IR 05000247/1978035
| ML19283B758 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/26/1979 |
| From: | Keimig R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19283B752 | List: |
| References | |
| 50-247-78-35, NUDOCS 7903140445 | |
| Download: ML19283B758 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No. 60-247/78-35 Docket No. 50-247 License No. DPR-26 Priority Category C
Licensee:
Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Facility Name:
Indian Point Nuclear Generating Station, Unit 2 Inspection at:
Buchanan, New York Inspection conducted: November 12 to December 9,1978 Inspectors-
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$~ 71 T. RebeloM Resident Reactor Inspector
/date signed date signed
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date sig ed Approved by/
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um
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. R. Keimicf( Chief, Reactor Projects 6 ate signdd Section No. 1 R0&NS Branch Inspection Summary:
Inspection on November 12 to December 9,1978 (Report No. 50-247/78-35)
Areas Inspected:
Routine inspection by the resident inspector of plant operations including tours of the facility ; maintenance outage activities; calibration / surveillance of instrumentation; observation of physical protection in the areas of access control, barriers, search, escort, comunications and compensatory measures; radiological training; and licensee reported items.
The inspection involved 30 inspector-hours on site by the NRC resident inspector.
Results: No items of noncompliance were identified.
Region I Form 12
(Rev. April 77)
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DETAILS 1.
Persons Contacted Mr. A. Decker, Technical Engineer
- Mr. T. Law, Plant Manager
- Mr. C. Limoges, Reactor Engineer
- Mr. J. Makepeace, Technical Engineering Director Mr. W. Monti, Manager Nuclear Power Generation Department Mr. A. Nespoli, Operations Engineer Mr. M. Shatkowski, Chief Operations Enginear 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.
- denotes attendees at exit interview.
2.
Maintenance Outage The licensee entered into an unscheduled maintenance outage on November 23, 1978, due to a small leak that developed in a drain line socket weld in the reactor coolant pump seal injection header.
Cooldown and repairs were completed on November 26, 1978.
During the outage, No. 21 Residual Heat Removal (RHR) pump experienced a trip.
Examination of the pump indicated that the pump had seized.
Further review of the event will be made during a subsequent inspection.
Unit 2 returned to power on December 3,1978.
No items of noncompliance were identified during the inspectors review of the aforementioned events.
3.
Review of Plant Operations a.
Shift Logs and Operating Records The inspector reviewed the following logs and records for the period of November 9 to December 3,1978.
Senior Reactor Operator Log
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Watch Supervisor Log
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Conventional Nuclear Plant Operator Log Nuclear Plant Operator Log
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Night Order Book
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Jumper Log Significant Occurrence Reports
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Flux Difference Log Sheet
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Reactor Coolant Leakage Surveillance Sheet Rod Position Indication Log
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Thermal Power Calculation Sheet Containment Leakage Calculation
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Quadrant Power Tilt Calculation Sheet 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
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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 y
with Technical Specifications.
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Jumper Log entries did not conflict with Technical Specifications.
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Significant Occurrence Reports confirm compliance with
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Technical Specification reporting and LC0 requirements.
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Log book entries involvirg abnormal conditions are sufficiently detailed.
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Spacifications and the following licensee procedure.
0AD-3, " Plant Surveillance ad Log Keeping Policy";
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SAO-126, " Jumper Log",
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SA0-124, " Reporting of Anomalous Conditions"
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No items of noncompliance or unresolved items were identified during the inspector's review of logs and records.
b.
Plant Tour 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
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Security Control Building Spent Fuel Pool Area, Unit 1
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Waste Handling Control Room The following observations / determinations were made.
Radiation protection controls: step-off pads, storage /
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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.
Piping vibration:
all areas toured were examined for
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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.
Selected valve positions / equipment start positions.
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Discussions with watch personnel pertaining to reasons
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for selected lighted annuciators:
the Watch Supervisor was questioned to determine if he was knowledgeable of the reasons for all lighted annunciator Seismic restraint oil levels:
a sampling of plant hydraulic
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restraints was perfonned.
Monitoring instrumentation:
Control Room instrumentation
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including Power Range Channels, Control Rod Positions, Accumulator Tank Levels and Pressures, Reactor Coolant AP, Turbine Vibration and Containment Temperatures and Pressure.
Plant housekeeping conditions / cleanliness:
Minor adverse
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conditions were identified and corrected by the licensee in area of storage.
LSSS/LC0: equipment status or operating parameters were
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observed for conformance to the LSSS/LCO requirements.
Shift turnovers of control room operators and watch
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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 and the following licansee procedures.
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SA0 105, " Work Permits"
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SA0 114, " Station Fire Protection Systems"
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SA0 116, " Housekeeping Policy"
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SA0 126, " Jumper Log"
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SA0 128, " Security Plan Im.amentation"
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r No items of noncompliance were identified during the plant tours. Minor housekeeping problems were identified by the inspector and corrected by licensee.
4.
Calibration / Surveillance Observation The inspector observed a portion of the following calibration tests.
PTM4, " Pressurizer Level Analog Test", (portion that demonstrated
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pressurizer level bistable operability)
PTM14A, " Reactor Protection Logic Channel Functional Test",
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(portion that demonstrated pressurizer low and high pressure trips operability)
Items reviewed and observed by the inspector included test instrument calibration, procedure adherance, LC0 compliance, and technician cognizance of the test effect on system parameters.
No items of noncompliance were identified.
5.
Observations of Physical Security The resident inspector made observations, witnessed and/or verified, during regualar and off-shift hours, that the selected aspects of the security plan were in accordance with regulatory requirements, physical security plans and approved procedures.
a.
Physical Protection Security Organization Observations and personnal interviews indicated that a
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full time member of the curity organization with authority to direct physical security actions was present, as required.
Manning of all three shifts on various days was observed
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to be as required.
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All physical security members observed appeared capable
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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.
c.
Access Control Observations of the following items were made:
Identification, authorization and badging
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Access control searches
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Escorting
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Comunications
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Compensatory measures when required
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d.
Findings The inspector identified no items of noncompliance.
6.
Radiological Training The inspector attended and observed the licensee training course for qualification of plant personnel and contractors for unescorted access to radiological environments.
The course included site orientation, overview of radiological concerns, proper health physics protective methods and practical use of protective clothing and monitoring instrumentation.
No items of noncompliance were identified.
7.
Licensee Reported Items a.
In-Office Review of Licensee Event Reports A review was conducted of the Licensee Event Reports (LER's)
received in the Region I office to verify that the details of the events were el arly reported, including the accuracy of the description of the cause and the adequacy of the corrective action.
The LER's were also reviewed to determine whether further information was required from the licensee and whether generic implications were involved.
The following licensee event reports were reviewed.
Report Number Subject LER-78-018/03L-0 Bonnet Crack on Level instrumentation Line Isolation Valve for Buron Injection Tank.
LER-78-019/03L-0 Socket Weld Leak on Elbow of Seal Injection Line.
LER-78-020/04T-0 ETSR-Anomalous Measurement of Water Sample LER-78-021/03L-0 Main Steam Isolation Valve Failed to Close LER-78-022/0lT-0 Pressurizer Power Operated Relief Valves Installed with Incorrect Trim Package
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LER-78-023/04T-0 Aquatic Vegetation Sampling Anomaly LER-78-024/04L-0 Chromate Release LER-78-025/04L-0 Heat Rejection Rate Calculations LER-78-026/03L-0 Improper Support Location for RHR Piping LER-78-027/03L-0 Seal Failure - Boric Acid Transfer Pump No. 21 LER-78-028/0lT-0 Leak at Elbow between Containment Isolation Valves LER 78-029/03L-0 Reduction in Condensate Storage Tank Level LER 78-030/03L-0 Instrument Anomaly on PC-439A b.,
Onsite Licensee Event Followup All the LER's listed in Paragraph 7a above were selected for onsite followup. The inspector verified that the reporting requirements of Technical Specifications, Station Administrative Orders No. 124 and No. 125 had been met, that appropriate corrective action had been taken, that the event was reviewed by the Technical Engineering Director and that continued operation of the facility was conducted in conformance with the Technical Specification limits.
The inspector's findings regarding the licensee events were acceptable, unless otherwise noted below.
(1)
LER 78-022/0lT-0 - The licensee wiil install the new trim
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package at the next shutdown of sufficient duration to complete the work. This item remains unresolved pending installation of the new trim package.
(247/78-35-01).
(2)
LER 78-025/04L-0 - The licensee subnitted a change to the ETSR on December 5,1978.
Pending revision of the ETSR, the licensee will submit licensee event reports at intervals specified by NRR.
This item is unresolved pending issuance of reviseo ETSR reporting requirements.
(247/78-35-02)
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(3) LER 78-026/03L-0 - The licensee has not completed cmanent repairs to the cracked RHR piping.
In addition, tne licensee has not determined (1) the extent of crack propagation and (2) details as to the permanent hangers designed to prevent similar occurrence on the redundant RHR loop.
Pending Completion of permanent repairs and NRC review of the above licensee determinations is an unresolved item (247/78-35-03).
(4) LER 78-028/017-0 - The licensee has not completed his analysis of removed piping.
Pending licensee completion of material analysis this item is unresolved.
(247/78-35-04)
(5) LER's 78-018/03L-0, 78-019/03L-0, and 78-023/04T-0 - The licensee has submitted updated reports for these events.
The additional information and corrective actions were reviewed by the inspector and found acceptable.
The inspector had no further questions concerning these LER's.
8.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations.
Unresolved items disclosed during this inspection are discussed in Paragraph 7b.
9.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection.
The inspector summarized the inspection findings including the unresolved items.