IR 05000414/1985050
| ML20137E175 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/14/1985 |
| From: | Conlon T, Miller W, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20137E151 | List: |
| References | |
| 50-414-85-50, NUDOCS 8511270213 | |
| Download: ML20137E175 (10) | |
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- UNITED STATES u
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NUCLEAR REGULATORY COMMISSION
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- REGION 11 101 MARIETTA STREET, N.W.
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Report No.:
50-414/85-50 Licensee:
Duke-Power Company 422 South Church Street Charlotte, NC 28242 Docket No.:
50-414 License No.:
CPPR-117 Facility Name:
Catawba 2 Inspection Conduc ed:
ctob 21 - 25, 1985 Inspectors:[
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W. H. Mfller, Jr. W Date Signed J/-/9-Rf
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G. R. Wiseman~
Date Signbd Approved by:
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/ / " / Y-M T. E. Conlon, Section Chief Date Signed Plant Systems Section, Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, announced inspection entailed 70 inspector-hours on site in the area of fire protection.
Results:
No riolations or deviations were identified.
0511270213 851118
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- N. B. Barron, Superintendent of Operations C. Biggers, QA Technician
- H..D. Brandes, Design Engineering L
S. R. Christopher, Design Engineering
- T. R. Gill, Construction Technical Support
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- D. James, QA Technician
- P. G. LeRoy, Compliance J. Norris, Construction QA Inspector
- 0. B. O'Brien, Construction Technical Support
- T. Robertson, Construction Technical Support J. M. Rucci, Design Engineering
- F. P. Schiffley, II, Licensing Engineering A. Wellmaker, Mechanical Technical Support Other licensee employees contacted included construction craftsmen,
-engineers, technicians, operators, mechanics, and office personnel.
Other Organization
- W. M. Crute, Project Engineer /Bahnson
- G. A. Gatson, QC Engineer /Bahnson
- B. Williams, QC Engineer /Bahnson NRC Resident Inspectors
- P. VanDoorn
- P. Skinner
- Attended exit interview 2.
Exit Interview
.The inspection scope and findings were summarized on October 25, 1985, with those persons indicated in paragraph above.
The inspector described the
. areas inspected and discussed in detail the inspection findings.
No
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dissenting comments were received from the licensee, a.
Inspector Followup Item (414/85-50-01), Review of Completed Fire Protection and Detection System Inspections and Functional Tests -
paragraph 5.a.(2), 5.b, 5.c, 5.d, and 5.e.
b.
Inspector Followup Item (414/85-50-02), Review of Unit 2 Valve Position Verification / Surveillance Program for CO Systems paragraph 5.a.2.
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c.
Inspector Followup Item (414/85-50-03), Lock or Seal Control Valves to the Water Flow Alarms for the Automatic Sprinkler Systems in Open Position paragraph 5.b.
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-d.
Inspector Followup Item (414/85-50-04), Failure to. Provide Fire Proofing Material to Structural Steel Supporting the Fire Rated Cable i
Raceway Enclosures - paragraph 5.h.
e.
Inspector Followup Item (414/85-50-05), Completion of Alternative /
Dedicated. Shutdown Capability - paragraph 5.1.
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Inspector Followup Item (414/85-50-06), Procedures Required for Functional Test of Hydrogen Gas Excess Flow Valve paragraph 5.k.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Permanent Plant Fire Protecticn Program The inspector reviewed the following permanent plant fire protection features. The -licensee's Catawba Nuclear Station Fire Protection Review of July 1983 and the NRC's Fire Protection Safety Evaluation Reports were used to determine the fire protection commitments and requirements,
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a.
Carbon-Dioxide Systems The inspector reviewed the carbon dioxide (C0 ) system installations
for the Unit 2 diesel generator rooms and auxiliary feedwater pump (AFWP) pits and enclosures.
(1) Piping Installation and Configuration Inspection QC Procedure FP-7, Unit 2 Auxiliary Feedwater Pumps CO System
Date of Drawing No.
Rev. No.
QC Inspection CN-2492-RF001
6/27/85 CN-2492-RF002
6/27/85 CN-2492-RF008
6/27/85 CNM-1206-08-0081-001 DK 6/27/85 CNM-1206-08-0093-002 DK 6/27/85
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- i These inspections verified that the installed system' piping, i
valves, and nozzles conformed to the design drawings.
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(2) Field Applied Coatings Inspection, Unit 2 Diesel Generator Building, FP-17 Drawing No.
Date of QC Inspection
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CN-2506-04.85-00 1/3/85 CN-2506-04.85-02 2/7/85 These inspections were to verify proper installation of the protective coatings for the underground portion of the CO2 system piping to the diesel generator building. Based on the inspector's walkdown, the CO systems appeared to be installed in accordance
with the requirements of the manufacturer or construction drawings.
The installation of the AFWP and diesel generator CO systems is
complete and QC inspections are complete, but the final turnover and functional testing has not been accomplished.
Test Procedure
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Nos. TP/2/A/1400/05B (dated 5/17/85) and TP/2/A/1400/05C (dated 4/19/85) for the CO Fire Protection System D/G Building and
Auxiliary Feedwater Pumps Functional Tests, respectively, were reviewed and they appear adequate. However, until these tests are completed by the licensee this is identified as Inspector Followup Item (414/85-50-01), Review of Completed Fire Protection and Detection System Inspections and Functional Tests.
The tests results will be reviewed during a future NRC inspection.
In addition, a control valve position verification surveillance program has not been developed for the Unit 2 CO2 systems. This is identified as Inspector Followup Item (414/85-50-02), Review of Unit 2 Valve Position Verification / Surveillance Program for CO 2 systems and will be reviewed during a subsequent NRC inspection, b.
Automatic Sprinkler System A review and inspection was made of the automatic sprinkler systems provided for the following areas:
Sprinkler System Design Location Drawing Nos.
Pipe Corridor (Tunnel Area)
CNM 2206.09-0036-001 Reactor Building Annulus CN-2491-RF017 561' Elevation CN-2491-RF031 thru CN-2491-RF037 Auxiliary Feedwater Pump Room CNM2206.09-0001-001
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These systems appeared to meet the installation requirements of the
' f construction drawings and the applicable code, National Fire Protection
. Association (NFPA) 13, Automatic Sprinkler Systems, except the control
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valve to' the water flow alarm device for the ' system in the auxiliary feedwater pump room is not designed to be sealed or locked in the open position.
NFPA-13, Section 3-17.4 requires these valves to be so constructed and installed that they may be locked or sealed in the open position. The control valve to the water flow alarm device for the cable room corridor sprinkler system was the 'same type valve, and was found. to be in the closed position during this inspection.
The inspector suggested that the licensee replace or modify these control valves and keep these valves locked or sealed in the open position.
This is identified as Inspector Followup Item (414/85-50-03), Lock or Seal Control Valves to the Water Flow Alarms for the Automatic Sprinkler Systems in Open Position, and will be reviewed during a I
subsequent NRC inspection.
A review was made of the following construction test and QC inspection documents:
Date of Date of Final QC System Hydrostatic Tests Configuration Inspection
. Pipe Corridor 5-10-85 Not Complete Reactor Building 5-10-85 6-10-85 Annulus - 561'
Elevation Auxiliary Feed-3-22-85 6-27-85 water Pump Room The above tests and inspection records were satisfactory. However, the functional tests on the electrical components of the sprinkler had not been completed.
This is identified as another example of Inspector Followup Item (414/85-50-01). Except as noted above, the installation of the sprinkler systems appear to meet the NFPA design and instal-lation requirements and the NRC guidelines. A QC inspection program is provided to verify that the installed systems meet the construction drawings, c.
Fire Detection System (EFA)
The October 11, 1985, QC inspector record drawings CN-1762-01.02 Revision 24 and CN-1762-01.03 Revision 28 were reviewed.
This QC inspection required verification of (1) the location of the detector
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unit base to the design drawings; (2) detector. type, setting and position; and (3) presence of UL/FM label on detector unit and included detection Zones 68 (motor control center),19 (Auxiliary Feedwater Pump areas), 25 and 26 (charging pump rooms).
The inspector conducted a
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- wal k. down inspection of zones 19, 25 and 26 and verified that the detector installations conformed to the construction drawings.
The QC inspection did not include calibration of the detector head sensitivity nor' a functional test. The licensee is evaluating this apparent discrepancy.
Review of -this item will be performed during a future NRC inspectton and is another example of Inspector Followup Item (414/85-50-01).
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d.
Fire Barrier Penetration Seals The inspector reviewed the following fire barrier penetration seals:
Date of Final Penetration No.
Location Type QA/QC Inspection JAX-518-W6 Train A Switchgear M
6/24/85 HVAC Room JAX-534-F10 Train B Disconnect E
4/3/85-F9 Cubicle E
4/3/85 JAX-534-F3 Train A Disconnect E
4/3/85-F4-Switchgear Room E
4/3/85 JAX-535-W1 Train A Switchgear E
4/18/85 Room to renetra-tion Room-CAX-260-F28 Turbine Driven AFWP M
9/7/85-F27 Room M
9/7/85 These penetrations were inspected and appeared to conform to the design requirements.
The inspector observed a penetration seal foaming
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operation and licensee inspection for a Auxiliary Building electrical-penetration.
The licensee's QC inspection of the seal revealed that several large void areas were left in the penetration seal fire stop due to the formation of inadequate foam cell structure. The defective foam material was removed and the seal repaired in accordance with Specification CNS-1390.01-00-0098, Specification for Installation and Repairing of Cable Penetration Firestops.
Review of the final QA/QC inspection documentation for this cable penetration firestop will be reviewed during a future NRC inspection.
This is another example of Inspector Followup Item (414/85-50-01).
e.
Fire Doors The installed fire doors were not reviewed during this inspection. The licensee stated that the installation of the doors was practically complete with final adjustments being made to the doors. The final QC inspection of the doors is scheduled to be completed prior to L
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December 1, 1985. These doors will be reviewed during a subsequent NRC-inspection.
This is another example of Inspector Followup. Item
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414/85-50-01).
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Fire Dampers-The design and construction documents were reviewed and an inspection was made of the following fire dampers 'to verify that these dampers were installed to meet the manufacturer's requirements:
Date of Final System Opening Size Manufacturer QC" Inspection 2VF-FD-11 38" x 48" Pacific Air
- 1-23-84 2VF-FD-2A&B 30" x 70" Pacific Air
- 11-14-83 2CRA-FD-19 30" x 36" Ruskin 6-18-81
- 2-12-84 2CRA-FD-20 30" x 36" Ruskin 6-24-81
- 2-12-84 2VA-FD-114 36" x 54"
3-28-83
- 4-19-84 2VA-FD-115.
36" x 54"
3-24-83
- 4-19-84 2VA-FD-151 10" x 6"
~12-17-82
- 4-17-84 2VA-FD-6 36" x 48" Pacific Air 9-22-83
- 11-1-83
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2CRA-FD-21 24" x 18" Ruskin 7-7-81
- 2-11-84 2CRA-FD-22A&B 47" x 91" Ruskin 9-10-82
- 2-12-84 1CRA-FD-24A&B 39" x'88" Ruskin 3-13-82, 3-14-82
- 2-13-84
' NOTES:
Damper inspected and functionally tested.
- Damper only~ functionally tested.
These dampers were not inspected by the NRC inspector.
Ventilation system was operating and licensee would not issue a system shutdown order. /
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The installation of the ' dampers inspected appear to meet the manu-facturer's and construction documents requirements.
However, the required clearance between the damper sleeves / duct material and wall opening could not be verified. This item was reportedly inspected and verified during the licensee's QC inspection program.
g.
Fire Barrier Walls, Fireproofing of Seismic iteel Using Gypsum Wall Board
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The inspector reviewed the following fire barrier assemblies which utilize gypsum wall board for fireproofing of structural ste'el:
.y Elevation Location Date of QC Inspection
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543'
Oolumn AA-CC and 61-62 3/28/85
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560'
Column CC-DD and 62 3/26/85
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These QA/QC inspections ' were to verify proper installation of the gypsum wall board fireproofing to the structural steel.
The above
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inspections wer.e satisfactory.
Based upon the, inspectors walkthrough and review, thase fireproofing applications appear tc meet the s
installation requirements of the construction drawings CN-1202-)
through 3 and the licensee's previously analyzed and tested fire
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barrier configurations.
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One Hour Fire Rated Raceway Fire Barriers The one-hour fire rated raceway liire ' carriers provided to meet the separation and fire. protection requirements for the redundant cables in
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the auxiliary feedkater pump room were reviewed.
The raceway fire j-barriers were inspected by 'the licensee's QC organization on September 7,1985 for civil items /and September 20, 1985 for electrica)
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items.
However, during a review of the QC inspection records the inspector noted that the raceway fire barriers were apparently installed and QC " inspections performed _using uncontrolled design drawings. The inspector made a'walkdown inspection and it appears that the installation meets the final controlled construction drawings, however, this item has been identified by the licensee as Nonconforming Item Report No. 19972. The licensee has initiated the necessary action to prevent future occurrence.
The inspector verified that the following cables were enclosed within-the one-hour barrier:
Cable Nos.
Cable Nos.
2CA 875 2*CA'763 2*CA 743 2*CA 770 2*CA 760 2*NV 631 2*CA 761 2*WL 561 2*CA 762 2*WL 790 2*CA 762
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The structural steel supports for the raceway fire barrier enclosure
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are not fireproofed with a one-hour fire-resistive material.
This is
.-identical to Unresolved Item (413/85-15-01) for Unit 1.
For Unit 2 this.is identified as Inspector Followup Item (414/85-50-04), Failure to Provide Fire Proofing Material To Structural Steel Supporting the Fire Rated Cable Raceway Enclosures. A deviation request has been sent to NRC/NRR by the licensee to justify this discrepancy.
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Standby Shutdown System
..The licensee has not completed the procedures for Unit 2 shutdown using
"the standby shutdown system, the associated circuit analysis, and the y.
damage or repair procedures required to bring the plant to cold N
shutdown in the event of fire in certain plant areas.
These are scheduled to be completed by early December 1985, at which time a detailed NRC followup inspection will be made.
This is identified as
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Inspector Followup Item (414/85-50-05), Completion of Alternative /
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Dedicated Shutdown Capability.
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Reactor Coolant Pump 011 Collection System
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An oil collection system has been provided for the lubricating system for each reactor coolant pump motor to meet the provisions of
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Program.
The collection systems for the Catawba Unit 2 RCPs are arranged to catch any leakage from the following sources: upper oil coolers; upper
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oil pot fill and drain valve; upper oil pot, pot level indicator reservoir and site glass; oil lift pumps; lower oil pot, pot level
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indicator reservoir and site glass; and, lower pot fill and drain valves. :The collection system for each pump is arranged to drain into an independent drain tank of 385 gallons capacity which is of suf ficient size to hold the entire lubrication system capacity 'of 265 gall'ons from each pump.
A walkdown inspection of the collection systems indicated that the systems appear to. meet the design and
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construction requirement and requirements of the Standard Review Plan.
A flame arrestor was not provided for the tank vents due to the high
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The following QC inspection documentation was reviewed:
Type Inspection Date of QC Inspection
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L Piping configuration-4-24-85
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. Tank installation 7-16-85
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- The licensee is revising Procedure OP/A/6100/01, Unit Startup
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' Procedure, to require the oil collection tanks to be drained and/or y
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l verified to be empty prior' to each unit startup.
This procedure
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revision will be verified during a subsequent NRC inspection.
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Hydrogen Piping System
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A review:was made of the hydrogen gas piping system to the drain tank n'
>for.the reactor coolant pumps. This piping extends from two cylinders in the bulk gas storage building located outside the plant structures through underground piping in the yard and exposed piping in the
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auxiliary and reactor buildings to the drain tank.
An excess flow l
valve has been installed in the distribution piping at the cylinders to limit the maximum hydrogen concentration in the event of a line break to less than 2% in the effected area. The inspector. verified that the eicess flow valve (Dragon Model 15600-15SW) was installed.
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~ The licensee stated that the excess flow valve was to be functionally tested prior to licensing and annually thereafter to verify valve's operability. These procedures had not yet been issued and will be reviewed during a subsequent NRC inspection. This is identified as Inspector Followup Item. (414/85-50-06), Procedures Required for 4.,
Functional Test of Hydrogen Gas Excess Flow Valve.
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