IR 05000298/1994001

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SALP Cycle 012 Rept 50-298/94-01 for Period 930425-941022, Final
ML20217G025
Person / Time
Site: Cooper Entergy icon.png
Issue date: 01/19/1994
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20217F876 List:
References
FOIA-97-148 50-298-94-01, 50-298-94-1, NUDOCS 9708070071
Download: ML20217G025 (5)


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COOPER NUCLEAR STATION

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EXECUTIVE SUMMARY QUARTERLY PLANT PERFORMANCE REVIEW 94-01 January 19, 1994 FINAL SALP CYCLE 012 (APRIL 25, 1993 THRU October 22,1994)

I.

OVERVIEW There has been a lack of a questioning attitude by plant personnel

throughout the organization.

Significant weaknesses with identification and resolution of problems continue to exist.

The OSTI found that there was no evidence of significant demonstrated

improvements in plant performance from that observe during the corrective actions inspection.

The bases for licensee improvement plans was a licensee review of the

existing documentation of site problems (SALPs, INP0 evaluations, Entercon assessment), showing a reluctance of licensee management to recognize and find their performance issues.

/II.

SUMMARY OF SIGNIFICANT REGULATORY ISSUES An escalated enforcement action with a proposed Civil Penalty of $200,000 was issued on October 13, 1993, which addressed plant managements' apparent continuing inability to aggressively pursue effectively identify, and re~ solve safety-related equipment deficiencies.

The licensee paid the civil penalty.

Two 01 investigations are c,,an concerning a procedure change that permitted movement of heavy loads around the reactor vessel without maintaining secondary containment integrity, and that terminal lugs had been inadequately installed and a CNS inspector failed to identify the discrepancy.

An enforcement conference is scheduled for January 24, 1994 to adaress potential inoperable diesel generators because relays were misadjusted during the refueling outage.

Overall recommendation - implement SMM deci::1ons, as applicable.

III. PLANT OPERATIONS PREVIOUS RATINGS-1-9708070071 970805 PDR FOIA f)

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MATTHEW 97-148 PDR

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4199

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SALP 92: 2 93: 2

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QFPR 93-03: (NC)

SPPR 93-04: (NC) QPPR 94-01: (NC)

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PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

Operator training has improved.

Good operator performance was observed

in the recent EP exercise and in response to the recent reactor scram.

The OSTI found that the STA function at Cooper was marginally

implemented.

Management has not established expectations for some routine operational

activities such as-log keeping and shift turnovers.

Operators demonstrated a poor questioning attitude toward annunciator

response (HPCI drip leg and SGTS blown seal).

IV.

MAINTENANCE PREVIOUS RATINGS SALP 92: 1 93: 3 QPPR 92-03: (NC)

SPPR 93-04: (NC) QPPR 94-01: (-)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

There is an increasing number of examples where disparity between skill-

of-the-craft and procedure adequacy has resulted in problems (setting of emergency diesel relays, fire door inspections).

The maintenance work process was not effectively implemented:

modification was conducted under an MWO MW0s were left open after work activity was completed to facilitate coverage of additional work activities preventive maintenance tasks were not well defined MW0s were used to troubleshoot and correct adverse conditions.

011 samples from safety-related equipment that were contaminated were

not being analyzed as specified in the preventive maintenance program.

Maintenance on a fire door resulted in the door being removed from its

hinges and rendering the control room envelop in' operable without anyone recognizing that the control room envelop was affected by the maintenance.

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,,a ENGINEERING

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PREVIOUS RATINGS

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SALP 92: 2 93: 20 l

QPPR 93-03: (-)

SPPR 93-04: (-) QPPR 94-01: (-)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

Testing and installation of the RPV level instrumentation modification

was good.

The OSTI found increased engineering involvement in problem resolution

and increased ownership by system engineers for their assigned systems.

The OSTI also found that:

Modifications were left open for excessive periods of time

Drawings, procedures, and PMs were not updated when a modification

was turned over for operation temporary mods were implemented without the required review

and, a large engineering work load adversely impacted on system

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engineer's ability to get into the plant and observe the performance of assigned systems.The licensee apparently agrees that engineering is an area that needs improvement, and a new engineering manager from INP0 is onsite.

VI.

PLANT SUPPORT

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PREVIOUS RATINGS SALP 92:-(HP-2,EP-2,SEC-1)

93:

(HP-2,EP-2,SEC-1)

SPPR 93-04: (NA)

QPPR 94,-01: (NC)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

The recent EP exercise showed improvement in timeliness of notifications

and assessments of emergency conditions.

On November 8,1993 after both diesel were declared inoperable, the SS

did not declare a NOUE until prompted by the plant manager.

The OSTI found significant weaknesses in fire brigade training, STA

training, operator training on revised remote shutdown procedures, and personnel performing fire door inspections.

Overall performance was good.

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VIII. TIA STATUS N

Thermo-Lagradian(energyshield-_lssuedJuly 21, 1993

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93TIA003 (TAC ?)

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IX.

MAJOR SITEsACTIVITIES Completed Corrective Act n Inspection Operational Safety Team Inspection Planned Service Water System T Inspection

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COOPER NUCLEAR STATION

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y QUARTERLY PLANT PERFORMANCE REVIEW 94-01 January 19,1994 SUMMARY OF MIP CHANGES MODULE TITLE AREA IPE FM TO DELTA Code 71707-12 OSV OPS RI 412 188-224 71707-13 OSV OPS RI

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+224

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37700-02 ENG ENG RI

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+35 2515/109 M0V ENG SI O

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+200 92701-03 F/V OPS RI

0-40 NET CHANGE

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JUSTIFICATION 71707-12 Reas:ign hours to another occurrence (71707-13) since this 71707-13 occurrence (71707-12) was inadvertently closed 37700 Add additional hours to reflect amount actually required for inspection 2515/109 Add hours to perform the TI 92701 Delete hours as this module will not be performed-5-

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