IR 05000309/1979002
| ML19259C041 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/27/1979 |
| From: | Baunack W, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19259C036 | List: |
| References | |
| 50-309-79-02, 50-309-79-2, NUDOCS 7906120251 | |
| Download: ML19259C041 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-309/79-02 Docket No.
50-309 License No. DPR-36 Priority Category C
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Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road h
Westborough, Massachusetts 01581
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Facility Name:
Maine Yankee Atomic Power Station Inspection at: Wiscasset, Maine Inspection conducted:
March 6-9, 1979 CLLvoc/
Inspectors:
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W. H. Baunack, Reactor Inspector dats signed date signed date si ned
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Approved by:
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B. K1 ster,Thier, f4uclear dupport
'date s'igne'd Section No. 2, RO&NS Branch Inspection Summary:
Inspection on March 6-9,1979 (Report No. 50-309/79-02)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee action on previous inspection findings; administrative controls for surveil ance procedures; surveillance testing; inspector's witnessing of surveillance testing; technician qualification; and facility tour. The inspection involved 26 inspector-hours onsite by one NRC inspector.
Results : Of the six areas inspected, no items of noncompliance were found in five areas; one apparent item of noncompliance was found in one area (Infraction - failure to adhere to administrative controls - paragraph 4.c).
22M IM 7906120a5l Region I Form 12
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(Rev. April 77)
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DETAILS 1.
Persors Contacted
- P. Anderson, Staff Assistant to Plant Superintendent R. Arsenault, Shift Superintendent R. Forrest, Staff Engineer
- C. Frizzle, Assistant Plant Coperintendent L. Grimard, Supervisory Control Room Operator W. Paine, Operations Supervisor R. Prouty, Maintenance Supervisor
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R. Radasch, Instrument and Control Supervisor
- S. Sadosky, Operational QA Department Engineer D. Sturniolo, Chemistry and Health Physics Supervisor
- E. Wood, Plant Superintendent The inspector also interviewed other licensee employees, including members of the technical and engineering staff and reactor operations personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous _ Inspection Findinas (Closed) Infraction (309/78-17-05): The basis for the "Tygon H O
Manometer" calibration has been placed in the Dead We ght Tester Calibration Check List Manual.
3.
Administrative Controls for Surveiliance Procedures The inspector perfonned an audit of the licensee's administrative controls by conducting a sampling review of the below listed admin-istrative procedures with respect to the requirements of the Technical Specifications, Section 5, " Administrative Controls," ANSI N18.7
" Administrative Controls for Nuclear Power Plants" and Regulatory Guide 1.33 " Qual:ty Assurance Program Requirements."
Procedure No. 0-06-1, Procedure Preparation, Classification and
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Format, Revision 3, July 28,1977.
Procedure No. 0-06-2, Procedure Review, Approval, and Distribution
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Revision 8, December 21, 1978.
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Procedure No. 0-10-2, Surveillance Tests and Records, Revision 4, August 8, 1977.
No items of noncompliance were identifie*.
d 4.
Surveillance Testing a.
The inspector reviewed surveillance tests on a sampling basis to verify the following:
Tests required by Technical Specifications are covered
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by properly approved procedures.
Test format and technical context are adequate and provide
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satisfactory testing of related systems or components.
Test results of selected tests are in conformance with
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Technical Specifications and procedure requirements have been reviewed by someone other than the tester or individual directing the test.
b.
The following surveillance tests were reviewed to verify the items identified above:
Procedure No. 3.1.8, CEA Exercising, Revision 7, October 3,
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1978.
Data was reviewed for six tests performed December 27, 1978 through March 1, 1979.
Procedure No. 3.1.9, Fire Pump Testing, Revision 7, December 8,
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1977.
Data was reviewed for seven tests performed September 5, 1978 through February 12, 1979.
Procedure No. 3.1.19, Reactor Coolant System Leakage Evalu-
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ation, Revision 1, November 22, 1977.
Data was reviewed for daily evaluations performed February 1, 1979 through February 28, 1979.
Procedure No. 3.1.2, ECCS Routine Testing, Revision 9,
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August 9, 1978.
Data was reviewed for tests performed November 8,1978, December 7,1978, January 8,1979, and February 8, 1979.
Procedure No. 3.1.20, CIS Trip Valve Testing, Revision 4,
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December 8, 1977.
Data was reviewed for five tests performed February 16, 1978 through February 13, 1979.
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Procedure No. 3.1.4, Emergency Diesel Generator - Monthly
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Surveillance Testing.
Data was reviewed for eight tests performed on the 1A Diesel September 7, 1978 through March 6,1979 and six tests performed on the 1B Diesel September 26, 1978 through February 26, 1979.
Secondary Side Log MY-0-24-73 January 29, 1979 through
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February 25, 1979.
Data reviewed for Cardox storage tank level and pressure.
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Procedure No. 3.60.5, Fire Pump Capacity Test, Revision 0, June 23, 1978.
Data was reviewed for test performed June 26, 1978.
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Procedure No. 7.209.118, Water and Sediment in Fuel Oils, Revision 0, February 1, 1979.
Data was reviewed for test performed January 29, 1979.
Test results also reviewed for samples taken April 27, 1978, August 8,1978, and November 18, 1978 which were analyzed at Yankee Rowe.
Boric Acid Concentration data reviewed for weekly samples
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analyzed June 25, 1978 through January 7, 1979.
c.
The following items were identified as a result of the above review:
(1) Surveillance record sheets are not being prepared as administratively required for the daily reactor coolant system leakage evaluations.
(2) The Master Surveillance Schedule administratively required to be maintained by PEQAG has not been kept current.
Also, the daily reactor coolant system leakage evaluation sur-veillance is not included in the Master Surveillance Schedule.
(3) Documentation associated with ECCS routine testing performed December 7,1978 and CIS Trip Valve Testing performed February 16, 1978, which included completed surveillance tests and maintenance requests, was completed in such a manner that verification of equipment acceptability could not be detennined. This verification of acceptability is administratively required.
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(4) Acceptance criteria has not been established on appropriate data sheets for Cardox storage tank level and pressure, and the boric acid tank concentration. The establishment of acceptance criteria in surveillance tests where appropriate is required by facility administrative procedures.
(5) The accuracy of the test instrument used in the performance of the Fire Pump Capacity Test perfurmed in June 1978 was not verifiable as administratively required.
(6) The diesel fire pump fuel quarterly surveillance for viscosity, water content and sediment was performed on January 29, 1979 using an unapproved procedure.
The use of an unapproved procedure is contrary to the requirements
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of facility administrative procedures.
(7) Surveillances associated with diesel fire pump testing failed to document the auto-start of the engine required by Tech-nical Specification 4.12.B.S.3.b each refueling interval.
The above examples of failure to adhere to facility administrative controls is contrary to Technical Specification 5.8.1 and is considered to be an item of noncompliance at the Infraction level.
(309/79-02-01)
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Inspector's Witnessing of Surveillance Testing a.
The inspector witnessed the performance of surveillance testing of selected components to verify the following:
Surveillance test procedure was available and in use
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Special test equipment required by procedure was calibrated
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and in use Test prerequisites were met
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The procedure was adequately detailed to assure performance of a satisfactory surveillance.
b.
The inspector witnessed the performance of LPSI pumps testing, containment spray pumps testing, safeguards locked valve inspectior inside containment, and portions of ECCS valve testing all in accordance with Procedure No. 3.1.2, ECCS Routine Testing, Revision 9, August 9, 1978.
A routine containment inspection was also witnessed by the inspector.
No items of noncompliance were identified.
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6.
Technician Qualification The inspector discussed the qualifications of personnel having responsibility for surveillance testing of safety-related components and equipment to verify that the individuals' experience level and training were in accordance with the guidelines of ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel.
fio ;i. ems of noncompliance were identified.
7.
Facility Tour On several occasions during the inspection, tours of the facility were conducted of portions of the Turbine Building, Auxiliary Building, Containment and the Control Room.
During the tours, the inspector discussed plant operations and observed housekeeping, radiation control measures, monitoring instrumentation and controls for Tech-nical Specification compliance.
In addition, the inspector observed control room operations for control room manning and facility operation in accordance with Administrative and Technical Specification require-meats.
No items of noncompliance were identified.
8.
Exit Interview The inspector met with licensee representatives (denoted in paragraph i) at the conclusion of the inspection on March 9,1979. The purpose, scope and findings of the inspection were summarized.
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