IR 05000322/1986012

Insp Rept 50-322/86-12 on 860601-0715.No Unacceptable Conditions Noted.Major Areas Inspected:Conduct of Surveillance & Maint Activities & Other Routine Resident Inspector Activities

ML20205C569
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/29/1986
From:	Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205C550	List: IR 05000322/1986012 ML20205C545
References
50-322-86-12, NUDOCS 8608120369
Download: ML20205C569 (8)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

REPORT N /86-12 DOCKET N LICENSE N NPF-36 LICENSEE: Long Island Lighting Company P. O. Box 618 Shoreham Nuclear Power Station Wading River, New York 11792 INSPECTION AT: Wading River, New York INSPECTION CONDUCTED: June 1-July 15, 1986 INSPECTORS: John A. Berry, Senior Resident Inspector Clay C. Warren, Resident Inspector AoPROVED: 7/U!84-

/J/. R. Strosnider, Chief, Reactors Projects Date Signed V Section 18, Division of Reactor Projects SUMMARY: During this inspection period covering June 1,1986 through July 15, 1986, 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> of direct inspection effort were per-formed by the Senior Resident Inspector, and the Resident In-spector. The facility remained shutdown during this inspection period. The inspectors observed the conduct of surveillance and maintenance activities, and performed other routine resident in-spection activitie No unacceptable conditions were identified. One item was closed as a result of this inspection. One inspector followup item, and two unresolved items were opene .-

8608120369 860806 PDR ADOCK 05000322 G PDR -

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. 2 1. Status of Previous Inspection Items 1.1 (closed) 82-09-41: Control Room Design Review This item was opened to track the licensee's action on NUREG 0900 Control Room Design Review. This review was required by the NR The requirement for a control room design review has been incor-porated in Facility License NPF-36, Attachment 1, Item 2, and is tracked as part of the NRC TMI Action Plan Status Tracking Syste Based on this, there is no need to track this as an Inspector Follow Item. This item is close .2 (update) 86-10-02: Notice of Violation This violation involved licensee failure to provide adequate written procedures for maintenance activities on safety related equipmen Work was performed on Emergency Diesel Generator 103 (EDG-103) in accordance with Maintenance Work Request 86-0746 which provided no specific or generic written procedures. This lack of approved written procedures was in conflict with Regulatory Guide 1.33, the provisions of which are requirea by Tech. Spec. 6. The licensee condected a review of 20% of all open Maintenance Work Requests and found no other work being performed on safety related equipment without adequate written instructio Maintenance Procedure SP 31.010.01 has been reviewed and will be revised to more clearly define the scope of work allowed without approved written procedures. This revision will more closely follow section 9.1 of Regulatory Guide 1.33, which allows some maintenance activities to rely on the skill of the craft. The inspector will review the revision to SP 31.010.01 to ensure that the requirements and intent of Regulatory Guide 1.33 are me Upon completion of that review, and approval by the plant manager of the procedure revision, this item will be close . Review of Facility Operations 2.1 Plant Status Summary During the period covered by Inspection Report 86-12, the facility remained in Mode 4, Cold Shutdown, pending start-up and completion of retests on equipment modified during the source replacement and level instrument reference leg modification outages. The licensee performed required surveillances and routine maintenance activities, w

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2.2 Operational Safety Verification The inspector toured the control room periodically to verify proper shift manning, use of and adherence to approved procedures, and compliance with Technical Specification Limiting Conditions for Operation. Control panel instrumentation and recorder traces were observed and the status of annunciators was reviewed. Nuclear instrumentation and reactor protection system status were examine Electrical distribution panels were examined for verification of proper lineups of backup and emergency electrical power sources as required by the Technical Specification The inspector reviewed Watch Engineer and Nuclear Station Operator logs for adequacy of review by oncming watchstanders, and for proper entries. A periodic review of Night Orders, Maintenance Work Requests, lechnical Specification LCO Log, and other control room logs and records was made. Shift turnovers were observed on a periodic basi The inspector also observed and reviewed the adequacy of access centrols to the Main Control Room, and verified that no loitering by unauthorized personnel in the Control Room Area was permitted. The inspector observed the conduct of Shift personnel to ensure adherence to Shoreham Procedures 21.001.01, " Shift Operations" and 21.004.01, " Main Control Room - Conduct for Personnel".

2.3 Plant and Site Tours The inspector conducted periodic tours of accessible areas of plant and site throughout the inspection period. These included: the Turbine and Reactor Buildings, the Rad Waste Building, the Control Building, the Screenwell Structure, the Fire Pump House, the Security Building, and the Colt Diesel Generator Buildin During these tours, the following specific items were evaluated:

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Fire Equipment - Operability and evidence of periodic inspection of fire suppression equipment;

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Housekeeping - Maintenance of required cleaniiness levels;

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Equipment Preservation - Maintenance of special precautionary measures for installed equipment, as applicable;

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QA/QC Surveillance - Pertinent activities were being surveilled on a sampling basis by qualified QA/QC personnel;

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Component Tagging - Implementation of appropriate equipment tagging for safety, equipment protection, and jurisdiction; i

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Personnel adherence to Radiological Controlled Area rules, including proper Personnel frisking upon RCA exit;

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Access control to the Protected Area, including search activities, escorting and badging, and vehicle access control;

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Integrity of the Protected Area boundar During plant tours by a region-based inspector, and in subsequent tours by the resident inspectors, it was determined that a large number of limitorque actuator covers were installed improperly, either with an inadequate number of bolts, with improper bolting material, or with loose bolt Subsequent licensee QA investigation discovered numerous problems with inadequately secured and fastened flex conduit, missing and loose bolts, and improper bolting materia The licensee generated two LILC0 Deficiency Reports, LDR 86-246 and LDR 86-261 to document these non-conformances and track corrective action Discussions with the Maintenance Division Manager as to this situation were held. The manager stated that the licensee is detersining appropriate actions to preclude this occurring in the future. Acticns being contemplated include procedure revision and additional trainin Although these valve deficiencies are a potential violation of NRC requirements, this will be designated as Unresolved Item 86-12-01 pending further ' investigation by the inspectors and licensee corrective actio . Licensee Reports 3.1 In Office Review of Licensee Event Reports '

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The inspector reviewed Licensee Event Reports (LERs) submitted to the NRC to verify that details were clearly reported, including accuracy of the cause description and adequacy of corrective actio The inspector determined whether further information was required from the licensee, whether generic implications were involved, and whether the event warranted onsite follow-up. The following LERs were reviewe : Procedural deficiency resulted in a RBSVS/CRAC "A" initiation due to reactor building differential pressur : Full RPS actuation due to personnel error while performing an operations surveillance tes : Full RPS actuation while I&C Technicians were valving in a level transmitter after a surveillance test.

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. 5 86-022: Failure to retain particulate filters from the Station Ventilation Exhaust Monitor due to personnel error resulting in a violation of Technical Specification 4.11.2. : Missed noble gas grab samples required by Action Statement 120 of Technical Specification 3.3.7.1 : RBCLCW "A" side isolation while I&C Technicians were performing a surveillance tes : Noble gas samples required by Action Statement 120 of Technical Specification 3.3.7.11 were discarded prior to being analysed for gross activit The inspectors determined that there were a large number of Licensee Event Reports related to personnel errors by Chemistry Technician The inspectors will follow licensee actions in response to LER numbers86-022, 86-023 and 86-025. Pending the completion of the licensee's actions, and inspector review of these personnel errors, this will be Unresolved Item 86-12-02. The inspector has no further Concern . Monthly Surveillance and Maintenance _ Observation 4.1 Surveillance Activities The inspector observed the performance of various surveillance tests to verify that; the surveillance procedure conformed to technical specification requirements, administrative approvals and tagging requirements were reviewed and approved prior to test initiation, testing was accomplished by qualified personnel, current approved procedures were used, test instrumentation was currently calibrated, limiting conditions for operation were met, test data was accurately and completely recorded, removal and restoration of affected components was properly accomplished, and tests were completed within the required Technical Specification-frequenc During the inspection period the follow'ng_ surveillance activities were observed for licensee performance:

24.108.01 Diesel Auxiliary Systems Operability Tes .119.04 Reactor Core Isolation Cooling System Valve Operability Test 24.121.02 Residual Heat Removal System Valve Operability Test.

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24.123.05 Standby Liquid Control Valve Lineup Verificatio . - - .- . ..

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0 6 24.601.01 Source Renge Monitor Functional Tes No unacceptable conditions were note .2 Maintenance Activities The inspector observed the conduct of various maintenance activities throughout the inspection period. During this observation, the inspector verified that; maintenance activities were conducted within the requirements of the plant's administrative procedures and technical specifications, proper radiological controls were implemented and observed, proper safety precautions were observed, and that activities which have the potential to impact plant operations are properly coordinated with the control roo The inspector observed the following licensee maintenance activities during the inspection period:

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Emergency Diesel Generator Cam Gallery inspectio Repair of Fuel and Lube Oil Leaks on Emergency Diesel Generator (EDG-103).

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Inspection and Wire Replacement on Various Limitorque Motor Valve Operator No unacceptable conditions were note . Review and Followup of I&E Notices, Bulletins and Generic Letters 5.1 I&E Notices The inspector reviewed notices issued by the Office of Inspection and Enforcement during the inspection period. Review was to determ'.ne; if the subject of the notice was applicable to the Shoretam Nuclear Power Station, and if followup of the licensee's action was required by the inspecto The following IE Information Notices were received during the period covered by Inspection Report 86-12:

IE Notice 86-40: Degraded Ability to Isolate the Reactor Coolant System from Low Pressure Coolant Systems in BWR' IE Notice 86-42: Improper Maintenance of Radiation Monitoring System IE Notice 86-43: Problems with Silver Zeolite Sampling of Airborne Radiciodin _

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. 7 IE Notice 86-44: Failure to Follow Procedures when Working in High Radiation Area IE Notice 86-45: Potential Falsification of Test Reports on Flanges Manufactured by Golden Gate Forge and Flange, In IE Notice 86-46: Improper Cleaning and Cecontamination of Respiratory Protection Equipment.

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IE Notice 86-47: Erratic Behavior of Static "0" Ring Differential Pressure Switche IE Notice 86-48: Inadequate Testing of Boron Solution Concentration in the Standby Liquid Control Syste IE Notice 86-49: Age / Environment Induced Electrical Cable Failure IE Notice 86-50: Inadequate Testing to Detect Failures of Safety Related Pneumatic Components or System IE Notice 86-51: Excessive Pneumatic Leakage in the Automatic Depressurization Syste IE Notice 86-52: Conductor Insulation Degradation on Foxboro Model E Controller IE Notice 86-53: Improper Installation of Heat Shrinkable Tubin The large scale use of heat shrinkable tubing in a broad category of applications makes licensee response to IE Notice 86-53 of particular interest and it will be tracked as Inspector Followup Item 86-12-0 Licensee response to all remaining Information Notices will be re-viewed as part of routine resident inspection . Licensee Response to IE Notice 86-03 In response to IE Notice 86-03: Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Qualification Testing and Inspection 86-13, the licensee has initiated an inspection program to identify and replace unqualified or non-documented wire in limitorque motor operators. The program is in progress at this time and the inspection will be performed on all safety related valves inside the Reactor Building (249 valves). The inspectors are following the licensee's performance of this inspection and results will be detailed in Inspection Report 86-1 __

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, 8 Licensee Response to IE Compliance Bulletin 86-01: Minimum Flow Logic Problems that Could Disable RHR Pumps The RHR minimum flow valve logic configuration at Pilgrim Nuclear Power Station is such that sufficient flow in either A or B RHR Loops will close the minimum flow valves in both loops. A single failure of a flow sensing element could render both RHR loops inoperativ The licensee conducted a design review of the existing RHR flow logic configuration at Shoreham to determine if this same failure mode is possible at the facility. Review of as-built drawings shows that the flow sensing element in each loop controls only its associated minimum flow valve. The licensee concludes from this evaluation that a single failure could not disable all RHR pumps at Shoreham. The inspector agrees with this evaluatio . Unresolved Items Areas for which more information is required for acceptability are considered unresolved. Unresolved items are discussed in Sections and . Management Meetings At periodic intervals during the course of this inspection, meetings were held with licensee management to discuss the scope and findings of this inspectio Based on NRC Region I review of this report, and discussions with licensee representatives, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction The inspectors also attended entrance and exit interviews for inspections conducted by region-based inspectors during the perio __ -