IR 05000298/1989027
| ML20247C066 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/05/1989 |
| From: | Bundy H, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20247C062 | List: |
| References | |
| 50-298-89-27, NUDOCS 8909130229 | |
| Download: ML20247C066 (5) | |
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APPENDIX-
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U.S. NUCLEAR' REGULATORY COMMISSION
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REGION IV
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' NRC Inspection' Report: l50-298/69-27 Operating License:.DPR-46 Derket:i-50-298 m
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. Licensee:- Nebraska'Public Power District'(NPPD).
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P.O. Box 499 o
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Columbus, Nebraske 68602-0499 m
. Tacility Name: CooperNuclearstation.(CNS)
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-Inspection At: CNS, Brownville, Nebraska-Inspection Conducted: August 21-25, 1989 Inspector:
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H. F. Bundy, Reactor Inspector, Test Programs Date
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Section. Division of Reactor Safety
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e W. C. Seidle, Chie7, Test Programs Section Date Division ~of Reactor Safety
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' f,InspectionSummary;
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TInspection Conducted August 21-25;'1989 (Report 501298/89-27)
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Area Inspected:- Routine, unannounced inspection of the~ licensee's surveillance procedures (SPs) and records. -
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Results* The-licensee's SPs and records appeared to satisfy hil Technical
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Specifications (TS)requirementsreviewed. Acceptance criteria were clearly.
stated and in each instance the SP records indicated that the criteria had been met.'
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DETAILS
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Persons Contacted-NPPD
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- G. R. Horn, Division Manager - Nuclear Operations
- J. M. Meacham, Senior Manager - Operations
. E. M. Mace, Engineering Manager
- G. E. Smith, Quality Assurance Manager
- R. Brungardt, Operations Manager
- H. A. Jantzen, Instrumentation and Control Supervisor
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- P. L. Ballinger, Operations Engineering Supervisor D. C. Shrader Assistant to Operations Supervisor
- L. E. Bray, Regulatory Compliance Specialist NRC
- W. R. Bennett, Senior Resident Inspector
- G. A. Pick, Resident Inspector-The NRC inspector r.lso interviewed other licensee employees during the course of the inspection.
- Denotes those present during exit interview held on August 25, 1989.
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Surveillance Procedures and Records (61700)
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The purpose of this inspection was to ascertain whether the surveillance of safety-related systems and components was being conducted in accordance with approved procedures as required by the TS.
Pursuant to this objective, the inspector reviewed the following licensee documents:
Procedure 0.26, Revision 3 " Surveillance Program"
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Procedure 0.27, Revision 4.." Component Operability"
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The inspector then selected certain TS surveillance requirements and reviewed the associated licensee SP and an appropriate number of test
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L results. records for each procedure. Also, selected test personnel were verified to have appropriate qualifications. The T5 surveillance requirements, together with the associated SPs reviewed by the inspector.
-are tabulated in the attachment.
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The inspector determined that the required tests were being scheduled and l
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performed as required in accordance with approved procedures. Acceptance criteria were specified in the procedures and the records stated satisfaction
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-3-of/ acceptance criteria. Appropriate' instructions for returning equipment to' service.following testing were given. With the one exception discussed below,-'there was evidence that surveillance tests were being properly.
evaluated and documented.
In~ reviewing the' data for'SP 6.1.18.2, which was completed on April 29, 1989,'the inspector. observed that a value of'-53.05 VDC was recorded for
. Step 8.3.2.
This.was outside the tolerance band of -53.4 to.-53.6 VDC c
given in Table 1.
Because this number had not been challenged in the review and approval cycle, the licensee was asked for an explanation.
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turned out to be an inadvertent oversight and a nonconfonnance report was initiated by the licensee on August 23, 1989, to disposition the deviation. The licensee stated that the value had been adjusted within the tolerance band in a later calibration. Engineering Memorandum CNSS897454 issued on August 25, 1989, stated that the as-left value was within vendor. specifications for'the associated "B" reactor recirculation flow unit and therefore, no operability concern would have existed.
No violations or deviations were identified.
3.
Exit Interview
The inspector met with the licensee representatives denoted in paragraph 1 on August 25, 1989, and summarized the scope and findings of this inspection. The' licensee did not identify, as proprietary, any of the materials provided to, or reviewed by, the inspector during this inspection.
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ATTACHMENT ProceduresandRecoidsReviewed y
T_S Description SP Number
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Table 4.1'.2 APRM ;11 Flux Flow Bias Signal ~ Internal 6.1.18.2, R2 Power and Flow Test Table 4.1.2 Main Steam Line Isolation Valve Closure 6.2.2.7.1,.R7 Table 4.2.B Item 11, RCIC Steam Line Hi Delta P 6.2.2.6.1, R17
' Actuation Timer Calibration
Table 4.2.D Stan'dby Gas Treatment Initiation Logic 6.2.1.5.2, R22 4.3.A.1 Evaluate Core Shutdown Margin Considering 10.16. R17
"R" Value 4.3.G.1 Verify SDV Vent and Drain Valves Open 6.3.10.13. R7 Prior to Reactor Startup, 4.3.G.2-SDV Vent and Drain Valves Close Within 6.1.15. R8-
-30 Seconds of Scram' Signal
4.4.A.2.c Verify Operability of SLC by Manual-6.3.8.4, R16 Initiation of SLC Pumps to Pump Demin.
Water Into RV From Test Tank 4.5.A.1.a Simulate Auto Actuation of CS 6.3.4.3, R27 4.5.B.1.c Air Test Drywell and Torus Headers and 6.3.5.4, R8 Nozzles 4.5.E.1 Simulate Auto Actuation of ADS 6.3.2.2, R16
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4.7.A.1.a-Check Suppression Pool Level and
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Temperature Once Per Day 4.7.A.1.d Perform Visual Inspection of Suppression 6.3.10.1, R6 Chamber Interior 4.7 A.3.b Test Each Pressure Suppression Chamber -
6.2.5.1, R19 Reactor Building Vacuum Breaker to Determine Opening Force 4.7.B.4.a Demonstrate Auto Initiation of Each Branch 6.2.1.5.2, R22 of SGT System
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-2-4.7.C.I.c Demonstrate Capability of One SGT Train to 6.3.10.8, R11 Maintain Secondary Containment at 1/4 Inch of Water Vacuum
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4.9.A.1 Simulate Loss of Voltage to Demonr, rate Load 6.3.4.3, R27 Shedding and-Under-Voltage to Demonstrate Disconnection from Offsite Power for Emergency Busses 4.10.A.1 Functionu'ly Test Refuelirig inte: locks 6.1.27.4 Prior to FL91 Handling and Weekiy 6.1.27.3 Thereafter 4.11 Check Core Tlermal Limits Daily 6.2.4.1 4.12.B.I.c Check Flow Rate of Reactor Building Closed 6.3.16.3, R11 Cooling Water Pumps i
4.12.C.I.c Perform Service k'*ter Pump Discharge Head 6.3.18.3, R22 Test 4.15.A.4 Perform a Simulated Fire Suppression Water 6.4.5.2, R40 Supply System functional Test 4.18.A.2 Inspect Fire Hose Stations by Removing Hose 6.4.5.2, R40 and Reracking and Replacing all Degraded Gaskets in Coupling
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