IR 05000247/1979008
| ML19254D563 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/11/1979 |
| From: | Keimig R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254D562 | List: |
| References | |
| 50-247-79-08, 50-247-79-8, NUDOCS 7910290084 | |
| Download: ML19254D563 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-247/79-08 Docket No.
50-247 License No.
DPR-26 Priority
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Category c
Licensee:
Consolidated Edison Company of New York, Inc.
4 Irving Place
New York, NY 10003
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Facility Name:
Indian Point Nuclear Generatina Station, Unit 2 Inspection at:
Buchanan, New York Inspection cond cted: April 1-28,1979 Inspecto
%W
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T. Rebel /wski,ResidentReactorInspector
'dat'e signed date signed date signed Approved b
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I R.' R. KeimigYChief, Reactor Projects
"datt signed Section No. 1, RO&NS Branch Inspection Summary:
Inspection on Aoril 1-28, 1979 (Report'No. 50-247/79-08)
Areas Inspected:
Routine inspections of plant operations; facility tours; observations of physical security; licensee plans for coping with strike of guard force; new fuel inspection; training; licensee reported events; rad waste cask contamination; inservice inspection program; and maintenance. The inspection involved 38 inspector-hours on site by the NRC resident reactor inspector.
Results:
No items of noncompliance were identified.
1221 257 Region I Form 12 (Rev. April 77)
7 9102 90CS t'
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DETAILS 1.
Persons Contacted Mr. A. Decker, Technical Engineer Mr. W. Ferreira, QA Engineer 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. Shatkouski, Plant Manager
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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 and corporate personnel including nuclear engineering staff members.
2.
Review of Plant Operations a.
Shift Logs and Operating Records The inspector. reviewed the following logs and records for the period of April 1-21, 1979:
Senior Reactor Operator Log
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Watch Supervisor 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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Flux Difference Log Sheet
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Reactor Coolant Leakage Surveillance Sheet Thermal Power Calculation Sheet
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Containment Leakage Calculation Quadrant Power Tilt Calculation Sheet
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High Radiation Area Locked Gate List
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Control Room Log Sheet Conventional Area Log Sheet
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Nuclear Area Log Sheet
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Boric Acid Heat Trace Circuits
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Running Equipment 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.
Instructions in the Night Order Book did not conflict
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with Technical Specifications.
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Significant Occurrence Reports confirm compliance with Technical
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Specification reporting and LC0 requirements.
Log book entries involving abnormal conditions are sufficiently
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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" SAO-126, " Jumper Log"
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SA0-124, " Reporting of Anomalous Conditions"
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No items of noncompliance were identified during the inspector's review of i n and records.
b.
P_lant Tours At various times during the inspection, the inspector toured the foliowing accessible plant araas:
Control Room
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P.'imary Auxiliary Building Tu.-bine Building
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Intike Structure Security Control Building
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The following observations / determinations were made:
Radiation protection controls:
step-off pads, storage / disposal
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of protective clothing, and control of high radiation areas were obse.ved for adequacy in all areas toured.
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Fluid leaks-all areas toured were examined for evidence of excessive fluid leakage.
Piping vibrations:
all areas toured were examined for evidence
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of excessive pioing vibration.
Control Room and Nuclear Plant Operator station manning:
these
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areas were observed to determine compliance with regulatory requirements.
Selected valve positions / equipment start positions were observed.
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Discussions with watch personnel pertaining to reasons for
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selected lighted annuciators:
the Watch Supervisor was questioned to determine if he was knowledgeable of the reasons for all lighted annunciators.
Seismic restraint oil levels:
a sampling of plant hydraulic
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restraints was performed.
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Monitoring instrumentation:
Control Room instrumentation including Control Rod Positions, Accumulator Tank Levels and Pressures, Power Range Nuclear Instrumentation, and various on-line recorders were observed.
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Plant housekeeping conditions / cleanliness were noted.
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LSSS/LCO:
equipment status or operating parameters were observed
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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:
AP-S, " Reporting of Significant Occurrences;"
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AP-13, " Jumper Control;"
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AP-21, " Conduct of Operations;"
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AP-21.4, " Log Keeping;" and,
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AP-21.5, " Night Order Book."
No items of noncompliance were identified during the plant tours.
3.
Observation of Physical Security The resident inspector made observations, witnessed and/or verified during regular and off-shif t 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 personnel interviews indicated that a full
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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 shifts on various days was observed to be
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as required.
All physical security members observed appeared capable of
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performing their assigned tasks.
b.
Physical Barriers Selected barriers in tae 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
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Observations of the following items were made:
Identification, althorization 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
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d.
Findings The inspector identified no items of noncompliance.
4.
Licensee Plans for Coping with Strike of Guard Force The inspector reviewed the licensee's contingency plans for the turnover to nonstriking personnel the duties normally performed by guard force personnel expected to go on s:rike.
The review included staffing, quali-fications of nonstriking personnel taking over duties of striking personnel, arrangements made with support agencies, and the capability of the licensee to implement the emergency plan during the strike.
The strike did not take place, and the inspector had no further questions with the licensee's plans for coping with a strike of the guard force.
S.
New Fuel Inspection a.
The inspector reviewed the follow ng procedure to verify that a i
ter.nriically adequate, approved procedure is available to cover the receipt, inspection, and storage of new fuel.
Procedure No. 2-CM-2.14, Unloading, Storage and Handling of New
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Fuel Assemblies, Revision 1, April 4, 1979.
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b.
The inspector witnessed the receipt, removal from shipping containers, inspection, handling, and storage of new fuel to verify it was performed in accardance with the licensee's pror.edures.
c.
No items of noncompliance were identified.
6.
Training a.
The anspector tttended a portion of the special NRC briefing on the events at the Three Mile Island Station conducted at Indian Point on April 19, 1979.
Additionally, the inspector verified that operators who missed the NRC presentation on April 19, 1979, were fully briefed
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on April 25, 1979.
b.
The inspector witnessed new fuel handling training presented to maintenance, QC, and operating personnel involved in the receipt and handling of new fuel.
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 clearly reported, including the accuracy of the description of the cause and the adequacy of the corrective action.
The LER's were also reviewee 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-78-030/03L-0 Instrument drift of steam line pressure bistable identified during surveillance testing LER-78-031/03L-0 During normal operation, one instrument channel of the containment pressure safeguards logic became deenergized when the static inverter associated with that channel failed.
LER-78-032/03L-0 Socket weld leak on seal inject.an line drain valve.
I221 262
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LER-78-033/0IT-0 Blockage in discharge line from the boron injection tank.
LER-78-034/04L-0 Error in calculation of heat rejected to the river.
LER-78-035/03L-0 Service water pump failure.
LER-78-036/03L-0 Hairline crack identified in a charging pump fluid cylinder.
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LER-76 037/03L-0 Diesel Generator declared inoperable due to air start motor problem.
LER-78-038/04T-0 Anomalous off-site precipitation sample.
LER-79-001/04L-0 Release of chromated water to river due to leak at str 'on air compressor.
LER-79-002/04T-0 Anomalous off-site precipitation sample.
LER-79-003/03L-0 Frozen refueling water storage tank level sensing line.
LER-79-004/03L-0 Radiation monitor R-11 and R-12 vacrum pumps inoperable.
LER-79-005/04L-0 Error in calculation of heat rejected to the river.
LER-79 t06/03L-0 Boric acid transfer pump inoperable.
LER-79-007/03L-0 Hydrogen recombiner inoperable.
LER-79-008/03L-0 Inoperable fan cooler unit.
LER-79-009/03L-0 Diaphragm failure on boric acid filter outlet valve.
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b.
Onsite Licensee Event Followup All the LER's listed 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 b c set, 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 confor-mance with the Technical Specification limits.
The inspector's findings regarding the licensee events were acceptaole.
Details on LER's78-032, 78-034 and 79-005, and 79-008 are included
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to indicate examples of methods used by the licensee to complete corrective actions.
LER 78-032/03L-0 The inspector's review cf licensee action to repair drain valve C-15 included:
MWR (Maintenance Work Request) N-28109
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MWR N-28105
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Engineering weld data
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Visual and LPT inspection as performed by licensee and witnessed
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by Q.4. group.
The existing valve was cut out and a new valve instasled per RWP No.
1983.
Material certifications were available and acceptable.
LER 78-034/04L-0, LER 79-005/04L-0 The Technica' Specifications were amended to reflect proper heat rejection rate calculations.
LER 79-008/03L-0 The inspector reviewed the Maintenance Work Request (MWR) 8604, and found no items of noncompliances.
The beari gs and bearing adapters had the required material certification.
8.
Inservice Inspection Program (Valve & Pumps)
The licensee has implemented the inservice insn". tion requirements as required by 10 CFR 50.55a, paragraph g.
A we
.1g group from NRC:NRR held a meeting on site on March 7, 1979 to discuss the testing program as submitted in supplement No. 3 of the licensee's Inservice Inspection and Testing Program.
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The resident inspector attended the session which addressed the following topics:
Full flow operational criteria
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Check valve testing
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Criteria for valve stroking The wo: king group discussed the licensee's valve testing submittal and conducted a review of valves and their function in regard to safety related systems necessary to prevent or mitigate ar. analyzed accident.
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The licensee will revise the program to detail the need for relief from testing under specified conditions.
The inspector has no further questions at this time regarding this matter.
9.
Maintenance The inspector observed and verified the instrument and control department activities on the repair of No. 21 Electric Cable Tunnel exhaust fan.
Work permit 50719 was issued and properly authorized repair as requested in MWR Serial 26792.
Retest of fan was performed per PT-R-31, Rev. 2.
The controls required cleaning.
The maintenance activity as observed by ir.spector was performed under the supervision of I&C Foreman.
No items of noncompliance were identified.
10.
Rad Waste Cask Trailer Contamination The licensee's method of removal of concentrated radwaste (evaporator bottoms) is to solidify the concentrate in a shipping cask.
During this process, on March 26, 1979, a pressure buildup in the mixing rig was caused by the inadvertent closing of a air operated fill valve.
The air operated fill valve closed due to a restricted air line (air line was pinched).
The pressure buildup caused a rubber urea / formaldehyde (U/F)
addition hose to pressurize and a small split (less than 1/8 in.) opened in hose causing concentrated waste U/F mixture to spray.
The spray caused contamination under the truck body, truck tires and an adjacent area of approximately 10 X 30 feet.
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The inspector observed the decontamination of the area and truck body and tires.
The licensee halted additional transfer waste operations until a review was completed by the Maintenance Superintendent and the Health Physics Superintendent.
A review of the licensee's actions were conducted by the inspector and found to be acceptable.
Long term modifications to the fill head and transfer rig were planned.
The inspector has no further questions on this item at this time.
No item of noncompliance was identified.
11.
Exit Interview At periodic intervals during the course of this inspection, meetings were
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held with senior facility management to discuss inspection scope and findings.
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