IR 05000271/1978027
| ML19282B216 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/12/1979 |
| From: | Ebneter S, Koltay P, Paulino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19282B213 | List: |
| References | |
| 50-271-78-27, NUDOCS 7903090379 | |
| Download: ML19282B216 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-271/78-27 Docket No.
50-271 License No.
OPR-28 Priority Category C
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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-December 12-14, 1978 Inspectors:
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J.f[Qn%ReactorInspector I'date signed
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t/8/79 P. S. Koltay, React W Inspector
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date signed Approved by:
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S. D. Ebneter, Chief, Engineering Support
/ date signed Section No. 2, RC&ES Branch Inspection Summary:
Inspection on December 12-14,1978 (Report No. 50-271/78-27)
Areas Inspected:
Routine, unannounced off shift inspection of the~ Vermont Yankee Nuclear Facility to ascertain whether special work controls for fire prevention /
protection during operation, modification and maintenance activities continue to be implemented in accordance with the licensee's response to IE Bulletin Nos.
75-04 and 75-04A, and Amendment No. 43, as revised and supplemented November 30, 1977. The inspection involved 32 inspect'ar-hours on site by two regionally based NRC inspectors.
Resul ts:
No items of noncompliance were identified.
Region I Form 12 7903090 3 79 (Rev. April 77)
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l DETAILS 1.
Persons Contacted Vermont Yankee Power Corporation
- Mr. William F. Conway, Plant Superintendent
- Mr. William J. Penniman, Plant Fire Protection Coordinator Mr. L. W. Anson, Training Coordinator
- Mr. R. W. Burke, Engineering Support Supervisor
- Mr. D. C. Girroir, Engineering Assistant Mr. William Wittner, Electrical Engineer Yankee Atomic Electric Company Mr. L. J. Bozek, Engineer - Quality Assurance denotes those present at the exit interview
2.
Plant Status The plant was in the ;perational mode - 100% power.
3.
Work Control Procedures a.
The inspector verified that there are work control procedures which define requirements for operations personnel approval and control of all construction, modifications and maintenance activities performed within the operating plant boundary.
Procedures examined for this determination include:
(1) Administrative Procedure (AP)-0021, Revision 6, dated May 8,1978, entitled " Maintenance Requests" (2) Administrative Procedure (AP)-6000, Revision 7, dated May 8,1978, entitled " Plant Design Change Requests" (3) Administrative Procedure (AP)-6003, Revision 7, dated September 11, 1978, entitled " Plant Alteration Requests" (4) Administrative Procedure (AP)-6004, Revision 6, dated August 1,1978, entitled " Engineering Design Change Requests"
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b.
The inspector reviewed Administrative Procedure (AP)-0042, Revision 2, dated May 8, 1978, entitled " Fire Prevention,"
verifying that the licensee has established work control procedures for activities involving welding, open flame and other ignition sources.
The procedures also take cog-nizance of nearby flammable and combustible materials.
c.
In addition to the above, Administrative Procedure (AP)-0042, also describes requirements for a fire watch when welding, grinding or burning operations are performed near flanmable and/or combustible materials.
No items of noncompliance were identified.
4.
Quality Assurance Surveillance a.
The inspector verified that the licensee has established quality assurance procedures that require periodic audit of work author-izations for modification and maintenance activities to ensure that such activities are performed in conformance with established controls.
The following governing documents were in'e'ffect at the time of
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the inspection.
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(1) Yankee Operational Quality Assurance Program Manual Y0QAP-1 A, Revision 7, dated November 2,1978 (2)
Fire Protection System Design YA-GEN-9 (3) Administrative Procedure (AP)-6010, Revision 3, dated March 8, 1977, entitled "Inplant Audits" b.
The inspector examined Quality Assurance Audit No. 78-10, dated April 3,1978, verifying that the licensee performs quality assurance surveillance of construction, modification and main-tenance activities and conformance with established controls.
No items of noncompliance were identified.
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c.
By work observation and examination of records, the inspectors verified that the licensee's quality assurance verification was performed to confirm that noncombustible materials were used in cable penetration seals.
Document examined for this determination was PDCR 78-05 which consists of the installation of the fire detection system supervision and annunciation.
No items of noncompliance were identified.
5.
Design Chance Controls a.
The inspector verified that an administrative procedure had been prepared which specifies the type of cable penetration seal to preclude the use of flammable materials in the event seal modification is necessary.
The procedure, OP-5224, Revision 1, dated October 28, 1976, entitled " Cable Penetration Sealing" and referenced in Adminis-trative Procedures AP-6000, AP-6003 and AP-6004.
b.
The inspectors reviewed a sampling of 'lant Design Changes for P
1978 verifying that flammable materials were not used.
Documents (Plant Design Change Requests - PDCR) examined include:
(1) PDCR 78-07. Installation of Foam System - Recirculating MG Sets, dated March 9, 1978 (2) PDCR 78-09, Manual Sprinkler Systems - Diesel Generator Rooms, dated March 9, 1978 (3) PDCR 78-10, Sprinkler System - Cable Penetration Area, dated March 9, 1978 (4) PDCR 78-11, Sprinkler System - Loading Bay, dated March 9, 1978 (5) PDCR 78-04, R; actor Building Standpipe System, dated August 29, 1978 6.
Emergency Procedures a.
The inspector examined the following Operations Procedure (0P)
verifying that procedures have been established for fighting fires in vital areas.
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Procedures examined include:
(1) OP-3020, Revision 7, dated November 7,1978, entitled
" Plant Fire Brigade / Fire Fighting Procedures"
~(2) OP-3107, entitled " Loss of Switchgear Room or Cable Vault." This procedure is awaiting final approval of plant management.
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b.
The inspector verified that there are procedures for accomplishing an orderly plant shutdown in case of loss of normal coolant sup-ply systems. AP-0150, Revision 9, dated November 7,1978, en-titled " Responsibilities and Authorities of Operations Department Personnel" delineates the responsibilities and authorities of members of the Operations Department during startup, normal power operation and shutdown conditions.
OP 01.~1, Revision 8, dated July 13, 1978, entitled " Shutdown ta cold Shutdown" provides detailed instructions to ensure pro-per operator response during a reactor plant shutdown from a low power standby condition.
7.
Facility Inspection
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a.
The inspector audited the most recent fire inspection report, prepared by the licensee's insurer, American Nuclear Insurer, (formerly the Nuclear Energy Liability / Property Insurance As-sociation (NELPIA)) for Property File No. N-128, dated June 21, 1978.
b.
The report includes the results of tests conducted on the diesel and electric fire pumps. The pumps were satisfactorily tested, listing the net pressure, RPM and flow.
The report contains one new recommendation (78-1) which pertains to a manual shutdown arrangement for the electric motor driven fire pump.
In addition, the report lists nine (9) previously stated recommendations dating back to 1969.
c.
On December 12 and 14,1978, the inspectors walked through the facility with a licensee representative to observe housekeeping activities and to ascertain whether activity pertaining to the inspection and operability of fire fighting equipment have been
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performed in accordance with established procedures.
The in-spectors examined the control room, cable vault, reactor building, diesel generator rooms, turbine building, battery rooms and lube oil storage facility. The items examined in these areas include but were not limited to:
fire detection and alarm system, fixed fire protection systems, portable fire protection equipment and records of the licensee's in-spection and main 6 nance of fire fighting and protection equipment.
Documents examined include: OP-4020, Revision 6, dated September 22, 1978, entitled " Surveillance of Fire Protection Equipment" and which consists of the following sections:
AP-4020.01 - Weekly Surveillance of the Diesel Fire Pump Batteries AP-4020.02 - Monthly Surveillance of Fire Pump Operational Check AP-4020.03 - Monthly Surveillance of Vital Valves in the Water Suppression System AP-4020.05 - Monthly Surveillance of Hose Stations and Communications Equipment
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AP-4020.4 - Monthly Surveillance of Portable Fire Extinguishers AP-4020.12 - Semiannual Surveillance of Smoke and Flame Detection Devices AP-4020.14 - Annual Suruillance of Hydrostatic Testing of Fire Hose
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'o items of noncompliance were identified.
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8.
Fire Drills and Training The inspectors verified that the licensee is conducting fire drills and personnel training in accordance with established procedures.
Documents examined for this determination include:
a.
Vermont Yankee Training Form VYAPF 3023.02, which lists course subjects, fire brigade members and attendance dates.
b.
Vermont Yankee Fire Drill Form VYAPF 3023.05, which identifies drills held during 1978.
The inspector noted that five (5) of the nine (9) annually required drills have been scheduled for the month of December.
As of December 12, three drills remain to be completed.
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c.
Vermont Yankee Fire Drill Critique Form VYAPF 3023.05 for fire drill conducted on May 4,1978.
No items of noncompliance were identified.
8.
Status of Previously Identified Unresolved Items (Closed) Unresolved Item (50-271/77-21-01):
Pertaining to storage of combustibles on the turbine deck under cable trays at elevation 318' - 0" and various areas of elevation 345' - 0" and 252' - 0".
The inspector examined these areas, as well as, the areas noted in the licensee's fire hazard report of October 4,1977, observing that combustibles had been removed from the areas in question. This item is resolved.
(Closed) Unresolved Item (50-271/78-22-02):
Pertaining to revision of Administrative Procedure AP-0042, to include the Off-Gas System in the Fire Protection / Prevention Program. The inspector examined Department Instruction DI-78-18, dated October 4,1978 and Section 6 of Appendix A to AP-0042, Revision 3, verifying the inclusion of the Off-Gas System in the Fire Protection / Prevention Program. This item is resolved.
(Closed) Unresolved Item (50-271/78-26-03):
Pertaining to coiled cables in cable trays. The inspector examined the cable spreading room and the cable vault noting that there were no cables coiled on top of cables in cable trays.
The inspector did observe several cables which were not terminated.
However, the wire ends were taped and tagged.
This item is resolved.
9.
Closecut of IE Circulars C..'cular 78-04, dated May 18, 1978, pertaining to sliding fire door closers.
The facility has one sliding door which isolates the HPCI room at elevation 213' - 9".
The licensee stated they had reviewed the circular and determined they do not use the doo; mechanism re-ferenced in the IE Circular.
The inspector had no further question.
10.
Implementation of Fire Prevention / Protection Procram By work observation and examination of QA records, the inspector verified licensee compliance with scheduled implementation dates for completion of the proposed Fire Prevention / Protection modifi-cations identified in Table 3.1 of Amendment 43 to the Facility License No. DPR-28.
For this determination the inspector examined the following items scheduled for completion prior to the date of inspection:
a.
SER 3.1.1 Fire Detection System Plant Design Change Request (PDCR) 78-05. The installation and testing of equipment has been completed.
Fire detector sur-veillance list is being updated to reflect the installation of additional detection devices in various plant areas.
b.
SER 3.1.2 Fire Water Supply Shutoff, isolation and sectionalizing valves on the fire water supply system are provided with tampar-proof seals and the valves are inspected monthly in accordance with Operational Procedure OP-4020.03.
c.
SER 3.1.3 Hose Stat'.ons In accordance with Plant Design Change Request (PDCR) 78-04, two risers providing water supplies to hose stations and fixed suppression systems in the Reactor Building have been installed, tested and placed in service. A copy of the hydraulic calcu-lations, which will t.e submitted to the NRC, has been given to the inspector at the,ite.
d.
SER 3.1.4 Water Suppression Systems Automatic Water Suppression Systems have been installed in ac-cordance with Plant Design Change Requests 78-8,10 and 11.
The installations provide automatic water suppression capability in the cable penetration area of the Reactor Building, the diesel fire pump enclosure, and in the Turbine Building loading bay.
Manually Activated Water Suppression Systems have been installed in accordance with Plant Design Change Request 78-9.
The in-stallations provide manually activated water suppression capa-bility in the diesel generator roo *
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e.
SER 3.1.5 Foam Suppression System Foam Suppression System has been installed as per Plant Design Change Request PDCR 78-7.
The installation provides a manually activated foam suppression system to protect the recirculation pump motor generator sets in the Reactor Building.
f.
SER 3.1.7 Portable Extinguishers Halon 1211 type portable extinguishers providing Class A fire fighting capability have been installed in the control room.
g.
SER 3.1.9 Fire Doors The replacement and installation of fire doors has been delayed until November,1978 as per letter WVY 78-86, dated September 7,1978, to the Office of Nuclear Reactor Regulation, Division of Operating Reactors.
In a subsequent telephone discussion the licensee informed the NRR of additional delays resulting in a new projected completion date of February 1979.
This item is unresolved pending NRC review (78-27-01).
h.
SER 3.1.10 Supervision of Fire Doors Supervision is keyed in with the installation of the fire doors noted above in item g.
i.
SER 3.1.12 Protection for Structures This item is incomplete. The licensee stated his objections in a letter WVY 78-85, dated September 6,1978 to the Office of Nuclear Reactor Regulation.
This item is unresolved pending NRC review (78-27-02).
j.
SER 3.1.13 Portable Ventilation Equipment Six portable ventilation units, 5000 cfm fans with 20 feet of trunk line each, have been distributed as follows:
2 units in the Turbine Building elevation 252'
2 units in the Reactor Building elevation 213'
2 units in the Reactor Building elevation 280'
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k.
SER 3.1.15 Access to Fire Areas Covers from cable trays and risers in the cable spreading room have been removed.
Original manhole covers in the switchgear room have been re-placed with covers made of lightweight material.
The installation of access door to the intake structure service water pump area has been delayed, pending receipt of fire doors.
(Ref: SER3.1.9)
This item is unresolved pending NRC review (78-27-03).
1.
SER 3.1.16 Testing Emergency Lighting Monthly tests in accordance with Operational Procedures (0P)-4021 are performed by the licensee.
m.
SER 3.1.18 Control of Combustibles (1)
Due to the delay in the installation of fire doors (Ref:
SER 3.1.9) the installation of the berm between the diesel generator rooms has been re-scheduled for February 1979 This item is unresolved pending NRC review (78-27-04).
(2) The installation of guard piping around the fuel line leading to the fire pump diesel is keyed in with the installation of a gaseous suppression system in the area, due to be completed in 1979 This item is unresolved pending NRC review (78-27-05).
(3) All other items under this SER section have been completed on schedule n.
SER 3.1.19 Hose Houses Hose houses have been modified as per the SER section 4 o.
SER 3.1.20 Protection of Essential Power Sources Operational Procedure OP-2145 has been established to satisfy this item.
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11. Unresolved Items Unresolved 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 the inspection are discussed in paragraphs 10.g, i, k, m(1),
and(2).
12.
Exit Interview The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on December 14, 1978.
He sumarized the purpose, scope, and findings of the inspection.