IR 05000309/1981004
| ML19346A065 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/03/1981 |
| From: | Ebneter S, Koltay P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19346A064 | List: |
| References | |
| 50-309-81-04, 50-309-81-4, NUDOCS 8106040502 | |
| Download: ML19346A065 (7) | |
Text
.
.
O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-309/81-U4 Docket No.
50-309 License No.
OPR-36 Priority Category C
Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road
__
Westborough Massachusetts Facility Name:
Maine Yankee Atomic Power Station Inspection At:
Wiscasset and Augusta, Maine Inspection Conducted:
February 23-27, 1981
.
, n Inspectors:
rWM M~
//.d/cF/
Peter Koltay, Reactor' Inspector dite date date-Approved by:
'Y S f/
'
l S. D. Ebneter/ Chief
/ date l
Plant Systifms Section, DETI i
l Inspection Summary:
Inspection on February 23-27, 1981 (Report No. 50-309/81-04)
Areas Inspected:
Routine unannounced inspection of the plant's Fire Protection /
Prevention Program including:
implementation of administrative procedures; fire l
brigade training; observation of ignition source and combustible material control;
!
review and observation of fire protection systems modifications; review of
!
surveillance test records associated with fire protection systems; and, review of actions taken on previous inspecti m findings. The inspection involved 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> on site by one NRC regional Msed inspector.
l Results:
No items of 7 wmpliance were identified.
Items of deviation from NRC guidelines and licensee commitment were identified in two areas.
(Paragraphs
!
l 4 and 6a).
Region I Form 12 l
(Rev. April 1977)
8106 0 40f0;2.
_-
--
.
..
.
-
_
.
I REPORT DETAILS 1.
Persons Cantacted
- P. Anderson, Administrative Department Head
- J. Brinkler, Assistant Plant Manager
- R. Forest, Fire Loss Prevention Coordinator C. Frizzle, Manager of Nuclear Support
- E. Wood, Plant Manager
- Denotes those present at the exit interview.
2.
Action on Previous Inspection Finding (Closed) Unresolved Item (309/79-08-01).
The plant fire brigade failed to meet the objectives of fire drills conducted on June 13, 1979, by delayed response and by failing to demonstrate proficiency in the use and operation of fire protection equipment. The inspector reviewed critiques of fire drills conducted during 1980 and found that fire brigade response was reduced to approximately five minutes, and fire brigade members demonstrated their ability to handle the necessary fire protection equipment.
-
.
3.
Fire Protection / Prevention Program a.
Administrative Procedures The inspector reviewed the following administrative procedures:
YAEC Safety Manual, dated 9/14/77,
--
Section 4, Material Storage; Section 5, Hazardous Materials; Section 2, Housekeeping; Section 8, Welding, Cutting, Brazing; Section 10, Fire Prevention and Control;
--
Fire Protection Plan, Procedure 2.60.7 Welding and Cutting Safety Procedure, revision 1, 7/16/79; The inspector verified that the licensee has developed administrative
,
procedures which include:
(1) Control of combustibles:
(a) Special authorization for the use of combustible, flammable or explosive hazardous material in safety related areas.
(b) Prohibition., the storage of combustible, flammable or explosive hazardous material in safety related areas.
t
.
.-
-
- -
--
.
.
(c) Requirement for the removal of all wastes, debris, rags, oil spills or other combustible materials resulting from the work activity following completion of the activity or at the end of each work shift, whichever is sooner.
(d) Requirement for periodic inspection for accumulation of combustibles.
(2) Welding and cutting operations and other open flame ignition sources are controlled by work permit and are properly safe-guarded in areas containing safety-related equipment and components.
.
(3) Smoking in safety related areas is prohibited except where
" smoking permitted" areas have been specifically designated by plant management.
(4) Housekeeping is properly maintained in areas containing safety-related equipment and components.
(5) Work authorization, is provided for review and approval of modification, construction and maintenance activities which could adversely affect the safety of the facility.
(6) Fire reporting instructions for general plant personnel.
(7) Periodic audits.
(8)
Fire protection / prevention program included in the licensee's QA Program.
No item of noncompliance was identified.
b.
Quality Assurance Audits The inspector reviewed the following quality assurance audits of the fire protection program:
--
Quality Assurance Audit - Fire Protection, 8/13-15/1979;
--
Quality Assurance Audit No. 80-10, 9/25/80; No item of noncompliance was identified.
c.
Fire Brigade Training The inspector reviewed the following procedures:
,
Procedure No. 2.60.6, Fire Training, revision 2, 11/6/80; Procedure No. 2.60.8, Fire Fighting Plan For Oil Storage Room, revision on 4/10/80;
.
.
-
Procedure No. 2.60.9, Fire Fighting Plan for Cable Vault, revision 0, 4/10/80; Procedure No. 2.60.10 Fire Fighting Plan for Control Room, revision 0, 4/10/80; The inspector verified that the licensee has established a fire brigade training program in accordance with guidelines outlined in the NRC document, Nuclear Plant Fire Protection Functional Responsibilities, Attachment 2.
Adequate facilities are provided for conducting fire fighting practice sessions on site for fire brigade members.
No item of noncompliance was identified.
4.
Maintenance, Inspection and Tests The inspector reviewed the following procedures:
--
Procedure No. 2.60.2, Fire Equipment Inspection, revision 1, May 20, 1980,
--
Procedure No. 3.1.9, Fire Pump Testing, and the attached valve position check list, revision 9.
The inspector verified that the licensee conducts a monthly inspection of the plant's fire protection systems and fire brigade equipment. Maintenance and test requirements of the fire protection systems are specified.
During the verification of fire protection valve positions the inspector noted that the indicators of several post indicator type underground valves in the fire main are missing, thus valve position cannot be identified without actual valve cycling.
Cycling the valves is not part of the monthly inspection procedure.
The inspector also identified that post indicator type divisional valves on the underground yard main are not locked in the open position. The valves involved are FS-II, FS-12, FS-42, FS-45, FS-38, FS-39, FS-36 and FS-33.
The NRC guidelines on valve supervision in Appendix A of the Branch Technical Position 9.5-1 of the Standard Review Plan states in part:
"When electrical supervision of fire protection valves in not practicable, an adequate management supervisor program should be provided.
Such a program should include locking valves open with strict key control; tamper proof seals; and periodic visual check of all valves..."
,
Appendix A of the Fire Protection Safety Evaluation Report issued with Amendmenc No. 37 to License No. DPR-36 states in part: "The licensee will lock fire water system valves, that are not electrically supervised, in their normal operating position."
The licensee's failure to satisfy the above guidelines is considered to be a deviation from the licensee's commitment in Amendment No. 37 to License No. DPR-36.
(309/81-04-01)
-
.
5.
Review of Surveillance Test Records Associated with Technical Specification Requirement The inspector selected and reviewed the following records to verify that the associated required Fire Protection Program surveillances had been performed and that the acceptance criteria had been met.
--
Procedure 3.60.1, Carbon Dioxide System Testing, April 1, 1980; Procedure 3.60.2, Fire Main System Testing, May 20, 1980;
--
Procedure 3.60.3, Smoke Detector Testing, April 25, 1980;
--
Procedure 3.60.4, Fire Barrier Penetration Seals, May 20, 1980;
--
--
Procedure 3.60.5, Fire Pump Capacity Test, May 20, 1980; Procedure 3.60.6, Sprinkler System Testing, October 22, 1979;
--
No item of noncompliance was identified.
6.
Fire Protection Modifications Required by Amendment 37 to DPR-36 By review and examination of records, including specifications, drawings, and associated quality assurance documents, and by examination of installed fire protection equipment throughout the plant, the inspector verified the licensee's implementation of scheduled modifications identified in Amendment 37 to License No. OPR-36.
For this determination the inspector examined the items listed in Amendment 37 Section 3, paragraphs 3.1.1 through 3.1.18.
The inspector reviewed the following quality assurance document and verified that the licensee established a quality assurance program applicable to fire protection, in accordance with NRC guidelines outlined in Fire Protection Functional Repsonsibilities, Attachment No. 6.
YA - Gen. - 9 Fire Protection Systems Design, 4/13/78; The inspector verified that for all fire protection related modifications, the design and installation of equipment is in accordance with the codes and standards of the National Fire Protection Association. Also, all fire protection equipment is Underwriters Laboratories listed and/or Factory Mutual approved.
a.
Item 3.1.8 - Fire Dampers lhe inspector reviewed Safety Evaluation Report item No. 3.1.8, Fire Da?pers, and Plant Design Change Request - PDCR 5-78.
The inspector noted that four fire dampers, FAD-1, FAD-2, FAD-3 and FAD-4 have not been installed in accordance with the manufacturer's recommendations.
The licensee stated that new fire damper blades are on order, however, the completion of the installation will not meet the completion date of 1980 refueling outage, stated in the Safety Evaluation Report.
.
..
.
.
Safety Evaluation Report item No. 3.1.12e, PDCR 6-79 Battery Room Air Flow Supervision due to be installed by 1978 refueling outage has only been partially completed. Due to improper equipment, the loss of air flow in the lower battery room cannot be detected.
Amendment No. 37 states in part:
"This amendment authorizes certain of the modifications, upon specified implementation schedules;..."
The licensee's failure to satisfy implementation dates for modifications constitutes a deviation from commitments. (309/81-04-02)
During the review of PDCR 5-78, Fire Dampers, the inspector noted that the manufacturer of the dampers performed the following on-site fixes to assure proper damper closure:
- installed a clip to improve spring stop;
- installed a snap-in strip to prevent damper blades from jamming; The fire dampers were tested and listed by underwriters laboratories without the above alterations. The inspector could not determine the effect of the alterations on the U.L. listing. The item is considered unresolved pending NRC review of documentation upholding the validity of the U.L. listing.
(309-81-04-03)
b.
Item 3.1.1 Fire Detection Systems The inspector reviewed PDCR 6-79 and verified that the licensee installed fire detection devices in all areas identified in the SER.
Power supply to the system is obtained from a vital bus.
Technical Specification surveillance procedure hs: been updated to reflect the new installations.
c.
Item 3.1.2 Hose Stations The inspector verified that the licensee extended. hose protection to all areas outlined in the SER.
The inspector noted that based on the fire pump's capacity, pressure at standpipe outlets at low elevations may exceed the 100 psi limit set by the National Fire Protection Association code No 14, Standpipe and Hose Systems. The inspector
~
could not verify the installation of pressure limiting devices. This item is considered unresolved pending NRC review of the licensee's evaluation and corrective action.
(309/81-04-04)
d.
Item 3.1.4 Water Suppression System The inspector reviewed PDCR 11-79 and PDCR 9-79 and verified that the licensee installed water suppression systems in the following areas:
Protected cable vault - manually activated,
--
Comp;nent cooling water pumps area - automatic sprinklers,
--
Radioactive control area - automatic sorinklers,
--
_
_
-
_
_
_
_ _ _
_
~
A
&
Isophase bus duct penetration area - automatic sprinklers,
--
Containment spray pump cubicles preaction sprinklers,
--
Diesel generator rooms - aqueous film forming foam sprinklers,
--
Siydroaen seal oil unit - aqueous film forming foam sprinklers.
--
The inspector noted that the calculated water demand for the diesel generator rooms is 90 gpm at 145 psi at the valve header.
The inspector could not verify that the fire pumps rated at 3,000 gpm at 110 psi can satisfy the required pressure demand for effective tuppression capability. This item is considered unresolved pending nRC review of the licensee's evaluation and corrective action where necessary.
(309/80-04-05)
e.
Item 3.1.5 Gas Suppression Systems The inspector reviewed PDCR 7-79 and verified that the licensee installed on automatic halon suppression system to protect the control room cable chase.
The inspector verified that the licensee installed a manually activated carbon dioxide system to protect the turbine generator bearings area; and the carbon dioxide suppression system in the protected cable tray room has been modified to provide automati: actuation.
f.
Item 3.1.12 Control of Combustibles The inspector verified the installation of oil retention curbs around the turbine lube oil storage tank, generator seal oil unit, and diesel generator day tanks.
g.
Item 3.1.14 Charcoal Filters The inspector verified the installation of heat detectors in the charcoal filter housings, which alarm in the control room.
7.
Unresolved Items Unresolved items are matters about which more information is required to ascertain,hether they are acceptable items, items of noncompliance, or
<
deviations.
Unresolved items disclosed during the inspection are discussed in paragraphs Aa, 6c and 6d.
8.
Exit Interview The inspector met with the licensee representatives denoted in Details (paragraph 1) at the site on February 27, 1981, and summarized the purpose and scope of the inspection findings.