IR 05000298/1993003
| ML20217F989 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/13/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20217F876 | List:
|
| References | |
| FOIA-97-148 50-298-93-03, 50-298-93-3, NUDOCS 9708070064 | |
| Download: ML20217F989 (5) | |
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QUARTERLY PLANT PERFORMANCE REVIEW (QPPR 93-03)
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COOPER NUCLEAR STATION EXECliflVE SUMMARY
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-SALP CYCLE 011 (APRIL 25, 1993 THRU JULY 30,1994)
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FINAL
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JULY 13, 1993 1.
OVERVIEW
The refueling outage which was originally scheduled for 56 days. was extended significantly because of equipment problems.
Licensee performance in the area of problem resolution has shown significant weakness.
The initial SALP report was issued on June 23. 1993 for the SALP period ending April 24, 1993.
II, PERFORMANCE INDICATORS
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Quarter 93-01
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Analysis:
Performance indicators do not indicate situations that would warrant changes to the MIP.
Safety System Failures may indicate plant
performance which is consistent with ineffective problem resolution.
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III, SUMMARY OF SIGNIFICANT REGULATORY ISSUES The corrective actions inspection identified significant weaknesses in problem resolution.
Licensee corrective actions to address this area.have not.yet been fully implemented, and this remains a current concern.
An enforcement i
conference is scheduled on July 27 to address several significant apparent violations.
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A public meeting was conducted with licensee management on June 22, 1993, at Cooper Station to discuss the 10 start up items that the licensee was committed to resolve prior to plant start-up.
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The licensee requested mitigation of the civil penalties proposed for the start-up strainer and the 50.9 violations.
The original cps were imposed by order on June 23, 1993.
The licensee requested and was granted a rescheduling of the Service Water
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team inspection.
IV.
PLANT OPERATIONS
PREVIOUS RATINGS
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SALP 92: 2 93: 2 OP P."
0/-13: (NC)
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4 970005 NATTHEW97-148 PDR O YU300 bll
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PERFORMANCE ASSESSMENT: An on-the-spot change to a special nuclear material movement form for an abnormal fuel movement did not identify that all control rods must be inserted prior to loading bundles into the core.
Operators then loaded 2 fuel bundles without having all controi rods fully inserted.
An error in a radiation release procedure was introduced during a procedure change.
These items may indicate weakness in the verification and validation process during procedure changes.
V.
RADIOLOGICAL CONTROLS PREVIOUS RATINGS SALP 92: 2 93: 21 OPPR 07-13:
(NA)
PERFORMANCE ASSESSMENT:
No significant performance data since the SALP report.
VI.
MAINTENANCE / SURVEILLANCE PREVIOUS RATINGS SALP 92: 1 93: 3 QPPR 07-13: (NC)
PERFORMANCE ASSESSMENT:
Maintenance workers showed a lack of rigor in over-filling the batteries with electrolyte and torquing SRV flange studs without clearly having sufficient thread engagement.
VII, EMERGENCY PREPAREDNESS PREVIOUS RATINGS SALP 92: 2 93: 20 OPPR 07;13:
(NA)
PERFORMANCE ASSESSMENT:
No performance assessment since the SALP report.
VIII. SECURITY PREVIOUS RATINGS SALP 92: 1 93: 1 OPPR 07-13:
(NA)
PERFORMANCE ASSESSMENT:
No performance assessment since the SALP report.
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IV.
ENGINEERING / TECHNICAL SUPPORT t
PREVIOUS RATINGS SALP 92: 2 93: 2 QPPR 07-13:
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PERFORMANCE ASSESSMENT:
The engineering for a modification to replace drywell radiation monitors showed significant weaknesses in that an instrument designed for 2 psi was approved for use in the containment pressure boundary.
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SAFETY ASSESSMENT /0VALITY VERIFICATION PREVIOUS RATINGS SALP 92: 2 93: 3 OPPR 07-13: (NC)
PERFORMANCE ASSESSMENT:
The licensee appears to have adequately addressed the 10 start-up items.
Additionally, the licensee has identified additional items to be resolved.
XI.
0FFICE OF NUCLEAR REACTOR REGULATION SAFETY ASSESSMENT AND OUALITY VERIFICATION The continuing problems at Cooper associated with correcting the numerous problems found during the current refueling outage is indicative of weaknesses in the licensee's corrective action program.
The continuing problems indicate that the licensee needs to develop a more self-critical attitude, to get to i
the root cause of problems and resolve them with finality rather than finding a short-term fix, and to t,e more open and forthright in its dealings with the staff.
General Licensina Comments The licensing organization i Nebraska Public Power District (NPPD. or the licensee) appears to be competent, although somewhat understaffed. and does an adequate jo) of communicating with NRR and Region IV.
However. NPPD continues to be caught flat-footed by problems, and has requested expedited licensing actions on several recent occasions including (1) an exigent technical specification change requested on April 23. 1993, and issued on May 19. 1993, and (2) an expedited exemption from the requirements of Appendix J. requested on June 7. 1993. and issued on June 23, 1993.
There are 10 outstanding licensing tasks for Cooper, which is a little less than average for a plant of its vintage.
Seven of these are generic issues and three are site-specific issues. Most licensing submittals are acceptable.
but two of the site-specific issues, the battery technical specification (TS)
change and the diesel fuel oil TS change, have been extensively modified by the licensee at the request of the staff.
To the licensee's credit most of 3-l
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the changes suggested by the staff were incorporated by the licensee into its modi fied submittals.
The other outstanding site-specific task is review of i
the Inservice inspection (ISI) program.
NRR review of this issue is on hold l
pending resolution of the question of inclusion of the Service Water system and the Reactor Equipment Cooling system, both safety-related systems, into
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i the ISI program.
The licensee is still resisting this, although their j
approach appears to be a violation of 10 CFR 50.55a(g).
Overall, we see the licensee's performance as average, with some areas of strength and some areas of weakness.
In general, their submittals have been acceptable, although some license amendment requests ha.ve been deficient, both in accuracy and completeness.
We should continue to emphasize to the licensee the need for complete and accurate information in its licensing submittals.
License Amendments and Exemotions - OPPR Period 04/24/93-07/06/93
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1.
Amendment 163 issued on May 19. 1993, modified the plant technical specifications to delete Section 3/4.5.H. " Engineered Safeguards Compartments Cooling." and the associated Bases section from the TS.
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2.
Schedular exemption from the requirements of 10 CFR 50. Appendix J.
issued on June 23, 1993.
This exemption allowed Type C (local leak-rate testing of 10 containment isolation valves in the reverse direction instead of the forward direction until the next refueling outage.
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l SUMMARY OF MIP CHANGES
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CNS QPPR MEETING JULY 13, 1993 MODULE TITLE AREA ADD /
FM TO DELTA CHANGE
92702 COR:tECTIVE ACTIONS SA0V C
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-120
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30702 MEETINGS OTH C
6-54 92701-02 FOLLOWUP SA0V A
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NET CHANGE-114 i
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Justifications:
Deleted 92702 - Special corrective action inspection
not being performed.
Mini-OSTI will be conducted instead.
Changed 30702 - Reduced hours to reflect actual meeting time required.
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Added 92701 - Provide hours for required followup
inspections as a result of the many issues being identi fied.
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