IR 05000298/1987018
| ML20236K837 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/03/1987 |
| From: | Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236K822 | List: |
| References | |
| 50-298-87-18, GL-84-11, IEB-82-03, IEB-82-3, IEB-83-02, IEB-83-2, TAC-55595, NUDOCS 8708100017 | |
| Download: ML20236K837 (5) | |
Text
{{#Wiki_filter:N .. , APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-298/87-18 License: DPR-46 Docket: 50-298 Licensee: Nebraska Public Power District (NPPD) P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station (CNS) Inspection At: CNS Site, Brownville, Nebraska , Inspection Conducted: July 20-24, 1987 W .(.1[[ b'!3!b7 Inspector: . . W. M. McNeill, Project Enginebr, Project Date~ Section A, Reactor Project Branch Approved: das / g2 ,, ,- P/ Jaud9fi, Chief i Fi'oj6ct Section A IT/te' eacitor Prbjects Branch Inspection Summary Inspection Conducted July 20-24, 1987 (Report 50-298/87-18) I l Areas Inspected: Routine, unannounced itspection of licensee action on ' previous inspection findings; IE bulletiris/ Temporary Instructions; and licensee event report followup.
Results: Within the area inspected, one violation was identified (failure to report as required by 10 CFR 50.73).
l l 8708100017 870804 i PDR ADOCK 05000290 ! O PDR l , - - - _ - _. - - - - _. _ - _ _ _ _ _. _ - - _ - - _ _. _. - _ _ _ _ _ _ _ _. _ _ _
I l .. . i
! ! DETAILS 1.
Persons Contacted NPPD B. Brungardt, Operations Manager J. C. Ditto, QA Specialist J. R. Flaherty, Plar.t Engineering Supervisor R. Foust, Lead Electrical /I&C Engineer S. S. Freborg, Lead Mechanical Engineer
- C, R. Goings-Merrill, Regulatory Compliance Specialist G. R. Horn, Nuclear Operations Division Manager
- G. M. Mace, Plant Engineering Supervisor
- J. M. Meacham, Techanical Manager D. L. Reeves, Staff Engineer
- D. R. Robinson, QA Specialist M. J. Spencer, Performance Engineer V. L. Wolstenholm, QA Division Manager
- Denotes personnel attending exit meeting.
l The NRC inspector also contacted other plant personnel including administrative and clerical personnel.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item 298/8620-01: This item involved the licensee's nonconformance trend report program.
The licensee has issued quarterly trend reports for the last three quarters.
The trend program is still under review. As of yet, the trend program does not address outside i audits such as INP0, identify the discipline or work unit responsible for a nonconformance, correct for activity levels, or apply a Pareto Principle to the trends.
(0 pen) Open Item 298/8630-09: This item involved the licensee's ') identification of the cause of cracking in the standby diesel generator I heads.
The Nonconformance Report (NCR) No. 5182 documenting this problem is open. A suggested scenario has been documented in the supplement to Licensee Event Report (LER) No. 86-26 dated December 31, 1986. However, confirmatory evidence, such as a vendor review and comment on the scenario, has not been obtained.
) i 3.
IE Bulletins / Temporary Instructions l The following temporary instruction was reviewed by the NRC inspector for l applicability to CNS and to determine if the licensee had performed the required actions.
- - _ _ _ _ _ _ _ _
--___ , .. .
(Closed) Temporary Instruction (TI) 2515/89, " Inspection of Licensee's Actions Taken to Implement Generic Letter 84-11: Inspections of Boiling ' Water Reactors Stainless Steel Piping," requires that piping susceptible to intergranular stress corrosion cracking (IGSCC) identified as a result of IE Bulletins 82-03 and 83-02 be verified in regard to the inspection program, competence of ultrasonic (UT) examiners, leak detection, and { performance of inspection and subsequent sections.
In regard to the inspection program, previous NRC Inspection Reports 298/83-10 and 83-14 I addressed the review of the program and procedures as well as the l witnessing and review of inspection activities.
This included repair by ' weld overlays.
These same reports also reviewed and witnessed the qualification of the personnel used at CNS.
Leak detection limits and technical specification revision was addressed in previous NRC Inspection Report 298/83-18 which closed out the bulletins in question.
The competence of UT examiners, performance of inspection, and subsequent actions has been previously addressed in NRC Inspection Report 298/86-34.
This report was of inservice inspection activities of the replacement piping which is not suspect to IGSCC failure.
In the fall of 1985, all j suspect piping was replaced.
NPPD's response letter to GL 84-11 dated
June 4, 1984 (NLS 8400159), identifies that replacement pipe supercedes the requirement for reinspection of IGSCC.
Replacement pipe was type 316 with.02 percent carbon and nitrogen added acceptable per NUREG 0313 and solution heat treated to further minimize IGSCC.
Temporary Instruction 2515/89 is closed for Cooper Nuclear Station.
, J 4.
Licensee Event Report (LER) Followup The following LERs were closed on the basis of the inspector reviews, reviews of licensee documentation, and discussions with licensee personnel: 87-10 Automatic Starting of Diesel Generators Upon Loss of the Emergency Transformer Due to Inclement Wecther 87-13 Unplanned Actuation of Diesel Generator #2 Due to Loss of voltage on 4160V-1G Bus During Transfer of Power from its Startup to Normal Service 87-14 Unplanned Reactor Shutdown'as a Result of High Reactor Water Conductivity Due to Condenser Tube Leakage 87-16 Unplanned Automatic Startup of Both Diesel Generators Due to a Suspected Lightning Strike on the Offsite 69 RV Emergency Power Supply Transmission System In the review of the above LERs for Station Operations Review Committee (SORC) approval, it was noted that there were six NCRs that were decided by S0RC to be nnt reportable. One of these was NCR 87-03B dated May 12, 1987.
This NCR documented that a Group III Primary ContainmentIsolationSystem(PCIS)actuationoccurredonMay 12, 1987.
____
- _ ., . .
During perforn.ance of Surveillance Procedure SP 6.2.1.2.1, "PCIS RWCU High Flow Calibration and Functional / Functional Test", at Step No.15, the isolation relay 941-16A-K26 remained open. As a result, when the M0-15 valve breaker was re-energized, a trip signal was present for the inboard isolation valve.
l The CNS staff had concluded that because a valid actuation signal had not ' l occurred, not all of the system isolation occurred (outboard valve had remained open) and that M0-15 was not a part of the ESF, but the ESF was limited to the isolation circuit associated with pressure switch 170A.
On t this basis, 50RC voted to not report NCR No. 87-038. One nonvoting member of the 50RC (QA) disagreed with this determination.
It should be noted that the Updated Safety Analysis Report (USAR) identifies in Appendix F l that in response to criterion 43, for example, the system discussed in j of the PCIS, which Technical Specifications (TS)y penetration X-14, a part VII-3 is an ESF system.
USAR VII-3 does identif and USAR both identify as to include valve RWCU M0-15. The failure to report the ESF actuation is anapparentviolation(298/8718-01).
Another NCR, 81-02], identified that on April 14, 1987, during , l performance of surveillance procedure SP 6.1.11, three of four turbine first stage pressure switches were found to be greater than procedure set I points.
TS limits were not exceeded.
The staff evaluation dated April 28,1987, concluded that although TS limits were not exceeded, there was still a possibility of deportability under 10 CFR 50.73(a)(2)(v) and (vi), if a generic problem exists. The engineering evaluation of the NCR I dated June 30, 1987, appears to conclude that there is a generic problem with these pressure switches (Barksdale B2T) in this application. A previous NCR, No. 4252, had identified problems with t1ese same pressure switches in other applications. The immediate corrective action to NCR 87-021 was to increase the frequency of surveillance.
The NCR also stated that, "the ultimate solution to the problem of Barksdale B2T setpoint drift... appears to be the implementation of the Analog Trip modification." The NRC inspector thus concluded that a generic problem has been established for at least one application.
Since the deportability time for this had not yet run out, the deportability of this item will be checked during a future inspection, and it is considered to be an unresolved item. (298/8718-02).
5.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether or not the items are acceptable, violations, or deviations.
The following unresolved item is discussed in this report: Paragraph Item Subject
298/8718-02 Possible deportability of Barksdale setpoint problems
... i
6.
Exit Meeting The NRC inspector conducted an exit meeting on July 24, 1987, with the licensee personnel denoted in paragraph 1.
The CNS SRI also attended. At this meeting, the scope and findings of the inspection were sungnarized.
l , ' i i l ! l i . .. . . . . .. . }}