IR 05000309/1980017
| ML20003B599 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/24/1980 |
| From: | Chung J, Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20003B596 | List: |
| References | |
| 50-309-80-17, NUDOCS 8102120543 | |
| Download: ML20003B599 (10) | |
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i U.S. NUCLEAR REGULATORY COMMISSION G
OFFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No.
50-309/80-17 Docket No.
50-309 License No.
DPR-36 Priority Category C
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Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road
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Westborough, Massachusetts 01581 Facility Name.
Maine Yankee Atomic Power Station Inspection at:
Wiscasset, Maine Inspection conduc ed: November 3-7, 1980 Inspectors:
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. Chung, Reactor nspector, Nuclear date signed upport Section o 2, RO&NS Branch
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date signed date signed M
/2-2f-80 _
Approved by:
a E. G. Greenman, Chief, Nuclear Support date signed Section No. 2, R0&NS Branch
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l Inspection Summary:
Inspection on November 3-7, 1980 (Report No. 50-309/80-17)
Areas Inspected:
Routine, unannounced inspection by a region-based inspector of followup on previously identified items; administrative controls for safety-related maintenance; review of safety-related maintenance activities; maintenance personnel qualifications; and control room and facility tours.
The inspection involved 26 inspector-hours onsite by a region-based inspector.
Resul ts:
Noncompliances:
None i
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Region I Form 12 i
(Rev. April 77)
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DETAILS 1.
Persons Contacted Principal Licensee Employees P. L. Anderson, Administration Department Head
- R. E. Arsenault, Plant Shift Superintendent D. A. Caron, Malatenance Department Mechanical Supervisor C. Frizzle, Assistant Plant Manager L. E. Grimard, Training Group Supervisor
- J. R. Hebert Director, Plant Engineering
- A. G. Jordan, Q.A. Inspector W. A. Lach, Primary Chemist W. Paine, Operations Department Head R. L. Painter, Maintenance Department Electrical Supervisor
- R. F. Prouty, Maintenance Department Head R. Radasch, Instruaent and Control Supervisor
- E. C. Wood, Plant Manager USNRC
- W. Lazarus, Senior Resident Inspector
- P. D. Swetland, Resident Inspector The inspector also 'nterviewed other licensee employees during the inspec-tion, including Administrative Support personnel, Technical personnel, and Maintenance and Performance members.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings
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(Closed) Unresolved Item (309/79-12-01):
Incomplete grading and analysis of the grading of the 1979 operator requalification examination results.
The inspector verified by review of "Requalification Examination Summary, 1978-1979" and the Examination Answers that the grading and analysis of the examination had been completed in accordance with the approved requali-fication program.
(Closed)UnresolvedItem(309/79-12-02):
Review of records for the requa-lification period 1978-1979 was not accomplished. The inspector *iviewed the 1978-1979 training records of licensed operators to verify t:.e docu-mentation of:
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annual written examination answers; reactivity change manipulations;
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review and discussion of emergency or abnormal procedures;
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results of performance evaluations.
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The inspector also conducted an interview with a licensed operator to verify
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that the records reflect the actual training received.
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(Closed) Inspector Follow Item (309/79-12-03):
Issuance and implementa-tion of a temporary procedure change to formalize a remedial program for
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those individuals who failed to attain a grade of 70% on any part of I
annual examinations.
The inspector verified by review of records and pro-cedure 0-00-5, " Licensed Operator Qualification and Requalification Program",
Revision 8, July 31, 1980, that the remedial program was included in Me revised procedure.
This procedure requires licensed operators who do not attain a passing grade of 70% in any individual category to participate in an accelerated training program and to attain a grade of 80% on a re-test
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in that category.
A similar remedial program has been established for operators.
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who score less than 80% of overall grade.
(Closed) Inspector Follow Item (309/79-12-04):
Security iorce training
to be established on a two-year retraining cycle for general training, consistent with the requirements for other contractor personnel.
The inspector verified by review of the training records for selected indivi-
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duals that the general retraining for the security force was conducted on
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a two-year cycle.
(Closed) Inspector Follow Item (309/79-12-05):
The chemists were to requalify in major chemistry surveillance tests every two years.
Records reviewed showed that the latest dates for requalification were November and December of 1977.
The inspector verified by review of the records and i
documentation that the requalification program for the chemists had been l
conducted 5 accordance with the requirements and in two year intervals.
l The documents reviewed included:
New Employee Training Check-off Sheet, 1977 through 1980.
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Employee Chemistry Retraining Check-off Sheet,1977 through 1980.
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Lecture Attendance S'.et,1978.
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(0 pen) Unresolved Item (309/79-14-06):
Procedures had been established
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for disassembly of the reactor coolant pumps and motors.
However, no pro-
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cedures existed for reassembly of these components.
The inspector reviewed draft copies of procedures, MYM-5-27 "Ressembly of a Reactor Coolant Pump" and MYM-5-28 " Installation of a Reactor Coolant Pump Motor". A licensee representative sta ed that these procedures would be further reviewed prior
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to submittal to PORC and would be implemented by December 31, 1980.
This item remains unresolved pending procedure issuance and review during a subsequent inspection.
(0 pen) Inspector Follow Item (309/80-01-03):
Increased test frequency of Matrix Relay AC-1 and BD-3 until new relays are installed.
The inspec-tor verified by review of relay test records that the surveillance frequency was increased to weekly from the normal monthly test requirement. A licens-ee representative stated that the new relays would be installed by January 1, 1981, provided that no additional problems are identified.
Weekly testing is continuing in the interim.
This iten remains open pending installation of relays and review during a subsequent inspection.
3.
Administrative Controls for Safety-Related Maintenance Administrative controls were reviewed to verify the licensee's program for implementing requirements associated with the conduct of safety-related maintenance was as specified in Technical Specifications. Section 6; Regu-latory Guide 1.33, Quality Assurance Program Requirements; and ANSI N18.7, Administrative Controls for Nuclear Plants.
The following documents were reviewed:
MYM5-5-200, Administration of the Preventive Maintenance Program,
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Revision 1, September 5,1980 (Reference Findings Detail 5.c)
0-00-6, General Plant Training Program, Revision 3, December 12, 1979
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0-05-1, Document Control, Revision 4, July 17,1978; reviewed on
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July 18, 1980 0-06-2, Procedure Review, Approval and Distribution, Revision 8,
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December 21, 1978 0-07-1, Installation and Maintenance of Safety Class System, Components
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and Structures, Revision 5, May 26, 1978; reviewed on May 26, 1980 0-07-3, Maintenance Requests, Revision 6, May 16,1979
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0-07-5, Cleaning Procedure, Revision 1, June 7, 1978; reviewed on
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June 7, 1980 0-06-5, Control of Measuring and Test Equipment, Revision 5,
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December 21, 1978 Minutes of PORC Meetings, 1979-1980
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One unresolved item was identified as a result of this review (Reference Detail 5.c).
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4.
Maintenance Procedures a.
The inspector reviewed maintenance and preventive maintenanc < proce-dures, and temporary procedure changes, on a random basis to verify the following.
Provisions for fire protection / prevention, cleanliness, and
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housekeeping were included.
Testing requirements, Inspection and Hold points were included.
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The procedures included provisions for adherence to Technical
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Specification during the maintenance activities and for return to service.
Properly specified parts and materials were identified for use.
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Procedures and changes were in conformance with the administra-
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tive requirements.
Consideration was given to the radiological hazards involved.
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b.
The following procedures were reviewed:
MYNS-3, Packing RCL Bypass Valves Nos. RC-M-13, 23, 33.
Revi-
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sion 1, October 27, 1980 MYMS-23, Installation and Test for Normally Energized NBFD/BFD
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Relays in SIAS Circuits, Revision 0, January 22, 1980 MYMS-144, Inspection and Repair of GE AK-2 Circuit Breakers,
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Revision 0, September 13, 1979 3.17.6.6, Inservice Testing of Safeguard Pumps, Revision 1,
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October 22,1979 (Reference Findings Detail 4.c)
MYMS-108, Cable Penetration. Sealing, Revision 2, September 10,
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1980 MYMS-49, Replacement of Radioactive Service Filters, Revision 3,
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October 27, 1980 MYMS-20, Pressurizer Safety Valve Removal and Installation,
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Revision 2, August 21, 1980 MYMS-4, Testing and Setting of Pressurizer Safety Valves, Revi-
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sion 2, July 16, 1978; Change February 25, 1980 MYMS-50, Replacement of LPSI Pump Mechanical Seals, Revision 1,
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December 12, 1979
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MYMS-53, Installation of the Containment Building Equipment
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Access Hatch Cover, Revision 0, January 2, 1979 Inservice Inspection Program, for the period August 28, 1979 to
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December 28, 1982, Appendix A Procedure 3.17.6 Preventive Maintenance Procedures, per MYMS-5-200, Revision 1,
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September 5, 1980
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(1)
E6-X-B, MG set IB Visual Inspection (2)
M-26-Q-B, DG-1B Emergency Diesel System, GM Model 999-20 (3)
M-1-Q-A, Reactor Coolant Pump Spare Motor Starter (4)
M-13-Q-A, Air Compressor for P-70A Reactor Containment Foundation Drain Pump c.
Findings The licensee's Inservice Testing Procedure for Safeguard Pumps, 3.17.6.6, requires measurement of vibration amplitudes of the safe-guard pumps and recording the measurements on the pump test data sheet in accordance with ASME Code Section XI, Article IWP-3000.
The inspectors review indicated the acceptance criteria in the procedure as well as the corresponding test data sheet did not have the allowable ranges of test quantities and the limits, as required by Article IWP-6000.
Discussion with a cognizant licensee representative resulted in a comitment that procedure 3.17.6.6 would be revised to include the nurerical acceptance criteria by February 1, 1981.
This item will be reviewed during a subsequent NRC:RI re-inspection (309/
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l 80-17-01) to assure that appropriate changes have been made to 3.17.6.6.
5.
Review of Safety-Related Maintenance Activities a.
The inspector reviewed safety-related maintenance activities and Preventive Maintenance conducted by the licensee on a sampling basis to verify that:
Technical Specification requirements were met while equipment
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was out of service, and that a Licensee Event Report had been submitted for maintenance associated with a reportable occurrence when required.
Required administrative approvals were obtained to. perform the
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work.
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An approved procedure was used as appropriate.
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Records to substantiate the quality of work and parts used
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were available (this included documentation associated with procurement, inspections and test results).
b.
Documentation of the following maintenance and preventive maintenance activities was reviewed:
3-6.2.1.9, Excore NI Dual Linear Power Range Channel 5, 6, 7,
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8, 9, and 10 calibration, Revision 3, October, 1980.
(1) Maintenance Request (MR) #1863-78, Replacement of JY-005-1, performed December 15, 1978 (2) MR#007-79, Flux Level Trip adjustment, performed January 3, *
1979 (3) MR#838-79, Channel 9 and 10 Linear Amplitt.de Adjustment, performed July 12, 1979 3-6.2.1.9, Appendix B, Dual Linear Power Sub-Channel (s) Calibra-
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tion-Fit, Revision 3, October 1980, performed January 20, 1977 3-6. 2.2. 10, Reactor Trip Breaker Monthly Test, Revision 3,
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Octobar, 1980, 12 tests performed February 26, 1979 through April 3,1980 E-6, Rod Drive Power Supply
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(1) MR#579-79, Operational Checks of the Reactor Trip Breakers per IE Bulletin No. 79-09, performed July 2, 1980 (2) Preventive Maintenance (PM) Card, E6-X-B, MG set IB Visual
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l Inspection, performed May 1, 1975 E-7, Protective and Monitoring System
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l (1). MR#321-80, BFD and NBFD Relay Checks, and replacement of l
relay 63xps2010c, performed March 10, 1980 (2) MR#503-79, Replacement of the breaker control switch subse-
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quent to 4R breaker failures, performed April 13, 1979
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l M1, Reactor Main Coolant System
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(1) MR#818-79, Replacement of Reactor Coolant System Valves RC-331, performed February 16, 1980 t
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(2) PM card, M-1-Q-A, Reactor Coolant Pump Spare Motor Starter, performed December 7,1979 and July 9,1980 M26, Emergency Diesel System
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(1) MR#1449-79, Replacement of four fuel oil filters, performed October 22, 1979 (2) MR#0258-80, DG-1B 4160 volts breaker #3-17, performed February 12, 1980 (3) MR#1530-80, Replacement of filter o-ring, performed September 25, 1980 (4)
PM card, M-26-Q-8, DG-1B Emergency Diesel System GM Model 999-20, performed June 20 and September 26, 1980 M7, Safety Injection System
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(1) MR#1273-79, Installation of Pressure Taps on suction side of P-12A and P-12B, performed September 28, 1979 (2) MR#0140-80, Installation of 0-60 psig pressure gauge on suction piping, performed March 10, 1980 (3) MR#0173-80, Adjustment of packing leaks on valves LSI-M-31 and LSI-M-55 M13, Reactor Containment
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(1) MR#38-80, Fabrication and installation of an access barrier to the Refueling Canal, performed March 8,1980 (2) MR#1669-79, Installation of new sump pump #481084, performed December 6, 1979 l
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PM card, M-13-Q-A, Air Compressor for P-70A Reactor Contain-l ment Drain Pump, performed June 2 and September 15, 1980 (4) MR#0978-80, VP-A-1 leak test; cleaned disc and seat ring; adjusted rubber seal, performed June 10, 1980 M-18, Feedwater System
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(1) MR#0211-80, Replacement of flanges and machining a gasket joint for feedwater venturi access flanges, performed
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February 10, 1980 l
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c.
Findings The inspector determined by review of Preventive Maintenance records and discussion with a licensee representative that the Preventive Maintenance (PM) Scheduling is established every three months, and the detailed schedule, including the assignment of technicians, is posted on the PM board.
Upon completion of a quarterly PM program, the licensee conducts a review of repetitive equipment failures and a new schedule is posted after updating the PM and Machinery History cards.
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The inspector detcrmined the records of the PM schedules are not maintained in the plant files nor;~are the individuals who conducted the PM activities recorded cn the PM cards.
The inspecicr expressed his concerns regarding the PM record keeping practices, including ability to reconstruct significant events and to retrieve the information regarding to' the safety-related PM activities, which include the qualification review of the technicians who performed the PM's, con-sistent with the safety-related maintenance and inspection programs.
The licensee committed that procedure MYM5200, " Administration of the Preventive Maintenance Program" would be revised to include the require-ment for signing the FM cards by the technicians who perform these activities by December 31, 1980.
This item is unresolved pending a subsequent re-inspection of the PM record and the procedure revision (309/801702).
6.
Maintenance Personnel Qualifications The inspector reviewed the qualification records of selected technicians and craft personnel who performed maintenance on safety-related systems and components to verify that the individual's experience level and train-ing were in accordance with the guidelines of ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel", Section 4.
No unacceptable conditions were identified.
7.
Control Room Observations and Facility Tours a.
The inspector observed Control Room Operations regarding minimum staffing and control room manning, shift turnover, log sheets, and facility operation to verify that operations were in accordance with the Administrative procedures and Technical Specifications require-
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ments.
The inspector also conducted a tour of Turbine / Generator Building ano selected protected areas including the Primary Auxiliary Building, Service Area, the Machine Shop, Service / Circulating pumps and Screen Heuse to ensure that housekeeping practices were adequate.
Observations included:
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posting signs and work in progress.
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b.
Findings The inspector during routine control room observations observed that
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" Heat Tracing" alarm on panel S-38 had been annunciated and could not be cleared.
A licensee representative stated that this annunciated condition was caused by an electrical wiring problem on one of the local Heat Tracing panels for a non-safety related tank, SCSA.
The inspector examined the local panel to verify that work was in progress and that necessary maintenance tagging practices were being adhered to.
The inspector also determined by review of MR#1136 that the MR had been originally issued on August 27, 1979 for corrective mainte-nance work.
The maintenance involves extensive rewiring.
The inspec-tor expressed his concern regarding the control room annunciator, par-ticularly during cold weather conditions, and stated that the control room alarm should be restored to an operable status as soon as possible for other safety-related heat tracers, either by reviewing the feasabi-lity of bypassing the non-safety related local panel function or by accelerating the corrective maintenance work.
This item will be reviewed further during a subsequent NRC:RI re-inspection (309/80-17-03).
8.
Unresolved Items Unresolved items are matters about which more information is required to clarify whether they are acceptable, or items of noncompliance, or devia-tions.
One unresolved item was identified and detailed in Paragraph 5.c.
9.
Entrance and Exit Interview Licensee management was informed of the purpose and scope of the inspection at the entrance interview, and the findings of the inspection were periodi-cally discussed with the licensee representatives as summarized in the following:
Date Reportable Details Covered November 4, 1980 Entrance November 5, 1980 4.c, 5.c November 6, 1980 5.c, 7.c November 7, 1980 4.c, 5.c, 7.c Exit The inspector conducted an exit interview with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection.
The licens-ee acknowledged the inspectiun findings.
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