IR 05000213/1981009
| ML20032D420 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/26/1981 |
| From: | Elsasser T, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20032D418 | List: |
| References | |
| 50-213-81-09, 50-213-81-9, NUDOCS 8111130763 | |
| Download: ML20032D420 (7) | |
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s U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-213/81-09 Docket No.
50-213 License No. DPR-61 Priority Category C
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Licensee:
Connecticut Yankee Atomic Power Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name:
Haddam Neck Plant Inspection at:
Haddam, Connecticut Inspection conducted:
J ly 27 - August 2, August 8 - 15, and September 2 - 13, 1981 Inspectors:
Kfl 1 lb)
/0/19 l8J d~ ate 'igned T.H. Smith," Senior Resident Inspector s
date signed date signed
/8/MA/-
Approved by:
p T.C. Elfeest+, Chief, Reactor Projects date signed Section 1B, Division of Resident and Project Inspection Inspection Summary:
Inspection on July 27 - August 2, August 8 - 15, and September 2 - 13, 1981 TEeportNo. 50 ?.13/81-09)
Areas Inspected:
Routine inspections by the resident inspector of plant operations including tours of the facility; log and record reviews; review of licensee events; operating events; review of periodic and special reports and review of TMI Action i
Plan items. The inspection involved 58 inspector-hours by the resident NRC inspector.
Resul ts:
No items of noncompliance were identified.
ONN3 PDR m Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted The below listed technical and supervisory personnel were among those.
contacted:
G.H. Bouchard, Maintenance Supervisor R.E. Brown, Operations Supervisor T.W. Campbell, Instrument and Control Supervisor H.E. Clow, Health Physics Supervisor J.H. Ferguson, Station Services Superintendent R.L. Gracie, Operations Assistant R.H. Graves, Station Superintendent G.R. Hallberg, Security Supervisor R.Z. Test, Engineering Supervisor R.P. Traggio, Unit Superintendent Other licensee staff and operating personnel were also interviewed during the course of the inspection.
2.
Review of Plant Operation - Plant Inspections a.
Dur'ing the course of the inspection, the inspector conducted multiple tours of the following plant areas:
-- Control ~ Room.
-- Primary Auxiliary Building
-- Vital Switchgear Room
-- Diesel Generator Rooms
-- Turbine Building
-- Intake Building
-- Control Point
-- Security Building
-- Yard Areas
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b.
The following observations / determinations were made:
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-- Radiation protection controls. The inspector reviewed or observed l
the following: Radiation Work ~ Permits (RWP) in use, personnel
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compliance with RWP's, routine radiation area surveys, posting of
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radiation and high radiation areas and use of protective clothing L
and personal monitoring devices. No unsatisfactory conditions were identified.
-- Monitoring instrumentation.
Control room instruments were observed for proper operation, correlation between channels ~and that the t
i displayed parametars were within technical specification limits.
No unsatisfactory conditiens were iden.tified.
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-- Equipment lineups. The inspector verified that selected valves and breakers were in a position or condition required by the technical specifications.
-- Control room annunciators. Lighted annunciators were discussed with control room operators to verify that the reasons for them were under-stood and corrective action, if required, was being taken. On average, only one or two annunciators were lighted on each control room visit.
-- Plant housekeeping controls.
Plant housekeeping controls were observed including control and storage of flammable material, control of potential safety. hazards and licensee action to control the spread of surface and airborne contamination. No unsatisfactory conditions were identified.
-- Fluid leaks, piping vibrations. All areas toured were examined for evidence of fluid leaks and piping vibrations. None were found.
-- Fire protection / prevention. The inspector examined the condition of selected pieces of fire fighting equipment. Combustible materials were being controlled and were not found near vital areas. Selected cable penetrations were examined and fire barriers were found intact.
Cable trays were clear of debris.
-- Control room manning. The inspector verified that control room manning requirements of the technical spccificationswere being met.
-- Securi ty. During the inspection, observations were made of plant security including adequacy of physical barriers, access control, vehicle control, and searches.
No unacceptable conditions were identified.
3.
Shirt Logs and Operating Records a.
The inspector reviewed selected operating logs and records against th: requirements of the following procedures:
-- ADM 1.1-5, Control Room Operating Log;
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-- QA 1.2-14.1, Bypass and Jumper Control;
-- ADM 1.1-43, Control Room Area Limits for Control Operators;
-- N0P 2.2-2, Steady State Operation and Surveillance;
-- ADM 1.1-44, Shift Relief and Turnover;
-- QA 1.2-2.4, Housekeeping Requirements;
-- QA 1.2-16.1, Plant Information Reports; and
-- QA 1.2-14.2, Equipment Control.
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b.
Shift logs and operating records were reviewed to verify that:
-- Control Room log sheet entries are filled out and initialed;
-- Auxiliary log sheets are filled out and initialed;
-- Control Room log entries involving abnormal conditions provide sufficient detail to comunicate equipment status, lockout status, correction and restoration;
-- Operating Ordert do not conflict with Technical Specifications;
-- Plant Information Reports confirm there are no violations of Technical Spacification requirements; and
-- Logs and records are maintained in accordance with Technical Specifications and the procedures noted above.
c.
The following operating logs and records were reviewed:
-- N0P 2.2-2, Log sheets which consist of Control Room, Part 1 and 2, Primary Side Surveillance Form, Secondary Side Surveillance Form, and Radiation Monitoring System Daily Log;
-- Shift Turnover Sheets;
-- Jumper Log;
-- Tag Log; and
-- Control Rcom Operating Log.
d.
No unacceptable conditions were identified in this area.
4.
Licensee Event Reports (LER's)
The following LER's were reviewed to verify that the details of the event were clearly reported, including the accuracy of the description of the cause and the adequacy of the corrective action. The inspector determined whether further information was required, and whether there were generic implications. The inspector also verified that the reporting requirements of Technical Specifications and Station Administrative and Operating Procedures had been met, that appropriate corrective action had been taken and that the continued operation of the facility was conducted within Technical Specification limits.
81-09 Low Population Zone (LPZ) distance calculation error.
During the assessment of SEP Topic II-IB, Population Distribution, the licensee determined that the LPZ distance for the Haddam Neck Plant is not in confonnance
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with the criteria in 10 CFR 100.11. Preliminary calculations indicate that a smaller LPZ distance will not result in doses at the LPZ boundary in excess of 10 CFR 100 guidelines. Additional analyses are being conducted by the licensee. The results will be submitted to the NRC.
81-10 Oil leak on "B" charging pump. The pump was taken out of service to repair a small oil leak on a threaded
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connection.
81-11 Diesel generator overload.
During a surveillance test the 2A diesel was observed to have overloaded itself. A maximum load of 3300 KW was reached. The technical specification limit is 2850 KW. Adjustments were made to the governor.
81-12 Primary to secondary leak. Number two steam generator has primary to secondary leak varying between one and 12 gallons per day. Repair is planned during upcoming refueling outage.
81-13 Diesel generator 2A could not be phased.
Governor was repaired.
5.
Review of Periodic and Special Reports Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specification 6.9.1 were reviewed by the inspector.
This review included the following considerations: the report includes the information required to be reported by NRC requirements; planned corrective action is adequate for resolution of identified problems; determination whether any information in the report should be classified as an abnormal occurrence; and the validity of reported information.
Within the scope of the above, the following periodic reports were reviewed by the inspector:
Monthly Operating Report 81-7 for the month of July 1981.
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Monthly Operating Report 81-8 for the month of August 1981.
Semiannual Radioactive Effluent and Waste Disposal Report
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for the period January 1 - June 30,1981, dated August 24, 1981.
No unacceptable conditions were identified.
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6.
Operating Events Reactor Coolant System Leakage July 24. High temperature alarm on valve stem _ leakoff. system. This-system connects between dual stem packings on the eight reactor coolant loop isolation valves, the residual heat removal suction and discharge isolation valves ar.d various other reactor coolant system (RCS) boundary valves. Reactor coolant system leakage was approximately 0.3 GPM, slightly above normal but well below the 10 GPM technical specification limit.
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July 25. Plant power was reduced to 65 percent to alternately idle loops three and four to adjust the packing on the loop stop valves.
RCS leakage centinued to increase after these adjustments.
July 27. Plant power was again reduced to 65 percent to idle loop two and adjust the packing on the loop two isolai. ion valves.
RCS leakage continued to increase to approximately 1.2 GPM.
July 29. The licensee determined that the source of leakage into the valve stem leakoff system was possibly the RHR discharge isolation valve to RCS loop two. Any repair or packing adjustments made to the suspected-RHR valve required that the valve be tested in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.
Since the valve could only
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be tested with RCS pressure below 400 PSIG, a reactor shutdown was initiated.
s At 20 percent power during the shutdown, the plant tripped. A sticking relay in the low pressure steam dump system caused a turbine and reactor trip.
All systems functioned properly. after the trip. Adjustments were made to
.the RHR valve and it was tested successfully. After startup, RCS leakage continued to increase, reaching a maximum of 2.7 GPM.
August 23. The plant was shutdown again to repair and test the RHR system isolation valve. After startup on August 25, RC6 leakage returned to normal.
Plant Trip, September 10 At 9:54 p.m., the plant was manually tripped from full power when the control room operators heard a loud noise from the turbine floor and noted pressurizer pressure and primary temperature increasing. The cause of the event was the spurious closing of one of the two Turbine Stop Trip Valves. All systems fut ctioned properly after the trip. The valve was exercised and tested successfully.
No cause for the closure was determined.
Power generation was resumed at about 7:30 a.m., September 11.
No ur. satisfactory conditions in these areas were identifie,
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7.
TMI Action Plan Item III.D.3.3 Improved Inplant Iodine Instrumentation Under Accident Conditions a.
Requirement Each licensee shall provide equipment and associated training and procedures for accurately determining the airborne iodine concentration in areas within the facility where plant personnel may be present during an accident.
b.
Inspection Findings The following documents were reviewed by the inspector.
-- Counsil to Eisenhut letter dated December 31, 1981.
-- EPP l.5-8-C, E0F Emergency Radiological Surveys, dated September 21, 1981.
-- EPP 1.5-9-C, On-Site Emergency Radiological Surveys, dated September 21, 1981.
-- EPP 1.5-10-C, Off-Site Emergency Radiological Surveys, dated September 21, 1981.
The licensee is able to measure airborne radioiodine using portable emergency radiological response kits. The kits contain portable air samplers with silver-gel iodine cartridges and PS-2-2 Portable Scalers. The procedures noted above provide instructions for the use of the equipment. Training was provided to all required personnel covering the use of the equipment and the appropriate Emergency Plan Procedures during the month of July 1981.
In addition, several semi-portable Particulate Iodine and Noble Gas (PING) monitors are located in the plant including a unit in the Control Room / Technical Support Center (common ventilation) and the Emergency Offsite Facility.
Licensee action on this item is satisfactory.
8.
Exit Intervi a At periodic intervals during the course of the inspection, meetings were held with senior licensee management personnel to discuss inspection scope and findings.
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