IR 05000334/1989017

Insp Repts 50-334/89-17 & 50-412/89-17 on 890731-0810.No Violations or Deviations Noted.Major Areas Inspected: Corporate Engineering Support Program,Including Staffing,Qa, Training,Mgt Support & Communications

ML20246K574
Person / Time
Site:	Beaver Valley
Issue date:	08/24/1989
From:	Strosnider J, Winters R, Woodard C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20246K571	List: IR 05000334/1989017 ML20246K569
References
50-334-89-17, 50-412-89-17, NUDOCS 8909050509
Download: ML20246K574 (16)

Text

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I U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No /89-17 50-412/89-17 t

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Docket N License N DPR-66~

NPE-73

. Licensee: Duquesne Light-Company P. O. Box 4 Shippingport, Pennsylvania 15077 Facility Name: Beaver Valley Power Station, Units 1 and 2 Inspection At: Shippingport, Pennsylvania Inspection Dates: July 31 - August 10, 1989 Inspectors: i 23 N R. W. Winters, ' Reactor Engineer, MPS, EB, da'te DRS, Region I C#4)dA C. H. Woodard, ReRtor Engineer, PSS, EB, 2/zr/11 d/te DRS, Region I Approved by: h 1 R. Strosnider Chief, MPS, S/'f//f date ngineering Branch, DRS, RI Inspection Summary: A routine unannounced inspection was performed from July 31 - August 10, 1989 (Combined Report Nos. 50-334/89-17 and 50-412/89-17). The Corporate Engineering support program for Beaver Valley Units 1 and 2 was inspected. Areas inspected included organization, staffing, quality assurance, training, management support, and communications. The inspection also included the receipt and storage of fuel oil for the emergency diesel generator Results: No violations or deviations were identified. One unresolved item concerning diesel fuel analysis was identifie PDR ADOCK 05000334 G PNU

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DETAILS a

1.0 Persons Contacted Duquesne ~ Light Compan ~

L. Arch,: Project Manager,, Safety System Functional . Evaluation .

A. Bakken, III,= Shift Technical Adviso . (1)(2) G. Beatty, . Senior Licensing Supervisor (1) J. Crockett, General. Manager, Corporate Nuclear. Services R. Dambaugh, Power..and Distribution Systems Engineer (2) L. Freeland, Operations Supervisor (1)(2) K. Grada, Manager, Nuclear Safety G. Guzak, Maintenance Enginee H. Hruby, Materials, Codes and Standards Enginee (2) J. Kasunick, Site Maintenance Director

.K. LeGoullon,' Instrumentation, Control and Systems Engineer l' (1) R. Martin., Director, Nuclear and Mechanical. Engineering

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(1)LT. Noonan, General Manager, Nuclear Operations. Unit (2) D. Orndorf, Chemistry Supervisor (1)(2) B. Selelak, Licensing Engincer C. Schmitt, Director Electrical and Control. Engineering (1) N.'Tonet, Manager,. Nuclear Engineering D.' Weakland, Supervisor, Materials and Standards K. Woessner,. Team Leader, Safety System Functional Evaluation United States Nuclear Regulatory Commission (1) P. Tam,--NRR, Senior Project Manager (1) P. Wilson, Resident Inspector (1) Denotes those attending the' August 4, 1989 exit meetin (2) Denotes those attending the August 10 1989 exit meetin The inspectors also conta.cted other administrative and technical

. personnel-during the inspectio .

2.0 -Inspection Scope The scope of this' inspection included engineering activities performed

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for design changes and modifications. This included both modifications and changes that require NRC approval and those that do

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not. The inspection also covered the installation of selected p modifications to verify the adequacy of the desig In addition an inspection of the receipt, handling and storage of the fuel oil for the emergency diesel generators was included.

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3.0 References snd Requirements Procedures and documents reviewed are listed in Attachment _ _ - _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ - - _ - _ _ - _ - _ _ -

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4.01 Organization (37700, 37701', 37702)-

The Duquesne Light Company Nuclear' Group is organized.under the Vice President Nuclear into four sections for the operation of the Beave Valley Power Station. The sections are:

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Nuclear Operations.

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Nuclear Operations Services

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Corporate. Nuclear Services

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The Nuclear Engineering Department (NED)l reports to theLVice. President Nuclear through the Corporate Nuclear Services sectio NED is organized primarily into four groups that. report to the

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General and Plant' Engineering

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Electrical. and Control Engineering

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Nuclear and. Mechanical Engineering

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' Materials and Standards Engineering

'The Safety System Functional Evaluation (SSFE) Project Manager reports to the Manager, NED. The Stone and Webster (S&W) Project also reports to the Manager, NED, however,- S&W is contracted to provide services on g a task basis and.each task is supervised by the cognizant NED engineering group superviso The. inspectors interviewed managers, supervisors and engineers and reviewed selected projects to ascertain the effectiveness of the organization, training of the individuals, communications between organizations and the plants, quality assurance involvement, and the adequacy of the_ staffing. Selected projects were reviewed to verify the above were effectively implemente .0 Staffing The inspectors discussed staffing with cognizant managers and supervisors to determine whether the current levels were adequat :The managers stated that the licensee planned to staff the engineering

' department to a level such that 80% to 90% of the routine workload

.could be handled by licensee personnel. The licensee plans to use q contracted engineering organizations to provide personnel for tha 4 remaining work. Work on contracted tasks is performed under the J l

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direct supervision of cognizant licensee engineers. Specialized engineering projects also are purchased from outside contractors. In this manner the licensee plans.to keep a stable engineering workforce and keep the plant experience level hig .There were currently 25 to 30 S&W engineers working in the NED office reporting to licensee management. These engineers were supervised as if they were licensee personnel. The licensee stated that present plans included replacing these individuals with permanent personnel by the end of 198 The inspectors observed that there were only a few engineers working overtime during the inspection. In most cases this was ' casual'

overtime werked at the discretion of the individuals. During preparation for and during outages and in special cases overtime is routinely scheduled to assure timely completion of design work and adequate coverage of installation wor Conclusions The staffing of the engineering group was adequate. The licensee does not plan to staff for complete coverage of the required engineerin By purchasing the engineering for spect ic tasks from contractors the licensee maintains control of the work done on these tasks and maintains direct supervision of the contractor By performing 80% to 90% of the engineering work 'in house' the licensee is building a stable engineering force and high level of plant specific experienc .0 Workload The licensee has established a system whereby the lead engineer on a project is responsible for that project for the duration of his assignment in the engineering department. This assures that there is continuity from inception of the project through installation and operation. Multidiscipline projects are assigned to a lead engineer

. of the principle discipline with support of assigned engineers from other disciplines as require Each engineer in most cases is assigned to multiple projects and is responsible for scheduling the work to avoid conflict NED provides engineering support to the plant The plants depend on NED for engineering support of operation Management overview of the engineering activities is provided through periodic reviews of project status. These include review of project status and problems, and verification of the priority, schedule, and cost. As a result of these reviews changes in emphasis are made depending on updated plant requirement l L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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The current-workload in engineering is relatively heavy in preparation for'the Unit 1,,R7 outage. The engineeri_ng group has as an objective

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to finish ~ the engineering work 90 days prior to outage start. The'90 day objective is to provide time for outage planning and to allow

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procurement of the required materials and supplies in a timely manne In meeting this objective the workload tends to drop shortly before L

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the outage starts and'then increase rapidly during the outage when the

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actual installations begin.

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Priorities are set in accordance with the Beaver Valley Power Station-

' Workload Priority System Manual. The priority-is achieved through'a-set of weighting factors that include nuclear safety; significance,-

, regulatory requirements, industrial safety, cost / benefits, efficiency, n and other management consideration Conclusions-The licensee has established a viable system for controlling the engineering workload, for est-ablishing and revising priorities, and controlling the activities of the engineering organization.to meet cu rent plant requirement .0 Communications Communications within the engineering department are largely dependent

. on daily individual interactions, and discussions among the various engineers and supervisors. The inspectors noted during discussions with engineers that each was familiar with the plant and had a good working relationship with individuals at the plant Communications with personnel at the plant include the use of the-Engineering Memorandum in establishing projects, Design Change Package review, and various formal design meetings.- NED also is represented at the morning and afternoon plant status meetings to assure they are current on the plant activitie Conclusions Much of the communication with the between engineers and plant personnel.is informal. However, since the lead engineers are responsible not only far the design but also for the installation, this leads to close w(eking relationships between engineering and operations. These communications are enhanced by the onsite location of the engineering office. Attendance of the NED representative at-the daily plant status meetings assures that engineering is abreast of plant activities and statu !

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L 8.0 Training l

The inspectors reviewed training records ar.d discussed engineering training.with cognizant managers and engineers.- As a-result of these reviews and discussions the inspectors determined'that the licensee has an extensive engineering training program in. addition to the requirements fnr site acces Engineering Directive (ED) No. 42 L describes- the.raandatory training required for the engineering staf This directive' contains a matrix of courses mandatory.-for individuals in various. positions. Of the. thirteen courses in this matrix not all

are required for each position. Courses in Quality Assurance,

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Administrative Procedures, and Station Orientation are required fo all positions. Other courses such as Reactor Theory, Auxiliary Systems, and Power Generation are mandatory for selected positions only but are available to all other positions if elected by the individual. The training received by each employee is tracked and reported periodically to. department Directors. The inspectors reviewed the' records for selected individuals and determined that these individuals had taken the. mandatory-training as required by

.ED-42. . Management. estimates.that engineers new to the company spend two to three weeks in training during the first two years of employment and one to two weeks in training after the initial courses L have been complete In addition to the above mandatory courses, there are many technical courses available to engineering personnel. These courses include subjects such as system and equipment operation and maintenanc Some course titles are:

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Fire Protection

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Emergency Diesel Generators

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. Reactor Protection

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Main Steam

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Feedwater Heater Vents and Drains The licensee has'a mandatory continuing training program, conducted quarterly. . This continuing training includes plant and industry events and selected plant activitie On June 21, 1989 NED held a Technical Information Presentation Symposium to discuss activities of the engineering department. This symposium.was open to all engineering and management personnel of the company. Topics covered included the following:

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Design Basis Documents

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Safe Shutdown Analysis Appendix R

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Piping Erosion / Corrosion Measurement Data Analysis

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Probabilistic Risk Assessment The purpose of this symposium was to inform management and technical personnel of activities that are in progress in the compan Conclusions The licensee has developed and implemented a comprehensive mandatory training program for engineering and management personnel. This program includes a large number of elective course. In a review of the training records attendance was found high. Management strongly supports these training programs as evidenced by the high number of courses available and the number of individuals participating. This represents a significant commitment to training by the license .0 Review of Air Start System Modification (DCP 576) (37701)

l The inspectors selected a recently completed design change to install i air driers in the air compressor starting system for the EDGs. The

! purpose of this modification was to replace oversized check valves for I more reliable operation and to provide dry air to the starter motors of the EDG.

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The inspectors reviewed the design package to determine that this package was prepared, reviewed, and approved as required by the licensee's program. The inspectors discussed the package with the lead engineer and then wa'ked down the resultant modification. The L manufacturers instruction manual for the air drier was not included in l the design packag However, when questioned about this manual by the l inspectors the lead engineer located it by accessing the Master l Equipment List (MEL) via a conveniently located computer termina The information requested was quickly located by this method. As a side issue the lead engineer demonstrated the use of the MEL for

. retrieving engineering informatio It was apparent that the lead engineer was knowledgeable in the use of the MEL. The inspectors also verified that the drawings of the air drier system had been revised to include this modificatio During the walkdown of the system the lead engineer invited the Shift Technical Advisor (STA) to accompany the inspectors. The STA demonstrated good knowledge of the modification and thorough understanding of the Diesel Generator Syste Conclusions The design package for the installation of the air drier in the Emergency Diesel Generator starting system was found to be in

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accordance with the licensee's program. The-installation was complete and:the operations. personnel demonstrated good knowledge of the operation of this modification and of the EDG Syste The lead engineer demonstrated a good working knowledge of the' Master Equipment List and showed it had been revised to include the equipment installed as a result of this modificatio .

-10.0 Safety System Functional Evaluation (SSFE) (37700, 37701)

The purpose of the SSFE and Design Basis Reconciliation Program is to

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reconciling the Unit 1 licensing and design basis and configuration baseline for the safety systems in the plan The objective of the SSFE program are as follows:

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To demonstrate that safety systems are capable of performing the'

specified design b sis function To provide a basis for confidence that the operational readiness of safety systems is maintaine To determine that the safety systems are adequately teste To determine that training procedures and programs are adequate to assure proper operation and maintenance of the syste To determine that controls are adequate to verify the reliability and safety of the system To identify and consolidate the design and licensing basi To reconcile the design to conform to the licensing and design basis and to safely support plant operatio To establish base line documentation consistent with the Configuration Management requirement To document the design and licensing basis for efficient retrieval and applicatio To identify appropriate historical records to support the plan !

The project receives overall direction from the SSFE Management Overview Committe In addition to providing overall direction this committee is responsible- for assessing the safety significant issues during the evaluation. The Management Overview Committee consists of the following individuals:

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General Manager, Corporate Nuclear Services General Manager, Nuclear Operations Manager, Nuclear Engineering-Manager Nuclear Safety Manager, Quality Assurance Plant Manager

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The. inspectors interviewed the Project Manager and other individuals concerned with the SSFE project for Unit I and discussed the schedule for reviewing the plant systems. The Project Manager reported that management support has been excellent and that there were three systems completed in 1988 and there should be an additional four systems completed in 1989. When the SSFE. group completes work on a system a preliminary report is written that contains information on

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unresolved questions. _The Management Overview Committee reviews these unresolved questions and determines the safety significance and priority for resolving these questions. Once the priorities have been established the Project Manager assigns an individual to follow the items through'until they have been closed. The inspectors reviewed selected reports issued by the SSFE group and observed that they were

' thorough and complet Conclusions

The Safety System Functional Evaluation (SSFE) team approach is an excellent method of updating the design basis documents for the plan The composition of the Management Overview Committee indicates that there is significant upper. level management support for this projec Responses to unresolved questions were found timely and thoroug A secondary benefit of this project is the communications brought about during the performance of the evaluations between plant operations, quality. assurance, and engineering.

l 11.0 Erosion - Corrosion Control Program (37701)

The inspectors reviewed the erosion program and discussed the method of selecting components to be included with cognizant personnel. The licensee selects components based on EPRI, NUMARC and the plant operating experience. Initial inspections were parformed in 1983 for Unit 1, and the program was formalized in 1987 for both Unit I and 2 after the failure experienced at Surry. After publication of Generic L Letter 89-08-a Nuclear Group Directive was written and is scheduled

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for publication as soon as the internal reviews have been completed.

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construction prepares these components by removing insulation, cleaning, erecting scaffolding, etc., and the Inservice Inspection group performs the inspections. Component are marked with a grid pattern using high temperature paint that will remain between outages

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thus assuring that the same points can be later inspected for trending.

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' The' licensee has worked with a vendor to develop a computer based'

7 means of collecting and ana'yzing the data collected. This ' system allows the data to be. electronically recorded as it is collected the again electronically transferred to the computer for analysis thus

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analysis of thinning rates in the absence of initial wall thickness

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data, the-licensee has taken a conservative approach by assuming the

. initial wall' thickness of components to be at the lower tolerance of F the commercial' thicknes The computer analysis program allows data analysis by printing established ranges of wall thickness in various colors to visually aid E the operator'in; establishing areas of reduced wall thickness. In addition this program has the feature of representing the component in three dimensions, at operator selected attitudes, in colors representing'the' wall. thickness. In addition to,the.three dimensional display described above the program also can present the image in two -

. dimensions. The.' licensee uses prints drawn by the computer as part of the package to describe areas to be repaire During the Unit 1, R6 outage, selection of components was as follows:

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ten components selected by the CHEK computer program based on experience at other plants eight were selected based on NRC concerns

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five,were chosen as a direct result of experience at the Trojan plant

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32 were selected by engineering based on plant experience

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ten were components that had been inspected befor As a result of these inspections one component was found with a wall thickness below design minimum wall thickness and was repaired by weld

. build up. Five other components were found for which the wall thickness was projected to be below design minimum wall thickness before the next outage. Two of these were cut out and replaced, the other three were repaired by weld build up. All of these components were in a single phase system. Three were in the condensate and three were in the feedwater syste During the Unit 1, R7 outage the licensee has tentatively identified 60 components for inspection in the erosion - corrosion program. Of these 60 components 45 are to be components previously inspected and 15 are to be component not previously inspected.

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The . licensee has established an erosion '- corrosion inspection progra : based on industry information (INPO, NUMARC,5 other plants) and plant ,

specific data. The inspections during the R6 outage identified six-components requiring repair,or replacement. -The computer. program

! . developed for the. licensee has eliminated the largest sources of error f in data handling, and provides a very versatile methods for analyzing the information. Thess analysis methods include the ability to

> display the data in both two and three dimensions, in color and to rotate the three_ dimensional' display for most effective viewing. This program is designed to allow direct comparison of the data with additional.information collected in the future thus allowing effective.'

trendin .0 Emergency Diesel Generator (EDG) Fuel Oil (TI 2515/100)

12.1 Background For proper operation of the standby diesel generators, it is necessary to ensure the proper quality of the fuel oil. Appendix'B to 10 CFR 50, as supplemented by Regulatory Guide (RG) 1.137, serves as an acceptable basis for licensees to maintain a program to ensure the quality of the EDG fuel oi The NRC issued Information Notice 87-04 on January 16, 1987 to alert licensees to potentially significant problems. pertaining to the long/ term storage of fuel oil. Assurance of the proper fuel oil _ requires purchasing the correct fuel oil and a receipt inspec-tion to verify that the fuel oil is proper prior to addition to the storage tanks. Since fuel oil degrades with time and external sources contribute contamination, periodic inspection'is required to assure continued fuel oil qualit .2 Fuel Procurement Regulatory Guide 1.137 states that the oil to be used for filling or refilling the supply tank should meet the requirements of ASTM-D975-77, Standard Specification for Diesel Fuel Oils; or the require-ments of the diesel generator manufacturer whichever is more restric-tive. The licensee procures type 2-D diesel fuel oil under a blanket purchase order in which the detailed chemical and physical require-ments cited match those specified by ASTM D975. -These requirements also meet the fuel recommendations of the EDG manufacturer. The licensee purchase order further imposes documentation and records requirements and audit privileges. The purchase order and several

.recent fuel receipt documents were reviewed. Diesel fuel procure-ment including an acceptable quality assurance program were previously addressed in detail in NRC Inspection Report 50-412/89-01. No deficiencies were noted in the licensee's fuel procurement progra '

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12.3 Fuel Receipt Inspection l

Unit 1 Technical Specifications require meeting only a portion of ASTM D975 (water, viscosity, sediment and specific gravity) however, the licensee.has elected to meet all of the ASTM D975 requirement Unit 2 LTechnical Specifications are written to match the require-ments of ASTM D97 The Unit 1 storage. facility consists of two 8,000 gallon receiving tanks, two 20,000-gallon storage tanks, two 550 gallon day tanks and and two 550 gallon tanks that are. integral with the EDGs. The

, Unit 2 storage facility consists of two 58,000 gallon storage tanks and two 1,100 gallon day tank New fuel. arriving at the site is sampled and analyzed to determine if. it-meets the requirements of ASTM D975 using chemistry pro-cedure C.M.2-3.61'as follows:

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For water sediment, viscosity and specific gravity prior to adding it.to the 58,000 gallon fuel storage tanks at Unit 2 and the 8,000 gallon holding tank Unit For oxidation stability within one week after receipt and

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adding to the above tank The remainder of the ASTM D975 parameters are analyzed withi two weeks (flash point, cetane number, carbon residue, ash, sulfur, copper strip corrosion, 90% distillation temperature, and cloud point).

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After analysis the fuel is transferred from the 8,000 gallon holding tank to one of two-20,000 storage tank At the time of new fuel arrival any accumulated water in the-receiving tanks is measured and if over a specified level remove .

. These samples are taken from the delivery tanker using an all-levels sampler. Both the sample parameters and sample analysis completion times are within Regulatory Guide 1.137 guideline No deficiencies were noted in the fuel receipt, inspection or

, analysi .4 Stored Fuel Degradation Information Notice 87-04 alerts licensee's to potential significant problems pertaining to the long term storage of fuel oil for the diesel engines. The notice described an incident of EDG shutdown,

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which was caused hy aged and degraded fuel particulate which blocked fuel filters and caused engine shutdown. A review was made of the licensee's internal documentation of applicability and impact for both Units 1 and 2. Conclusions reached by the licensee were that the design, operation, surveillance, and maintenance of the EDG units were such that failures as described by the informa-tion notice are not expected to occur at Beaver Valley. The inspector found no discrepancies in the licensee's analysis. However, there are some concerns which are detailed in other sections of this repor In addition , the licensee does not use fuel additives to retard oxidation and inhibit biological growth in the fuel. An analysis is currently underway to evaluate the use of these additives and/or additional sampling to detect fuel degradation in long term storag The fuel storage tanks are pumped out and cleaned on a ten year interval basis in accordance with Regulatory Guide 1.137. Both Unit I tanks were cleaned in 1986. Unit 2 tanks are scheduled for cleaning in 199 .5 EDG Fuel System - Unit 1 Each EDG fuel system has redundant fuel oil pumps and strainers to provide fuel from the 20,000 gallon storage tanks to the 550 gallon day tanks. Fuel oil from the day tanks is gravity fed to integral EDG 550 gallon tanks. Fuel oil from the integral tanks is pumped by both an electrical and engine driven pump througn a filter to the EDG injectors. Either pump can sustain EDG operation. Although the filter is duplex, it is operated in the 'both' mod The filters are routinely inspected and replaced each refueling outag For Unit 1, the licensee performs monthly routine sampling and analyses for water, viscosity and sediment on fuel oil removed from the large storage tanks and the day tanks. However, the inspector observed that there are no sampling / analysis of fuel in the integral day tanks nor are there additional analyses of the samples to determine the other ASTM D975 parameters to detect long term fuel degradation or biological growth (ASTM D2274). The extremely long residence time of fuel oil in the 20,000 gallon storage tank without the use of additives to inhibit breakdown by oxidation and to prevent biological growth may lead to sufficient fuel oil degradation to cause EDG failure to start or operat The licensee is currently evaluating the need for additional testing and fuel additives. The long term quality analyses of the EDG fuel oil is an unresolved item pending the iicensee's determi-nation of the need for fuel additions or additional sampling and NRC review of this determination (50-334/89-17-01).

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12.6 Fuel System - Unit 2

. Unit 2 fuel oil system requires, receipt of incoming fuel oil-directly into 58,000 gallon underground EDG fuel oil storage tanks. Fuel pumping.to each EDG is via redundant safety related 1 pumps'to a 1100 gallon day tank. Fuel from the. day tank is pumped via an electric (start /back up) and gear driven engine N

fuel pump. Fuel to the EDG units is filtered by.a duplex filter

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prior to injection The' filter is instrumented to provide indication / alarm during operation. The duplex feature permits switchover/changeout of the filter during operation. The filters are inspected / replaced each outage. No deficiencies were observed in the Unit 2 fuel syste .7 EDG Fuel Oil Control - Units 1 and 2 FLe1. flow to the EDG injectors is controlled by tho Woodward governor which has provisions .for local control. A review of the governor operating, control and shutdown circuits revealed that the governor is fail safe, i.e. in the event of loss of contro power it will continue to operate as a mechanical governo Manual operation and shutdown capability is provided. Detailed operating procedures provide the specific information required for operating in this mode. The procedures provided to the operators'

for local EDG operation were deemed adequat .8 Adequacy of EDG Fuel Oil Supply NRC Information Notice 89-50 identifies a pctential for the existence of an inadequate onsite EDG fuel supply. The Notice indicated that a nuclear plant recently updated its EDG seven day fuel oil consumption calculation based upon the equipment loading and found this value to exceed their minimum Technical Specifica-tion fuel supply requirements. -Since receipt of this Information Notice, the licensee had conducted an evaluation of the current EDG loading and fuel consumption for both Units 1 and 2. A review

. of-the licensee's evaluation including the basis and conclusions indicates that the fuel supply is adequate and it exceeds Technical Specification minimum requirement .9 Conclusions The licensee's program for the procurement, receipt, sampling and inspection of the EDG fuel oil is considered to meet the guidelines c established in Regulatory Guide 1.137 except that in Unit I the integral 550 gallon tank and the 20,000 gallon fuel storage tank are not periodically sanpled and analyzed to assure that the fuel is in compliance with ASTM D975 parameter _ - _ _ _ - _ _ _ _ _ _ - _ - _ - _ - - _ - _ _ _ - _ .

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There is:some' concern for the long. term d.9radation of the fuel oil as described by Information Notice 8' 34. The licensee's

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' current evaluation of the need for fuel additives and/or additional'

sampling and analysis should resolve this concern' .

13.0 Unresolved Items Unresolved items are matters about which more information is required

in order to ascertain whether they are acceptable' items or violation Unresolved items are discussed abov Management Meetings-Licensee, management was informed of the scope and purpose of the inspection at the beginning of the inspection. The findings of the inspection.were discussed with licensee representatives during the course of the inspection and presented to licensee management at the August 4 and 10, 1989 exit interviews (see paragraph 1.0 for

- attendees).

At no' time during the inspection was written material provided to the

. licensee by'the. inspector. .The licensee did not indicate that

. proprietary information was involved within the scope of this inspectio ,

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ATTACHMENT'A

_ DOCUMENTS AND REQUIREMENTS REVIEWED

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Document Revision' Tith Number ..

,10/10/88' .. Safety System Funct'ional Evaluation and Design :

' Basis Reconciliation Program Manual Safety System Functional Evaluation and Design-basis. Reconciliation Program Manual ED-47 -5 -Nuclear. Technology Training for Technical Staff and Managers 6/21/89 Technical Information Presentation Symposium

' NEAP-Zal -1 Station Modification Requests-NEAP- :Desig'n Change Control

. Classification of Structures, Systems and

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L NEAP- lL Components-

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NEAP- . Design Concepts NEAP-2.71 1 . Engineering Specifications NEAP-2.17 0 ISI Drawings NEAP-3.3-(UAP-3.3) ' Contracted Engineering Services NEAP-6.8; O MEL Control and Update ASTM D975-77 Standard Specification for Diesel Fuel Oil ASTM D2274-80 Standard Test Method for Oxidation Stability of Distillate Fuel Oils

!USNRC Regulatory Guide 1.137 - Fuel Oil Systems for Standby Diesel Generators L_ _ _ _ _ _ _ _ _ _ _ . . - _ - _ _ _ _ - _ _ __ _ - _ - _ _ _ . - - _ - -