IR 05000298/1987030
| ML20236X626 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/03/1987 |
| From: | Hunnicutt D, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236X624 | List: |
| References | |
| 50-298-87-30, GL-87-01, GL-87-02, GL-87-03, GL-87-04, GL-87-05, GL-87-06, GL-87-07, GL-87-08, GL-87-09, GL-87-1, GL-87-10, GL-87-11, GL-87-12, GL-87-13, GL-87-14, GL-87-2, GL-87-3, GL-87-4, GL-87-5, GL-87-6, GL-87-7, GL-87-8, GL-87-9, IEB-79-01B, IEB-79-1B, IEB-85-003, IEB-85-3, IEB-86-001, IEB-86-002, IEB-86-003, IEB-86-1, IEB-86-2, IEB-86-3, IEIN-86-064, IEIN-86-065, IEIN-86-066, IEIN-86-067, IEIN-86-068, IEIN-86-069, IEIN-86-070, IEIN-86-071, IEIN-86-072, IEIN-86-073, IEIN-86-074, IEIN-86-075, IEIN-86-076, IEIN-86-077, IEIN-86-078, IEIN-86-64, IEIN-86-65, IEIN-86-66, IEIN-86-67, IEIN-86-68, IEIN-86-69, IEIN-86-70, IEIN-86-71, IEIN-86-72, IEIN-86-73, IEIN-86-74, IEIN-86-75, IEIN-86-76, IEIN-86-77, IEIN-86-78, NUDOCS 8712090343 | |
| Download: ML20236X626 (7) | |
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APPENDIX V.S. REGULATORY COMMISSION REGION IV.
NRC Inspection Report:
50-298/87-30 Operating License:
. Docket:
50-298'
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l-Licensee:
Nebrask' a Public Power District (NPPD)
.P.O. Box 499 l
Columbus, NE 68601 Facility Name:. Cooper Nuclear Station (CNS)
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' Inspection At:
CNS, Brownville, Nebraska Inspection Conducted:
November 16-20, 1987,
/2/J/rP Inspector:
w M. E. Skow, Reactor Inspector, Test Programs Dat'e Sect on, Operations Branch
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J 11 3 b 0 ratio [ns Branch. M. Huipicutt, Chief, Test Programs Section Date l
Inspection Summary Inspection Conducted November 16-20, 1987 (Report 50-298/87-30)
I Areas Inspected:
Routine, unannounced inspection of followup of 10 CFR Part 21 reports, inspection and enforcement notices, bulletins sent for information, generic letters, and licensee event reports.
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Results: Within the three areas inspected, no violations or deviations were identified.
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L 2-DETAILS i
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Persons Centacted
- J. M. Meacham, Acting Division' Manager of Nuclear Operations
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G. R. Horn, Division Manager of. Nuclear Operations
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E. M. Mace, Manager, Engineering
- L. E. i' ray, Regulatory Compliance Specialist
- C. R. Moeller,. Technical Staff Supervisor S. J. Jobe, Simulator Supervisor
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- J.. Ditto, Quality Assurance
- J. R. Flaherty, Plant Engineering.
The NRC ins)ectors also interviewed other licensee employees during the-course of tie inspection.
- Denotes those present during the exit interview held on November 20, 1987.
2.
Licensee Action on Previous Inspection Findings-The following items were reviewed by'the NRC inspectors to verify that the licensee's responses to the items identified in previous inspection reports are now in conformance with regulatory requirements and that corrective reasures were completed in a' timely manner.
.(Closed) Violation (298/8630-01):
Primary Containment' Integrated Leak Rate Test. This violation concerned failure to document "as found" conditions.. Procedure No. 6.3.1.3, Revision 9, " Primary ' Containment Integrated Leakage Test," was revised to measure and document potentially excessive leakage..This' item is closed.
(Closed) Open Item (298/8719-01):
Drawing and Label Deficiencies.
This item discussed deficiencies between 50P 2.2.22. Revision 16, Appendix B, and Drawing Burns & Roe 3010.
Revision 17 of S0P 2.2.22.has been issued and was found to agree with'the drawing and the labels on the breaker panels. This item is closed.
(Closed)OpenItem(298/8712-03):
Drawing and Label Deficiencies.
This item discussed deficiencies between S0P 2.2.73, Appendix A. Revision 11, and Drawing Burns & Roe 2037.. Document Change Notice 87-1548, dated July 7, 1987, was issued to correct the drawing. This item is closed.
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(Closed) Unresolved Item (298/8718-02):
Setpoint Drift of Barksdale
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Bourdon Tube Pressure Switches, Model-B2T. The licensee reported that Barksdale Model B2T pressure switch drift problems had been identified.
The setpoint drift was postulated to be the result of seasonal environmental variations. The setpoint drift wa; reported as a generic interest to aid other utilities in their evaluatiori of Barksdale setpoint problems.
This item is closed.
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Followup of-10 CFR 21 Reports, Inspection and Enforcement' Notices,- an'd
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Bulletins sent for Information-The' purpose of:this inspection was to verify (that' the licensee: reviewed
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10 CFR Part --21 reports..Information Notices ins),andInspectionand-N
. Enforcement Bulletins (IEBs) for applicability, provided. appropriate
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-distribution, and scheduled'.or performed appropriate corrective ~ actions,
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if applicable.-
The;NRC inspectors reviewed the.following IEBs:
a.
'IEB'79-01B;79-01B, $2; and-79-01B, S3; " Environmental 1 Qualification of~
i Class _IE Equipment.".. These bulletins were addressed as.part of NRC'
Inspection 1 Report 50-298/86-28.- That report stated,;"No deficiencies
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were foundLin the licensee's implementation of corrective action-commitments made as'a result of identified deficiencies 0in the:
'(1) January-30,'1985,SER;(2) December 9,1982,SER/ November 24-
L 1982,.FRC TER; and (3) NPPD response letter of April 24,1984, documenting _ corrective action commitments.as a result of:the March 29, 1984, meeting between NPPD and.NRC." These IEBs are closed.
.b.
IEB 86-01, " Minimum Flow logic Problems _ That Could Disable RHR Pumps," dated May 23, 1986.. This IEB.is'.not applicable to the Cooper.
Nuclear Station- (CNS). EThis IEB is closed' at 'CNS.
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IEB 86-02, " Static 0-Ring Differential Pressure Switches," dated July 18. 1986.
This IEB is not applicable to.the CNS. This IEB:is closed at CNS.
d.
IEB 86-03, " Potential Failure of Multiple ECCS Pumps Due to Single.
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Failure of' Air-0perated Valve in. Minimum Flow. Recirculation Line "
dated October 8, 1986. This IEB is not applicable to the CNS. This IEB;is closed at CNS.
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IEB 85-03, " Motor Operated Vaive Common Mode Failures During Plant Transients Due to Improper Switch Settings," dated November 15, 1985.
This IEB was issued as a result of several events at nuclear power-plants during which MOVs failed to function on demand. The purpose of this IEB was to request licensees to develop and implement l
r programs to ensure that switch settings on certain safety-related
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M0Vs are selected, set, and maintained correctly. The switch settings should accommodate maximum differential pressure (DP)
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j expected on these valves during normal and unusual events within the design basis of the nuclear power plant.
The NRC inputs and methodology adopted by the Boiling Water Reactor Owners Group (BWROG) were utilized to select safety-related MOV in high pressure systems. Vendor design documents and formulation i
recommended in the SWROG report (GE BWROG' Report on Operational Design Basis of Selected Safety-Related M0V, NEDC31322,
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Septemb'er 1986) were used to de'termine.the design and maximum
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expected DP for each MOV.
CNS identified the HPCI and RCIC Systems as the focus of their response subsequent to a review of this report.
The licensee had scheduled testing of the above 6 referenced valves during the refueling outoge between February and April 1988.
This letter from M0 VATS Incorporated to Nebraska Public Power District (NPPD)datedAugust3,1987,statedthatthrustrequirements for 19 valves under DP conditions were recalculated with updated DP and system pressure values supplied by NPPD. A review of the DP base data indicated no DP testing for 13 of the4 19 valves was required.
M0 VATS recommended that 6 valves be tested under pressure to verify operability testing. The valves recommended for testing were listed as follows:
HPCI-MOV-M021, HPCI-MOV-M025, RCIC-M0V-M0131, RCIC-MOV-M0132, RCIC-M0V-M027, and RCIC-MOV-M030.
- The. licensee has prepared a procedure, " Differential Pressure Testing.
of Limitorque MOV Using the M0 VATS Valve Analysis System,"
Revision'O. The licensee will use this procedure during testing of-the valves. The licensee has scheduled testing of the'above.6-refererced valves during the 1988 refueling outage between February and. April 1988.
IEB 85-03 remains open pending acceptable completion of required testing of these six valves.
The NRC inspector reviewed ins 86-64 through 86-110 and 87-01 through 87-47.-
Procedure Nos. 0.10.1, Revision 1, " Operating Experience Review," and 0.15 Revision 4, " Commitment and Open Item Tracking,"
were also reviewed. The ins appeared to have been processed according'to procedures, were routed and reviewed appropriately, and action taken when appropriate. The NRC inspector noted that some ins appeared not to have been reviewed, because the Regulatory Compliance
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Specialist had received neither completed documentation back nor status information from personnel assigned action. The NRC inspector then reviewed the licensee's overdue list and found that certain open ins were from as far back as 1985. The NRC inspector noted that Procedure 0.15 requires that a due date be assigned'for action on the ins.
Computer reports are prepared and distributed that include overdue items.
However, the procedure does not require any specific action or management inquiry for overdue ins.
After discussing the overdue ins with licensee personnel, the NRC inspector concluded that the ins were reviewed but in some cases documentation was late due to other higher priority items taking precedence. The ins 86-64 through 86-110 and 87-01 through 87-47 are considered closed.
Part 21 reports were received by the licensee from a variety of sources, most often from vendors and the resident inspectors.
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licensee processed incoming Part 21 reports in accordance with l
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_ Procedure 0.15.. Routing, distribution :and action appeared to be-
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adequate.
Included in the review ~were Partl21 Report Nos.86-003
Jthrough 87-061; these reports are considered closed.
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No. violations:or deviations'were noted.
3.
Generic Letter' Followup #
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The purpose of this' inspection was to ascertain the information' discussed '
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in. generic lettersL(GLs) was addressed.by the licensee;and. appeared
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adequate.. Any. technical review performed'by the NRC inspector was not-
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. intended 'to replace; the technical review of: licensee responses performed-
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.by NRR.. Rather,-the review was-intended to concentrate on policy,
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operational or procedural changes, schedules, and equipment. GLs 87-001 through-87-014 were reviewed during this' inspection.-
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The following GLs were for information only, and the information appeared i
E to have been adequately' distributed: 87-001,87-004, 87-007, and 87-008..
These GLs are' considered closed.
The following GLs requested information from the: licensee: 87-005,-
l 87-006, and 87-014. The responses appeared complete and adequate. These GLs are considered closed.
o The following GLs did not' apply to CNS: 87-012 and 87-013. These.GLs'are_
considered closed.
GL 87-010 discussed 10 CFR 73.57_ requirements for fingerprinting temporary'
workers. The licensee revised Procedure 1.1.1, Revision 1 " Criminal History Records Check," in response to the GL. GL 87-010 is closed.
l The following GLs remain open pending licensee resolution: 87-002,87-003, 87-009, and 87-011.
No violations or deviations were noted.
4.
License Event Reports Followup The following licensee event reports (LERs) were closed on the basis of the NRC inspectors revie'<!s of licensee documentation and discussions with licensee personnel:
87-008 Unplanned Actuation of Group VI Isolation Due to Personnel Error While: Calibrating Area Radiation Monitors.
Procedure 6.4.9.1,
" Area Radiation Monitor Functional: Test," was revised by the
' licensee.87-011 Unplanned Actuation of the RPS and Containment Isolation Valve Groups 2, 3, and 6 Initiated During and Subsequent to Turbine Valve Testing Due to Operator Error.
Procedure 6.4.8.2.3,
" Main Turbine Trip Functional Test," was revised by the licensee.
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87-012 Unplanned Actuation of Group I Isolation Valves During
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Surveillance Testing Due to Operator Error.
Procedure 6.4.1.5.1,
"PCIC Main Steam Line/ Reactor Water Sample Valve Isolation Logic Function Test," was revised by the licensee and surveillance requirements discussed with the' crew.87-015 Unplanned Group'I Isolation and Reactor Scram While Shut Down Due to Overtravel of.the Reactor Mode Switch When Operated.
The licensee added a " CAUTION" note to General Operating Procedure 2.1.1, " Cold Startup Procedure."
87-017-Unplanned Automatic Startup_of Both Diesel Generators Due to a and Lightning Strike on the Offsite 69KV Emergency Power Supply-87-018 Transmission System.
NPPD evaluated the lightning protection on the Omaha Public Power District's (OPPDs) 69KV line and determined that the. transmission lines were shielded, appeared-to be in good condition, the right-of-way was maintained, and'
was free of interference.
No design changes had been made that
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Emergency Diesel Generators.87-019 Initiation of Plant Shutdown Due to Malfunctioning Pressure Suppression Chamber-Reactor Building Vacuum Breaker Valves.
Procedure 6.2.5.1, " Suppression Chamber - Reactor Building Vacuum Breakers Calibration And Functional Test," was revised by the licensee to prescribe the technique to be employed during operability testing and to verify that the wafer check valves are closed following demonstration of their operability.87-020 Apparent Noncompliance with Surveillance Testing Frequency Requirements. The licensee submitted a Technical Specification (TS) change request to NRR._ This request, if granted, would permit an interval of up to 18 months between diesel generator inspections during shutdowns. Cooper Bessemer, the diesel generator manufacturer, concurred with the conditions of this TS request.
If this request is granted by NRR, the CNS TS would be consistent with GE Standard TS, paragraph 4.8.1.1.2.e.l.87-021 Unplanned Automatic Actuations of the Diesel Generators Starting Logic in 1984 and 1985 Which Were Not Previously Reported. This LER is related to LER 87-017 and 87-018 ilghtning-related challenges to the diesel generators startups.
!87-023 Setpoint Drift of Barksdale Bourdon Tube Pressure Switches, Model B2T. The licensee had determined that the drift in these switches is caused by seasonal (winter and summer) conditions.
The licensee reported this item for its generic interest to aid
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other utilities in evaluation of Barksdale setpoint problems.
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Exit' Interview The NRC inspectors conducted an exit interview on November 20, 1987, with the licensee personnel denoted in paragraph 1.
At this meeting, the scope and findings of the inspection were summarized.
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