IR 05000269/1975012
| ML19322B844 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/24/1975 |
| From: | Epps T, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19322B839 | List: |
| References | |
| 50-269-75-12, 50-287-75-14, NUDOCS 7912050820 | |
| Download: ML19322B844 (6) | |
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UMITCD STATEt
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NUCLEAR REGUi.ATORY COMMISSION f
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230 PEACHTREC STRCET N. W, SUITE s ts
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ATI.ANTA.GCOhCIA 30333
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IE Inspection Report Nos. 50-269/75-12, 50-270/75-13 and 50-287/75-14
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Licensce: Duke Power Company Power Building 422 South Church Street Charlotte, North Carolina 28201 Facility Name:
Oconee Units 1, 2 and 3 Docket Nos.:
50-269, 50-270 and 50-287 License Nos.:
DPR-38, 47 and 55 Category:
C,C,C Location:
Scacca, South Carolina Type of License:
Type of Inspection:
Routine, Unannounced Dates of Inspection: November 4-7, 1975 Dates of Previous Inspect:.on:
September 22-24, 1975
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Principal Inspector:../
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', ' u Date T. N. Epps, Rc;act.r luspector Facilities Oper$tiens Branch l
Accompanying Incpectors:
None
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Reviewed by:
Date R. C. Lewis, Section Lecder Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
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IE Rpt. Nos. 50-269/75-12,
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50-270/75-13, and 50-287/75-14-2-j /~)
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SUmfARY OF FINT INGS I.
Enforcement Items
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None II.
Licensee *: tion on Previously Identified Enforcement Matters
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Not inspected.
III. New Unresolved Items
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75-12, 13, 14/1 Several weaknesses were found in the licensee's fire protection program.
(Details I, paragraph 2)
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Status of Previously Reported Unrecalved Items
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Oconee 1 (50-269)
73-12/1 Calibration of Effluent Monitors Not inspected.
73-13/1 Wasteuster Collection Basin Modification Not inspected.
74-3/3 Tra',ina of Unlicensed Utility Operators
This item remains open.
f 74-12/1 Incomplete Inserrice Inspection Plan The licensee will obtain further information frca the a
NSSS vendor on this subject. The item remains cpen.
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Oconee 3 (50-?S7)
74-13/2 Reactor Coclant Flow Anomalf
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This problem has been referred to the Office of Reactor Regulation (Licensing).
It remains open.
74-14/2 Ventilation Contr 1 Between Auxiliary and Turbine Euildings
~his item remains open.
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Duke Power Company-2-
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submitted, it must fully identify the bases for bhich information is claimed to be proprietary. The application should be prepared so that information sought to be withheld is incorporategl in.' separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement, If we are not contacted as l
should be submitted to us within 20 days.
specified, the enclosed report and this letter may then be placed in the
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Public Document Room.
Should you have any questions concerning this ictter, vc til be glad to discuss them with you.
Very truly yours,
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Norman C. Moscicy Director
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Enclosure:
IE Inspection Report Nos.
50-269/75-12, 50-270/75-13, 50-287/75-14
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cc u/ report:
J. E. Smith, Station Manager J
P. O. Box 1175 Seneca, South Carolina 29678
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IE Rpt. Mos. 50-269/75-12,
50-270/75-13 and 50-287/75-14-3-l
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Oconce 1, 2 and ' (50-269, 50-270 and 50-287)
74-10, 08, 11/3 Operator Replacement rnining i
This program has not received final approval.
The itou remains open.
74-10, 08, 11/4 SRC Quorum Not inspected.
74-10, 08, 11/5 Procedure Changes Not inspected.
74-10, 08, 11/11 Non-Technical Specification Violations Not irspected.
- 75-2/2 Sensitivity of Reactor Coolant Prec7ure Boundarv Lee'nce Detection Syste.is Not inspected.
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Other Signif
_., dings None VI.
Manatenant Interview A management interview was held on November 7,1975, with "r.
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. Smith and members of his staff.
Itens discucced included a sunmary of inspec-tion topics included in this inspection and weaknesses idens ified during the in pector'r re;/iew of the licensee's fire protection program.
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.lE Rpt. Nos. 50-2u9/75-12 I-l hD ak
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.i 50-270/75-13 and 50-287/75-14
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DETA.*LS I Prepared by:
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T. N. Epps, Reictor Inspector Date f
Reactor Projects S-ction No. 2,
Reactor Operations and Nucicar Support j
Branch I
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Dates of Inspection:
November 4-7, 1975
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Reviewed by:
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R. C. Lewis, Section Leader Date Reactor Projects Section No. 2, l
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Rcactor Operations and Nuc1 car Support
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Branch
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ladividual-Contceted
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Duke Pouar Company (DPC)
J. E. Snith - Manager, Oconce Nuclear Station
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J. W. Hampton - Directo', Administrative Services L. E. Schmid - Operatin:, Superintendent a
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0. S. Bradham - Mainten..::e Superintendent R. M. Koe'aler - Technical Services fcJerintendent T. S. Barr - Technical En31neer
J. Iten - Sc'et-, Supervisor J. Cox - Station Senior QA E gineer 2.
Fire Prevention
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i Part of this inspeerion involved review of the license e'c program for fire prevention and protection.
This review incirded licensee procedurcs, Qu.-lity Assurance program for fire relateel controls, fire inspectio..s, fira fighting training and fire cla;:m systems.
j During this review, several weaknesses were identifiel as listed below and codLined as Unresolved Iten 75-12, 13 and 14/l:
a.
Flame Safety Permits and Fire k'atches
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The site maintenance group uses flame scfety permits and forms
establishing a fire watch for work involving use of an open flame.
However, control of the use of these forms by inter-facing organir.ations appears weak. The licensee had a draft administrative prc:cdure titled, "h'ciding and Burnin: Safety Procedure".
Thir procedurc will require use of the 'J1;..e
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IE F. Nos. 50-269/75-12 I-2
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50-z70/75-13 and 50-287/75-14
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Safety Permit" and a fire watch, where appropriate, for any k involving an open flame by any organization while working
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Oconce.
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approval, l
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(A Reviews
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The QA organization audits fire fighting training cograms but does not review the use of flame safety permits or the replace-ment of fire stops.
A licensee representative stated that adminictrative pr,cedures covering fire watches would be included in QA audits and that QC sign-offs would be included in fire stop maintenanca procedu-es when issued.
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Replacement Materials in Fire Stoor
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a rire stop caterials used at Oconce are presently specified in a construction specification used for th original installation of fire stops.
There is no Ocenee maintenance procedure which
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specifics materials to be used when replacing fire stops that are rtmoved during =aintenance.
A licensee representative
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stated that a mainten nce procedure for the a'ove purpose would be Lepicmented by LT.cc:.ber 15, 1975.
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Fire Alarm Svn' 2 l
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Another weakness was identified by the inspector durin; a tou-i through the facility.
i Statalarms were lighted in each centrol roca f r.dicating a fire alarm. When the fire alarm pancis in the back of each centrol room were observed, fire alarm lights indicated that a fire detcetor was actuated in each containment.
Operations personnel stated thut this condition had existed for some time due to facity der.ectors.
After further questioning it was detarmined that no reriash mechanis= existed on the fire alarm systemc and additit :a1 actuations of the fire alarm syste. vould not alarm in the control room.
The licensco stated that a modification to the fire alarm system to alleviate this probica would be implemented but no i
date for conplc ton c-Id be given.
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I$ Rpt. No. 50-269/75-12 I-3
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50-270/75-13 and 50-287/75-14 D #747 D 6"
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The above items will be the subject of futt:re review.
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3.
Traiqing
i The licensee implemented a fire fighting training program to train j
Oconce operations personnel, guard force personnel and other personnel in health physics, instrumentation, and chemistry.
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j A licensee representative stated that fire drills will b conducted i
approximately each quarter beginnin3 t;e first quarter of 1976.
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A licensee representative stated that Oconee personnel are responsible l
for fire fighting within the Oconee facility.
Outside help will only be called in if fire is outside the facility.
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Plant Onorations i
The inspection of Units 1 and 2 involved a review of plant operating records and incident reports, discussient with operating peraennel and a plant tour.
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j During the plant tour the inspector noticed that a fire stop (6"
dia: eter) had been removed from the Unit 2 control room floor in j
the rcar of the control room.
This le:t an open 6-inch pipe between j
the cable spreadi:c; roem belou and the control roen.
A licenseo
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representativ2 stated that some instrucentation cable had been j
installed and the fire stop uas to be replaced.
It was replaced before the inspection was completed.
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