IR 05000298/1994003

SALP Cycle 012 Rept 50-298/94-03 for Period 930425-941022, Draft Quarterly Plant Performance Review

ML20217G051
Person / Time
Site:	Cooper
Issue date:	07/28/1994
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20217F876	List: IA-97-148, First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Made Available in PDR IR 05000298/1993001 IR 05000298/1993002 IR 05000298/1993003 IR 05000298/1993004 IR 05000298/1994001 IR 05000298/1994002 IR 05000298/1994003 IR 05000298/1994004 IR 05000298/1995001 IR 05000298/1995002 IR 05000298/1995003 IR 05000298/1995004 ML20217F873 ML20217F903
References
FOIA-97-148 50-298-94-03, 50-298-94-3, NUDOCS 9708070076
Download: ML20217G051 (5)

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COOPER NUCLEAR STATION EXECUTIVE SUMMARY QUARTERLY PLANT PERFORMANCE REVIEW 94 03 July 28.~ 1994

. DRAFT SALP CYCLE 012 (APRIL 25, 1993 THRU October 22, 1994) OVERVIEW The plant has been shutdown since May 26, 199 Recent licensee and NRC evaluations-have identified a number of deficiencies stemming from both past and present weakne:ces. Design basis and as-built plant eculpment problems identified by both the licensee and NRC reviews have demanced the reallocation-of resources and has detracted from any improvement efforts that the licensee has initiated through their performance improvement plan, Currently, four

)ossible escalated enforcement case.s are working (load shed testing of vital

)usses. control room ventilation, containment penetrations, and providing

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inadequate information to the NRC). The licensee announced various management changes, including a new position of site manage Engineering support for various plant problems and challenges was poor. This was due to the numerous activities, including EDG undervoltage relays, containment penetrations, and control room ventilation, potentially overburdened the engineering staff. The self-assessment teams associated with several of the plant issues have not been thorough and failed to identify operability concern I SUMMARY OF SIGNIFICANT REGULATORY ISSUES An enforcement conference was conducted on April 4. 1994, to discuss issues raised during the operational safety team inspection conducted at Cooper Nuclear Station during November 1993. Eight Severity Level IV violations were identified (most with several examples). The violations included failure to

. follow procedures, inadequate procedures, design control, and failure to comply with the Technical Specifications. No civil penalty was propose No enforcement conferences are scheduled at this time; however, the potential for escalated enforcement exists for four area III.- PLANT OPERATIONS-PREVIOUS RATINGS-1-97000

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i SALP 92: 2 93: 2 l OPPR 93-03: (NC) SPPR 93-04: (NC) OPPR 94-01: (NC) SPPR 94-02: (NC)

l QPPR 94-03: (NC)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

Routine operation activities continue to be good. The use of formal communications and repeat backs by the control room staff has continued. CNS management has increased oversight of operations. Daily control room panel walkdowns and log book reviews were being performed by upper management. The operations / engineering interface appears to be poo No adverse trends have been identified within the operations area. Overall performance in this area has remained unchanged since the last assessmen No changes in current MIP inspection hours are recommende IV, MAINTENANCE PREVIOUS RATINGS SALP 92: 1 93: 3 QPPR 92-03: (NC) SPPR 93-04: (NC) OPPR 94-01: (-) SPPR 94-02: (NC)

OPPR 94-02: (NC)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

Two significant maintenance activities associated with valve repairs were goo Vendor technical assistance was requested and the vendor recommendations provided for appropriate repairs on both valve Maintenance procedures still require skill-of-the-craft for nunerous activities instead of specifying measurable performance / acceptance criteri Durirg the followup inspection on the failure of the control room pressurization test, the surveillance procedure was found to be inadecuate since the )rocedure did not contain acceptance criteria based on the cesign or licensing Jasis and did not specify an appropriate test method. Additional problems were discovered where the licensee manipulated adjoining building ventilation systems in order to pass the surveillance test. Examples from other' inspections indicate that the utility personnel may have preconditioned systems and/or components to allow surveillance tests to pas Both EDGs were declared inoperable after the licensee identified that a 480-volt load shed device was inoperable. Surveillance procedures designed to test the electrical system did not include the undervoltage relays. Numerous examples of violations or questionable work practices were identified:

• Inadequate procedures were used for both maintenance and surveillance testing activities on safety-related switchgea i

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• Several examples of preconditioning of electrical breakers prior to taking as-found data were identified by the inspector No changes in the current MIP are recommende V, ENGINEERING PREVIOUS RATINGS SALP 92: 2 93: 20 OPPR 93-03: (-) SPPR 93-04: (-) OPPR 94 91: (-) SPPR 94-02: (NC)

OPPR 94 03: (NC)

PERFORMANCE ASSESSMENT WITH RECOMMENDATIONS:

System engineering personnel supported several valve maintenance activitie System engineers demonstrated a willingness to initiate condition reports for safety-related equipment anomalie Numerous weaknesses and violations were associated with the engineering department during this period, some of which included:

• Containment penetrations had been incorrectly classified and the required local leak rate tests and nondestructive examinations were not conducted. Additionally, a number of penetrations did not have two containment barriers outside of the crimary containmen * Engineering personnel failed to recognize the design basis of the control room envelop The control room ventilation system was unable to maintain the positive design pressure in the control roo * The licensee's self-assessments of the control room envelope testing and undervoltage relay problems were lacked aggressiveness and depth as operability concerns were not identified. During tha control room envelope assessment, the assessment recognized that the turbine and radwaste building ventilatirn systems were not operating as designed, but did not fully resolve these deficiencies or their potential impact on the control room ventilation syste * Many of the procedural, design basis, and operability concerns associated with the EDG undervoltage relays were identified by NRC inspectors well after the licensee had the opportunity to identify the Overall. engineering performance was poor and has been severely challenged by numerous events. No additional inspection hours are recommende V PLANY SUPPORT PREVIOUS RATINGS-3-

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SALP 92: (HP-2. EP-2. SEC-1) 93: (i'P-2. EP-2. SEC-1)

OPPR 93-03: (NA) SPPR 93-04: (NA) UPrR 94-01: (NC) SPPR 94 02: (NA)

OPPR 94-03: (NC)

PERFORKANCE ASSESSMENT WITH RECOMMENDATIONS:

The operating crews generally demonstrated an improved knowledge and performance of emergency pre 3aredness duties in previously identified weak areas. However, two new weacnesses were identified during EP walkthroughs dealing with event classification timeliness and the failure to activate the emergency response call-out pager syste Excellent radiological environmental monitoring and meteorological monitoring programs were maintained by the licensee. The licensee has continued aggressive decontamination efforts and has reduced contaminated areas within the reactor buildin Generally, housekeeping has improved in most areas, with exceptions noted in the less traveled areas of the plan No inspection resource changes are recommende '

VIII. TIA STATUS 93TIA003 Thermo-Lag radiant energy shield - Issued July 21, 1993 (TAC M87286)

94TIA008 Licensing basis for EDGs - Issued March 15. 1994 (TAC M89103)

I HAJOR SITE ACTIVITIES Comnleted Corrective Action Inspection Operational Safety Team Inspection Service Water System Team Inspection Planned DET-4-

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l o- e COOPER NUCLEAR STATION QUARTERLY PLANT PERFORMANCE REVIEW 94 03 July 28,1994 SUMMARY OF MIP CHANGf3 MODULE TITLE AREA IPE FM TO DELTA Code 71707 OPER SAFE VERIF OPS RI 224 374 150 92903- FOLLOWUP-ENGR ENGR RI 60 120 60 NET CHANGE +210-5-