IR 05000271/1979021
| ML19290E188 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/02/1980 |
| From: | Martin T, Raymond W, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19290E180 | List: |
| References | |
| 50-271-79-21, NUDOCS 8003050029 | |
| Download: ML19290E188 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-271/79-21 Docket No.
50-271 License No. DPR-28 Priority
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Category C
Licensee: Vermont Yankee Nuclear Power Corporation 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name:
Vermont Yankee Nuclear Power Station Inspection at:
Vernon, Vermont Inspection conducted:
November 28-30, 1979 Inspectors:
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2/ 79 W. J. Raymond[/ React /r Inspector d&te signed h WS W E J.7/9W7$
T./. Std a, Reactor IMspector date signed F
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da e si ned Approved by:
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7-h T. Q 1 art y Chief, Reactgf Projects Section date signed No. 3, ROANS Branch Inspection Summary:
Inspection on November 28-30, 1979 (Report No. 50-271/79-21)
Areas Inspected:
Routine, unannounced inspection of plant operations, including facility records and inspection tours of accessible plant areas; licensee action on previous inspection items; followup on IE Bulletin and Circulars; licensee review of Temporary Procedure Changes; Licensee Event Reports and Monthly Operating Reports; and, licensee action on Small Break LOCA procedures.
The inspection involved 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> on site by two regional based inspectors.
Results:
No items of noncompliance were identified in the six areas inspected.
Region I Form 12 (Rev. April 77)
8 0 0 3 0 5 (d 2-.%
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DETAILS 1.
Persons Contacted a.
Licensee Personnel Mr. E. Bowles, Operator Training Supervisor Mr. R. Branch, Assistant Operations Supervisor Mr. R. Burke, Engineering Support Supervisor
- Mr. W. Conway, Plant Superintendent Mr. P. Donnelly, I&C Supervisor Mr. H. Fitzroy, Shift Supervisor
- Mr. D. Girroir, Technical Assistant Mr. S. Jefferson, Reactor Engineering and Computer Supervisor Mr. W. Murphy, Assistant Plant Superintendent Mr. J. Pelletier, Maintenance Supervisor Mr. R. Sojka, Operations Supervisor b.
Yankee Atomic Electric Co:npany (YAllC1
- Mr. L. Heider, Vice President
- Mr. D. Moody, Manager of Ope.'ations c.
General Electric Company Mr. D. Pullen, Resident Engineer
- present at the exit interview on November 30, 1979.
2.
Licensee Action on Previous Inspection Items (0 pen) Unresolved Item (271/79-17-03):
The licensee has added a weekly check requirement to the I&C technicians work list to assure that the torus level transmitter reference legs remain filled.
The licensee has not yet completed an investigation into a design change that would automatically keep these reference legs filled.
(Closed) Noncompliance (271/79-12-01):
The importance of procedure adherence has been stressed to operations personnel by entry in the Night Orders and by stressing this item in the licensed operators' re-training progra.
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(Closed) Unresolved Item (271/79-04-03):
The licensee revised procedure 5305, Solenoid Valve Maintenance, with DI79-29 to list each HCU valve and thus provide for tracking of the installation of the BUNA-N components.
Procedure 5305 is a part of the outage surveillance schedule that is reviewed pr'or to each outage.
3.
Review of Plant Operations a.
Shift Logs and Operating Records The inspector reviewed the records listed below for compliance with the licensee's administrative procedure for Operations Department Logs.
(1) Night Orders for the period November 1-27, 1979.
(2) Shift Supervisor's Log for the period October 31, 1979 to November 28, 1979.
(3) Control Room Operator Log for the period October 31, 1979 to November 28, 1979.
(4)
Process Computer Data Sheets for November 28-29, 1979.
Inspection consisted of verifying adequate licensee management review, correct identification of problem areas, completeness and determination that conditions contrary to the Technicial Specifica-tions do not exist.
No unacceptable conditions were identified.
b.
Tour of Accessible Areas Inspection tours of various plant areas were conducted periodically during the period November 28-30, 1979 to observe plant / system status and operations in progress.
The areas toured included the Reactor Building (including all Corner Rooms), Turbine Building, Diesel Generator Rooms, Radwaste Facility, Cable Spreading Room, Switchgear Room, Intake Structure and Site Security Perimeter.
(1) Monitoring Instrumentation - The following instrumentation was observed tn verify that indicatad parameters were in accordance with Technical Specification Limiting Conditions for Operations:
Reactor Vessel Level and Pressure;
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Reactor Power Level;
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Control Rod Positions;
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Equipment Operating Status;
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Area Radiation and Stack Gas Monitoring; Jet Pump Flow;
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Suppression Chamber Water Temperature and Volume;
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Process Computer Core Operating Parameters; Standby Liquid Control Tank Temperature;
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Suppression Chambers to Drywell Differential Pressure; and, Main Steam Flow.
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(2) Annunciator Alarms - The inspector observed various alarm conditions received and acknowledged by the control room operator on duty.
The alarmed conditions were discussed with the operator who was knowledgeable of the reasons for the alarm conditions and the required alarm response actions.
Continuous alarms were identified and the reasons for them were known to operating personnel.
(3) Shift Staffing - The inspector verified at various times during the inspection that control room shift staffing met Section 6 of the Technical Specifications with regard to number of personnel and types of licenses.
The inspector observed a shift turnover on November 29, 1979 to verify that continuity of system status information was maintained.
(4) Radiation Areas - Radiation control zones were observed to verify proper identification and implementation of health physics controls.
These observations included review of step-off pad conditions, radiation area posting and disposal of anti-contamination clothing.
Specific controls established over the CRD lay-down area in the Reactor Building were discussed with licensee personnel.
No adverse conditions were identifie (5) Plant Housekeeping Conditions - Storage of material and com-ponents were observed with respect to safety and fire hazards.
Replacement of anchor bolts to meet the requirements of IEB 79-02 was in progress and many areas were in need of cleanup.
No conditions that would create a fire hazard were identified.
Progress on housekeeping and plant cleanup will be reviewed on subsequent inspections.
(6) Fluid Leaks - No process system fluid leaks were noted.
(7) Piping Vibrations - No excessive piping vibrations were observed.
(8) Pipe Hangers / Seismic Restraints - Several pipe hangers and snubbers on safety related systems were observed to verify proper conditions.
The status of work in progress to upgrade suppression chamber support columns (gusset installation)
was observed and discussed with licensee personnel.
Findings were acceptable.
(9) Valve Postion/ Equipment Start Positions - The positions of valves in the Core Spray, Standby Liquid Control, HPCI, RCIC, Diesel Generator, Fuel Oil and CRD (scram discharge volume) systems were observed to verify correct positioning and implementation of administrative controls.
No discre-pancies were observed.
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Fire Protection - Fire extinguishers and fire fighting equipment were observed to be unobstructed and recently inspected for operability.
No evidence of smoking in designated
"No Smoking" areas was observed.
The cardox fire suppression systems was observed to be operable.
4.
IE Bulletin and Circular Review a.
IEB 79-03 The licensee conducted a search of construction records, purchase orders (P0's), material purchase requests (MPR's) and Job Order files to verify that no welded pipe has been used or planned to be used at Vermont Yankee.
This search was documented in a new response letter to the NRC dated November 26, 197 b.
IEB 79-12 The licensee issued instructions to operations personnel and revised applicable procedures to preclude the occurrence of short periods during reactor startup.
OP 0100, Reactor Startup to Criticality, was revised (Rev.10) to provide:
precautions against the use of notch override during the final steps on an approach to critical; precautions to maintain reactor period greater than 30 seconds, along with instructions on required operator action should reactor period become less than 30 seconds; instructions to test the Emergency-In function on the first control rod withdrawn in group one; a requirement to use the two highest reading source range monitors on fast speed during an approach to critical. Additionally, Department Instruction (DI)
79-14 dated August 23, 1979 revised the rod withdrawal sequence of OP 2404 to minimize high notch worths during reactor startup.
The inspector verified that the rod withdrawal sequence (Form 7-A-1, Rev.1) used fur Cycle 7 startup incorporated guidelines in accordance with DI 79-14.
The inspector had no further comments regarding licensee actions taken for IEB 79-12.
5.
Review of Procedure Temporary Changes During review of licensee actions taken for IEB 79-14, the inspector noted that DI 79-14 dated August 23, 1979 had not been reviewed by the Plant Operations Review Committee (PORC) nor approved by the Plant Superintendent as of November 29, 1979.
Further review of dis issued by the Reactor Engineering Group revealed two others that had not received review / approval:
DI 79-19 dated October 29,1979 and DI 79-20 dated October 31, 1979.
The inspector stated that, although plant Technical Specifications and Administrative Procedures establish no time limit for performing the review / approval functions following the issuance of a temporary change, timely reviews by the PORC are important to ensure proper implementation of administrative controls.
The licensee noted the inspector's comments and stated that the subject dis would be reviewed, and further that instructions would be issued to the Reactor Engineering Group to reemphasize the need to provide expeditious processing of temporary procedure changes.
This item is unresolved pending completion of the licensee action described above and further review on a subsequent inspection (50-271/79-21-01).
6.
NRC In Office Review a.
NRC:RI in office review of LERs 79-27 and 79-28 has been completed and no inadequacies were identified.
b.
NRC:RI in office review of the Monthly Operating Report for the month of October, 1979 has been completed with no unacceptable conditions identified.
7.
Implementation of NUREG 0578 Items The inspector met with licensee personnel responsible for implementing the short term recommendation of NUREG 0578 to discuss, specifically, the status of changes being made to small break LOCA (SBL) procedures.
Draft copies of OP 3116, Loss of Reactor Coolant, and OP 3124, Loss of Reactor Coolant Outside of Primary Containment, were reviewed to verify that the procedures incorporate guidelines developed by the GE BWR Owners Group, as accepted by NRC:NRR.
The inspector identified no discrepancies between the GE SBL guidelines and the draft procedures.
The inspector also reviewed a list of short term action items along with their respective completion dates as documented in a licensee letter to NRC:NRR dated October 18, 1979.
The licensee stated that work in progress is on schedule and, except for items possibly subject to delays in material delivery, all action items should be completed by the January 1, 1980 deadline.
The inspector had no further questions on the NUREG 0578 items at the present.
This area will be futher reviewed on subsequent inspections.
8.
Unresolved Items Unresolved items are those items for which further information is required to determine whether the items are acceptable or items of noncompliance.
An Unresolved item is discussed in paragraph 5 of this report.
9.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on November 30, 1979.
The inspection purpose, scope and findings were discussed as they are presented in this report.
The inspector stated that, as of November 30, 1979, Mr. William J. Raymond has assumed the duties of Principal Inspector for Vermont Yankee replacing Mr. Thomas F. Stetka.