IR 05000286/1978030
| ML19274D912 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/02/1979 |
| From: | Keimig R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19063C795 | List: |
| References | |
| 50-286-78-30, NUDOCS 7902270216 | |
| Download: ML19274D912 (10) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-286/78-10, Docket No. _ 50-286 License No.
DPR-64 Priority Category C
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Licensee:
Power Authority of the State of New York 10 Columbus Circk New York, New York 10019 Facility Name:
Indian Point Nuclear Generating Station, Unit 3 Inspection at: Buchanan, New York Inspection conducted:
October 29 - November 25, 1978 3c,e6 /97[
Inspectors: \\
h b
T. Rebelowski, Resident Reactor Inspector date signed date signed date signed Approved by-e
/[2/7f~
. R. Keffnig, thlet, Heactor FroJects
'date' signed Section No. 1, R0&NS Branch
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Inspection Summary:
Inspection on October 29 - November 25, 1978 (Report No. 50-286/78-30)
Areas Inspected: Routine inspection by the resident inspector of previously reported inspection findings; plant operations including: tours of the facility; physical protection in the areas of access control, barriers, search, escort, communications and compensatory measures; observations of Radiation Emergency Drill and environmental surveillance.
The inspection involved 31 inspector-hours onsite by the NRC resident inspector.
Results:
No items of noncompliance or deviations were identified.
790227021(o Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Mr. M. Albright, I&C Superintendent Mr. J. Bayne, Resident Manager Mr. S. Cantone, Superintendent of Power Mr. J. Kelly, Radiological and Environmental Services Superintendent Mr. J. Kilduff, Assistant to Resident Manager Mr. N. Passman, Reactor Analyst Supervisor Mr. S. Porter, Porter-Gertz Consultant Inc.
Mr. E. Tagiomonte, Operations Superintendent Mr. B. Weiser, Security and Safety Superintendent Mr. S. Zulla, Technical Services Superintendent The inspector also interviewed other licensee employees including members of operations, maintenance, health physics, security and quality assurance staffs.
2.
Licensee Action on Previous Inspection Findinas (Closed) Unresolved item (286/77-01-10): All testing listed in Detail 9.a of Inspection Report No. 50-286/77-01 has been completed including INT.P.P.4.6.4.
This item is resolved.
(Closed) Unresolved item (286/77-28-05): The licensee has revised PEP-ES-1 A, Revision 4, Loss of Coolant to Containment to reflect valve listings of Technical Specification Table 3.6.1.
This item is resolved.
(Closed) Unresolved item (286/77-38-01): The licensee has clarified the use of the traveler in Administrative Procedure 28.
This item is resolved.
(Closed) Unresolved item (286/77-38-02): The inspector reviewed weld inspection reports including Material FW1 of six welds and qualification histories.
This item is resolved.
(Closed) Unresolved item (286/78-01-13): The licensee has documented the qualifications of personnel to level 2 on PT and MT procedures.
This item is resolved.
(Closed) Unresolved item (286/78-01-02): The licensee has revised the SRC and PORC administrative procedures in the area of member-ship and quorum.
This item is resolve.
(Closed) Unresolved item (286/78-20-05): The licensee has incor-porated 10 CFR 21 information on purchase orders involving safety related material.
This item is resolved.
(Closed) Unresolved item (286/78-26-02): The licensee has obtained requalification records of personnel transferred from Unit 2.
This item is resolved.
3.
Review of Plant Operations a.
Shift Logs and Operating Records (1) The inspector reviewed the following logs and records:
(a) Senior Reactor Operator Log (October 24,1978 to November 24,1978)
(b) Watch Supervisor's Log (October 24, 1978 to November 24,1978)
(c) Conventional Nuclear Plant Operator Log (October 24, 1978 to November 21,1978)
(d) Night Order Book (e) Jumper Log to November 23, 1978 (f)
Significant Occurrence Reports (08-3-74) (October 24, 1978 to November 23, 1978 (g)
Flux Difference Log Sheet (October 23, 1978 to November 24,1978)
(h)
Reactor Coolant Leakage Surveillance Sheet (October 28, 1978 to November 23,1978)
(i)
Rod Position Indication Log (October 28, 1978 to November 23, 1978)
(j) Thermal Power Calculation Sheet (October 28, 1978 to November 23,1978)
(k)
Containment Leakage Calculation Sheet (October 28, 1978 to November 23,1978)
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(1) Quadrant Power Tilt Calculation Sheet (October 25, 1978 to November 23, 1978)
(m) High Radiation Area Locked Gate List (October 25, 1978 to November 24,1978)
(n) Control Room Log Sheet (October 26, 1978 to November 24, 1978)
(o)
Conventional Area Log Sheet (October 25, 1978 to November 21,1978)
(p)
Nuclear Area Log Sheet (October 23, 1978 to November 24, 1978)
(q) Nuclear Plant Operator Log (October 23,1978 to November 24,1978)
(2) The logs and records were reviewed to verify:
(a)
Log Book reviews are being conducted by the staff; (b)
Instructions in the Night Order Book did not conflict with Technical Specifications; (c) Jumper Log entries did not conflict with Technical Specifications ;
(d) Significant Occurrence Reports confinn compliance with Technical Specification reporting and LC0 requirements; and, (e)
Log book entries involving abnormal conditions are sufficiently detailed.
(3) The inspector used the following acceptance criteria for the above items.
(a)
Technical Specifications.
(b)
Licensee Procedures:
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AP-8, " 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-21.6, " Night Order Book."
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(c)
Inspector Judgnent.
(4)
Findings:
The inspector had no questions / comments on the above inspection items except as described below:
Quadrant Power Tilt Calculation Sheet The inspector's review of the Quadrant Power Tilt Calcu-lation Sheet for November 14,1978 at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> indicated that the calibrated detector current for N42B (0.99 amp.)
was substituted for the detector current for N448 (0.998 amp.).
Calculations of the Quadrant Power Tilt-Bottom using the corrected current (0.998 amp) indicated a value of 1.0207 which would have required a reduct'on in power of 4%.
No such reduction was noted in the operating logs.
The licensee instituted a review of the computer reactor core information system and the anomaly could not be found for that period of time.
Quadrant Power Tilt Calculations (QPTC) on November 14 @
1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> indicated a QPTC of 1.007 and on November 15 @
0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> a QPTC of 1.006.
The current reading of 0.998 was believed to have been misread as 0.988.
This error in calculations was one of three found that had no effect on the total calculations.
This item will be reinspected.
b.
Plant Tour (1) The inspector toured accessible areas of the plant at various times during the inspection and took independent readings on safety related equipment.
The tours included the following areas:
(a)
Control Room (b)
Primary Auxiliary Building
(c) Turbine Building (d) Transformer Yard (e)
Intake Structure (f) Security Control Building (g) Auxiliary Boiler Feed Building (h)
Diesel Generator Rooms.
(2)
The following observations / determinations were made:
(a)
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.
(b)
Fluid leaks: all areas toured were examined for evidence of excessive fluid leakage.
(c)
Piping vibration:
all areas toured were e>:amined for evidence of excessive piping vibration.
The inspector identii.ad the main boiler feed valve bypass lines as an area that requires evaluation by the licensee for the damping of vibrational effects on this piping.
(d)
Control Room and Nuclear Plant Operator station manning:
these areas were observed to determine compliance with regulatory requirements.
(e) Selected valve positions / equipment start positions.
(f)
Discussions with watch personnel pertaining to reasons for selected lighted annunciators:
the Watch Supervisor was questioned to determine if he was knowledgeable of the reasons for all lighted annunciators.
(g) Seismic restraint oil levels:
a sampling of plant hydraulic restraints was performed.
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(h) Monitoring instrumentation: Control Room instrumenta-tion including Radiation Monitoring, Power Range Channels, Control Rod positions, Pressurizer Levels, Pressurizer Pressure, Accumulator Tank Levels, S. I.
Lineups.
(i) Plant housekeeping conditions / cleanliness:
the use of absorbent paper for soaking oil dripping from the diesel engines was questioned by inspector.
Pieces of oil soaked absorbent paper were spread on the floors of the diesel generator rooms below diesel engines.
A sample of the paper (unsoaked) was removed from diesel area and was found to support combustion.
The licensee removed the material from the areas. A program to eliminate oil from the diesel area has been instituted.
The inspector had no further questions on this matter at this time.
(j)
LSSS/LCO:
equipment status or operating parameters were observed for conformance to the LSSS/LC0 require-ments.
(k) Shift turnovers of control room operators and watch supervisors were observed on regular and back shifts.
(3) The inspector used the following acceptance criteria for the above items:
(a) Technical Specifications Table 6.2-1.
(b)
(c)
(d)
Licensee Procedures:
AP-10, " Work Permits, Radiation Exposure Author-
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izations, Operating Orders."
AP-21.5, " Confines of the Control Room."
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AP-27.2, " Housekeeping."
AP-27.3, " Fire Protection."
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(e)
Inspector judgmen (4)
Findings:
The inspector had no further questions /connents on the above inspection items except as described below:
Diesel Generator Instrumentation.
The inspector requested the licensee to determine the required instrumentation calibration /surveillanca frequency for electrical and mechanical instruments that monitor the loading, running and starting of the emergency diesel generators.
The licensee stated that this review will be performed by December 22, 1978.
This item is unresolved.
(50-286/78-30-01 )
4.
Observations of Physical Security The resident inspector made observations, witnessed and/or verified, during regular and off-shift hours, that 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
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full time member of the security organization with authority to direct physical security action was present, as required.
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Manning of all three shifts on various days was observed to be as required.
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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Escorting
Communications
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Compensatory measures, when required
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d.
Findings The inspector identified no items of noncompliance.
5.
Radiation Emergency Drill a.
General The licensee conducted a radiation emergency medical drill on November 1, 1978.
The assumed emergency consisted of a postulated accident occurring with the impingement of primary coolant on a main-tenance worker.
The unannounced drill consisted of actions taken by the Control Room Operator, Shift Supervisor, Health Physics Technicians, Medical Representative, ambulance response and the Community Hospital.
b.
Procedures The licensee's response to the accident was detailed in the implementation procedure, IP-1012, "On Site Medical Emergency."
The procedures include the implementing details for the First Aid Team, Health Physics group, RN/ Medical Representatives and transportation and necessary equipment, such as transportation kit and the portable Decontamination Kit.
c.
Observations The licensee had monitors located in various areas to observe the actions of personnel.
The inspector observed the arrival of the off-site ambulance, removal of assumed victim from the first aid room / decontamination center, and the loading of the ambulance with off-site and on-site personnel.
All personnel cbserved were equipped with proper dosimetry devices.
A review of the licensee's critique will be made at a subsequent inspection. The inspector had no further questions on the drill at that time.
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6.
Environmental Surveillance The Unit 3 plant is a part of a program of environmental surveillance including the determination and reporting of fish impingement at the site's intake screens. The objectives of the impingement studies are to provide, in part:
estimates of the number, length, weight and types of species
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of fish killed by impingement on individual intake screens; a limit on the number of fish collected on the traveling
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screens; a study and evaluation of the causes of impingement;
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a schedule for reporting of data on fish collected at the
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intake screens for all units; and, an evaluation of the ecological significance of the effects of
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fish impingement on population density, size, abundance and diversity.
Daily collections of impinged fish are taken by rotating and back-washing each traveling water screen for the circulators in use and for those circulators which were secured during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
On November 2 and November 5, the specified limits of impingement were exceeded. The licensee's action was to contact the Department of Environmental Conservation of New York State and NRC:NRR/IE and to reduce the on-line circulators.
Fish impingement was reduced within specified limits on November 3 and November 8,1978.
7.
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 duri.'g this inspection are discussed in Paragraph 3.b.(4).
8.
Exit Interview At periodic intervals during the course of this inspection, meetings were held with senior facility management to discuss inspection scope and findings.