IR 05000029/1980012
| ML19345D107 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/16/1980 |
| From: | Foley T, Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345D102 | List: |
| References | |
| 50-029-80-12, 50-29-80-12, NUDOCS 8012090084 | |
| Download: ML19345D107 (10) | |
Text
{{#Wiki_filter:, . . U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT ] Region I Report No.
50-29/80-12 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 Pmier Statinn (Yankee Rowe) Inspection at: Rowe, Massachusetts Inspection conducted: July 14 - August 6, 1980 Inspectors: [[
- 9b /_
fN FC T. Foley, Resident Inspec;,6 date signed date signed date signed /4/f'D Approved by: T. T. Martin, Chief, Reactor Projects date signed Section No. 3, RO&NS Branch a Inspection Summary: Inspection on July 14-Auaust 6,1980 (Report Number 50-29/80-12) Areas Inspected: Routine, unannounced inspection on normal and backshif ts by the resident inspector (57 hours) of plant operations including: log and record review; tour of the facility; observation of physical security; housekeeping; radiation pro-tection controls; waste shipment activities; maintenance activities; followup of selected IE Bulletins; and, followuo of selected IE Circulars.
Results: Of the nine t reas inspected, no items of noncompliance were identified in eight areas; one apparent item of noncomp;iance was found in one area (infraction - failure to check access controlled doors physically secured, paragraph 3.b.(2)(a)). Region I Form 12 (Rev. April 77) 8012090 094
. - . DETAILS 1.
Persons Contacted D. Army, Technical Assistant
- H. Autio, Plant Superintendent T. Danek, Operations Supervisor S. Ellis, Security 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
, The inspector interviewed other licensee employees including members of the operations, maintenance, health physics and security staffs.
denotes those present at the exit interview.
- 2.
Status of Previous Inspection Items (Closed) Unresolved Item (29/80-02-04): The inspector reviewed documenta-tion from Stone and Webster describing the results of a February,1977 sur-vey of cracks in the Fuel Transfer Pit.
The survey reports concluded that the cracks appeared reasonable for the structure and nothing was observed that would prevent the structure from perfonning its intended function.
Additionally, the cracking is quite common and does not constitute an unsafe condition.
Further documentation was reviewed which indicated that the cracks were subsequently filled with an epoxy compound to prevent seepage.
This item is closed.
3.
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 July 14 to August 6,1980.
Switching and Tagging Log -- Maintenance Request Log -= Bypass of Safety Function and Jumper Control Log --
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Operating Log -- Rowe Station Log Sheets -- Rowe Station Shutdown Log Sheets -- Primary A.O. Log Sheets -- Shift Relief Checklist -- Primary Chemistry Log -- Secondary Chemistry Log -- 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 LC0 requirements Acceptar.ce criteria for the above review included: YNPS Technical 'e.,ecifications -- The Code of Federal Regulations Title 10, Part 50 -- YAEC Plant Procedures -- Inspector Judgment -- No items of noncompliance were identified.
b.
Plant Tour Inspection tours of selected plant areas were conducted at various times during the inspection, including backshifts.
These areas were inspected with respect to housekeeping and cleanliness, physical
security, fire protection, radiation controls,and general operations l compliance with plant procedures and Technical Specifications.
The I inspector toured the following areas: Control Room -- . ( Frimary Auxiliary Building --
Vapor Container -- ! l ! ! I ' .
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Switchgear Room -- Diesel Generator Rooms -- Radwaste Building -- Turbine Building -- Safety Injection Pump Room -- New Fuel Vahlt -- 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 were determined to be knowledgeable of the -- reasons for all lighted annunciators Fire fighting equipment was observed to be checked by plant per- -- sonnel and to have an operable appearance Radiation areas within the controlled area were independently moni- -- tored to be within regulatory requirements ! Shift turnovers of control room operators and shift supervisors -- were observed on regular and backshifts to be acceptable ' 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 -- - .. -.- . ... ,, -,. - _ _ - - -
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YNPS AP-0222, Job Orders -- YNPS Radiation Protection Manual -- YNPS AP-0400, Physical Security Organization -- YNPS DP-0437, Radiological and Portal Monitoring -- YNPS DP-0448, Vital Area / Access Control Area / Protected Area -- Patrol Coverage Inspector Judgment -- The inspector also walked down accessible portions of the Chemical Shutdown System to verify system operability. The inspector also witnessed activities related to the packaging and preparation of
radwaste for shipment.
With the exception of the items noted below, no inadequacies were identified.
(1) Radiation Protection Controls Radiation protection control areas were inspected.
Radiation ' Work Permits in use were reviewed and compliance with those documents were observed during plant tours. Proper posting of radiation and high radiation areas was reviewed in addition to verifying requirements for wearing appropriate personnel monitoring devices.
The inspector noted that in one area of the Primary Auxiliary Building the controlled area boundary for a contamination area was positioned such that entrance into the contamination area could be gained without knowledge of being in a controlled area.
Health Physics technicians subsequently repositioned the area boundary.
The inspector had no further coment on this area at the present tim. . ,
THIS PAGE, CONTAINING 10 CFR 2.790 INFORMATION, NOT FOR PUBLIC DISCLOSURE, IS INTENTIONALLY LEFT BLAN._ -... _ -. . _. - _- - . ..
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' 4.
Maintenance The inspector observed and/or reviewed station maintenance activities of safety-related systems and components to ascertain that these activities were conducted in accordance with approved procedures, industry codes, regulatory guides and technical specifications.
The following items were considered during this review: limiting conditions for operation were met while the component was -- removed from service; i.ic activity was accomp"shed using approved procedures and was in- -- spected, as applicable; functional testing and/or calibrations were performed prior to re- -- turning the components to service; quality control records were maintained; -- activities were accomplished by qualified personnel; -- radiological controls were implemented; -- housekeeping controls were implemented; -- fire prevention controls were implemented.
-- The following maintenance activities were observed and/or reviewed: repair of Chemical Shutdown Valve CS-540 -- overhaul of No.1 Circulating Water Pump ' -- overhaul of No.1 Service Water Pump -- overhaul of the Low Pressure Service Air Compressor -- installation of High Density Spent Fuel Racks -- Following completion of maintenance on CS-540, the inspector reviewed the results of the hydrostatic test and the operational functional test and then verified that the chemical shutdown system had been returned to ser-vice.
No inadequacies were identifie _.
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5.
Review of Radioactive Material Shipment (80-39) . The inspector reviewed activities concerning the shipment of six ooxes of Low Specific Activity (LSA) waste to the Barnwell, South Carolina burial site.
Those activities included inspection of the vehicle, radiation surveys, and completion of the administrative and quality control require-ments prior to shipment.
No inadequacies were identified.
6.
IE Bulletin Followup For the IE Bulletins listed below, the inspector verified that the written response was within.the time period stated in the bulletin, that the response included adequate corrective action commitments based on information presented in the bulletin and the licensee's response, that management forwarded copies of the bulletin to appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written response.
The following IE Bulletins were reviewed: IEB 80-15 Possible Loss of Emergency Notification System (ENS) With -- Loss of Offsite Power During the inspection period, the inspector took part in a test of the onsite communications systems.
OP 2000.82, Functional Test of Security / Communications System Standby Power Supplies, Revision Original, was performed with satisfactory results.
The inspector verified operable communication systems in the onsite resident office. Communications were established with NRC Headquarters in Bethesda, Maryland on the ENS network, and with other NRC resident site offices on the Health Physics network, while on the emergency power supply.
IEB 80-06 Engineering Safety Feature (ESF) Reset Controls -- The inspector witnessed portions of the installation and portions of the functional testing of a Containment Isolation modification performed during the January 1980 outage.
This modification was installed to i preclude automatic loss of containnent isolation as a result of reset-ting containment isolation signals.
At the time of inspection, all circuit modifications had not been complete.
Subsequently, the inspector reviewed the results of test procedure OP-4610, Revision 6, Calibration and Containment Isolation System Operability Test.
This test verifies that emergency core cooling equipment remains in the emergency mode upon removal of the actuating signal and that the manual resetting of the various isolating or actuation signals does not autanatically cause loss of containment isolation.
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The licensee response to the bulletin states that circuit modifica-tions will be complete prior to startup.
This matter will be verified by the inspector during a subsequent inspection.
(29/80-12-03) 7.
IE Circular Followup For the IE Circulars listed below, the inspector verified the circular was received by the licensee management, that a review for applicability was performed, and that if the circular was applicable to the facility, appro-priate corrective actions were taken or were scheduled to be taken.
The following circulars were reviewed: IEC 79-02 Failure of 120 Volt Vital AC Power Supplies -- IEC 79-04 Loose Locking Nut on Limitorque Valve Operators -- IEC 79-05 Moisture Leakage in Stranded Wire Conductors -- IEC 79-08 Attempted Extortion - Lcw Enriched Uranium -- -- IEC 79-09 Occurrence of Split or Punctured Regulator Diaphragms In Certain Self Contained Breathing Apparatus -- IEC 79-10 Pipefittings Manufactured From Unacceptable Material IEC 79-12 Potential Diesel Generator Turbocharger Problem -- IEC 79-13 Replacement of Diesel Fire Pump Starting Contactors -- IEC 79-15 Bursting of High Pressure Hose and Malfunction of Relief -- Valve and "0"-Ring in Self Contained Breathing Apparatus -- IEC 79-17 Contact Problem in SB-12 Switches on General Electric Metalclad Circuit Breakers IEC 79-18 Proper Installation of Target Rock Safety-Relief Valves -- IEC 79-20 Failure of GTE Sylvania Relay, Type PM Bulletin 7305 -- Catalog SU12-ll-AC with a 120 VAC Coil IEC 79-21 Prevention of Unplanned Releases of Radioactivity -- -- IEC 79-22 Stroke Times For Power Operated Relief Valves IEC 79-23 Motor Starters And Contactors Failed to Operate -- - - - . .. . .
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IEC 79-25 Shock Arrestor Strut Assembly Interference -- No items of noncompliance were identified.
8.
Location of Electrical Load Centers The inspector received a letter dated July 24, 1980, from the Director, Division of Reactor Operations Inspection, IE to the Director of Region I, requesting a survey be performed to determine whether certain load centers or circuit breakers exist within the containment structure. The inspector toured the Vapor Container and found no load centers or circuit breakers within the containment.
The inspector reaffirmed this observation through discussions with the plant staff and no inadequacies were identified.
9.
Exit Interview At periodic intervals during the course of the inspection, meetings were held with senior facility management to discuss the inspection scope and findings.
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