IR 05000336/1987009
| ML20206Q790 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/13/1987 |
| From: | Blumberg N, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206Q759 | List: |
| References | |
| 50-336-87-09, 50-336-87-9, NUDOCS 8704220037 | |
| Download: ML20206Q790 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-336/87-09 Docket No.
50-336 License No.
DPR-65 Licensee:
Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 Facility Name:
Millstone Nuclear Power Station Unit 2 Inspection At:
Waterford, Connecticut Inspection Conducted: March 16-19, 1987
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Inspectors:
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A. Finkel, Le'ad Reactor Engineer 6/
daYe Approved by:
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/kb N. Blumberg,/ Acting Chief,
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' date Operational Programs, Sectid OB, DRS Inspection Summary:
Routine, unannounced maintenance inspection conducted on March 16-19, 1987 (Report No. 50-336/87-09)
Areas Inspected:
Routine unannounced inspection of licensee activities in the areas of maintenance organization, maintenance program, maintenance activities, measuring and test equipment program, trouble reporting system, insulation degradation, QA/QC interfaces, and transformer maintenance. The inspection was conducted onsite by one region-based inspector.
Results: No violations or deviations were identified.
G704220037 870415 POR ADOCK 05000336 O
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i DETAILS 1.0 Persons Contacted j
Northeast Nuclear Energy _ Company
- J. Keenen, Unit 2 Superintendent
- M. Sforza, Senior Engineer
- D. Tracey, Production Test Coordinator
United States Nuclear Regulatory Commission i
T. Rebelowski, Senior Resident Inspector
J. Grant, Resident Inspector
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- Denotes those present at the exit interview.
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The inspector also held discussions with managers, supervisors and other
licensee employees during the course of the inspection, including oper-
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ations, technical and administrative personnel.
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2.0 Maintenance Organization
2.1 Administrative Controls
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The purpose of this inspection was to review and evaluate the i
licenste's program plans for controlling safety-related maintenance and to determine the effectiveness of the maintenance program on
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plant equipment. The documents reviewed by the inspector during
l this inspection period are listed in Attachment A to this report.
i The program was inspected for compliance to the requirements of
10 CFR 50, Appendix B; ANSI N 18.7-1976, " Quality Control for Oper-l ational Nuclear Power Plants"; and Regulatory Guide 1.33 1978.
2.2 Maintenance Program Controls i
l The licensee has a formal maintenance program which includes both corrective and preventive maintenance activities and is documented
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intheProductionMaintenanceManagementSystem(PMMS).
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The PMMS documents part history, corrective actions, quality control
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inspection status and management directions / approvals.
Using the PMMS data history, trending is being performed on selected compo-i nents, but the licensee does not have an overall trending program for j
this site.
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The PMMS generates preventive and corrective work orders as well as providing work order status data. The inspectors review of the PMMS data verified that Technical Specification (TS) requirements were
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part of the data system and that TS requirements were scheduled. The PMMS is in the processed of being up graded with an estimated com-pletion date of the third quarter of 1987.
No violations or deviations were identified.
2.3 Documentation Review and Equipment Inspection The inspector reviewed the maintenance work orders and records of selected safety-related equipment to verify that the following
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subject areas were identifled and documented as required by the TS and the site Quality Assurance Program:
--Required administrative approvals were obtained prior to initiation of work and at the completion of the task;
--Appropriate approved procedures, instructions and/or drawings were used to perform the task; i
--Post maintenance testing was required prior to returning equipment to service;
--Hold points were appropriately identified and implemented;
--Test equipment and tools used were required to be identified with range and tolerance listed;
--Acceptance criteria was identified with requirement for signature verification that the criteria was met; and,
--Records were assembled, stored and retrievable as part of the maintenance system.
During the course of the above verification process the inspector observed the following in process maintenance activities:
--Battery Pilot Cell Surveillance, DC batteries 201A and 2010, Procedure SP2736A,
--MCC Breaker PM, B1213, Work Order M2-86-02185
--MCC Breaker, PM, B1231, Work Order M2-86-02186
--Heater PM, T8A-P142, Work Order M2-86-02192
--Diesel Generator H70, Work Order M2-87-01180
--Motor Generator Set B, Work Order M2-87-02341
--Motor Generator Set A, Work Order M2-87-03043
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Observations of the above listed items verified that the following actions were accomplished:
--Approved, up-to-date procedures were used by the maintenance personnel;
--Procedures were adequately detailed to assure satisfactory performance;
--Parts and materials were identified; and,
--Test equipment was identified with calibration date and serial number recorded.
The inspector reviewed the qualification records of the maintenance personnel performing the PM's on the above work orders and determined from a records review and discussions with the personnel that their training records were up-to-date and that they were knowledgeable of the work they were performing.
No violations or deviations were identified.
3.0 Measuring and Test Equipment (M&TE) Program The Measuring and Test Equipment (M&TE) program was reviewed to assess compliance with the requirements of the FSAR, ANSI-NIC.7-1976 and the site Quality Assurance program requirements.
A random examination of the M&TE equipment used by the maintenance per-sonnel disclosed that the equipment sampled was within the required cal-ibration dates and that the personnel using the equipment were knowledge-able of the requirements for maintaining the calibration status of equip-ment. The records of the equipment were current and in compliance with their program procedure ACP-QA-9.04, " Control and Calibration of Measuring and Test Equipment." The responsibility for this procedure is the Unit 2 I&C supervisor.
The inspector reviewed the equipment recall system and verified that the maintenance records were in compliance with site procedures.
The Production Maintenance Management System (PMMS) maintains the status of the recall system which is updated by the maintenance group.
Using the latest PMMS run pertaining to the M&TE records, the inspector verified that the equipment and use dates were within the calibration due dates.
No violations or deviations were identified.
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4.0 Trouble Reporting / Work Orders The Trouble Reporting System (TRS) is a method that the licensee has developed for reporting problems.
The TRS identifies the subject item and the problem but does not in itself constitute a work order. The TRS allows personnel to report, inquire, update and approve problems requiring the generation of a work order and functions in the same manner as filling out a maintenance request.
This TRS information becomes part of the work order (WO) if the request is determined to be processed through the system.
If the TRS is processed through the WO system them the PMMS will track the item.
The WO system is used to control and document both QA and non-QA work items.
In addition, the W0 system provides the following type of management programs and status:
--Report of failures / problems requiring corrective action;
--Disposition of work requests;
--Documentation of retests or functional verifications performed;
--Provision of a work schedule, man power loading requirements and a progress of WO status; and,
--Trending of data parameters.
The purpose and applicability of the Work Order procedure is defined in Administrative Control Procedure (ACP) ACP-QA-202C, " Work Orders."
No violations or deviations were identified.
5.0 Electrical Bushwack Insulation-Degradation-Unit 2 Cracking and splitting of the "NORYL" insulation sleeves which cover the main bus bars has been identified by the General Electric Company and disseminated to the industry via their Service Instruction and Advice Letters (SILS). General Electric investigations have shown that the thermoplastic sleeve insulation (NORYL), while normally stable and suit-able for this application, may undergo stress cracking if significant stresses and any of several petroleum - based greases, plasticizer, paint thinners, industrial cicaning fluids or chemical containments are present.
The stresses may be heat, vibration or fabrication induced. The current sleeving degradation, appears in proximity to joints containing the non-compatibio grease and is generally absent where the grease is absent.
General Electric currently recommends the use of only one type of joint compound with no substitutes, having found other types are not compatible with the sleeving. Also, the use of cleaning agents other than denatured alcohol is not recommended.
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In response to the above SIL, the licensee.has replaced the sleeving on the nonsafety 6.9 KV buses (25A 'and 258), and the 4160 volt safety buses.
In addition the licensee maintenance procedures have been revised to re-flect the General Electric recommendations for this switchgear. The work orders that were issued to correct the safety-related switchgear are listed in Attachment A of this report.
No violations or deviations were identified.
6.0 Quality Assurance / Quality Control Interfaces Quality Assurance representation is established both at the Millstone site and at the corporate level located in Berlin, Connecticut. However, at this time both corporate and on-site QA groups are separate from each other in that they report organizationally under different Vice Presi-dents. On-site QA activities are controlled by the Northeast Nuclear Energy Company (NNECO); while corporate QA is part of the Northeast Utilities Service Company (NUSCO). Both NNECO and NUSCO Vice Presidents report to the same Senior Vice President. NNECO QA activities are gov-
erned under Administrative Control Procedures (ACP's) and NUSCO QA follows haclear Quality Assurance Procedures (NQA's).
The audits reviewed by the inspector were performed on the maintenance function at the site by the NUSCO organization and were in accordance with Nuclear Quality Assurance Procedure (NQA) 2.06, Revision 1, June 26,1986, titled "A Conduct, Reporting and Follow-Up of Audits." The following audits were selected by the inspector for compliance with Regulatory Guide (RG) 1.144, " Auditing of Quality Assurance Programs for Nuclear Power Plants," September,1980; ANSI N45.2.121977 " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants, and NUQAP Topical Report:
--Audit Report A60567, October 3 - January 21, 1987, Corrective Maintenance Ouring the MP-2 Refueling Outage;
--Audit Report A22002, August 18 - November 18, 1986, Millstone Unit 2 Technical Specification; and,
--Audit Report A22001, March 17-31, 1986, Millstone 2 Technical Specification, Section 6.5.3.7 " Audits".
Audit findings identified in the above referenced reports have been an-swered and are in the final review cycle to determine if the answers are acceptable.
The inspector review of the audit reports and their findings determined that there were no findings which could effect overall plant safety.
No violations or deviations were identified.
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7.0 Transformer Inspection The maintenance and inspection programs on large transformers was reviewed by the inspector to determine the overall effectiveness of their program.
The inspector selected the Reserve Station Service Transformer (RSST) to perform the inspection of methods and programs used by the licensee to determine the overall operational characteristics of the transformers.
The RSST is a General Electric type S/N 15G-22S with the following ratings:
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--High Side KV 345 Y, 385MVA @ 55 C;
--Tertiary KV 4.16 A, 23.5MVA @ 55 C;
--Gallons of 011 16,172; and
--Type / Class OA/FA/FOA Note: The 112% of rating @ 65 C for the OA/FA/FOA 3 4, 60HZ is listed as follows for 28.5 MVA:
ZH-X = 18.43%
ZX-Y = 32.06%
ZH-Y = 26.18%
The Z value is listed on licensee drawing 25203-30001 and defines the transformer connections required to obtain the above ratings.
The Production Test Department (PTD) reviews the daily transformer reports and if required performs or has performed the necessary maintenance on the s
transformers. The PTD performs the testing program outlined in Station Procedure PT 1411A/21411A/31411A. During,an outage or if the transformer is required to be off line, the PTD will perform the following testing:
--Doble testing of the transformer windings;
--Doble testing of the high and low side bushings;
--Doble testing of lightning arresters, where applicable;
--Rating test of the transformer on the in-service tap;
--Doble, hypot or megger testing of the buswork and cables;
--Sampling and analyzing of transformer oil;
--Operational testing of fans and pumps; and,
--Hot spot scanning, as required.
No violations or deviations were identified.
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=8.0 Exit Interviews
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The inspector met with licensee management representatives (see
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Section 1.0 for attendees) at an exit meeting on March 19, 1987. The
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inspector summarized the scoop and findings of the inspection at that-
time.
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4-At no time during this inspection was written material provided to the licensee by the inspector.-
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Appendix A Preventative Maintenance Work Orders WO-M2-86-00680 ES4 BUS DBT 24A WO-M2-86-00682 ES4 BUS DPT 24C WO-M2-86-00684 ES4 BUS DBT 24E
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WO-M2-86-00686 ES6 BUS DBT 25A WO-M2-87-02341 MG-SET-B WO-M2-87-03043 MG-SET-A WO-M2-86-02185 MCC BKR B1213 WO-M2-86-02186 MCC BKR 81231 WO-M2-87-01180 PGN GEN PRO H78 WO-M2-87-02325 PGN GEN PRO H7A Maintenance Procedures
--Procedure No. 2736A-1, Battery Pilot Cell Surveillance, Rev 0, August 18, 1980;
--Procedure No. 27368-1, Complete Battery Cell Measurement, Rev 4, July 23,1986
--Procedure No. 2701J-6, Transformers, Revision 3, May 15, 1983,
--Procedure No. 2701J-1, 480 Volt Breakers, Revision 12, January 15, 1987
--Procedure No. 2701J-4, 4160-6900 Volt Breakers, Revision 8, September 18, 1986
--Procedure No. 2701J-13, Diesel Generator Electrical, Revision 5, December 19, 1983
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