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Insp Rept 50-443/86-05 on 860127-0207.No Violation Noted. Major Areas Inspected:Preoperational Qc,Maint & Testing Program,Review of Preoperational Test Procedures & Evaluation of Maint & Calibr Results of Completed Tests
	ML20154A949
Person / Time
Site:	Seabrook
Issue date:	02/20/1986
From:	Finkel A, Jerrica Johnson, Napuda G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20154A906	List: IR 05000443/1986005; ML20154A902;
References
	50-443-86-05, 50-443-86-5, NUDOCS 8603040186
	Download: ML20154A949 (20)
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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-05 _ . Docket N a50-_443 License No. _ CFPR-135 Priority - Category B Licensee: Public Service Company of New Hampshire 1000 Elm Street Manchester, New Hampshire 03105 _ Facility Name: Seabrook Station, Unit 1 " J Inspection At: Seabrook, New Hampshire-

Inspection Conducted: January 27 - February 7,1986 i

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" Inspectors: A. Finkel, Lead Reactor Engineer

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    ' dpe G. #apuda, Lead Reactor Engineer  '

d(te b Approved by: -

J. Johhson, Chief, ppephtional Programs

    ' dat'e Section, Operati4ns Branch, DRS Inspection Summary:

< Inspection on January 27 - February 7, 1986 (Inspection Report No. 50-443/86-05)

Areas Inspected: Routine, announced inspection of the preoperational quality contrcl, maintenance and. testing program, the review of preoperational test procedures, the evaluation of maintenance and calibration results of completed tests, review of inspections-conducted by.the Seabrook Quality Assurance and Quality Ccntrol organization, safety review committees, Procurement Control Program, and lirensee actions on previous inspection findings. The inspection involved 77 hours onsite by two region-based inspector Results: No violations were identified.

, a 8603040186 860221 PDR ADOCK 05000443 G PDR *

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DETAILS 1.0 Pgrsons Contacted New Hampshire Yankee ~ Personnel I **G. Austin, Licensing Engineer

**J. Cady, Jr. , ISEG Supervisor .
***R. Guillette, Assistant Quality Assurance Manager, Construction
**M. Harrington, Senior Engineer (MRTF Supervisor)
**G. Kingston, Compliance Manager
**R. Lizotte, Administrative Services Department Manager
*G. Mcdonald, Quality Assurance Manager, Construction
**W, Middleton, Quality Assurance Staff Engineer
*T. Murphy, Department Head, I and C
*V. Sanchez, Licensing Engineer
**R. Streeter, Inventory Supervisor
*J. Tefft, Project Engineer
***J. Warnock, Nuclear Quality Manager U.S. Nuclear Regulatory Commission
*D. Ruscitto, Resident Inspector
*R. Barkley, Reactor Engineer
**A. Cerne, Senior Resident Inspector
* Denotes those present at the exit interview on January 31, 1986
** Denotes those present at the exit interview on February 7,1986
*** Denotes those present at both exit interviews 2.0 Follow-up of Previous Inspection Findings   E (Closed) Unresolved Item 85-15-11 - Perform inspection of Limitorque operators to verify that the pinion gears were installed in the correct configuratio The inspection of the safety-related motor operated valves (M0V's) was performed in accordance with the requirements of test procedure TPI-62-F01, Revision 2, July 11, 1985, titled " Inspection of Motor Operated Valves."

Attachment 9.2 of TPI-62-F01 listed 115 MOV's that were reinspecte The inspector verified that quality control verification of the reinspec-tion of the 115 MOV's has been completed and documented on Form SQCP 10-1, Revision 3, May 20, 1985. The inspector randomly selected 25 inspection reports for inspection verification of this task. The selected reports were completed and filed in the documentation cente Th!s item is close i

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i 3.0 Plant Procedures This inspection was to assure that the licensee has written and approved - plant procedures for the safe operation of the plant that are in compliance with the Regulatory Guidance (RG) and Final Safety Analysis Report (FSAR) issued for this site. The requirements are listed in Appendix A of this repor The Nuclear Production Management Manual (NPMM), Revision 0, March 8, 1984, is issued for interim use at this time. The NPMM program is not applicable to the Nuclear Projects and Start-up organization during this phase of the program. The Nuclear Projects and Start-up organization are following the program as stated in the Final Safety Analysis Report (FSAR) and Seabrook Station Preoperational Test Program, Revision 3, dated December 4, 198 * 3.1 Nuclear Production Management Manual (NPMM) The Nuclear Production Management Manual (NPMM) establishes and

provides the overall controls for the Nuclear Production Manuals.

1 The Nuclear Production organization avd major assignments of responsibility are described in the NPMM. The NMPP establishes Nuclear Production policies and programs that apply to organina-tional and procedural activities within Nuclear Productio The NFMM establishes the requirements for the existance of other ! manuals and administrative controls. All other manuals and administrative controls are considered to be subsets of the NPM Administrative controls covering the preparation, review, approval, and revision of manuals and Department Procedures are addressed in the NPM . Nuclear Production Program Manuals (NPMM)

The NPMM defines and describes .six prog +ams that apply to Nuclear Production and those required manuals. These program manuals describe the program,. assign pepgrammatic responsibilities, and provide the administrative controls for the implementation of the program. These program manuals are described belo Administration Program Manual (NPAD)

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Design tontrol Program Manual (NPOC)

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Emergency Response Program Manual (NPER)

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Operational Quality Assurance Program Manual (NPQA)

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Records Monagement Program Manual (NPRM)

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Reporting Program Manual (NPRE) l

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3. kaabrook Stction Management Manual The Seabroot Statfor. Management Manual (SSMM)' describes ' the organizatics of Seabroek Station and assigns major-respoosibilitie . Seabrook Station Program Manuals The Seabrook Station Program Manuals provide the guidance and administrative controls required to implement-programs at Seabrook Station. Chapters within Seabrook Station Program Manuals ~may contain administrative procedures for the implementation of.the program. These administrative-procedures are written and approved in accordance with the requirements of the SSM The Seabrook Station Program Manuals.are the:

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Fire Protection Program Manual (SSFP)

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Hazardous Waste Program Manual (SSHW)

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Maintenance Program Manual (SSMA)

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General and $pecialty Training Program Manaal (SSGT)

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Occupations 1 Safety Program Manual (SSOS)

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Procurement and Materials Program Manual (SSPM)

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Radiation Protection Program Manual (SSRP)

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Security Program Nanual (SSSP)

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Test Control Program Manual (SSTC) 3.1.4 Se3b rook Station Group Management Manuals The Operations, Administrative Services, and Technical Services Groups have the following manuals:

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Administrative Services Management Manual (ASMM)

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Operatiens Menagement Manual-(0PMM)

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Technical Services Management Manual-(TSMM)

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Maintenance Management Manual

These ganuals. describe their respective Groups. Each manual assigns major responsibilities acd provides guidance for the conduct of business within the Group. Each Group Management Manual may also contain administrative procedures. These procedures are approved and controlled in accordance with the administrative procedures of.the SSMM.

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3. Nuclear Support Services Group Management Manuals Each Group Msnagement Manual describes its respective Group and assigns major responsibilities. Administrative con-trols covering the Group's support of programs elated to the Station's operation are contained within the Group Management Manuals. Nuclear Support Services Group Manage-ment Manuals do not contain administrative procedure The Group Management Manuals are the:

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Nuclear Engineering Management Manual (NEMM)

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Nuclear Information Systems Management Manual (NISM)

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Nuclear Quality Management Manual (NQMM)

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Nuclear Services Management Manual (NSMM)

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Training Center Management Manual (TCMM) 3. Operating Procedures Seabrook Station prepares and approves Operating Procedures in accordance with Administrative Controls contained in the SSM These procedures address operating, maintenance, surveillance, and associated activities specified in Technical Specification 6. Operating Procedures are maintained sepra.Lely from the manual The Document Control Center indexes and distrib-utes them in accordance with the Nurlear Production Records Management Program Manual (NPRM).

3. Department Procedures Nuclear Production Department writes Department Procedures describing administrative guidance within individual departitent Depertment Procedures address additional department support of activities described in manual The Department Supervisor approves department procedures which are controlled within the appropriate departmen No violations were identifie .2 Manual Preparation, Review and Approval The Nuclear Production Management Manual (NPMM), Chapter 4, Section 2.0, lists and identifies the various parameters that are required to establish, control and verify the issuances of the vari-ous site documentation. The following areas are discussed in the NPM ., .-~ . - . . _ - . -. - ..

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Responsibilities for documentation issuance, review and update,

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Control of issuing new and revised procedures,- disposal of outdated and temporary changes to procedures, and-

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Organization review. The method to have documentation reviewed

is described in Chapter 4 titled " Manuals Development and

Control," paragraph 2.7, Processing. This paragraph describes the method that processing of documentation will follow and - ,

identifies the submitter and reviewer.

3.3 Standi~ng Operating Orders (S00)

The Operations Management Manual (OPMM), Revision 0, August 28, 1985, Chapter 6, describes the method that standing operating orders will i follow. The procedure provides instruction in the following areas:

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Provides a method for issuance and distribution, !,

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Provides requirement for review and updating,

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Assigns the Unit Shift Supervisor to maintain a file of active i S00's in the control room, and <

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Requires the period for which it is effective if a time span of , applicability is apprcpriat . Standing Operating Order Log (S00L) . ' The inspector reviewed the S00L book entries for 1986. The log contained approximately 18 items which were all active at this time. The 500 procedure (0PMM) requires that the Operations Administrative Supervisor conducts an annual review of the effective Standing Operating Orders to verify.

. their applicability, j Discussions with the on-shift reactor shift supervisor j indicated that he was aware of the procedure requirements and the use.of the S00 log book.

I No violations were identifie .4 Night Orders

! The Operations. Management Manual (0PMM), also describes the j Operations Manager Night Order Book. .Tne-Night Order Book (NOB) is ! a loose-leaf book with an index, an active section and an inactive j section. Orders are numbered sequentially by a five digit number l , i

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system, the first two digits of which indicates the year of issue (e.g.,86-000). Operations Assistant Operations Manager or Shift Superintendent can make entries into the Night Order Book. These entries include:

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A definition of the task to be accomplished,

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The date issued, and

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The applicable time period of the orde . Responsibility The responsibilt+.y of the Operations Manager is to ensure that entries that are no longer applicable are voided while the Shift Superintendent ensures that applicable night orders are carried rit on his shif . Applicable Night orders generally apply for a period of less than one month. After the applicable period is over, an order is filed in the inactive section of the Night Order Boo . Night Order Book Review The inspector reviewed the Night Order Book in the control room to assure that:

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Orders were being numbered sequentially,

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That the book was divided in en active and inactive section, and

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That orders that were over their applicable period of - time were filed in the inactive section of tha Night Order Boo The following conditions were identified by the inspector during his inspection of-the Control Room on January 29, 198 Of the ten (10) Night Orders written in 1986, the inspector found that item 86-006 was effective up to January 25, 1986 and should have been removed four days prior to this inspection,

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Two of the Night Order forms (OPMM Form .6-2A) were entered into the book, but did not carry a code number on the form, and

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The active / inactive top sections of the loose-leaf book were missing and pages were falling out of the boo The licensee was aware of the above. items and was in the process of the following action:

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Revise procedure 2.0, Operations Manager Night Order Book, Chapter 6.0 of OPMM, .to define who will verify that the orders are sequentially numbered and assure that the nysber appears on the OPMM Form 6-2A and verify entries and void as require Since Night Orders will not be required until conduct under-an operating license, this item-is unresolved pending iden-tification of the respoasibility to maintain the Night Order Book per the requirements rf procedure 2.D of OPMM and es-taolish a method to maintain the listed data in a retriev-able conditio (86-05-01) , 3.5 Operating Shift Crew Responsibility The Operations Management Manv?1 (OPMM), Revision 0, August'28, 1985, i dese.ribes the function and responsibility of the. operation crew. Such items as preparation of operating log entries, shift turnover, and log reviews are described. The details of the'above criteria are describ-ed in Chapter 3, Shift Operations, paragraph 3.0, Shift Records of the Operations Management Manual.

3.6 Dacumentation Responsibility

' Of the documents reviewed during this inspection period, the inspector determined tnat the procedures and manual define the responsibilities clearly and define actior that is required when a deviation is identi-fie . ' As discussed in paragraph 3.5 above, the Operating Shift Crew respon- . sibilities are well defined. When abnormal or out-of-limit parameters are recorded, the shift crew has been given specific information as what action to take. The instructions also give guidance on unusual or abnormal trends.

i 3.7 Station Operation Review Committee (SORC)

2 The purpose and principles of the Station Operation Review Committee, SORC, are described in the Seabrook Station Management Manual (SSMM), Revision 1, August 14, 1985, Chapter e _ ____._.___._______________.-..__._______________________m_ _ - _ . _ . _ _ _ _ . . - _ _ _ . . _ _ ..__..m _. _ _ _ .__ _ - _ ...._.-__ ._ . . . _ . _ _ _ _ - - - ._

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, 3. Standing Operation Review Committee Documentation

The inspector reviewed 30 SORC approved procedures and de< termined that they followed the requirements of Chapter 5 of the SSMM. The operating procedure cover form, in addi-tion to having various signature blocks also under Section E (SORC approval /SORC Meeting No.), identifies the SORC meet-ing number that approved the use of the procedure. This allows traceability to the SORC meeting notes which approved the documen ,

3. Issued Procedures ' The inspector. selected 10 SORC approved procedures of the-30 referenced in paragraph 3.7.1 above for verificatio ' , The site had issued the 10 approved peocedures and the - revision numbers of the procedures in use by the plant-staff personnel.were the same revision numbers indicated on the master document lis J No violations were identified.

, 3.8 Training - Fon-License The non-license training of plant staff personnel in the requirements , contained in the Seabrook Manuals and Procedures is a task that is required to be completed prior to . full load. Due to the volume of < new and revised documentation, the training of personnel in these site documents is a task that was not scheduled at the' time of this inspectio As a result of the inspector's concern in the non-license training , area during a previous inspection (January 13-24,1986), the licensee issued a memo on January 20, 1986, No. SS #22327/IMS #5A.02.02, re-questing the operating staff to establish a training matrix and sche-dule for their personnel. An overall training schedule would then be prepared for the operating staf This item is unresolved pending issuance of the training program and schedule based on the matrix' listed in the January 20, 1986 memo.

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4.0 Maintenance Procedures

This inspection was to assure that maintenance procedures have been prepar-ed to adequately control maintenance of safety-related systems within the applicable regulatory requirements for this sit (Reference Appendix A of this report).

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P The Seabrook Maintenance Program Manual (SSMA), Revision 3, January 22, 1986, describes the maintenance policy and program control for this site.

The criteria for the following areas are described in this manua .

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Control of Measuring and Test Equipment,

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Performing Maintenance, and

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Surveillance Procedure In addition to the items listed above, the SSMA also describes such areas ' as: i

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Classification of Maintenance,

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Work Control,

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Maintenance Histor Equipment Control, and

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Training and Qualifications.

- 4.1 Control of Measuring and Test Equipment The Seabrook Station Maintenance Program controls the following j areas: ) J

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The calibration of installed equipment,

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The measuring and test equipment (M&TE) used to test and cali-brate the installed equipment, and

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The calibration of the primary and secondary standards used to calibrate the installed equipmen . Records

Records of calibration and maintenance history of each item

of equipment are maintained as described in the maintenance control program, Chapter 2 of the licensee's Maintenance

Program Manual-(SSMA). A detailed inspection on this area

it described in IE Inspection Report No. 50-443/86-0 .2 Performing Maintenance _

.In the SSMA, maintenance has been classified as either preventive or correctiv )

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4. Preventive Maintenance The licensee has described preyentive maintenance as generally scheduled maintenance, and is performed on a < routine basis. Preventive caintenance in.cludes inspec-tions, verification examinations and test and calfbratio The elements which form a basis for establishing the criteria used by the licensee in performing the various types of maintenance were developed using the following criteria:

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Manufacturer's recommendations,

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Industry, regulatory requirements, and

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Seabrook history file The department supervisor determines which structures, systems and components require preventive maint3 nanc Each department also develops instructions, as necessary, for the scheduling, performance and recording of preventive maintenance activitie The details of approving the maintenance history and the frequency of testing is described in IE Inspection Report No. 50-443/86-02, 4. Corrective Maintenance Corrective eaintenance is defined as rework, repair, adjust or replace structures, systems or components. Both cor-rective and preventive mair.tenance activities are scheduled as defined in the Mainterance Program Manua . Surveillance Procedures Surveillance Procedures are being prepared in a master computer program which is scheduled to be released by _ May 1, 1986. This subject is addressed in IE Report.N /86-02 and is listed as an unresolved ite (86-02-01) 4.3 Maintenance Procedures The inspector rardomly selected the four listed station maintenance procedures that have been approved by the Station Operatics Review Committee (50RC) fcr review and compliance wf th the criteria defined in paragraph 4.2.1 of this repor __-____ .-_ __- ___ - ___ _____- __

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MS 0514.08, Revision'00, April 1, 1985,-Termination of 4.16 KV l and 13.8 KV Motor Leads,

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MS 0513.30, Revision 00, June 29,1984, Type IJCV 51A Over.- current with Voltage Resistraint Relay Inspection, Testing, and PM,

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MS 0519.16, Revision 00, Pressurizer Mechanical Safety Valve Installation, and

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MS 0524.07, Revision 00, General Procedure for the Removal of

Steam Generator Secondary Side Handhole Cover The above procedures either described or listed the following. areas

, in each of the procedures for the technicians to follow.

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Objective - Brief description of the test and condition of'the subject equipmen References - This section referred to such areas as maintenance criteria, standards, drawing and manufacturer's criteri Discussion - Identified the type of maintenance to be performed,

testing informaticn, in service - out of service criteria.

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Acceptance Criteria - This area has specific criteria for the ,

specific item and then references section 8.0 of the procedure

$ which listed the detail test criteria for the subject item.

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Precautions - This area of the procedure identifies equipment safety requirements as well as system configuration criteri ; As an example, MS 0524.07 listed the condition that the steam generator secondary side must be in and a requirement not to

damage the gasket recess area with nicks, gouges or scratches.

[ -- prerequisites - This area lists specific material like lifting or handling equipment, calibration equipment, bolt loosening sequence or flange sequence. These criteria are referenced in , , Figure 10.1 of each procedur ' k -- Initial Conditions - This area defines the condition of the i system such as " Reactor in Mode 5 or 6."

! After the procedure is completed, section 8.0, the technician's comments are listed, signed and dated. The procedure results are , reviewed and signed by the responsible superviso The analysis of the procedure results and action taken by the super- i visor is discussed in IE Report No. 50-443/86-02. An example of the ' type of data required by the procedures is listed below.

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Record as found cendition,

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Visual condition of equipment recorded, i -- Such items as bolts, screws, nuts and bolts are in place and tight, and .

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Condition of the equipment when it was returned to service.

2 All procedures have space for comments by the technician, which is to be reviewed and resolved, if necessary, by the signing supervisor.

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;   A random sample of 20 test procedures selected by the inspector

verified that the technicians were completing all input requirements of the test data sheets. Comments were reviewed and signed by the responsible-supervisor and discussions with operating personnel i

  -indicated that they were satisfied with the resolution of their :

recorded ite , No violations were identified.

. 5.0 _ Review Committees 5.1 Onsite deview Committee

, 5. program Review and Organization 4 i The inspector reviewed plant administrative procedure Station Operation Review Committee (SORC), Revision 0, part of Seabrook Station Management Manual, Chapter 5, to deter-

mine whether administrative controls have been established for the followin Independent review authority and responsibility I

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Ensuring the completion of reviews required by Tech-nical Specifications

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5. Implementation .. The committee has been established and is functioning l witn respect to its current respcasibilities. Objective i evidence that the committee was fulfilling its responsi-bilities such as review and approval of plant procedures, routing ilirs to members of items to be reviewed several , meeting minutes, and copies of reports were. reviewed or observed b.y the inspector. The chtirman demonstrated knowledge and understanding of committee authority, !

functions, and responsibilities.

The inspector-reviewed the 50RC membership.and selected appointed alternates'to verify their job position, educa- , tion, and experience and training. It was noted that the alternates equaled or exceeded the qualifications cf those members required by TS and FSAk, f 5. Findings i ) Based on the results of the review performed in this area,

the onsite review committee and current status of opera-J tional implementation is in compliance with TS_and FSAR commitment It was also determitied that the committe '

;  is ready to support plant operatioe No violations were identified.

f 5.2 Offsite Review Comnittee 5. Program Review and Organization The Nuclear Safety Audit and Rev!ew Committee (NSARC) i charter, approved by the Senior Vice President, and proce- , dure Nuclear Quality Group Administration, Revision 0, part ' i of the Nuclear Quality Management Manual, Chapter 5, were

reviewed to determine whether administrative controls have been established for the followin ; . -- Independent review and audit authority and-responsibility

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Manner by which TS Section 6 reviews and audits will " be accomplished -i

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Membership, alternate members, and quorum requirements '

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15 ; 5. Implementation The committee has been established and is functioning with respect to its current responsibilitie The com-mittee is also planning on how to accomplish near term responsibilities. The inspector noted that the committee meetings began in October, 1985 and will be held on a quarterly cycle until the first Refuelin The committee consists of nine members from New Hampshire Yankee Atomic (NHYA) and other Yankee Atomic Electric Company (YAEC) source The personnel files of all mem-bers and selected alternates were reviewed. Current members have the education, experience and training to meet or exceed the areas of expertise required by TS and the FSAR with one exception. The expertise in metallurgy will be provided by an appointed alternate as neede The inspector reviewed the minutes of meetings 85-001 and 86-001 and noted that topics discussed included licensing, startup test program, cable tray qualification, SORC minutes, audit reports, and NUREG-0737 items. Also, a formal method of tracking recommendations and their status has been established. The chairman demonstrated knowledge

,  and understanding of committee authority, functions and responsibilitie . Findings Based on the results of the review performed in this area, the offsite review committee and current status of operational implementation is in compliance with the TS and FSAR commitments. It was also determined that the committee is ready to support plant operation No violations were identifie .3 Independent safety Engineering Group (ISEG)

5. _ Program Review and Organization The inspector reviewed the ISEG Charter; ISEG Interface Agreement, Revision 2 (draft); and ISEG-01, Document Review Guidelines, Revision 1, to determine whether the following had been accomplishe The Charter and procedures were established in , accordance with regulatory requirements and licensec commitments

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The organization was delineated and staffed to meet regulatory requirements {

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Organizational independence existed and interfaces ' were delineated i

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Appropriate responsibilities were established and assigned

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Procedures were established for the control of ISEG activities .

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Provisions were established to assure that records are i properly mair.tained and transferred to a storage j facility 1 -- Administrative controls were established to support j the required organizational responsibilities

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Provisions were established to assure that ISEG < receives information and intelligence gathering l

resource materials upon which to base its reviews and activities

5.3.2 Implementation

The group has been functioning since April, 1984-and its reviews included INP0 SERs and SOERs, and Westinghouse Data Letters and Bulletins. Approximately 320 of 563 documents reviewed were INPO items with 70 of the latter still yet to be complete It was noted that about 190-recommendations, as a result of these reviews, were forwarded to the Station Manager, Nuclear QA Manager, Startup Manager and Training Center Manager. The review results and recommendations are currently tracked by way of a typed log and a computerized data base is anticipated for these and other information such as assignments and review status. The group super-visor also issues a monthly report to various managers and vice president The five current members possess education, experience , and/or training in chemistry / radiation protection, ' electrical.and mechanical engineering, maintenance, startup i and test, and nuclear reactor operations. All have exten- 1 sive experience in the latter area. It was noted that one ' , member is on loan to the preoperational test organizatio l

The group supervisor stated that this member will return to his ISEG position at least three months prior to initial . ; fuel loadin l i

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5.3,3 dn Fi ndi,ris_

Based on tne review performed in this area, the ISEG and current status of activities is in compliance with the TS and FSAR commitments. It wa3 also determined that the group is ready to support plant operation violations were identifie .0 Procurement 6.1 Procram Review The Procurement and Materials Program Manual was reviewed to deter-mine whethar adefoistrative controls were established for:

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The identificatico cf items purchased; identification of tests and/cr special instructions, technical requirements and docu-mentation to certify the item; assurance that the contractor / supplier has implemented a QA progran consistent with 10 CFR 50, Appendix B, and where deemd appropriate by the licensee, access to the supplier's plant or records for purposes of audit;

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Initiation of procurement documents; review and approval of specifications differing from the original design documents; review and approval of procurements, including changes thereto; and the designation of quality classification of procured items; and,

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Assignment of the evaluation and approval of bidders / suppliers, including review / update of the listing of approved suppliers; providing for rights of access to supplier's facilities and records; and maintenance of records of supplier's qualifications and audi .2 Implemen,tation An onsite engineering group, the 14aterials Review Task Force (MRTF), was established and has beer, reviewing requisitions for spare part Items, components, and subcomponents (i.e., internal parts) are evaluated as to their intended use and assigned to one of five procurement classifications. Procedures identify procurement require-ments (i.e., specific clauses) for the classifications. The item identifier, safety class, procurement classification and requirements, stock inventory and other pertinent information are entered into an electronic information system. The inspector conducted an overview of the spares purchasing and determined that engineering ovaluations were done; item, materials and subcomponents were classified as to the level of their intended use; this information was entered into the information system; and these activities were accomplished in accordance with established procedures.

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The offsite warehouse and storeroom located within the onsita

. administration building were toured to observe storage conditions and control. It was noted that a preventivs maintenance schedule and shelf life control had been establistled. The following items that had been purchased prior to the activation of the MRTF were selected for review to current purchasing pract ce QA501, Scienoid Valve
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84QA0154, Asco Valves j

82QA0214, Durametallic Mecharrical Sea)

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830A0101, SS Tubing q l

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82QA0047, Relays I j It was identiff ed that the items included in the first three pur- } chases above contained internal subcompotlents (f.e., parts) sub.iect i i to deterioration (i.e., aging) over a period of t:me. This. fact had not been entered into the shelf life control program. Further review ! and siscussions with the supervisor of MRTF disclos6d that the current ! precurement requirement (i.e., clause) for vendors to identify asy item containing such parts had not been established or used during the prevleus purchasing process. The supervidor of MRTF stated that

an effort would be initiated to identify items purchased prior to .J , ! MRTF that contained parts subject to shelf life and prior to the ! conclusion of this inspection, the licensee was planning the exact i methodology and controls to accomplish this task. The inspector 'I determined that the el.ectronic data base was amenable to a search for-such specific items that were previously purchased. Licensoe manage- j ment acknowledged the' intent to complete tnis effort at the exit i interview. The if cen'see also acknowledged that this area vould be 1 reviewed on a routine basis during subsequent inspectichs, j The education, experience, qualificatinn certifications and training of several warehouse receipt inspectors were reviewed to 1, verify their qualifications for inspection duties. Two Level II ( inspectors were interviewed and displayed an adequate understanding of their responsibilitie .3 Findings _

Based on the results of the review performed in this area, the procurement program is in comp 11ance with F5AR commitments and is ready to support plant operation No violations were identifie . . . _ . . . . . . . . . .. .

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7.0 Unresolved' Items Unresolved. items are matters about which more information is required to ascertain whether they are acceptable items, violations or deviation Unresolved items disclosed during the inspection are discussed in para-graphs 3.5 and l 8.0 Exit Interview

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l The inspectors met with licensee management representatives (see ' Lsection 1.0 for attendees) at a mini exit on January'31,1986 and a final exit on February 7, 1986. The inspectors summarized the scope and findings of the inspection at that tim At no time during this inspection was written material provided to the licensee by the inspectors, g "" i

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       ,l APPENDIX A     i Licensee Requirements and Commitments
* FSAR, Section 17
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Regulatory Guide 1.33 which endorses ANSI N13.7, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants."

ANSI N45.2,-" Quality Assurance Program Requirements for Nuclear Power Plants."

Technical Specifications (TS), Sections 6.2.3, 6.5.1 and 6. * Final Safety Analysis Report, Sections 13.4.1, 13.4.2 and 13. * ANSI N18.1-1971, Standard for Selection and Training of Personnel for Nuclear Power Plants

ANSI N45.2.13-1976, Quality Assurance Requirements for Control of Procurement of Items and Services'for Nuclear Power Plants

ANSI N45.2-1977, Quality Assurance Program Requirements

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Final Safety Analysis Report (FSAR), Sections 17.2.4 and 17. * Regulatory Guide 1.123,- Quality Assurance Requirements for. Control of Procurement of. Items and Services for Nuclear Power Plants, Revision 1 f t _ _ - _ _ - - _ _ _ - - - - - }}

IR 05000443/1986005

Text

REGION I

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