthly)

January 1, 1984 through September 13, 198 (4) PT/0/A/250/108, Fire Protection System Annual Check July 7, 1984 through August 9, 1985.

I (5) PT/0/A/250/25, Fire Protection Annual Flow Test September 12, 1983 through May 15, 198 Fire Protection Audits The most recent audit reports of the Oconee Fire Protection Program were reviewed by the inspector. These audits were: triennial audit of June 25-27, 1984 (Audit No. NP-84-10 (0N)); 24 month QA audit of May 13-29,1985 (Audit No. NP-85-10 (0N)); and, annual fire prevention audit by offsite personnel of May 22-29, 1985. These audit identified several discrepancies and unresolved items, and recommended several improvements. The licensee appeared to have taken the appropriate

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corrective action on the audit findings. The items had either been corrected or a scheduled date for completion of the corrective action had been established.

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Within the areas examined, no violations or deviations were identifie . Fire Protection / Prevention Program Implementation (64704)

A plant tour was made of the auxiliary building, turbine building, Unit 3 reactor building, control rooms, and Keowee Plant to review the licensee's implementation of the fire prevention administrative procedures. The control of combustible and flammable materials, liquids and gases, and the general housekeeping was found satisfactory in areas inspected; however, a number of minor improvements were needed on the 771' and 783' elevations of the auxiliary buildin Corrective action was initiated in these area One welding operation was observed in the radiation controlled are An approved " Hot Work" permit had been issued and the operations and fire prevention protection practices met the licensee's fire prevention procedure requirements. The fire protection systems within the areas toured were found to be in service and appeared to be well maintaine Within the areas examined, no violations or deviations were identifie . Reactor Coolant Pump Motor Oil Collection System Each reactor coolant pump motor at Oconee had been equipped with an independent oil collection system designed to withstand a safe shutdown earthquak The oil collection systems are arranged to collect lube oil from potential pressurized and unpressurized leakage from the following pump motor lube oil system components: lift pump and piping, overflow lines, lube oil coolers, oil fill and drain lines and plugs, flanged connections on oil lines and lube oil reservoirs. Each collection system is connected to a drain pipe which discharges into a 250 gallon tank. A separate tank is provided for each pum The vent pipe from each tank is provided with a flame arresto The drain tank is sized to hold the entire lube oil capacity for the pump moto The inspector reviewed the oil collection system for Unit 3 reactor coolant pump motor 38 and the spare pump motor stored within the warehouse. The collection systems appear adequate to meet the requirements of 10 CFR 50 Appendix R Section III.0. However, it was noted that some of the enclosure latch devices for portions of the Unit 3 system were becoming inoperative and that a portion of the gasket material provided to seal the seams of the collection system enclosures were in need of repair. These items were not serious and the system is considered functional. To prevent any further deterioration the licensee will place the entire oil collection system components into a periodic maintenance procedure. This should assure that the system will be properly maintained. Also, the collection system drain tanks are not periodically inspected and verified to be empty. The licensee agreed to revise procedure OP/A1102/01, Controlling Procedure for Unit Startup, to require the drain tanks to be verified empty prior to startup following an outage. These procedures changes are to be completed and implemented prior to the startup from the next scheduled refueling outage in 1986 for Units 1 and 2. These items are identified as Inspector Followup Item (269, 270, 287/85-34-01), Procedures to be Provided for Periodic ;

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Preventative Maintenance of the Reactor Coolant Pump Motor Oil Collection System and Verification that Oil Collection System Drain Tanks Are Empty, and will be reviewed during a subsequent NRC inspectio Within the areas examined, no violations or deviations were identifie . Inspector Followup Items (IFI) (Closed) IFI (269/80-14-01) Installation of Unit 1 Battery Room Ventilation System. An 80 CFM exhaust fan has been installed for this battery room. Duke Design has verified, Design File No. OS-72-C of December 23, 1981, that based on the room size and available ventilation, sufficient exhaust is provided for the vital battery rooms of each uni This item is close (Closed) IFI (270/85-01-01) Inoperable Fire Barrier The licensee stated that all of the plant's fire barrier penetrations have been provided with identification tags and have been included in surveil-lance procedure MP/A/1705/18, Fire Barrier Penetration Inspectio The inspector noted that all observed penetrations had an identification tag, an inspection of all penetrations was conducted and completed by the licensee on August 20, 1985, and that work requests were issued on identified discrepancies. A total of 42 people were involved in the inspection, installation or repair of fire barrier penetration These people were trained on fire barrier penetrations between April 9-18, 198 The licensee's corrective action met the commitments made to improve the surveillance inspection and maintenance of fire barrier penetrations. This item is close . Licensee Identified Item (Closed) Licensee Event Report (LER) 269/84-05, Exceeded Surveillance Interval for Keowee Fire Protection Equipmen The final report on this item was submitted to the NRC on December 17, 1984. The monthly surveillance inspection of the Keowee fire protection systems was exceeded by two days due to incorrect data being entered into the computer data ban The licensee instituted a second verification requirement by the preventive maintenance administrative personnel to assure that the correct information is entered into the compute (Closed) LER 269/85-08, Exceeded Surveillance Interval for Keowee Fire Protection System. The final report on this item was submitted to the NRC on June 20, 1985. The semi-annual surveillance inspection and test of the Keowee CO 2 system which was required to be conducted within a maximum of 270 days following the August 23, 1984 surveillance was conducted three days late. This error was attributed to the incorrect information being entered into the preventative maintenance computer schedule due to data on a printer being blurre The licensee is k

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g changing the ribbon on the computer printer more frequently and has instituted a second verification requirement by the preventive maintenance administrative personnel to assure that the correct information is entered into the computer.

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