IR 05000269/1975006
| ML19308A628 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/23/1975 |
| From: | Epps T, Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308A599 | List: |
| References | |
| 50-269-75-06, 50-269-75-6, 50-287-75-07, 50-287-75-7, NUDOCS 7911270786 | |
| Download: ML19308A628 (5) | |
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UNITED STATES d-NUCLEAR REGULATORY COMMISSION
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REGION il 230 PE ACHTREE STREET, N. W. SUITE $18
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ATLANTA, CEORGI A. 30303
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l IE Inspection-Report Nos. 50-269,'75-6, 50-270/75-7 and 50-287/75-7 Licensee:
Duke Power Cocpany i
Power Building 422 South Church Street Charlotte, North Carolina 28201
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Facility Nace : Oconee Units 1, 2 and 3 j
Docket Nos.:
50-269, 50-270 and 50-287
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License Nos. :
DPR-38, 47 and 55 Category :
C, C and 32 i
Location : Seneca, South Carolina Type of License: B&W, PWR, 2568, IN(t)
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Type of Inspection: Special, announced
Dates of Inspection: April 30 - May 2,19 75 Dates of Previous Inspection: April 22-25, 1975
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O, y Principal Inspector:
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T. N. Epps, Reactor Inspector
' Date Facilities Operations Branch Accompanying Inspectors : None
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Reviewed by :
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F. J. Long, Chief
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Date Facilities Operations Branch
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IE Rpt. Nos. 50-269/75-6, 50-270/75-7
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and 50-287/75-7-2-SU}MAPJ OF FINDINGS 1.
Enforcement Items None II.
Licensee Action on Previously Identified Enforcement Matters Not inspected.
III. New Unresolved Items None IV.
Status of Previously Reported Unresolved Items Not inspected.
V.
Other Significant Findings Oconee-2 reactor coolant flow appears to be close to the calculated core lift valve. This item will be referred to the Of fice of Reactor Regulation (Licensing).
VI.
Management Interview A managecent interview was held on May 2,1975, with Mr. J. E. Smith and members of his staff.
The fire stop inspection and the Unit 2 flow problem were discussed.
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Further discussions were held with licensee corporate managenent, on Iby 8,1975, concerning control of flacable materials and s=cking in the cable spreading roots and equipment root ~
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DETAILS I Prepared by:
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T. N. Epps, Reactor Inspector Date Facilities Operations Branch I
Dates of Inspection:
April 30 - May 2, 1975
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'Date F. J. Long, Chief -
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Facilities Operations Branch
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Individuals Contacted Duke Power Company (DPC)
J. E. Smith - Manager, Oconee Nuclear Station J. W. Hampton - Director, Administrative Services L. E. Schmid - Operating Superintendent O. S. Bradham - Maintenance Superintendent R. M. Koehler - Technical Services Superintendent T. S. Barr - Technical Services Engineer
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H. Hobs - Junior Field Engineer, Construction
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J. W. Davis - Field Engineer, Construction 2.
Fire Stops This part of the inspection involved obtaining information on fire stops used at Oconee.
The Oconee FSAR, Section 8.2.2.13.g, states that floor
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sleeves will be filled with a fire retardant material.
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8.2.2.13.h states that wherever physically possible, =etallically armored and protected cable systems will be used and that with this type construction fire stops as such are not required.
The-licensee, however, is presently installing and reworking fire stops in the followfng areas:
(a) turbine building to auxiliary building, (b) elec-trical equipment room walls, (c) electrical equipment room ceiling to cable room, (3) cable room walls, and (e) cable room ceiling to control room.
Information presented herein concerns practices and
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materials presently being used by the licensee.
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Materials The following materials are being used in fire stops at Oconee:
(1)
Flacemastic - is a fire resistant material sprayed on safety related control cables crossing-power cable trays.
This material is.coc=ercially available and tested.by a
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method that follows in principle American Standard-ASTM E-119.
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IE Rpt. No. 50-269/75-6 I-2
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i (2) Glastic - is a UL recognized flame retardant glass mat polyester laminate.
The thickness used at Oconee is
i 1/8 inch.
This material was tested according to ASTM
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D-229 Method I.
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(3) Monokote -5 - is a plaster like material used for fire proofing l
and tested and rated by Underwriters' Laboratories, Inc.
j in accordance with test method ASTM E119.
A 2-1/2 inch l
thickness provides fire proofing for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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The licensee uses a minimum of four inches in fire stop j
applications.
(4) Ar=aflex - is a rubber like material used in approximately 1
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inch thick sheets for sealing against air flow.
It retards i
burning and has been tested per ASTM D 1692 and by the licensee with a torch.
l The above materials are co==erically available and are purchased i
through a local contractor.
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Installation i
A licensee representative stated that efforts were recently
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initiated to upgrade fire stops at Oconee.
This is being conducted in two phases.
All open penetrations through walls l
that are fire barriers are to have fire stops installed.
The inspector observed several 6 inch diameter penetrations in the
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cable spreading roem ceilings that opened into the control rooms
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above that did not have fire stops installed.
The licensee stated that installation of fire stops would be completed in about three weeks.
The second phase involves reworking old fire stops and adding Monokote to a minimum thickness of 4 inches.
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Several configurations are planned for fire-stops at Oconee as
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follcws:
l (1) Where cable trays penetrate walls, either Armaflex or 1/8 inch thick Glastic for air scaling and a minimum of
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4 inches'of Monokote for fire stops will be used.
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(2) Where empty pipe sleeves in floors or walls exist 1/4 inch l
thick steel' plates will be tack welded in place to cover-i these openings.
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'IE Rpt. No. 50-269/75-6 I-3
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(3) Where pipe sleeves with cable, piping or instrument lines exist Monokote held in place by wire and steel supports will be used.
Some will have approximately 2 inch conduit installed for temporary instrumentation cables and asbestos cloth will be used as packing.
(4)
Small cable shafte between the cable spreading rooms and the control rooms will be sealed with 1/8 inch Glastic j
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i and Monokote.
i A licensee representative stated that no testing has been accomplished on fire stop assemblies, i
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Administrative Items
It appears that there is no specific requirement for repair of i
fire stops and re-inspection of reworked areas at Oconee. A
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licensee representative stated that such a requirement is being considered.
Licensee representatives stated that there is no requirement against smoking or control of fla=able materials in the cable
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spreading rooms or equipment rooms.
Concern was expressed with regard to this policy to Duke Power Company corporate
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management by telephone on May 8, 1975.
f The licensee response to IE Bulletin 75-04 and 75-04A has been received by Region II.
Licensee corporate management stated, on May 8, 1975, that an additional response to bulletin 75-04A would
i be submitted after additional review of the subject is co=pleted on June 16, 1975.
3.
Oconee 2 Reactor Coolant Flow j
The licensee reported that indications of Unit 2 reactor coolant flow, i
from a secondary system heat balance were above the core lift valve l-of 11.9% of design flow but that instrumentation problems were suspected.
On >by 4, 1975,'the licensee reported'that, after further testing of instrumentation-used in heat balance determinations, the Unit 2 ficw appeared to be 111.5% of design flow.
Further testing is being-conducted by the licensee to attempt.to verify whether or not core lift is occurring.
This matter.has been referred to the Office of Nuclear Reactor Regulation'
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(Licensing) for further review.
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