IR 05000321/1982010
| ML20053B375 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/25/1982 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053B360 | List: |
| References | |
| 50-321-82-10, 50-366-82-10, NUDOCS 8205280347 | |
| Download: ML20053B375 (8) | |
Text
8
%,
UNITED STATES
%
NUCLEAR REGULATORY COMMISSION
$
E REGION 11
o 101 MARIETTA ST., N.W., SulTE 3100 ATLANTA, GEORGIA 30303 o
.....
Report Nos. 50-321/82-10, 50-366/82-10 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302 Facility Name: Hatch Units 1 and 2 Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at Hatch site near Baxley, Georgia d' 28 '
Inspector:_
I
W. H. Miller, Jr.
Date Signed Approved by
_
_ 3 2.4~- I f
,
T. E. Conlon, Section Chief Date Signed Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on March 10-12, 1982
+
Areas Inspected This routine, Jnannounced inspection involved 22 inspector-hours on site in the area of fire protection.
Results Of the area inspected, one violation was identified (failure to follow fire protection implementation procedure - Paragraph 5.d). No deviations were found.
8205280SR'l
..
..
-
.
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. V. Green, Assistant Plant Manager
- C. T. Jones, Assistant Plant Manager
- S. B. Tipps, Superintendent Regulatory Compliance
- D. A. McCusker, QC Supervisor
- C. E. Belflower, QA Site Supervisor
- J. M. Bray, Senior QA Field Representative
- H. L. Sumner, Engineering Supervisor
- B. Brown, Senior Regulatory Specialist D. Smith, HP Supervisor
- M. Seymore, Associate Engineer
- C. L. Moore, Fire Protection Specialist Other Organizations T. D. Neesmith, Superintendent, Tompkin & Beckwith, Inc.
NRC Resident Inspector
- R. Rogers
- P. Holmes - Ray
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 12, 1982, with those persons indicated in paragraph 1 above.
3'.
Licensee Action on Previous Inspection Findings a.
(Closed) Deviation Item (321/80-02-01 and 366/80-02-01) - Inadequate Fire Protection QA Program:
The licensee has revised existing
,
l procedures to include fire protection systems in the plant QA/QC program. This item is closed.
'
b.
(Closed) Deviation Item (321/80-02-02 and 366/80-02) - Substandard i
Automatic Sprinkler Systems: The sprinker systems have been modified
!
to meet the provisions of National Fire Protection Association (NFPA)
!
Standard 13, Sprinkler Systems, where feasible. This item is closed.
l
i
-_...
_
_ _ _ _
-.
- - -
.
-
.
- i
.-
-
.
.
-
.
<
'
c.
(0 pen) Deviation Item (321/80-02-07 and 366/80-02-07) - Incorrect Type i
Fire Detector for Control Room Kitchen: A document charge request (DCR
'
80-16) has been prepared and approved by the PRB to change the descrip-I tion of the kitchen detection system from smoke detection to rata of rise type detection.
This change is scheduled to be incorporated in j
the next document change to the licensee's report, Evaluation of the Hatch Nuclear Plant Fire Frotection Program. This item will remain i
open until this revision has been completed.
d.
(Closed) Deviation Item (321/80-02-13 and 366/80-02-13) - Licensee's Reevaluation and Review of Fire Protection Administrative Procedures:
The plant procedures have been revised to meet the NRC guidelines.
Refer to below paragraph 5.a for details. This item is closed.
e.
(0 pen) Unresolved Item 321/80-36-03 and 366/80-36-03) - Nonautomatic
Fire Suppression Systems for Charcoal Filter Units in Safety-Related Areas:
A design is in process to change the water supply for the standby gas treatment filter sprinkler systems from the service water system to the fire protection water system at which time the systems are proposed to be restored to automatic operation. This item remains open.
f.
(0 pen) Unresolved Item (321/80-36-06 and 366/80-36-06) - Inadequate Fire Doors in Safety-Related Areas: The licensee stated that all fire doors had been inspected by QC and a discrepancy list developed, design
and maintenance requests issued, and work was in process to correct the
deficiencies. This work is scheduled to be completed by the end of the current refueling outage for Unit 2 (late May 1982). This item remains
)
open.
l 4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 5.a. and 6.c.
5.
Administrative Procedures r
The inspector reviewed the following licensee's fire protection l
procedures:
PROCEDURE NO.
TITLE HNP-205 Fire Protection Program (Rev. 9)
HNP-440 Fire Reports (Rev. 2)
HNP-500 Smoking and Eating Rules (Rev. 4)
i I
_ - -...
.,, -
a
_ _. _, _.
__
__
..
..
-
.
.
HNP-555 Control of Ignition Sources (Rev. 4)
HNP-556 Plant Housekeeping (Rev. 6)
HNP-559 Control of Transient Combustibles (Rev. 3)
HNP-1-3653 Standby Gas Treatment System Operability HNP-2-3653 Standby Gas Treatment System Operability HNP-4200 General Fire Procedure (Rev. 8)
HNP-4212 Emergency Diesel - Generator Building Fire (Rev. 3)
HNP-1-4226 Elevation 164' HVAC Room Fire (Rev. 0)
HNP-2-4217 Recirculation System M-G Set Room Fire (Rev. 1)
These procedures, in general, adhere to the NRC guidelines of the document entitled " Nuclear Plant Fire Protection Functional Responsi-bilities, Administrative Controls and Quality Assurance" dated June 14, 1977, except the identification and qualification of the position responsible for the formulation and implementation of the licensee's fire protection program were not available at the plant for review.
The qualifications for this position are included in Attachment 1 Paragraph 2.a of the above NRC guidelines. This item is identified as Unresolved Item (321/82-10-01 and 366/82-10-01), Qualifications of Position Responsible for Formulation and Implementation of the Fire Protection Program, and will be reviewed during a subsequent NRC i
inspection.
b.
Fire Brigade (1) Organization The plant fire brigade for each shift is composed of four plant a
equipment operators with the Unit 2 shift foreman serving as the i
brigade leader. A secondary brigade composed of employees from j
various other departments is also provided.
.
(2) Training and Drills
!
The inspector reviewed the training records for three shift
'
foremen and five brigade members (plant equipment operators) and found that each of these had received initial fire brigade training, quarterly fire brigade training for each quarter during 1981, an annual practice session, respirator training, and quarterly drills for 1981. Also, the shift foremen had received advance leadership training.
i The licensee provided annual training in radiation protection and fire fighting operations within nuclear power plants for the following local offsite fire departments: Lyons and Vidalia Fire Departments on December 17, 1981, and Baxley Fire Department on December 29, 1981.
l
..
_
_ -
_
.
. - - -
-
_ _ -
-
-.
-_ _
_
.
--
..
.
-
.
.
.
.
,
,
(3) Fire Brigade Equipment A sufficient quantity of turnout gear (coats, boots, helmets, gloves, etc.) was provided to equip 36 fire brigade members. This
.
equipment was stored in an outside equipment storage building, an exterior storage cabinet, and in storage cabinets adjacent to the control rcom. Additional fire brigade equipment (hose, handlight, smoke ejectors, portable foam equipment and self-contained breating apparatus) was also stored at these locations. This equipment appears to be properly maintained and in satisfactory condition.
The fire brigade was assigned 20 self-contained breathing apparatus with 45 additional units available from the HP Section.
A total of 62 spare cylinders were also available. The cylinders can be refilled by means of an air compressor. The emergency breathing air supply meets the commitments to the NRC, d.
Plant Tour A tour of the plant was made by the inspector.
The following fire protection systems were inspected and found in service:
three fire pumps, carbon dioxide system for diesel generator building, and automatic spinkler systems for the cable spreading room, service water intake structure, HPCI rooms, RPS cableways and reactor building HVAC equipment rooms. Also, hydrant equipment houses 3, 6 and 13 were inspected and the required equipment was provided and properly stored.
In Unit 1 Reactor building HVAC equipment room at elevation 164' the inspector noted an accumulation of combustible material consisting of new filters, contamination filter, cardboard boxes, charcoal material, compressed gas cylinders, maintenance materials, and general trash and
!
debris.
This material appeared to have been stored in this area for
several months. The licensee's procedure HNP-559, Control of Transient i
Combustibles, Section F. requires the senior regulatory specialist at
!
Hatch to determine if the storage of combustibles or proposed storage of combustibles in safety related areas is acceptable, what additional
'
fire protection features may be required, and post a storage permit in the storage area. The storage in this HVAC equipment room had not been evaluated.
This violates the licensee's fire protection procedures required by Technical Specification Section 6.8.1.f. and is identified as Violation Item (321/82-10-02), Failure to Follow Fire Protection Implementation Procedures.
While touring the Unit 1 portion of the plant the inspector noted three welding operations which had an incorrect welding or " hot work" permit.
Procedure HNP-555, Control of Ignition Sources, Section E.4 states that
>
during periods of normal plant operation the " hot work permit" shall be
, - _ _- -.
..
.- -. -..
- -
--
-
..
.
-
.
valid for one working shift.
However, one permit in the reactor building was issued on February 2,1982 for the duration of the job; anotner was issued on March 9, 1982 to expire on March 20, 1982, and a permit was issued February 8, 1981 for a job on the 130 foot elevation of the control building for the duration of the job. These items are violations of Technical Specification Section 6.8.1.f. and are another example of the above violation item (321/82-10-02).
Except as noted above, no additionas violations or deviations were identi-fied.
6.
Fire Protection Modification / Commitments a.
Fire Protection Safety Evaluation Report (FPSER)
The NRC FPSER dated October 4,1978 and the licensee's evaluation of the Hatch Plant Fire Protection Program dated October 1976 with Amendments 1 through 8 (EFPP), describe a number of fire protection modifications required at the facility.
NRC Reports 321/80-02 and 366/80-02 indicated the status of these items. The following open items from this report were reviewed during this inspection.
The numbers correspond to the modification items listed in paragraph 5.a of NRC Report 80-02:
NUMBER ITEM / LOCATION STATUS (1)
Automatic Sprinkler System Closed Cable Spreading Room (13)
River Intake Structure Closed (17)
Between HPIC & RHR Pump Area Closed (Unit 1)
_
(19)
Containment Area /Beneath Pumps
- Closed (26)
RPS Vertical Cableways Closed (28)
Control Building 130' Corridor Closed (40)
Reactor Building HVAC Room-Unit 1 Closed (42)
Reactor Building HVAC Room-Unit 2 Closed
- NOTE: The sprinkler system for the area beneath the Unit 2 recircu-lation pumps in the drywell is not to be installed. For details, refer to licensee's letter dated December 29, 1980 from W. A. Widner, Georgia Power, to the NRC (NRR).
i
._
...
.
.
b.
Fire Detection System The licensee is currently reevaluating the design and installation of the plant fire detection system. Portions of the existing installation are to be modified to meet the provisions of National Fire Protection Association (NFPA) Standard 72E, Automatic Fire Detectors. This item, which has been identified by the licensee in Special Report PM-82-164 of February 26, 1982, will be reviewed during a subsequent NRC inspection, c.
Fire Barriers The wall separating the Unit 2 HPCI pump room from the reactor building is of reinforced concrete construction; but according to construction records and EFPP Figure 23 Revision 2, this wall apparently does not have a 3-hour fire resistant rating. EFPP Section III.C.5.1 (page 21)
states that this wall will be made into a 3-hour fire wall.
FPSER Table 1 Item III.25A lists this as a required modification.
However, this item was previously reviewed during an NRC (NRR) site visit on March 21, 1978 and according to Trip Report of March 29,1978 from Cecil Thomas, NRR/ LWR 1, the lack of a 3-hour fire separation between the Unit 2 RHR and HPCI pumps was to be further evaluated.
The licensee. reported that no further comments had been received from the NRC on this item. Therefore, pending resolution of this problem, this item is identified as Unresolved Item (366/82-10-03), Requirements for Fire Barrier Between HPCI and RHR Pump Rooms.
d.
Emergency Lighting To meet the provision of 10 CFR 50 Appendix R Paragraph III.J, 8-hour
'
emergency lighting units have been installed by the licensee in all areas required for operation of safe shutdown equipment and in access and egress routes to these areas. The inspector reviewed maintenance work packages MR Nos. 1-81-7239 and 2-81-4009 which verified that all of these units had been installed and tested.
The final functional
'
tests on these units were completed on December 2, 1981 for Unit I and November 16, 1981 for Unit 2.
A tour was made of the plant and installation of the following units were verified:
i BUILDING LOCATION COLUMN Unit 1 Control Building 130' Stairs TH-T12 Unit 1 Control Building 164' Corridor TA-T12 Unit 1 Reactor Building 130' Elevation RL-R9 Unit 1 Reactor Building 158' Elevation RB-RIO Unit 2 Reactor Building 130' Elevation RA-R15 i
.. -
-
._.
- - -
- - - -
-. - - -
.
.
...
..
-
.
Unit 2 Reactor Building 130' Elevation RL-R19 Unit 2 Reactor Building 130' Elevation RB-R24 Unit 2 East Cableway 130' Elevation TA-T13 Diesel Generator Building Air Corridor 1-A/B Within the areas inspected no additional violations or deviations other than those identified above were noted.
.
-
-