IR 05000029/1980014
| ML19343B581 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/26/1980 |
| From: | Foley T, Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19343B576 | List: |
| References | |
| 50-029-80-14, 50-29-80-14, NUDOCS 8012240277 | |
| Download: ML19343B581 (8) | |
Text
{{#Wiki_filter:' ' . . U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-29/80-14 Docket No. 50-29 License No. DPR-3 Priority Category C -- Licensee: Yankee Atomic Electric Company 25 Research Drive ! Westborough, Massachusetts 01581 Facility Name: Yankee Nuclear Power Station (Yankee Rowe) Inspection at: Rowe, Massachusetts Inspection conducted: August 8-September 15, 1980 Inspectors: [[ Z //N 8C T. Foley, Resident Ingcto-date signed . date signed date signed Approved by: f/X//t T. T. Martin, Chief, Reactor Projects date signed Section No. 3, RO&NS Branch Inspection Summary: l Inspection on August 8-September 15, 1980 (Report No. 50-29/80-14) l Areas Inspected: Routine unannounced inspection of plant operations including: log and record review; tour of the facility; observation of physical security; ! radiation protection controls; housekeeping; fire protection; surveillance testing; maintenance activities and followup of selected IE Bulletins and Circulars.
The inspection involved 32 inspector hours onsite by the resident inspector.
' Results: One item of noncompliance was identified in one area (Infraction - failure to maintain a high radiation area barricaded, paragraph 2. b. (1) ). t i ! Region I Form 12 (Rev. April 77) g012240 277 .
v . . , . DETAILS 1.
Persons Contacted D. Army, Technical Assistant
- H. Autio, Plant Superintendent T. Danek, Operations Supervisor
- L. French, Engineering Assistant F. Hicks, Training Coordinator K. Jurentkuff, Day Shift Supervisor L. Laffond, Assistant Training Coordinator P. Laird, Maintenance Supervisor N. St. Laurent, Assistant Plant Superintendent R. Randall, Engineering Assistant
- J. Staub, Technical Assistant to Plant Superintendent J. Trejo, Plant Health Physicist D. Vassar, Assistant Operations Supervisor
- denotes those present during the exit interview.
2.
Review of Plant Operations a.
Shift Logs and Operating Records The inspector reviewed, on a sampling basis, the following logs and records, for the period August 8 - September 15, 1980: Switching and Tagging Log -- Maintenance Request Log -- Bypass of Safety Function and Jumper Control Log -- Operating Log -- -- Rowe Station Log Sheets -- Rowe Station Shutdown Log Sheets Primary A. O. Log Sheets -- Shift Relief Checklist -- The logs and records were reviewed to verify the following items: Log book entries are sufficiently detailed -- Log book reviews are being conducted by the staff -- Instructions in the Special Order Book did not conflict with -- Technical Specification reporting and LCO requirements
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Acceptance criteria for the above review included: YNPS Technical Specification -- The Code of Federal Regulations, Title 10, Part 50 -- YAEC Plant Procedures -- Inspector Judgement -- No items of noncompliance were identified.
b.
Plait Tour Inspection tours of selected plant areas were conducted at various times, including backshifts, during the inspection.
The areas were inspected with respect to housekeeping and cleanliness, physical security, fire protection, radiation controls, and general operations compliance with plant procedures and Technical Specifications.
The inspector toured the following areas: Control Room -- Primary Auxiliary Building -- Vapor Container -- -- Switch Gear Rooms -- Diesel Generator Rooms Radwaste Building -- Turbine Building -- -- Safety Injection Pump Room New Fuel Vault -- The following observations / determinations were made: Control Room manning was observed to be in compliance with -- regulatory requirements Selected valve position / equipment start positions were observed -- to be in the required position applicable to plant status Control Room Operators determined to be knowledgeable of the -- reasons for all lighted annunciators
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Control Room instrumentation was observed, including radiation -- monitoring, Vapor Container temperature and pressure, Reactor Coolant System temperature and pressure, Nuclear Instrumentation and Emergency Safeguard Features levels and pressures Fire fighting equipment was observed to be checked by plant -- personnel and to have an operable appearance Radiation areas within the controlled area were independently -- monitored to be within regulatory requirements Plant housekeeping conditions / cleanliness was noted -- Shift turnover of control room operators and shift supervisors -- were observed on regular and backshifts Physical security was observed to verify implementation in -- accordance with the Plant Security Plan and Procedures Acceptance criteria for the above items included the following: YNPS Technical Specifications -- -- The Code of Federal Regulations, Title 10, Part 50 The Code of Federal Regulations, Title 10, Part 20 -- -- YNPS AP-0216, Plant Housekeeping Program YNPS AP-0018, Bypass of Safety Function and Jumper Control -- -- YNPS AP-0017, Switching and Tagging of Plant Equipment YNPS AP-0222, Job Orders -- YNPS AP-0400, Physical Security Organization -- YNPS DP-0437, Radiological and Portal Monitoring -- YNPS DP-0475, Vital and Access Control Area Entry Controls -- YNPS Radiation Protection Manual -- Inspector Judgement -- With the exception of the items noted below, no inadequacies were identified.
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(1) During a backshift tour of the Primary Auxiliary Building, the inspector observed the Shutdown Cooling Heat Exchanger Room, a designated high radiation area, without a barricade.
Actual radiation intensity in the area of valve CHV-644 was 400 mrem /hr one foot away from the valve and 3000 mrem /hr on contact with the valve.
The licensee's representatives have subsequently taken permanent corrective action by installing swinging gates at each entrance to high radiation areas throughout the plant.
No further action in regard to this item is required.
This is an item of noncompliance designated as an infraction (50-29/80-14-01).
(2) Dcring the inspection, the licensee reported to the inspector that while transferring radioactive resin from the ion exchangers to a resin cask, a leak occurred which released approximately _ three gallons of radioactive liquid, and one quart of radioactive resin beads, resulting in the release of approximately fifty five (55) millicuries of radioactivity to the surrounding area.
The entire spill was confined within a previously established "potentially contaminated area" approximately 15 x 20 feet and inside the protected area.
The licensee subsequently cleaned up the spill and in the process of decontaminating the area, approximately one hundred cubic feet of contaminated soil and asphalt were removed and packaged as radioctive waste.
The inspector questioned licensee representatives as to whether a Licensee Event Report (LER) would be submitted to the NRC or the NRC Operations Center notified.
The licensee's representa-tives indicated they interpret the reporting requirements i I concerning " Controlled Radioactive Release", as stated in 10 CFR 50.72(a)(8), to mean releases to the environment, an area ! outside the protected area.
The inspector was informed that the licensee did not plan to notify the NRC Operations Center or submii an LER.
10 CFR 50.72(a), " Notification of Significant Events," Item (8) requires that licensees notify the NRC of any accidental, unplanned, o-uncontrolled radioactive release.
The inspector restated his position that the NRC should be notified of such matters, since the spill occurred outside (not within a building) and in an uncontrolled manner.
This item remains unresolved pending NRC review (50-29/80-14-02).
l ' c.
Surveillance l l l The inspector observed surveillance testing of the Station Power and l Diesel Generator Systems, and the Control and Service Air Systems, ' to verify that testing was performed in accordance with technically l . -.
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adequate procedures, that results were in conformance with Technical Specifications and procedure requirements, and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during testing were properly reviewed and resolved by management personnel.
d.
Maintenance Activities (1) The inspector observed licensee personnel involved in maintenance activities on valves TV-209 and TV-408, which failed a Type "C" leak rate test, and replacement of number one Steam Generator water box vent valve, which was leaking by the seat.
This observation was performed to verify that the activities were performed in accordance with the licensee's procedures and technical specififications.
The following determinations were made: -- appropriate QC hold points were included radiological controls were established -- activity was accomplished in accordance with approved pro- -- . cedures administrative approvals were obtained prior to commencing -- work The inspector toured the associated work area and reviewed the following documents: YNPS AP-0214, Maintenance and Change of Safety Classified -- Systems, Components or Structures ' YNPS AP-0205, Maintenance Request -- No inadequacies were identified.
e.
IE Bulletin Followup l l For the IE Bulletins listed below, the inspector verified that the written response was within the time period stated in the bulletin, that the written response included adequate corrective action commitments based on information presented in the bulletin and in the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's response was accurate, and that corrective action taken by the licensee was as described in the written response.
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, IEB 78-02, Terminal Block Qualification -- . IEB 78-05, Malfunction of Circuit Breaker Auxiliary Contact -- Mechanism - General Model CR 105X IEB 78-06, Defective Cutler-Hammer, Type M relays with DC Coils -- IEB 78-10, Bergen-Paterson Hydraulic Shock Suppressor Accumulator -- Spring Coils The inspector identified no inadequacies.
f.
IE Circular Followup For the IE Circulars listed below, the inspector verified that the circulars were received by the licensee management, that a review for applicability was performed, and that if the circulars were applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC 78-02, Proper Lubricating Oil for Terry Turbines -- IEC 78-03, Packaging Greater Than Type A Quantities of Low -- Specific Activities Radioactivity Material for Transportation f IEC 78-04, Installation Errors That Could Prevent Closing of -- Fire Doors IEC 78-06, Potential Common Mode Flooding of ECCS Equipment -- Rooms at BWR Facilities IEC 78-07, Damaged Components on a Bergen-Paterson Series 25000 -- Hydraulic Test Stand IEC 78-08, Environmental Qualification of Safety-Related Electrical -- Equipment of Nuclear Power Plants IEC 78-09, Arcing of General Electric Company NEMA Size 2 ' -- Contactors l -- IEC 78-17, Inadequate Guard Training / Qualification and Falsified l Training Records The inspector identified no inadequacies.
3.
Unresolved Items Unresolved items are matters about which more information is required in , ' order to determine whether they are acceptable items or items of noncompli-ance.
An unresolved item identified during this inspection is discussed in Paragraph 2.b.(2).
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4.
Exit Interview At periodic intervals during the course of the inspection, meetings were held with senior facility management denoted in Paragraph 1 to discuss the inspection scope and findings.
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