IR 05000286/1978028
| ML19284A532 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/06/1978 |
| From: | Keimig R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19284A528 | List: |
| References | |
| 50-286-78-28, NUDOCS 7903070089 | |
| Download: ML19284A532 (13) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION FN OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. Sn 2nU7A-?R Docket No. En 9M License No. DPR-64 Priority Category C
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Licensee:
Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Facility Name:
Indian Point Nuclear Generatina Station, Unit 3 Inspection at:
Buchanan, New York Inspection conducted:
Septem er 27-October 28, 1978 Inspectors
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JT. Rebelovdfki, Resident Reacter Inspector date ' signed date signed date signed
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/2 - d "78 Approved by:
/R. R. Kedi
, Chief
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actor Projects care signed Sectionf o. 1 Inspection Summary:
Inspection on September 27 to October 28, 1978 (Report No. 50-286/78-28)
Areas Inspected:
Routine inspection by the resident inspectcr of plant operations including:
tours of facility; radiation protection precautions; physical protection in the areas of access control, barriers, search, escort, communications and compensatory measures; calibration of safety related instrumentation required by technical specifications; and, licensee event r! ports.
The inspection involved 28 inspector hours on site by the NRC resident inspector.
Results:
Of the five areas inspected, one item of noncompliance was identified.
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(Infraction - plant physical prctection).
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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. D. Halama, Site QA Engineer
- Mr. J. Kelly, Radiological and Environmenta'. arvices Superintendent Mr. J. Kilduff, Assistant to Resident Manager Mr. N. Passman, Reactor Analyst Supervisor Mr. E. Tagiomonte, Operations Superintendent
- Mr. S. Zulla, Technical Services Superintendent
- Mr. B. Weiser, Security and Safety Superintendent The inspector also interviewed other licensee employees including members of operations, maintenance, health physics, security and quality assurance staffs.
- denotes those attending exit interview.
2.
. Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (286/73-01-06):
The inspector reviewed the qualification files of four members of PASNY's Quality Assurance group in the areas of Penetrant Testing (PT) and Magnetic Particle (MT) certification.
Formal training and test results conformed to the standards of SNT-TC-1A.
This item is closed.
(Closed) Unresolved Item (286/78-12-05):
The Engineering and Design Manual, DEP-3.3, Revision 1, was revised on May 31, 1978.
The EDP-3.3 requires, in Paragraph 6.2, that design changes be approved by the PORC and PE, or designee, before implementation.
This item is closed.
(Closed) Infraction (286/78-18-01):
The inspector verified that the licensee's changes to procedure RE-CA-056/1, titled " Reagents, Quality Control", addressed shelf life, expiration dates and the necessity of restandardizina the reagent.
Observations by the inspector of reagents, determined conformance to the procedural requirements.
This item is closed.
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(Closed) Unresolved Item (286/77-34-08):
The licensee's field inspection of spring hangers was in conformance with initial plant acceptance criteria. The steam generator restraints were
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consistent with system temperature at time of inspection.
The channel weld support for S-IR-356-3H was determined to be adequate as evidenced by a licensee engineering analysis which supported required loading.
This item is closed.
(Closed) Unresolved Item (286/77-34-09):
The licensee has reviewed and verified that the steam generator snubber attachments, as found, were correct. A missing cotter pin, has been replaced and the snubbers have been properly identified. This item is closed.
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 (September 27, 1978 to October 23,1978)
(b) Watch Supervisor's Log (September 27, 1978 to October 23, 1978)
(c) Conventional Nuclear Plant Operator Log (September 27, 1978 ta October 23,1978)
(d) Night Order Book (e) Jumper Log (thru No. 365)
(f)
Significant Occurrence Reports (September 27, 1978 to October 23,1978)
(g)
Flux Difference Log Sheet (September 27, 1978 to October 22,1978)
(h)
Reactor Coolant Leakage Surveillance Sheet (September 27, 1978 to October 27,1978)
(i)
Rod Position Indication Log (September 27, 1978 to October 27,1978)
(j)
Thermal Power Calculation Sheet (September 27, 1978 to October 27,1978)
(k)
Containment Leakage Calculation Sheet (September 27, 1978 to Octooer 27,1978)
(1) Quadrant Power Tilt Calculation Sheet (September 27, 1978 to October 27,1978)
(m)
High Ra-Jiation Area Locked Gate List (September 27, 1978 to October 24,1978)
(n)
Control Room Log Sheet (September 27, 1978 to October 25,1976)
(o)
Contentional Area Log Sheet (September 27, 1978 to October 25,1978)
(p)
Nuclear Area Log Sheet (September 27, 1978 to October 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 Specification; (c) Jumper Log entries did not conflict with Technical Specifications; (d)
Significant Occurrence Reports confirm compliance with Technical Specification reporting and LC0 requirements; and, (e)
Log book entries invol ting abnormal conditions are sufficiently detailed.
(3) The inspector used the following acceptance criteria for the above items.
(a) Technical Specification (b)
Licensee Procedures:
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 Judgement.
(4)
Findings:
The inspector had no further questions / comments on the above inspection items except as described below:
(a) The spray additive tanks were riding on the minimum level of 71% (TS 70%) for a number of days.
The licensee stated that additions were being made to raise the level above the annunciator alarm point.
The inspector confirmed licensee's action.
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) Electrical Tunnels (f) Spent Fuel Storage Building (g)
Intake Structure (h) Security Control Building
(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 examined for evidence of excessive piping vibration.
(d)
Control Room and fluclear 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 Sapervisor 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.
(h) Monitoring instrumentation:
Control Room instrumen-tation including Radiation Monitoring, Power Range Channels, Control Rod positions.
(i)
Plant housekeeping conditions / cleanliness:
storage of six acetylene cylinders was observed in the Penetration flitrogen Pressurization Area.
The licensee stated that cylinders would be removed.
This area will be reviewed at a subsequent inspection.
(j)
LSSS/LCO: equipment status or operating parameters were observed for conformance to the LSSS/LC0 require-ment (k)
Fire protection:
observations of fire extinguishing equipment, fire fighting equipment and emergency equipment were performed.
(1) Shift turnovers of control room operators and watch supervisors were observed on regular and back shift.
(3) The inspector used the following acceptance criteria for the above items:
(a) Technical Specifications Table 6.2-1.
(b)
(c)
(d)
Licensee Procedures:
3PT-V1, "Bergen-Paterson Shock Suppressor
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Inspection."
AP-10, " Work Permits, Radiation Exposure Author-
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izations, Operating Orders."
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AP-21.5, " Confines of the Control Room."
AP-27.2, " Housekeeping."
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AP-27.3, " Fire Protection."
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(e) Work Permit 23913 and Operating Orders 502 and 951683.
(f)
Inspector judgement.
(4) Findings:
The inspector had no further questions / comments on the above inspection items except as described below:
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(a) Vital Areas Access Control - During a tour of Primary Auxiliary Building on October 26,1978, at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, an entrance to a vital area was found blocked open and unattended.
The door was secured immediately and the guard force was notified.
The inspector deter-mined that the entrance was previously used to facilitate crane repairs within the vital area.
Discussions with the licensee indicated that the vital area was previously posted and that guards assumed that area was being manned by plant personnel while the repairs were in progress. Corrective action was taken immediately by guard force.
This item is considered an item of non-compliance at the infraction level.
(286/78-28-01)
(b) Modifications in the area of refueling. cavity drain system piping appeared to be improperly posted. A review of radiation levels determined that posting was satisfactory.
(c) The inspector's survey instrument indicated levels of radiation greater than posted survey levels in the area of CVC letdown piping (>30' mr vs 10 mr)
Discussi]n with the licensee indicated that the survey frequency met administrative procedure requirements and that the radiation levels were being reduced.
The levels in this area are affected by certain routine plant operations. The licensee stated that the require-ment for additional shielding of letdown line has been identified and modifications have been submitted.
The inspector had no further questions on this item.
4.
Radiation Protection Operations
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a.
Exposure Control The inspector examined the Radiation Exposure Authorizations in force on October 26, 1978.
During a tour of Primary Auxiliary Building, areas indicated on REA's as potential radiological hazards, were examined.
The controls established with regard to adherence to REA's were satisfactory.
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b.
Radiation Exposure Authorization (REA)
The inspector's review of REA's Nos. 729 and 730, which addressed requirements for the normal watch entries, in the area of additional precautions (protective clothing), indicated that the REA's were misnumbered.
A review of additional requirements was made by the inspector in the station radiological book at the REA entrance.
The additional instructions were available at Health Physics station.
The inspector identified no items of noncompliance in the area of protective clothing or respiratory devices required by REA's 729 and 730.
The licensee corrected the misnumbered REA's prior to inspector's egress from the primary auxiliary building.
5.
Observations of Physical Security The resident inspector made observations, witnessed and/or verified, during regular 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 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.
(See Detail Paragraph 3.(4)(a))
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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Communications
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Compensatory measures, when required
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d.
Training The inspector witnessed the field training of eight guards in the use of the weapons.
Field instructions were given by the instructor to supplement classroom training and fixed target firing in various body positions was conducted.
The inspector identified no inadequacies.
e.
Findings The inspector identified no items of noncompliance.
6.
Calibration The inspector witnessed portions of the calibration of the following systems:
Radiation Protection Equipment
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Power Range Instrumentation Electrical Heat Tracing (Intake Structure)
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a.
Radiation Protection Eauipment The inspector witnessed the calibration check of R-4 Charging Pump Room Area moaitor.
Check source strength was discussed with I&C superintendent.
Purchase requisitions have been submitted for replacement sources and the sources will be replaced before the effective life is expended.
(TestProcedure PTQO3, Revision 3).
b.
Power Range Instrumentation The inspector witnessed a section of Nuclear Power Range Calibration procedure PTM01, including a check of the overpower trips.
No items of noncompliance were identifie c.
Electrical Heat Tracing The inspector witnessed the sections of the Electrical Heat Tracing Procedure PTA-05 being performed at the intake struc-ture for heat tracing to various piping systems that supply bearing cooling and other screen wash services.
Observations indicated that a number of circuits require retesting as failures in the indicating circuit lamps were noted.
The licensee has been, and is presently, repairing the circuits.
A reexamination of test results will be made during a subsequent inspection. This item is unresolved.
(286/78-28-02)
The inspector identified no items of noncompliance.
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 acticn. The inspector conducted this review to determine whether generic problems were indicated and whether the event warranted on-site followup.
The following licensee events were reviewed:
Report Number Subject LER 78-017/03L-1 Reactor Coolant Temperature Transmitters outside of required tolerance.
LER 78-018/03L Refueling Water Storage Tank level. low level alarm outside of required tolerance.
LER 78-019/01T-0 Pressurizer Power Operated Relief Valves supplied with CV-38.5 vs. plan specification of CV-50 for trim package.
LER 78-20/03L-0 Undervoltage Relay 27-3A found to trip at a voltage less conservative than Technical Specifications.
LER 78-21/03L-0 Pressurizer Pressure Transmitter out of tolerance.
LER 78-22/03L-0 No. 32 RHR Pump Seal repaire Report Number Sub,iect LER 78-23/03L-0 Level Control Valve to Diesel Generator Day Tank Inoperative.
LER 78-24/03L-0 Auxiliary Boiler Feed Pump unable to reach full discharge pressure.
LER 78-25/03L-0 Service Water Pump shaft failure.
LER 78-26/03L-0 Condensate Storage Tank level below designated parameters.
LER 78-27/03L-0 Accumulator Level Transmitter indicating low level.
LER 78-28/03L-0 Condensate Storage Tank level below designated parameters LER 78-29/03L-0 Accumulator Level Transmitter indicating low levels.
LER 78-30L-0 RTD Bypass manifold hot leg isolation valves packing leakage.
LER 78-31/036-0 T-average Loop No.1 found decreasing.
b.
Onsite Licensee Event Followup All the LER's reviewed in Paragraph 7.a above were followed up onsite.
The inspector verified that the reporting requirements of Technical Specifications, Section 6.9.1.6, guidance in Regulatory Guide 1.16 and the licensee's initial identification of reportable events as described in Administrative Procedure 8, Revision 1, had been met, that appropriate corrective action had been taken, that the event was reviewed by the Superintendent of Power and that conti1ued operation of the facility was conducted in confor-mance with the Technical Specification limits.
The inspector's findings regarding the licensee events were acceptable with the following comments:
(1) LER 78-019/0lT0 - The licensee will install the new trim package at the next shutdown of sufficient duration to complete the job package. This item remains unresolved pending installation of new trim (286/78-28-06).
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(2) LER 78-24/03L - Auxiliary Boiler Feed Pump repair is awaiting additional replacement parts.
Pending the reassembly and completion of testing of the ABF pump, this item is unresolved (286/78-28-03).
(3) LER 78-23/03LO - The level control valve internal hydraulic actuator had not been received at the time of this inspection.
Pending reassembly of valve with the ordered parts, this item is unresolved (286/78-28-04).
The inspector noted that the equipment problems that were found during the refueling surveillance period will be subject to review after the next refueling to determine if the surveillance frequency is adequate.
Based on this review a reevaluation of surveillance period will be performed.
The inspector had no further comments on his review of the LER's other than unresolved items noted above.
8.
Unresolved Items Unresolve<' 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 Paragraphs 3.b(4)a, 6.c, 7.b(1),
(2) and (3).
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 item of noncom-pliance and unresolved items.