IR 05000322/1988002

Insp Rept 50-322/88-02 on 880221-0429.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Protection, Security,Plant Events,Maint,Surveillance,Outage Activities & Repts to NRC

ML20155D987
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/02/1988
From:	Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20155D984	List: IR 05000322/1988002 ML20155D979
References
50-322-88-02, 50-322-88-2, IEB-87-002, IEB-87-2, IEIN-86-053, IEIN-86-53, NUDOCS 8806150472
Download: ML20155D987 (10)

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U. S. NUCLEAR REGULATORY COMMIs$10N .

REGION I  :

Report No.:' 50-322/88-02

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Docket No.: 50-322 licensee: Long Island Lighting Company l Post Office Box 618 i Shoreham Nuclear Power Stction t Wading River, New York 11792 .

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Inspection At: Wading River, New York ,

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Inspection Conducted

February 21,1988-Adr41'29,198 "'

"[ t Inspector: F. J. Crescenzo, Senior Resident Inspector l Approved By: / [

A. Randy 81oug VA hief

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b b Oate i Reactor Projects Section No. 3B Division of Reactor Projects ,

Inspection Summary

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Ateas Inspected: Routine Resident Inspection of plant operations, radiation protection, security, plant events, maintenance, surveillance, outage activ- 'i

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ities, and reports to the NR One hundred eighty five hours of direct

.inspectien effort were expended for this inspectio !

Results: No violations were~ identifie The licensee responded promptly, thoroughly, and professionally to issues and events during this period. The  !

inspector noted a declining trend in the performance of maintenance activities l which the licensee is addressin ;

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8806150472 880604 PDR ADOCK 05000322 TA rerere

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DETAILS 1. Followup on Previous Inspection Items (MC 93702)

1.1 (Closed) Violation 87-10-01 Failure to adequately perform sample of the Standby Liquid Centrol Tank (SBLC)

This violation occurred as a result of the licensee's failure to ob-tain an adequate sample of the SBLC tank prior to entering opera-tional condition The sample was required to verify the isotopic concentration of boron-10 within the tank and was to be performed after the sodium pentaborate powder was mixed with water. The licen-see had misinterpreted this requirement and nerformed an isotopic analysis of the sodium pentaborate powder prior to mixing it into the SBLC tank. The inspector reviewed the licensee's corrective actions as documented in SNRC letter 1376 to W. T. Russell, (NRC) from J. D. Leonard (LILCo) dated October 2,198 The inspector had no further question This item is close .2 (Closed) inspector Follow Item 86-12-03 Response to IE Notice 86-53, Improper Installation of Heat Shrinkable Tubing The inspector reviewed the licensee's actions to identify and dis-position Raychem Heat Shrinkable tubing installations which could be non-environmentally qualified. The licensee has instituted an exten-sive program to identify and inspect all installations of this type within systems or components required to be operable during accident conditions. As a result of discrepancies found, the licensee has broadened the scope of the inspections to include other manufacturers of neat shrinkable tubing and electrical components. The results of these inspections have been discussed in previous NRC inspection reports 50-322/87-10 and 50-322/87-15. These inspection reports carry inspector tracking items which will include the scope of this follow ite This item is close ..

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1.3 (Closed) Inspector Follow Item 87-16-01 Defective fittings installed in Safety Related Systems This . item concerned defective fittings which were supplied to the licensee from Guyon Industries, now Radnor Industries, of Harrison, New Jersey. The fittings were purchased to ASME section 3 specifica-tions which allow no linear indications greater than one sixteenth inch in lengt Fifteen percent of the approximately 7000 fittings of various size and dimension were found to have rejectable indica-tions. The majority of these were never installed in plant systems but were held in the warehouse. The licensee has completed an exten-sive effort to identify, inspect, and disposition all such fittings installed in class 1 systems and an appropriately sized sample from class.2 and 3 system Of the installed fittings which were inspec-ted, approximately 10*; had indications which required blending, how-ever, none required replacement. The inspector reviewed the documen-tation regarding this issue and periodically observed activities associated with the dispositioning of individual fitting The inspector found the licensee's actions to resolve this issue to be exceptionally thoroug The inspector had no further questions relating to this issu This item is close .4 (Closed) Inspector Follow Item 87-15-01 Emergency Diesel Generator Turbocharger Diffuser Cracking This item addressed cracking which the licensee had identified on the Emergency Diesel Generator (EDG) Turbocharger Diffuser. The cracking was visually identified on the 101 EDG during the performance of a routine 18 month maintenance / inspection surveillance and was subse-quently identified on the remaining two diesel unit The licensee consulted with the vendor of the diffuser (Elliot) and with another utility which had experienced similar diffuser crackin The licen-see has determined that the flaws were hot tears or shrinkage cracks resulting from tri-directional solidification of molten metal during the casting proces Additionally, the licensee has determined, based on this analysis and industry experience, that the flaws were not of a critical nature and that gross failure of the turbocharger would not have occurre It should be noted that the licen>ee com-pleted weld repairs of the identified cracks and has purchased a spare diffuser in order to minimize scheduling impact should cracking be found in the futur The licensee has also added a specific

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section to-the 18 month inspection procedure (SP 34.307.01 Rev. 12)

to include a liquid penetrant examination of the turbocharger. The inspector reviewed the licensee's actions and conclusions with respect to this issue and consulted with regional specialist-inspec-tor The inspector found the licensee's actions and conclusions relating to this issue to be complete and adequat The inspector had no further question This item is close .5 (Closed) Inspector Follow Item 85-09-01 Surveillance of Main Steam Isolation Valve Leakage Control System (MSIVLCS) one minute timer l This item addressed a concern that certain one minute timers within the MSIVLCS were not adequately tested during performance of the 18 month functional surveillance test SP 24.406.03. The timers are part

of a logic circuit designed to detect gross leakage past the inboard MSIV's following system initiation and to initiate an MSIVLCS isola-tio The licensee has revised the procedure to include a functional test of the subject timers. The inspector reviewed the revision and found it to be adequat The inspector had no further questions relating to this issu This item is close .6 -(Closed) Notice of Violation dated March 28, 1988 This Notice of Violation documented five nen-compliant conditions

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identified during an NRC inspection conducted on January 27 through February 14, 1986 and two subsequent investigations conducted by the NRC Office of Investigation (01) in response to an allegation re-ceived by the NRC concerning deficiencies in the radiochemistry departmen The licensee replied to the Notice of Violation in letter SNRC-1454 dated April 27, 1988. The inspector reviewed the l licensee's discussion of the corrective actions taken to achieve com-pliance. Specifically, the inspector focused attention to those aspects of the licensee's corrective actions which dealt with in-creased management attention to implementation of the radiochemistry program and to the responsiveness of management to Quality Assurance finding The inspector concurre with the licensee's assessment that program changes within the ac ;ochemistry department have re-suited in substantial improvements in the management effectiveness of

, the program. Recent regional speciz. list inspections of the radio-l chemistry department and the most recent SALP category 1 rating sup-port this conclusion. The Quality Assurance department has conducted

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in-depth audits of the radiochemistry department on a bi-annual basis since identification of the subject program deficiencie These audits produced significant findings and observations which were

.promptly acted upon by plant management. The most recent audit found only minor observations and concluded that the program was being effectively ' implemented. . This has resulted in a management decision to return the frequency of the radiochemistry audits to the normal annual basi NRC inspections and reviews have found senior manage-ment attention to Quality Assurance identified problems to be excel-lent in all areas of facility operatio The most recent SALP as-signed a Category 1 rating for Assurance of Qualit Two of the non-compliant conditions identified in the NOV dealt with falsification of records. These concerns, in their speciric context, had not previously been addressed by the licensee in discussions or meetings with NRC personnel. The inspector found the licensee's issuance of a memorandum reiterating the policy and seriousness sur-rounding falsification of records to be odequate. It should also be noted that the persons involved in the subject falsifications are no longer employed by the license Several NRC inspection reports have been issued since February,1986, which document the adequacy of the licensee's corrective action These include the following: 50-322/86-07, 86-08, 86-10, 86-14, and 85-1 This item is close .7 (Closedj Actions in Response to NRC Compliance Bulletin 87-02 (Tl 2500/26, MC 92703)

NRC Inspection Report 50-322/87-22 discussed the licensee's actions relating to NRC Compliance Bulletin 87-02. This issue was held open pending review of the licensee's final response to the bulletin. The inspector reviewed the final responses submitted by the licensee and had no further question This item is close . Operational Safety Verification (MC 71707, 71709, 71881, 93702) Inspeccion Activities On a daily basis throughout the report period, inspections were con-ducted to verify that the f acility was operated safely and in con-formance with regulatory requirement The licensee's management control system was evaluated by direct observation of activities, tours of the facility, interviews and discussions with licensee per-sonnel, independent verification of safety system status and limiting

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conditions for operation, and review of . facility records. . The licen-see's compliance with' the radiological protection and security pro-grams was also audited. Significant events which occurred during the inspection period were followed or investigated by the inspecto These inspections were^ conducted in accordance with NRC inspection

- procedures 71707, 71709, 71881 and J70 .2 Inspection Findings The unit remained i' cold shutdown throughout the period of this repor Significant work activities continued on the Colt diesel modifications. The licensee also continued activities associated with inspections of electrical equipment to environmental qualifica-tion standards. Routine maintenance and surveillance activities were also conducte No violations wera identified by the inspecto . Surveillance Testing (MC 61726) Inspection Activity During this inspection period the inspector performed detailed tech-nical procedure reviews, witnessed in progress surveillance testing, and reviewed completed surveillance packages. The inspector verified that the surveillance tests were performed in accordance with Tech-nical Specifications, licensee approved procedures, and NRC regula-tions These inspection activities were conducted in accordance with NRC inspection procedure 6172 .2 Inspection Findings No violations were identifie . ' Maintenance Activities (MC 62703)

l Inspection Activity During this inspection period the inspector observed selected main-l tenance activities on safety related equipment to ascertain that l

t these activities were conducted in accordance with approved proce-( dures, Technical Specifications, and appropriate industrial codes and l standards. These inspections were conducted in accordance with NRC inspection procedure 62703.

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,c 4.2. Inspection Findings No . unacceptable conditions or violations were directly observed by the inspec'.or during the inspection perio The inspector has noted an increase in the number of personnel errors associated with maintenance activities. This trend has been observed over the past several months. More specifically, the following per-sonnel errers have been noted:

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On December 29, 1987, a maintenance crew performed work on the wrong valve. Details of this are described in NRC Inspection Report 50-322/87-2 During January,1988, two motor operated valves were rewired incorrectly resulting in backwards operation of the valve These deficiencies were identified by the licensee prior to returning the valves to servic A maintenance worker performed minor maintenance on the High Pressure Injection System (HPCI) booster pump thinking -he was working on the HPCI pump. This activity was observed by the licensee's quality assurance group as part of a maintenance program audit conducted during February, 198 The licensee has identified numerouss instances of minor non-compliance with its Maintenance Work Request form progra The inspector reviewed the above events and determined that each was of minor significance when considered independent of each other. The inspector discussed with senior plant management the apparent nega-tive trend in field performance of Maintenance and Quality Control personne The inmector noted that plant management has self-identified this trend and has taken positive actions to prevent further incident These actions have included discussions and

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training with personnel to reiterate the need for attention to-detail l

while conducting maintenance activities. For those incidents involv-ing Quality Control, significant personnel actions were taken against

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! individual inspector The inspector found these actions to be

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appropriate and adequate, however, future events resulting from these type personnel errors will continue to be evaluated by the inspecto Evaluations of future events of this nature for regulatory signifi-cance will include trending consideration as well as the safety significance of each event, i

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5. Engineered Safety Feature (ESF) System Walkdown (MC 71710) Inspection Activity The inspector verified the operability of selected ESF systems by performing a walkdown of accessible portions of the system to confirm that system lineup procedures match plant drawings and the as-built configuration. This ESF system walkdown was also conducted to iden-tify equipment conditions that might degrade performance, to deter-mine that instrumentation is calibrated and f';nctioning, and to verify that valves are properly positioned and louked as appropriat This inspection was conducted in accordance with NRC inspection pro-cedure 7171 .2 Inspection Findings The Residual Heat Removal System, Core Spray System, and Emergency AC Distribution System were inspected and found to be acceptabl No violations were identifie . Licensee Reports (MC 92700, 36100) In Office Review of Licensee Event Reports 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 action The inspector determined whether information was required from the licen-see, whether generic implications were involved, and whether the event warranted onsite follow-up. These reviews were conducted in accordance with NRC inspection procedure 92700. The following LERs were reviewed:

LER 88-01: Loss of continuous monitoring / sampling of Station Ventilation Exhaus LER 87-02: Missed Fire Protection surveillances l LER 87-35: Unplanned automatic initiation of RBSt' "A" Train due I to technician error during surveillance.

l The inspector had no further questions related to these LERs.

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8 Suspected crack propagation on Emergency Diesel Generator (EDG) 102 On April 4,1988, the -licensee obtained indications that a previously identified crack on the EDG 102 had grown in depth from 0.052 inches to -

0.195 inches. The crack is one of several located on the engine- cam gallery saddle which the licensee must periodically inspect to comply with License Condition 0 of attachment 3 to the facility license NPF-3 License Condition G of attachment 3 also requires NRC staff evaluation of

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any "degraded conditions" and NRC staff approval prior to further opera-

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tion of -the engin The licensee consulted with Failure Analysis Asso-ciates (FAA) of Palo Alto, CA to determine the cause of the growth indi-cation and to assess the impact on safety and reliability of the EDG 102 due to the growth of the indicatio The results of the FAA study produced the following significant conclusions:

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The crack in question has been exposed to compressive stresses only and no credible overstressing of the crack area has occurred since licensing of the engines. This leads to the conclusion that no con-dition has been present to cause growth in crack depth.

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The method of examination used by the licensee to measure the crack depth, although state of the art, is subject inaccuracie The instrument used in these examinations operates by passing an elec-trical current along the inner surface of the crac Because of this, small metal ligaments which form bridging current paths within the crack will cause readings less that the true crack depth, The subsequent degradation of these ligaments due to oxidation or local stresses causes an immediate growth in indicated crack depth. This is believed to be the cause for the indicated growth of the crac The licensee has completed its review of the FAA report and has concurred with the conclusions. The licensee has also determined that the indicated crack growth does not represent a "degraded condition" and therefore NRC evaluation and approval is not require The inspector, along with regional specialist inspectors, reviewed the licensee's actions relating to this issue and found no cause for disagreement with the licensee con-clusion . Region I Temporary Instruction 88-01 The inspector completed the subject Temporary Instruction which concerned review of the licensee's fitness for duty progra No concerns were identified by the inspector, and the information obtained was provided to NRC Region .

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9. Management Meetings (MC 30702)

At periodic intervals and at the completion of this inspection, the inspector briefed the licensee management on the scope and findings of this inspectio The inspector also attended entrance and exit interviews for inspections conducted by region-based inspectors during the perio These activities were conducted in accordance with NRC inspection proced-ure 30702.

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