IR 05000271/1978029
| ML19259B691 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/05/1979 |
| From: | Baunack W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19259B681 | List: |
| References | |
| 50-271-78-29, NUDOCS 7903130549 | |
| Download: ML19259B691 (8) | |
Text
h U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
78-29 Docket No.
50-271 C
License No.
DPR-28 ppjt,.ity Category
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Licensee:
Vermont Yankee Nuclear Power Corporation 20 Turnpike Road
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Westborough, Massachusetts 01581 Vermont Yankee Jacility Name: _
Inspection at:
Vernon, Vermont Inspection conducted: De mber 12-15,1 78 Inspectors:
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W. H. Baunack, Reactor Inspector
/ dYte signed date signed date signed Approw?d by:
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'H. B. Kis4er, Chief, Nuclear Support Section
'date signed No. 2, RO&NS Branch Inspection Summary:
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Inspection on December 12-15, 1978 (Report No. 50-271/78-29)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee action on previous inspection findings; administrative controls for facility procedures; technical content of facility procedures; review of facility procedures; review of night orders and department instructions; procedure changes resulting from Technical Specification Amendments; onsite licensee event followup; and a facility tour. The inspection involved 26 inspector-hours onsite by one regional based inspector.
Results: Of the eight areas inspected, no items of noncompliance were found in seven areas; two apparent items of noncompliance were found in one area (Infrac-tion-failure to provide adequate procedures, Paragraph 8; and Deficiency-failure to make a prompt report of an occurrence, Paragraph 8).
79031305@
Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- Mr. D. Abely, Technical Assistant
- Mr. F. Burger, Technical Assistant-QA
- Mr. R. Burke, Engineering Support Supervisor
- f;r. J. Cade, Engineering Assistant
- Mr. W. Conway, Plant Superintendent
- Mr. A. Diaz, I&C Supervisor
- Mr. R. Donald, Technical Assistant-QA Mr. P. Donnelly, Technical Assistant I&C Mr. D. Girroir, Engineering Assistant Mr. M. Lyster, Shift Supervisor
- Mr. W. Murphy, Assistant Plant Superintendent Mr. D. Reid, Lead Technical Assistant
- Mr. R. Sokja, Operations Supervisor
- Mr. G. Weyman, Chemistry and H... Supervisor The inspector also interviewed other licensee employees, including members of the technical and engineering staff and reactor operations personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed)
Unresolved item (271/77-19-16). A procedure change has been made to AP-201 which requires that a check be made of cali-brated test equipment on return from decontamination to insure that the calibration sticker is attached or a replacement attached as n cessary.
(Closed)
Unresolved Item (271/77-23-02): Co:apleted Plant Altera-tion Fonms 78-11, stack gas isolation system electrical modifica-tion, and 78-09, stack gas isolation system rechanical modification were verified to have been coa.pleted July 13, 1978 and July 22, 1978. Also, OP 4390 A0G Trip System Logic Functional / Calibration procedure was reviewed to verify inclusion of a check of solenoid valve SE-107- ). ??L ?_Y_hi :
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s (Closed) Noncompl1ance(271/77-28-02): Documentation was reviewed verifying that training has been provided to appropriate personnel
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relative to their responsibilities for insuring the proper documen-
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tation of activities affecting VY's Quality Assurance Program.
j 3.
Administrative Controls for Facility Procedures
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The inspector performed an audit of the licensee's administrative i
controls by conducting a sampling review of below listed Adminis-
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trative procedures with respect to the requirements of the Tech-
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nical Specifications, Section 5, " Administrative Controls," ANSI
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N18.7, " Administrative Controls for Nuclear Power Plants," and
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Regulatory Guide 1.33, " Quality Assurance Program Requirements."
AP 000i, Plant Procedures, Revision 4, May 8,1978.
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AP 0002, Department Instructions, Revision 4, May 25,1978.
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AP 0013, Plant Record Retention, Revision 7, October 2,1978.
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AP 0154, Control Room Night Order Book, Revision 4, December
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6, 1977.
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No items of noncompliance were identified.
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4.
Technical Content of Facility Procedures
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Facility procedures were reviewed on a sampling basis using FSAR
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System Descriptions, Piping and Instrument Diagrams and Technical Specifications, where necessary, to "erify that procedures were sufficiently detailed to control the operation or evolution de-scribed within Technical Specification Requirements.
The pro-s cedures reviewed with respect to this area are marked by asterisk (.*) in the next paragraph (Paragraph 5, Review of Facility Pre-
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cedures).
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No items of noncompliance were identified.
5.
Review of Facility Procedures
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The inspector reviewed facility procedures on a sampling basis
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to verify the following:
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Procedures, and any changes, were reviewed and approved
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in accordance with the requirements of the Technical Specifications and the licensee's administrative controls.
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The overall procedure fonnat and content were in conform-ance with the requirements of ANSI N18.7-1976, "Adminis-trative Controls for Nuclear Power Plants."
Checklists, where applicable, were compatible with the
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step-wise instructions in the procedures.
Appropriate Technical Specification Limitations had been
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included in the procedures.
Temporary changes were made in conformance with Technical
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Specification requirements.
b.
The following procedures were reviewed.
(1)
Operating Procedures
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OP 3100, Reactor Scram, Revision 7, July 26,1978.
OP 0102, Power Operation (Maneuvering at Power),
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Revision 8, June 6, 1978.
(2) System Operatino Procedures OP 2110, Reactor Recirc System, Revision 7, October
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12, 1978.
OP 2121, Reactor Core Isolation Cooling System,
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Revision 9, July 26, 1978.
RP 2182, Reactor Building Closed Cooling Water
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(.RNCCW), Revision 7, June 30, 1978.
OP 2113, Main and Auxiliary Steam, Revision 5, April
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28, 1977.
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OP 2117, Standby Gas Treatment, Revision 5, May 8, 1978.
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RP 2172, Feedwater System, Revision 6, September 26,
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1977.
OP 2142, 4KV Electrical System, Revision 4, March
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4, 1977.
OP 2134, Reactor Protection System, Revision 3,
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October 12, 1978.
(3)
Alann Response Procedures
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A2 8-1, SG15 Train A Humidity Hi.
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A2 9-4, CCW Eff Rad Hi.
A4 C-2, RCIC Pump Suct Pr Hi.
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A8 2-3, Mn Stm Ln Iso Vlv Clos.
A8 4-5, Scram Pilot Hdr Pr Hi/Lo.
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A7 3-7, Drywell Press Hi.
(4)
Emergency Procedures OP 3103, Loss of Normal Power Emergency Procedure,
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Revision 5, December 6, 1977.
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OP 3117, Containment High Pressure, Revision 5, July 26, 1978.
OP 3113, Loss of Service Water Emergency Procedure,
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Revision 1, April 28, 1977.
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OP 3121, Fuel Element Failure Emergency Procedure, Revision 6, July 26,1978.
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OP 3104, Main Turbine Pressure Regulator Malfunction Emergency Procedure, Revision 1, October 4,1977.
0? 3020, cire Brigade and Fire Fighting Procedure,
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Revision 7, November 7, 197 (5) Maintenance Procedures
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OP 5203, Shock Suppressors, Revision 3, December 14, 1977.
OP 5212, Safety System Electrical Equipment, Revis-
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ion 0, September 9, 1977.
OP 5220, Limitorque Operator Inspection, Revision
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3, August 12, 1977.
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OP 5310, Repair of Safety Related Instrumentation and Components, Revision 0, August 3,1977.
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RP 5322, Recirculation Pump MG Bailey Positioner Maintenance, Revision 1, May 25,1978.
(6) Administrative Procedures In addition to those procedures identified in Detail 3 above, the following procedures were reviewed:
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AP 0020, Lifted Lead / Installed Jumper Request Pro-cedi.re, Revision 3, September 11, 1978.
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OP 3140, Alarm Response, Revision 3, April 25,1978.
c.
During the review of the above procedures, the following items were identified.
Regulatory Guide 1.33, Appendix A, lists typical safety-
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related activities which should be covered by written pro-cedures.
Among the activities listed is, Loss of Contain-ment Integrity.
No procedure covering this activity appears to have been prepared.
The licensee will review this matter.
If existing proced-ures are found not to provide adequate coverage in this area, a new procedure will be prepared to provide the necessary coverage. This item is unresolved pending com-pletion of action by the licensee as stated above (271/
78-29-01).
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Operating Procedure OP 2110, Reactor Recirculation System
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does not include the requirements of Technical Specifica-tion 3.6.J.
The licensee stated the requirements of Technical Spec-ification 3.6.J would be included in the procedure. This item will be reviewed during a future inspection (271/
78-29-02).
6.
Review of Night Orders and Departmental Instructions The inspector reviewed Night Orders and selected Departmental Instruc-tions in effect to determine compatibility with facility procedures and Technical Specification requirements.
No items of noncompliance were identified.
7.
Procedure Char ges Resulting from Technical Specification Amendments The inspector reviewed License Anendments 42 through 48, and verified that applicable procedures were revised as necessary to reflect the changes to the Technical Specifications.
No items of noncompliance were identified.
8.
Onsite Licensee Event Followup The inspector reviewed circumstances associated with the occurrence described in Licensee Event Report 78-27/3L, High Main Steam Line Flow Switches inoperable.
Discussions with personnel, review of documentation, and physical observation of the instrument rack in-volved verified c'.;e event occurred as described by the licensee.
Factors which appeared to have contributed to the cause of the occurrence are:
Inadequate control over the placement of valve identification
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tags.
No documentation was available which identified the controls provided during a valve tagging program previously conducte Valve checkoffs associated with the pr;per valve lineup for
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the High Main Steam Line Flow Switches were incomplete in that certain valves located on the instrument rack containing the flow switches were omitted from the valve checkoff lists.
The failure to provide adequate procedures is contrary to the re-quirements of Technical Specification 6.5, Plant Operating Proced-ures and is considered to be an item of noncompliance at the Infrac-tion Level (271/78-29-03).
Additionally, the review of the circumstances associated with the event indicate the report should have been submitted ir. accordance with Technical Specification 6.7.8.1, Prompt Notification with Written Followup instead of Technical Specification 6.7.8.2 Thirty Day Written Reports.
This failure to properly report the occurrence is considered to be an item of noncompliance at the Deficiency Level (271/78-29-04).
9.
Facility Tour On several occasions during the inspection, tours of the facility were conducted of the Auxiliary Building and the Reactor Building.
During the tours, the inspector discussed plant operations and ob-served housekeeping, radiation control measures, monitoring instru-mentation and controls for Technical Specification compliance.
In addition, the inspector observed control room operations on both day and evening shifts for control room manning, shift turn-overs and facility operation in accordance with Administrative and Technical Specification requirements.
10. Unresolved Items Unresolved items are matters about which me a h formation is required in order to ascertain whether they are acceptable, an item of non-compliance or a deviation. An unresolved item disclosed during the inspection is discussed in Paragraph 5.c.
11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on December 15, 1978.
The in-spector sumarized the scope and findings of the inspection. A sub-sequent discussion on the inspection findings occurred in a telephone conversation between Mr. Conway and the inspector on Decenber 19, 1978.