ML20147E754

IE Inspec Rept 50-298/78 on 781030-1102 During Which No Items of Noncompliance Were Noted.Major Areas Inspected incl:records,follow-up on IE Bulletins,Circulars,Open Items, Unresolved Items & Prior Deviations

ML20147E754
Person / Time
Site:	Cooper
Issue date:	11/17/1978
From:	Cupp E, Johnson E, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20147E752	List: IR 05000298/1978018 ML20147E754
References
50-298-78-18, NUDOCS 7812210184
Download: ML20147E754 (7)

Text

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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No. 50-298/78-18 Docket No. 50-298 License flo. DPR-46 Licensee: Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station .

Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted: October 30 - November 2, 1978 Principal s i Inspector: Nd h " '7 %

E. H. Johnson, Reactor Inspector Date rson -

LYO ///~//79 E. A. Cupp, Reatt'or Inspector Oste m.

Approved By: dl Mkdc'"

G. L. Madsen, Chief, Reactor Operations and Mnh/

Date Nuclear Support Branch Inspection Summary Inspection on October 30 - November 2, 1978 (Report No. 50-298/78-18)

Areas Inspected: Routine, unannounced inspection of: (1) records; (2) follow up on IE Bulletins; (3) follow up on IE Circulars; (4) follow up on inspector identified open items; (5) follow up on unresolved items; and (6) follow up on previously identified items of noncompliance and deviations. The inspection involved forty-ei ht 9 (48) hours on-site by two NRC inspectors.

Results: No items of noncompliance or deviations were noted in the areas inspected.

't b 12 2101h

DETAILS Persons Contacted C. S. Barrus, Mechanical Engineer L. F. Bednar, Electrical Engineer R. Brungardt, Shift Supervisor P. F. Doan, Mechanical Engineer R. D. Flannigan, Nuclear Engineer W. F. Gilbert, Training Coordinator L. I. Lawrence, Maintenance Supervisor

• L. C. Lessor, Station Superintendent D. E. Mayer, Mechanical Engineer C. R. Noyes, Engineering Supervisor J. V. Sayer, Chemistry & HP Supervisor R. W. Seier, Qualty Assurance Supervisor M. G. Williams, Operations Supervisor W. H. Wunderlich, Administrative Supervisor

• Present at the exit interview.

i In addition to the above technical and supervisory personnel, the inspectors held discussions with various maintenance, operations, technical support and administrative members of the plant staff.

1. Plant Status During the period of this inspection, the plant was in routine power operation at 90% power.' No abnormalities in plant operating conditions were noted by the inspector.

2. Records The inspector reviewed the licensee's program for the control, storage, retention and retrieval of records and documents to verify its confor-mance with Technical Specifications.

The following records were retrieved and reviewed for proper storage, identification, receipt control, indexing, preservation and complete-ness:

Startup Test STI-31, Loss of Offsite Power and Generation Trip Major Design Change 76-2, ECCS Low Pressure Coolant Injection, Modifications for Performance Improvement Safety Relief Valve Set Pressure Calibration and Leakage Test Report,12/2/77

Chart #14, Reactor Pressure and Level, 2/78 Drywell Pressure Calibration Test - 5/14/76,10/14/76, 11/3/76 and 4/21/78 Licensee ' Event Report 76-03 The licensee has initiated a program to microfilm quality related -

records and documents. It was noted that Special Test Procedures and Licensee Event Reports had not been transferred to the vault follow-ing the active file period defined in Qualty Assurance Instruction 7.

The Station Superintendent indicated that QAI-7 would be changed to allow these to be held in the active file until they are microfilmed to minimize the number of transfers. The inspector had no further questions in this area.

The inspector also verified that routine QA audits of records and documents are being held and that appropriate retention periods have been assigned to each record or document.

In addition, the inspector reviewed the licensee's means of maintaining current as-built drawings. The following drawings were checked in the master microfilm copy and the controlled sets of drawings located in Engineering Instrument Shop, Rad Waste, Maintenance Shop, Operations (Control Room) and Electrical Shop to verify that the latest revisions were inserted and that applicable Drawing Change Notices were noted on them:

Burns & Roe 2016, Sheet 1 Burns & Roe 3255, Sheet 80A Burns a Roe 2039, Sheet 1 Burns & Roe 2045, Sheet 1 General Electric 791E264, Sheet 5 Burns & Roe 2040, Sheet 1 Burns & Roe 2044, Sheet 1 Burns & Roe 3255, Sheet 59 The inspector also reviewed the records of test and experiments that are required by 10 CFR 50.59(b). The following Special Test Procedures were reviewed in detail for completeness:

STP 73-2 Diesel Generator Reliability Testing Program STP 73-5 RCIC Flow Test STP 74-8 Reactor Recirc Bypass Line Vibration Testing STP 75-11 LPRM Vibration STP 76-2 Delta-P Containment Pressure Control STP 76-15 Pilot Operated Safety Relief Valves STP 77-29 Spring-Operated Safety Valves STP 78-1 RHR-M0-25 Valve Operability No deviations or items of noncompliance were identified in this area of the inspection.

3. Follow Up on IE Bulletins The inspector performed follow up on the following IE Bulletins to determine that the licensee s station staff had received a copy of the Bulletins and had reviewed them for applicability. The inspector reviewed the licensee's respo,ise for each Bulletin to determine that the response had been submitted in the time frame required and the information discussed in the licensee's reply was supported by facility records or a visual examination of the facility. The licensee's corrective actions were reviewed for appropriateness and completion.

IEB Ti tle Status 78-02 Terminal Block Qualification Closed 78-04 Environmental Qualification of Certain Closed Stem Mounted Limit Switches Inside Reactor Containment 78-06 Defective Culter-Hammer, Type M Relays Closed with DC Coils 78-07 Protection Afforded by Air-Line Closed Respirators and Supplied-Air Hoods 78-09 BWR Drywell Leakage Paths Associated with Closed Inadequate Drywell Closures 78-10 Bergen-Paterson Hydraulic Shock Suppressors Closed Accumulator Spring Coils In addition, the facility received IEB 78-08, " Radiation Levels from Fuel Element Transfer Tubes." Since the facility design does not incorporate a fuel element transfer tube, this Bulletin was not applicable to Cooper Nuclear Station. This Bulletin is considered closed.

No items of noncompliance or deviations were noted in this area.

4. Follow Up on IE Circulars The inspector reviewed the following IE Circulars to determine that the licensee's station staff had received these Circulars and reviewed them for applicability. The inspector reviewed the licensee's actions and proposed actions on each Circular to determine if these actions were consistent with the situation at the facility.

IEC Title Status 77-16 Emergency Diesel Generator Electrical Trip Closed - See below Lock-Out Features

e e IEC Title Status 78-06 Potential Common Mode Flooding of ECCS Closed Equipment Rooms at BWR Facilities 78-09 Arcing of General Electric Company Size 2 Closed Contactors 78-11 Recirculation M-G Set Overspeed Stops Closed 78-12 HPCI Turbine Control Valve Li ft Rod Bending Closed 78-13 Inoperability of Service Water Pumps Closed - See below 78-14 HPCI Turbine Reversing Chamber Hold Down Closed - See below Bolting 78-16 Limitorque Valve Actuators Closed No items of noncompliance or deviations were noted in this area.

The inspector reviewed IE Circular 77-16 with the licensee's Engineering staff. This Circular discusses the failure of the diesel generator performance test at a nuclear facility. The test failure occurred when the diesel generator output breaker opened on a trip feature which should have been bypassed by the automatic start circuitry. The inspector noted that for the diesel generator installed at Cooper Nuclear Station, all generator trips (FSAR Section 8, paragraph 5.5) are operative at all times. Engine trips (such as jacket water temperature high, low oil pressure, bearing temperature high)' are operative at all times on a normal start of diesel generator. On emergency start, they are locked out. The only engine trip that is operative during emergency diesel generator start is the overspeed trip. When an engine trip set point is reached, the engine control air system pressure is bled off and the fuel racks are tripped. On an emergency start condition, a solenoid valve in the control air system isolates all the aforementioned trips with the exceptian of the overspeed trip. The inspector noted that the once per cycle emergency start test of the diesel generator does not check this solenoid for proper operation. A licensee repre-sentative indicated that testing this solenoid would be easily accomplished and the appropriate surveillance procedure would be changed to accomplish this testing. This item will remain open for follow up during future inspections.

IE Circular 78-13 describes a situation in which a silt accumulation in the intake structure of one nuclear facility caused a loss of service water flow. The inspector noted that the licensee had conducted a review of facility procedures for the loss of service water flow as recommended by this Circular. The Station Superintendent indicated that a long-range study is being undertaken for the service water I

system to eliminate the similar silting conditions which had been I noted at this facility. Changes resulting from this service water system study will be handled as design changes and will be inspected during the routine review of facility design changes.

IE Circular 78-14 was written to describe a potential design deficiency in the HPCI turbine reversing chamber hold down bolting. The inspector noted that the licensee has received the information from the turbine vendor regarding this potential deficiency and a recommendation for a permanent fix. The licensee has written a minor design change to install this permanent fix and has scheduled installation for the April 1979 refueling outage.

5. Follow Up on Previously Identified Items of Noncompliance and Deviations .

The purpose of this inspection effort was to review the licensee's

} corrective action for previously identified items of noncompliance and deviations. This review was made to determine that the on-site staff had received the licensee's response to the item of noncompliance and that responsibility for the corrective action had been assigned.

Further, this review determined whether or not the corrective action and completion date committed to in the licensee's response letter to each item had been accomplished as described.

No items of non:ompliance or deviations were noted during this review.

The f ! lowing list represents the status of those items reviewed.

Report Item Status 78-07 Infraction A Closed 78-08 Infraction A Closed 78-13 Infraction D Closed 77-03 Deviation Closed 78-15 Deviation Closed

6. Follow Up on unresolved Items and Inspector Identified Open Items The following unresolved items and inspector identified open items were reviewed during this inspection. Their status is as indicated.

Resolved. Unresolved Item 7802-2, Procedure for Primary Containment Access. Administrative Procedure 1.4.13, Station Rules of Practice, has been revised to indicate that drywell entries will be controlled by a special work permit.

Resolved. Unresolved Item 7810-1, Housekeeping Following Maintenance _.

An emphasis on the proper housekeeping following maintenance activities has been added to the maintenance training program. The Maintenance Supervisor indicated to the inspector that during extensive maintenance outages, periodic short cleanups are to be conducted to ensure that unacceptable housekeeping conditions do not result.

Resolved. Unresolved Item 7812-1, Reactor Engineer Qualification.

This item war discussed with members of IE Headquarters staff who indicated that their interpretation of the licensee's FSAR commit-ment was the same as the interpretation given to the inspector by the Station Superintendent.

Closed. Reference IE Report 77-15, Details, paragraph 12. The licensee has added instructions for the control locked valves to Administrative Procedure 1.4.4.1.7, Revision 28, dated September 7, 1978. A locked valves log is in use in the control room.

Closed. Refererence IE Report 78-01, Details, paragraph 5. The licensee has issued Surveillance Procedure 6.3.12.8, " Diesel Generator Fuel Oil Transfer Pump Flow test," Revision 0, dated June 9,1978, for the performance of a flow test of the diesel generator fuel oil transfer pumps on a once per cycle frequency.

Closed. Reference IE Report 78-07, Details, paragraph 3. The licensee uses two man control in the drywell.

Closed. Reference IE Report 78-07, Details, paragraph 5. Administrative Procedure 1.10 has been revised by Revision 9, dated September 5, 1978, to correct the 10 CFR Part 21 designated responsible officer designation.

Closed. Reference IE Report 78-09, Details, paragraph 2. The inspector discussed the Emergency Plan training given to a recently hired temporary employee. An acceptable level of training on the Emergency Plan was provided.

Closed. Reference IE Report 78-12, Details, paragraph 4. Surveillance Procedure 6.1.19, " Local Power Range Monitor Calibration Test," Revision 3, dated August 11, 1978, includes a review of post calibration gain adjustment factors for the LPRM's and includes appropriate acceptance criteria.

7. Exit Interview The inspectors met with the Station Superintendent at the conclusion of the inspection. The scope of the inspection and the findings above were discussed.

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