IR 05000309/1987009

Safety Insp Rept 50-309/87-09 on 870427-0501.No Violations Noted.Major Areas Inspected:Radiation Protection Activities Associated W/Liquid & Gaseous Effluents,Including Training, Procedures,Semiannual Repts,Audits & Mgt Controls

ML20214Q487
Person / Time
Site:	Maine Yankee
Issue date:	05/26/1987
From:	Myers L, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214Q454	List: IR 05000309/1987009 ML20214Q453
References
50-309-87-09, 50-309-87-9, NUDOCS 8706050051
Download: ML20214Q487 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

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Report N /87-09

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Docket N License N DPR-36' Priority Category C Licensee: Maine Yankee Atomic Power Compa~ny 83 Edison Drive _

Augusta, Maine 04336 .

Facility Name: Maine Yankee Nuclear Generating Station i

Inspection At: Wiscasset, Maine

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Inspection Condccted: April 27 - May 1, 1987

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Inspectors: Jde 4" 7 L. Myers, t?on Specialist / date Approved b M c~

W. PascTak, Chiaf, Ef fluents f C[E7

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/ 'darie Radiation Protectior. Section Inspection Summary: Inspection on April 27 - May 1, 1987 (Report No. 50-309/87-09)

i Areas Inspected: Routine, unannounced safety inspection of the radiation i protection activities associated with liquid and gaseous effluents including:

i training, procedures, semi-annual reports, management controls, audits, ventilation systems, effluent control instruments, and liquid and gaseous j release I

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DETAILS 1.0 Persons Contacted 1.1 Licensee Personnel

• J. Garrity, Plant Manager

• E. Boulette, Assistc,t Plant Manager / Technical Support Manager

• R. Lawton, Manager, Quality Assurance

• P. Radsky, Chemistry Section Head L. Lawson, Quality Assurance Section Head R. Radasch, Instrumentation and Control Section Head 1.2 NRC Personnel

• C. Holden. Senior Resident Inspector R. Freudenburger, Resident Inspector Other licensee employees were contacted and interviesed during this inspectio *

Attended exit meetin .0 Management Controls <

The inscector reviewed the Technical Specif' cations, and the Maine Yankee Job Description Manual to determine the authorities and responsibilities in the area of liquid and gaseous effluent The Chemistry Section Head has the authority and the responsibility to manage the radioactive liquid and gaseous effluent programs. The Chemistry Section Head reports to the manager, Technical Support. The Manager, Technical Support reports to the Plant Manage The Instrumentation and Control Head has the responsibility to maintain, repair and calibrate the fr3truments associated with effluent conitoring. The Instrumentation and Control Section Head reports to the Maintenance Department Head who reports to the Plant Manage The Plant Engineering Department is responsible for surveillance testing of the ventilation systems associated with the effluents. The Plant Engineering Section Head reports to the Director of Plant Engineering who reports to the Manager of Operation The Radiological Controls Section has the responsibility to manage the waste reduction program and radioactive waste shipments. The Radiological Controls Secticn Head reports to the Manager, Technical Support who reports to the Plant Manage Within the scope of this review, no violations were identifie l l

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3.0 Semi-annual Radioactive Effluent Reports The licensees Technical Specifications requires that radioactive effluent reports be submitted to the Commission on a semi-annual basis. The inspector reviewed reports that were submitted for the periods of July 1 to December 31, 1985, January 1 to June 30, 1986, and July 1 to December 31, 1986. The Semi-annual Radioactive Effluent Report of July 1 to December 31, 1986 included dose calculations for releases for the year of 1986 and the changes in the Offsite Dose Calculation Manual as required by the Radiological Effluent Technical Specifications approved mid year 1986. The reports were timely, comprehensive, and complet Within the scope of this review, no violation were identifie .0 Radioactive Effluent Releases - Liquid and Gaseous The licensee's radioactive effluent control program was reviewed by the inspector to determine compliance with the Technical Specification Mid year 1986, Radiological Effluent Technical Specifications were incorporated into the licensee's Technical Specifications which required a different method of calcul.ating releases. The following specific areas were examined: limits for nuclide release rates, concentrations of nuclides during releases, dose rates during releases and doses due to releases, and total quantity of liquid and gaseous effluent released. The uses of effluent handling equipment and radiation monitors were reviewe The conduct of these operations was in conformance with applicable procedures and Technical Specification There were two unplanned releases. The first occurred December 30, 1986 when a blind flange on nitrogen line to the Volume Control Tank (VCT)

leaked some of the contents of the VCT through a malfunctioning check valve and a valve which had inadvertently been cracked open slightly to the blind flange. The release was through the Primary Auxiliary Building Ventilation system which is vented through the filtered and monitored Plant Vent Stack. The second release occurred when the Refueling Water Storage Tank valve leaked to the storm drain which drains to the wie l In both cases the licensee's methods of determining the amount released l were conservative and reasonable. Both releases were promptly identified i and stopped. C:rrective actions to prevent recurrence were rapid and '

effectiv Within the scope of this review, no violations were identifie .0 Procedures  !

The adequacy and effectiveness of the licensee's procedures were reviewed against the criteria contained in Technical Specification 5.8, '

" Procedures". The licensee's performance relative to these criteria was determined by discussion with the Chemistry Section Head, Instrumentation and Control personnel, and other licensee's personne .

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Procedures reviewed included;

- Procedure No. 3.7.1.1., " Liquid Radioactive Waste Discharges",

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' - Procedure No. 3.7.1.2., " Gaseous Radioactive Waste Discharges",

- Procedure No. 3.7.2. , " Sampling Procedures for Chemistry Technical

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' Specification Surveillance Tests",

- Procedure No.-7.304, " General Sampling Procedure",

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- Procedure No. 7.211, " Chemical Section Training", and

- Procedure No. 3-6.2.1.29, " Source Calibration of the Radiation Monitoring System".

The licensee's procedures were adequate to implement the effluent progra .

Within the scope of this review, no violations were identifie .

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6.0 Effluent Control Instrumentation The effluent control instruments were reviewed against the criteria 1 contained in Section 4.1 of the Technical Specification The licensee's performance in this area was determined by discussion with i

Instrument and Control personnel and by reviewing maintenance, repair, and calibration records. The instruments were maintained and calibrated in accordance with the regulatory requirement Within the scope of this review, no violations were identified.

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7.0 Audits The implementation of the licensee's audit program was reviewad against crite-ia contained in 10 CFR Part 50, Appendix B and the licensee's ;

Quality Assurance Manual. The licensee's performance relative to these criteria was determined by discussions with Quality Assurance personnel i

and by reviewing the Audit Report MY-36-20 of October 1986 and by selected quality control observations.

i The Audit Report MY-86-20 examined the Radiological Environmental and Effluents Programs to determine the capability of the programs with respect to the revised Technical Specifications. The audit was thorough, adequate and timely. The audit had several findings and observations -

which have been resolve Within the scope of this review, no violations were identifie ,

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8.0 Ventilation Systems Surveillance Testfnq Ventilation systems were reviewed against the criteria specified in Section 4.11 of the Technical Specifications. The systems reviewed included the Control Room Recirculation and Breathing Air Ventilation System, the Spent Fuel Pool Ventilation System, the Containment Ventilation / Purge System, the Waste Off Gas Filter, and the Radiological Control Storage Area Syste The licensee performance relative to these criteria was determined by interviewing an Er.gineer and reviewing appropriate document The ventilation systems were being maintained and tested as required by the Technical Specification Within the scope of this review, no violations were identifie .0 Training The licensee's training program in the chemistry area was reviewed against criteria contained in Tecnnical Specification 5.4, 10 CFR Part 50, Appendix B, and licensee procedure The licensee's performance relative to these criteria was determined by discussion with the Chemistry Section Head, Chemistry personnel, and reviewing record Retraining is on an annual basis and all personnel have been retrained in

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a timely manner. One chemist has been detailed to develop a training program which will meet the INPO training accreditation criteri i Within the scope of this review, no violations were identifie .0 Exit Interview The inspector met with licensee represefitatives (denoted in

paragraph 1) at the conclusion of the inspection on May 1, 1987. The inspector summarized the purpose and the scope of the inspection, and the inspection findings. At no time during this inspectign was written material provided to the licensee by the inspector.

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