IR 05000443/1986007

Insp Rept 50-443/86-07 on 860310-14.No Violations Noted. Major Areas Inspected:Qa for Startup Test Program,Maint Program & Test & Experiments Program

ML20205T389
Person / Time
Site:	Seabrook
Issue date:	05/22/1986
From:	Dev M, Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205T378	List: IR 05000443/1986007 ML20205T374
References
50-443-86-07, 50-443-86-7, NUDOCS 8606130128
Download: ML20205T389 (10)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-07 Docket N License N CPpR-135 Category B Licensee: Public Service Co. of New Hampshire 1000 Elm Street Manchester, New Hampshire 03105 Facility Name: Seabrook Station, Unit 1 Inspection At: Seabrook, New Hampshire Inspection Conducted: March 10-14, 1986 Inspectors: fo G 0UE W. Oliveira, Reactor Engineef ( date jok ~ A,] 5 21*86 M. Dev Reactor Enginesr '

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Dr. P. K. Eapen, Chibf dat Quality Assurance Section, 08, DRS Inspection Summary: Routine unannouced Inspection on March 10-14, 1986 (Report No. 50-443/86-07)

Areas Inspected: Quality assurance for Startup Test Program, Maintenance Program, and Test and Experiments Program by two region-based inspector Results: No violations were identifie O

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The program is described in the references listed in paragraph The inspector's program review included:

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Review of selected ST procedure Discussion with the Startup Test Department (STD) Manager and Startup Supervisor of the actions sampled from the ST procedures and the requirements for these action Training and Qualifications of STO personne Review Quality Assurance (QA) role in the ST Progra The primary document for the program is the Startup Test Program De-

, scription (STPD) issued August, 1985. This document provides guidance for the administration of the Startup Test Program and describes the types of tests which will be performed during the startup, the re-sponsibilities of the various personnel during performance of a test, and the administrative controls and procedures used to ensure that j all tests are conducted in a uniform and predetermined manner.

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Out of a total of 56 ST procedures, 32 have been approved by the Sta- .

tion Operations Review Committee (SORC) and issue The remaining procedures are in the review cycle in accordance with the STPD. The i inspector selected the following procedu"res for review:

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1-ST-1, Startup Program Administration, Revision 0

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1-ST-2, Primary Source Installation, Revision 0

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1-ST-3, Core Loading Prerequisites, Revision 0

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1-ST-10, RTD Bypass Loop Flow Verification, Revision 0

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1-ST-13, Operational Alignment of Nuclear Instrumentation, Revision 0

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1-ST-44, Loose Parts Monitoring, Revision 0 i

Theprocedureswereprepared,reviewedand', subs.ittedforSORC ,

approval in compliance with the STPD.

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The inspector discussed the specific procedure steps sampled from the STs with the STO Manager and Startup supervisor. Each step was ad-dressed and the applicable criteria and requirements were provide For example:

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1-ST-1, Paragraph 4.4. Intermediate and power range channel at

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100*4 power are set for 200 microamps for each detector as required by Westinghouse and confirmed by survey testing and *

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experiences of other nuclear power plant ,

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1-ST-2, Paragraph 6.1 Torque values were provided by Westinghouse.

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DETAILS 1.0 Persons Contacted Public Service Co. of New Hampshire

• D. Abely, Maintenance Department Supervisor F. Bean, Lead QA Engineer

• S. Buchwald, QA Surveillance Supervisor R. Cooney, Maintenance Services Manager W. Dickson, Lead Mechanical Engineer

• R. Guillette, Assistant QA Manager (Construction)

G. Kann, Startup Test Department Manager

• G. Kingston, Compliance Manager G. Kline, Technical Services Manager

• D McLain, Startup Test Manager

• T. Murphy, Instrumentation and Control Department Supervisor

• L. Rau, Reactor Startup Supervisor G. Sessler, Engineering Services Manager

• D. Turner, QA Engineer C. Vincent, QC Supervisor J. Warnock, Nuclear Operations QA Manager N. Wiggin, Station Staff Training Manager U. S.1_ Nuclear Regulatory Commission

• Barkley, Resident Inspector

• A. Cerne, Senior Resident Inspector

• Ruscitto, Resident Inspector

Denotes those present at the exit meeting on March 14, 1986.

2.0 Quality Assurance (QA) for the Startup Test Program 2.1 Requirements / References

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FSAR Chapters 14 and 17

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Startup Test Program Description (STPD), Revision 0

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New Hampshire Yankee Operational Quality Assurance Program Manual, Revision 3

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Regulatory Guide 1.58, Revision 1 (September,1980), Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel 2.2 Program Review The licensee is developing the startup test (ST) procedures for the Startup Test Program. By licensee's commitments these procedures are required to be in place 60 days prior to fuel loading which is sche-duled for June 30, 1986. ,

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1-ST-44, Paragraph 6.3.16. The formula for K (required) was provided by the vendor technical manua The inspector attended a SORC m?eting where the STD Reactor Startup-Supervisor presented three STs listed below for SORC approva '

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1-ST-16, Initial Criticality

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~ 1-ST-22, Natural Circulation Test

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1-ST-50, Moveable,Incore Detector System _

The supervisor explained those chang'es to the procedures that wera '.

incorporated during the review cycle and answered questions from the committee. The committee approved the three procedure Training and qualif'ication of STD personnel are described in the STPD paragraph 5.0 'anld FSAR 14.2;2 which commit to RG 1.58. The addi-tional trainirig described in the STPD and FSAR is awaiting reassign-ment of STPD persqnnel to the Startup and Test Group. _The training will include home study, examinations as well as'the training already described in the STPD and FSAR,'(e.g , transient analysis, detailed systemss.yndPWRinformat.ioncourse).

No violations orideviations were identifie .3 QA/QC Interface with the Startup Test Program '

The Yankee Atomic Electric Company (YAEC) QA organization is responsi-ble for the Quality Assurance (QA) aspect of the'. test prograr. The New Hampshire Yankee-(NHY) Nuclear QA Group (NQG)'is responsible for QA functions associated with the mainter;ance of t'h'se o spstems that were turned over to Operation The Startup Quality Assurance Inter- ^

face Agreement" document was developed to insure an orderly ' transfer of responsibilities from the YAEC QA orijanization to the NHY QAlorgan-izatio Measures aretestablished to control' completion of those ,

turned over systems that are only partially complete. The NHYQC is - ~

staffed with experienced Startup QC Specialists to provide adequate courage to turned over . systems, c ,

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3.0 QA for the Maintenance Program ,

3.1 Requirements / References '

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FSAR Chapters 13 and 17 *

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ANSI /ANS 3.1-1978, Selection and Training of Pirsonnel for Nuclea. Power Plants -

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Seabrook Station Maintenance Program, Revision 2

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NHY Operationaf Quality Assurance Program Manual, Revision 3

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3.2 Program Review The inspector reviewed the preventive and corrective maintenance ac-tivities of the Seabrook Maintenance Program as described in the re-ferences listed in Paragraph 3.1. Preventive maintenance (PM) and corrective maintenance (CM) are initiated by Repetitive Task Sheet (RTS) for PMs and by Work Request (WRs) for cms. The inspector re-viewed the specific procedures used during the walkdowns of completed maintenance activities. The procedures were prepared in accordance with the maintenance manual. The procedures contained the acceptance criteria as well as detailed steps for performing the activity and sign off The specific procedures reviewed were:

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151634.415, T-5688 Diesel Generator A Room Temp Calibration, (procedure included an approved change)

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MX0506.03, Quarterly Battery. Surveillance

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MX0506.02, Weekly Battery Surveillance 3.3 Program Implementation The inspector verified the program implementation by walkdowns of the following completed wor RTS No. 86 RIO506, T-5688 Diesel Generator A Room Temp Calibra-tion. The senior I&C technician who conducted this PM was the author of the procedure used to perform the PM. He was able to explain the change to the procedure and was knowledgeable of the requirements, prerequisites, precautions, accept criteria, use and care of M&TE, and reporting problems and deficiencie RTS No. 86RN00316 and 345, Quarterly and Weekly Battery Surveil-lances. The working foreman performed part of the quarterly sur-veillance. Only the pilot cells were checked during the weekly surveillance. The foreman was knowledgeable of the requirement The foreman informed the inspector that the specific gravity (SG), obtained from the weekly test, when corrected was below the minimum value. The proposed technical specification requires to correct the specific gravity within seven days. The SG was corrected in five days and the weekly surveillance was satis-factorily complete RTS 85RM06004, Administrative Review of Safety Tagging. The maintenance supervisor of either the mechanical or electrical group is expected to perform a bimonthly review of safety taggin This RTS appeared on the overdue RTS lis The supervisor was aware of the problem and assured that the bimonthly review will be conducted promptl .

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WR No. 85 M00039 and M01316 dealt with replacement of ferrore-sonant tuning capacitors for GE transformers. The capacitors were replaced because they exceeded the shelf life requirement The new capacitors have a nine year shelf life. The inspector reviewed the material order package with the department superviso WR No. 86 WM00059, Troubleshoot, repair or replace the Ammeter Relay on SWG-11B. The working foreman performed part of the troubleshooting action. An interference of an internal wire prevented proper contact. The. interference was removed and the relay was adequately teste The inspector also interviewed three department supervisors,two line supervisors, 2 working foremen, one mechanic, and two I&C technicians to discuss: reorganization of the maintenance group; new computerized maintenance program; staffing; training and qualifications of person-nel; and relationship with QA/QC. In each case the personnel were knowledgeable of the technical requirement No violations or deviations were identifie .4 OA/0C Interface for the Maintenance Program The Nuclear Quality Group (NQG) is involved in the reorganization of the Operations Maintenance Group (OMG). NQG will have by mid-March, 1986, a QA specialist in the OMG Planning and Scheduling Departmen Th2 specialist will review all the RTS and WRs and identify quality requirements and hold points. The NQG will also search the Main-tenance Program computer to: plan and schedule QC surveillances and hold points; track deficiencies and corrective actions; develop trends; and provide inputs to the periodic QA inspection, surveil-lance, and follow-up report The inspector reviewed the ceitification of three QC inspectors, one QC supervisor, and the NQG Manager. The certifications were in compliance with RG 1.53, complete and current. The inspector also reviewed three QA audits and one QA surveillance report related to the maintenance program. Also reviewed were the audit plans that were included in the QA audit announcement letters, and the QA audit and QA surveillance checklists. The audit plans and checklists were found to adequately cover the maintenance areas being audited and surveilled. The inspector noted that NQG is developing a five year QA audit schedule, and that QA surveillance personnel are performing surveillances- of the upper level programmatic effort. The QA surveil-lances include, design change control, Environmental Qualification (EQ) Program, etc.

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l 4.0 QA Program for Tests and Experiments 4.1 References / Requirements

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10 CFR 50, Appendix B, Criteria I and XI

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10 CFR 50.59, Changes, Test and Experiments

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Seabrook Station Final Safety Analysis Report, Section 13.5, Plant Procedures; and Section 17.2, Quality Assurance During the Operations Phase

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Seabrook Station (Proposed) Technical Specifications Section 6

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ANSI N45.2.8-1975, Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems

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ANSI N18.7-1976, Administrative Controls and Quality Assurance for the Operation Phase of Nuclear Power Plants 4.2 Program Review, Implementation and Findings The inspector reviewed the New Hampshire Yankee (NHY) Seabrook Station Management Manual (SSMM), Revision 2 and Station Management (SM) 1.6, Seatsrook Station Program Description, Revision 0, " Test Control Pro-gram" (See Attachment A for related procedures). The licensee has established the measures to control the testing and surveillance of Seabrook Station systems and components. The program encompasses the Technical Specification surveillance tests, construction verification tests, preoperational tests, preventive / corrective maintenance tests, startup tests, and special tests and experiments. The Station Manage-ment (SM) 6.1, Revision 0, " Station Administrative Procedure" addres-ses the preparation review, approval, revision and maintenance of administrative procedures. The station administrative procedures are divided into two separate manuals (management and program). These procedures are independently reviewed by knowiedgeable station person-nel. They are mandated for a periodic review every two years. The Station Administrative Procedure SM 6.2, Revision 2 " Station Operating Procedure" delineates preparation of special procedures necessary to support infrequent evolutions and testing requiring written proce-dures which are not covered by existing controlling documents and addresses format, reviews, approval, periodic review, distribution and records retentio The licensee proposes to conduct all tests, including spe.cial tests and experiments commencing with initial fuel load, in accordance with NHY Seabrook Station Test Control Program Manual, Revision 5. The Test Control Program provides the measures of controls described in 10 CFR 50 Appendix B, Criterion XI. It establishes the Seabrook

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Station Test Control policy with regards to preparation and use of approved procedures; planning; programs and organizational inter-faces; adequacy and qualification of personnel conducting the tests; operating conditions including test witnesses; acceptance criteria; and review of the test records. These programs are not fully imple-mented at present because the systems have not been completely turned over to the station operation staff. Upon the issuance of the facili-ty operating license the tests and experiments will be prepared in accordance with the Seabrook Station Maintenance Program Manual. Ac-cordingly, responsible departments are required to establish schedules for such tests; review test procedures; implement training and indoc-trination of the personnel; and review the work packages. The Test Control Program Manual delineates the responsibilities of the test supervisor and the test coordinator to incorporate the recommendations of the station management, Station Operation Review Committee (SORC),

and Nuclear Safety and Audit Review Committee (NSARC); and schedule the the tests in a timely manner. As established in the Test Control Program Manual Section TC 2.1, " General Test Requirements", the licen-see assures that any tests or experiments net described in the FSAR rtay only be conducted without prior NRC approval if they do not in-volve a change to the Technical Specification or an unreviewed safety concern as defined in 10 CFR 50.59. The procedure also calls for a SORC review prior to the conduct of the tests, and if reportability to the hRC is determined a safety evaluation is prepare In addition, the licensee's Test Control Program Manual Section TC 2.2, Revision 1 delineates methodology for the scheduling and performance of the FSAR Appendix A and Technical Specificatlon surveillances and testing; TC 3-1, Revision 0 delineates Inservice Testing of Pumps; TC 3.2, Revision 0 delineates Inservice Testing of Valves; and TC 3.3, Revision 1 delineates Inservice Inspection of Snubbers. Through the station Test Control Program TC 5.1, Revision 0 the licensee pro-poses to institute the Plant Performance Monitoring program to opti-mize overall plant performance and reliability. The related data collection is based on the system performance, system failures and its impact, industry experiences, vendor information, regulatory-re-quirements, and engineering judgmen No violations were identifie .3 QA/QC Interface The NHY Seabrook Station Management Manual, Revision 2 authorizes the Nuclear Quality Assurance group to perform independent review of qua-lity related work, and request work stoppages and remedial actions if conditions adverse to quality are encountered. Accordingly, the Nu-clear Operation Quality Assurance group reviews all safety-related tests and experiments programs and procedures, assigns witness and hold points, and witnesses and reviews the tests for program compli-anc r

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' Exit Meeting The inspectors met with the licensee representatives on March 14, 198 (see~ paragraph 1 for attendees) to summarize the scope and findings of the inspectio At no time during the inspection was written material provided to the licensee by the inspectors.

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ATTACHMENT A New Hampshire Yankee (NHY) Seabrook Station Test. Control Program Manual (SSTC), Revision 5 sections:

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TC 2.1, General Testing Requirements, Revision 0

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TC 2.2, Technical Specification Surveillances Scheduling and Ferformance, Rev 1, February 6, 1986

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TC 3.1, Inservice Testing of Pumps, Revision 0

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TC 3.2, Inservice Testing of Valves, Revision 0

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TC 3.3, Inservice Inspection of Snubbers, Revision 1

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TC 5.1, Plant Performance Monitoring Program, Revision 0 New Hampshire Yankee Nuclear Production Reporting Program Manual (NPRE),

Revision 4 NHY Nuclear Production Quality Assurance Program Manual (NPQA),

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Revision 3 NHY Nuclear Production Planning and Scheduling Program Menual (NPPS),

Revision 1 NHY Seabrook Station Maintenance Program Manual (SSMA), Revision 3 NHY Seabrook Station Management Manual (SSMM), Revision 2 sections:

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SM 1.6, Seabrook Station Program Description

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SM 6.1, Station Administrative Procedures, Revision 0

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SM 6.2, Station Operations Procedures Revision 2 Seabrook Station Startup Quality Assurance Interface Agreement, Revision 3