IR 05000247/1979004
| ML19225A152 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/14/1979 |
| From: | Dante Johnson, Keimig R, Rebelowski J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19225A145 | List: |
| References | |
| 50-247-79-04, 50-247-79-4, NUDOCS 7907180483 | |
| Download: ML19225A152 (10) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEfiENT Region I Report No. 50-247/79-04 Docket No. 50-247 License No. DPR-26 Priority
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Category C
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Licensee:
Consolidated Edison Company of New York 4 Irving Place New York, New York 10003 Facility Name:
Indian Point Nuclear Generating Station, Unit 2 Inspection at:
Buchanan, New York Inspection conducted:
February 4 - March 3, 1979 Inspectors:
d/b 79 b orbi P
den eactor Inspector
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D.JohnsonIReactorInspector
/date' signed date signed Approved by:
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.'R.Keimid,ChieheactorProjectsSect!ou date signed No. 1, R03NS Branch Inspection Summary:
Inspection on February 4 - March 3,1979 (Recort No. 50-247/79-04)_
Areas Insoected:
Routine inspection of plant onerations including:
tours of facility; physical protection in the areas of access control, barriers, search, escort, communications and compensatory measures; preparat:ons for and observations of a Site Emergency Drill; Calibration and sontrol of test equipment; radiation protection operations and radio-active waste system management.
The inspection involved 34 inspector-hours onsite by the NRC resident inspector and one regional based inspector.
Results:
No items of noncompliance were identified.
7907180483 Region I Form 12 ii
-,. l Iid j) 4 (Rev. April 77)
DETAILS 1.
Persons Contacteo Mr. A. Decker, Technical Engineer Mr. C. Limoges, Reactor Engineer Mr. J. Makepeace, Technical Engineering Director Mr. W. Monti, Manager, Nuclear Power Generation Department Mr. B. Moroney, Chief Operations Engineer Mr. M. Shatkouski, Plant Manager Mr. R. Warren, Security Supervisor The inspector also interviewed and observed other licensee employees including members of the operations, technical services, health physics, security and maintenance staffs.
2.
Review of Plant Operations a.
Shift Logs and Operating Records The inspector reviewed the following logs and records for the period of February 1 to February 23, 1979.
Senicr Reactor Operator Log
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Watch Supervisor Log
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Conventional Nuclear Plant Operator Log
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Nuclear Plant Operator Log
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Night Order Book
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Jumper Log
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Significant Occurrence Reports
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Flux Difference Log Sheet
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Reactor Coolant Leakage Surveillance Sheet
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Rod Position Indication Log 34[
l!}
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Thermal Power Calculation Sheet
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Containment Leakage Calculation
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Quadrant Power Tilt Calculation Sheet
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High Radiation Area Locked Gate List
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Control Room Log Sheet
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Conventional Area Log Sheet
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Nuclear Area Log Sheet The Logs and records were reviewed to verify the following items:
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Log book reviews are being conducted by the staff.
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Instructions in the Night Order Book did not conflict with Technical Specifications.
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Jumper Log entries did not conflict with Technical Specifications.
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Significant Occurrence Reports confir'a compliance with Technical Specification reporting and LC0 requirements.
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Log book entries involving abnornal conditions are sufficiently detailed.
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and the following licensee procedures:
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QAD-3, " Plant Surveillance and Log Keeping Policy"
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SA0-126, " Jumper Log"
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SAP-124, " Reporting of Anomalous Conditions" The inspector discussed findings of the ion review with licensee represents'ives in the following areas:
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Integrator Flow Reading - Zone I-
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Quadrant Power Tilt-Corrections Review, 347 112
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Spent fuel pool level records,
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Thermal Power Calculations and
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Period of logging during computer downtime.
The licensee has revised his Nuclear Area Log Sheet to contain additional monitor 2d areas and promote the ease of recording data.
An additional survey of Boric Acid Heat Trace Operability per COL-1 has been instituted in preparation for design changes during next refueling.
No items of noncompliance or unresolved items were identified during the inspector's review of logs and records.
b.
Plant Tour
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At various times during the inspection, the inspector toured the following accessible plant areas:
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Control Room Primary Auxiliary Building
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Turbine Building
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Intake Structure Security Control Building
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The following observations / determinations were made:
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Radiation protection controls:
step-off pads, storage /
disposal of protective clothing, and control of high radiation areas were observed for adequacy in all areas toured.
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Fluid leaks: all areas toured were examined for evidence of excessive fluid leakage.
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Piping vibrations:
all areas toured were examined for evidence of excessive piping vibration.
Control Room and Nuclear Plant Operator station manning:
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these areas were observed to determine compliance with regulatory requirements.
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Selected valve positions / equipment start positions were observed.
Discussions with watch personnel pertaining to reasons
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for selected lighted annunciators:
the Watch Supervisor was questioned to determine if he was knowledgeable of the reasons for all lighted annunciators.
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Seismic restraint oil levels:
a sampling of plant hydraulic restraints was performed.
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Monitoring instrumentation:
Control Room instrumentation including Control Rod Positions, Accumulator Tank Levels and Pressures, Reactor Coolant AP, Power Range Nuclear Instrumentation, Turbine Vibration and Containment Tempera-tures and Pressures, and various on-line recorders were observed.
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Plant housekeeping conditions / cleanliness were observed and found satisfactory.
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LSSS/LCO: equipment status or operating parameters were observed for conformance to the LSSS/LCO requirements.
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Shift turnovers of control room operators and watch supervisors were observed on regular and back shifts.
Acceptance criteria for the above items included inspector judgement and requirements of 10 CFR 50.54(k), Regulatory Guide 1.114, applicable Technical Specifications and the following licensee procedures:
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SA0105, " Work Permits"
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SA0114, " Station Fire Protection Systems"
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SA0 116, " Housekeeping Policy"
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SA0 126, " Jumper Log" SA0128, " Security Plan Implementation"
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No items of noncompliance were identified during the plant tours.
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3.
Emergency Planning Drill a.
Pre-Drill Activities A joint meeting with representatives from Consolidated Edison Company and the Power Authority of New York was held on February 13, 19/9.
The purpose of the meeting was to brief the referees on their duties and responsibilities and to discuss in detail the nature and scope of the drill scenario. The scenario involved a simulated Reactor Coolant sample line break outside containment on Unit #2 that could not be isolated outside containment and therefore would necessitate a contairiment entry.
The sample line break would result in an offsite release.
On Unit #3 a simulated loss of coolant accident (LOCA) in containment was planned with subsequent safety injection initiation.
The inspector determined that the outside support agencies (NRC, State and Lccal officials and the Coast Guard) had been notified of the drill.
The inspector also determined that the drill has been unannounced to licensee personnel to the extent that the drill scenario was known only to the drill observers, the NRC inspector and a limited number of licensee upper management.
The major objective of the drill is to evaluate the effectiveness of the emergency plan in combating a dual accident involving both Units.
b.
Drill Observation During the drill the NRC inspector made detailed observations of the following activities:
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Detection of and response to the simulated emergency conditions, including actions taken in accordance with approved procedures and plans;
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Notification of plant personnel and offsite agencies;
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Assessment actions;
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Dispatch of offsite monitoring teams; Comnunications; and
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Coordination and control of response actions.
No items of noncompliance were identified.
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4.
Calibration and Control of Test Eauipment a.
The calibration and control of test equipment used as standards were examined on a sampling basis to verify the following:
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Establishment and adherence to calibration schedules;
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fiaintenance of calibration records identifying standards used which have traceability to the flational Bureau of Standards or other independent testing organizations;
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Proper storage and labeling of test equipment; and,
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Adequate control of test equipment including record keeping.
b.
The inspector selected on a sampling basis, the following measuring and test devices stored and maintained in the I & C instrument shop.
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Chandler dead weight tester, Serial
.'lo. 9617, IC-447
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Chandler dead weight tester, Serial fio.13091, IC-411
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Mansfield - Green dead weight tester, Serial flo. 5494, IC-169
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Wallace & Tiernan test gauge FA-145, Serial flo. fH-13426
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Hickock Multi Channel Counter, DP-150, Serial flo. 38900157
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Heise Test Gauge, Serial flo. 24929
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Heise Test Gauge, Serial fio. 9847
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Digital Multivoltmeter, 8120H, Serial flo. 52430
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All instrun.ents stored in the emergency locker.
flo items of noncompliance were identified.
5.
Performance of Calibration / Functional Tests The inspector witnessed the performance of Surveillance Test, PT-f18, Steam Generator Level Analog Test.
Observations were mMe to verify that test performance was consistent with approved procedures and to verify the implementation of controls for test equipment.
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No itens of non:ompliance were identified.
6.
Radiation Protection Ooerations a.
Instrumentation The inspector examined portable instruments, area monitors, friskers and fixed counting equipment in the Health Physics lab to verify the following:
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Operability, by direct observation;
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Currency of calibration by observation from labeling on the instruments and review of calibration records; and,
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Performance of daily standard source checks including periodic statistical analysis performed in accordance with approved procedures on fixed counting equioment.
No items of noncompliance were identified.
b.
Exposure Control The inspettor reviewed all current Radioactive Work Pernits (RWP'S) in use and selected the follow *ing for direct observation to verify all requirements of the RWP's were being followed.
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RWP #1999, Calibration of Health Physics instruments inside containment;
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RWP #2118, Running conduit on the 80' and 95' levels of the Primary Auxiliary Building for the fire protection system; and
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RWP #1956, Marking of drums and transfer of solid waste for disposal.
No items of noncompliance were identified.
c.
Posting and Control e inspector verified by direct observation that the postinn uirements of 10 CFR 19.ll(a), (1), (2), (3), and (4) have
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been met including the requirenents of 10 CFR 19.ll(c).
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During tours of the controlled areas the inspector verified that high radiation areas are properly posted and access control is in accordance with 10 CFR 20.203 and the Technical Specifications.
No items of noncompliance were identified.
7.
Radioactive Ilaste Systems a.
Radioactive Effluent Releases - Liauid & Gaseous The inspector examined the records for liquid and gaseous releases for the period from January 1,1979 through January 9, 1979.
Based on review of the above records and interviews with licensee personnel, the inspector verified the following:
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All releases were within the allowable limits of the Technical Specifications and 10 CFR Part 20; Required approvals were obtained prior to release;
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Sampling requirements were in accordance with Technical Specifications and Licensee Administrative Procedures; and Releases were accomplished in accordance with technically
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adequate approved procedures.
No items of noncompliance were identified.
b.
Effluent Release Control Instrumentation The inspector verified by direct observation and review of representative records that instrumentation, designed to terminate releases if activities or concentrations exceed predetermined values, was operable and in use during releases examined in a. above.
8.
Observation of Phvsical Security The resident inspector made observations, witnessed and/or verified, during regular and off-shif t hours, that the selected aspects of
- security plan were in accordance with regulatory requirements, ysical security plans and approved procedures.
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a.
Physical Protection Security Organization
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Observations and personnel interviews indicated that a full time member of the security organization with authority to direct physical security actions was present, as required.
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Manning of all three shif ts on various days was observed to be as required.
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All physical security members observed appeared capable of performing their assigned tasks.
b.
Physical Barriers Selected barriers in the protected area (PA) and vital areas (VA) were observed and random monitoring of isolation zones was performed.
Observations of truck and car searches were made.
c.
Access Control Observations of the following items were made:
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Identification, authorization and badging
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Access control searches
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Escorting
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Communications
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Compensatory measures when required d.
Findings The inspector identified no items of noncompliance.
9.
Exit Interview At periodic intervals during the course of this inspection, meetings were held with senior facility management to discuss inspection scope and findincs.
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