IR 05000269/1973005
| ML19322A901 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/11/1973 |
| From: | Murphy C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19322A900 | List: |
| References | |
| 50-269-73-05, 50-269-73-5, NUDOCS 7911270657 | |
| Download: ML19322A901 (8) | |
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UNITED STATES
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ATOMIC ENERGY COMMISSION
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,e DIRECTORATE OF REGUIATCRY OPI?ATIONS
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RO Inspection Report No. 50-269/73-5 Licensee:
Duke Power Cor'pany Power Building 422 South Church Street Charlotte, North Carolina 28201
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Facility Name: Oconee Unit 1 Docket No.
50-269 License No.:
DPR-38 Category :
B2 Location: Oconee County, South Carolina Type of License:
Dates of Inspection: April 28 and 30,1973 Dates of Previous Inspection: April 11-12,1973
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April 17-20, 1973 Principal Inspector:
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R. F. Warnick,' Peactor Inspector
<Date Facilities Test and Startup Branch Accorpanying Inspectors: None Other Accocpanying Personnel: None Bevteved By: /
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C. E.' Murphy,. Acting #, Chief, Facilities Test and
/ D6te Startup Branch
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IO Rpt. No. 50-269/73-5-2-
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SUMMARY OF FINDINGS
1.
Enforcement Action A.
Violations d
None B.
Safety Items None II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations These matters were not inspected.
B.
Safety Items None j
III. New Unresolved Items i
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IV.
Status of Previously Reoorted Unresolved Items 71-7/1 gin Walled valves (RO '.nsrection Recort No. 50-269/71-5, j
Detailt C.3.)
The licensee's report on the wall thicknesses of valves t
within the reactor coolant system pressure boundary has been received by Region II and remaining deficiencies identified.1/ The region is awaiting action by DPC.
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71-10/1 Flewmeter Error Analysis and Tests i
TP-800/25, "NSS Heat Balance," verifies the accuracy of the primary flowmeter by determining reactor coolant system flow using a secondary heat balance. This item remains open until appropriate acceptance criteria are incorporated into the test procedure.
(Details I, paragraph 6)
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j 1/ See RO Inspection Report No. 50-269/73-1, Details VII, paragraph 3.
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RO Rpt. No. 50-269/73-5
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73-1/2 Resolution of Test Deficiencies This item remains active until penetration room filters
are retested at 1000 cfm.
(Details I, paragraph 7)
73-1/7 Emergency Coerating Procedures Two procedures remain to be written and both are under development. The lack of these two procedures will not compromise plant safety. This item remains open until both procedures are written and approved by DPC.
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73-3/1 Nitrocen In-Line Heater Desien Change Documentation Heaters have been added to the nitrogen supply line feeding the core flood tanks. The design change documentr. tion was requested for review. Only certain
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engineering calculations have been made available to
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date. This item will re:nain unresolved until sufficient information is available to determine if the requirements of Criterion III of Appendix B to 10 CFR 50 have been satisfied and until Region II has inspected the design change.
73-4/1 Reactor Coolant Pt:mo Flow The reactor coolant purp preoperational flow test at 2155 psig and 500*F indicates the acceptance criterion for maximum flow for the end of core life may be exceeded. Additional evaluations will be made at 75% of full pcwer. This item remains open until the evaluations are complete.
73-4/2 Inverse Multiplication Plots _
The inverse multiplication plots for the initial approach to critical were not as effective in predicting the point
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the reactor would achieve criticality as they ordinarily j
would be because of a " knee" in the curve and the delay i
experienced in obtaining boron sample results. This item
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remains open pending action by DPC.
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V.
Desien Changes
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None VI.
Unusual occurrences j
None
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RO Rpt. No. 50-269/73-5-4-
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VII. Other Significant Findines
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A.
Zero Power Physics Tests
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Zero power physics tests (ZPPT) are expected to be complete on May 1,1973, and DPC is ready to begin the power ascension test program. Prelim.incr/ results of the ZPPT have been evaluated daily by the test coordinators. The Station Review Committee (SRC) and B&W have reviewed preliminary test results and have found no problems to prevent DPC from going into the power ascension testing program.
(Details I, pargraph 3)
B.
Power Ascension Test Program The principal inspector has reviewed DPC's power ascension test procedures. His comments have been discussed with DPC and have been incorporated into the procedures. DPC is rea8f to begin power ascensien testing.
(Details I, paragraph 4)
VIII. Management Interview At the conclusion of the inspection, a mar agement interview was held on April 30, 1973, with the plant superintendent, J. E. Smith, to discuss the findings of the inspection.
The inspector stated that
<J aviewed the power ascension test procedures and it was 2.xs understanding t&at DPC was going to do the following:
A.
Petype TP-800/26, " Reactor Coolant Pump Restart Test."
This is needed for the 40% power level.
B.
Add an enclosure to TP-800/18, " Induced Power Oscillation Test," to explain hcw to verify that the escillations are within +3% prior to initiating a perturbation.
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C.
Add acceptance criteria for calculated flow versus measured flow in TP-800/25, "NSS Heat Balance," or else discuss the actions that vill be taken if the flows are not in agreement.
The plant superintendent indicated the inspector's understanriing was correct. The inspector was informed on May 4 that item A and B have been completed.
(Details I, paragraph 6)
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JO Rpt. No. 50-269/73-5 1-1
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r-I/d y DETAIIS I Prepared By:
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R. F. Warnick, Reactor Inspector
'Date Facilities Test and Startup Branch
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Dates of Inspection: April 28 and 30,1973 b?
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Reviewed I::
I oate C. E. Murphy,'Act,ing Chief Facilities Test and Startup Branch
1.
Individuals contacted Duke Power Comoany (DPC)
J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent M. D. McIntosh - Operating Engineer R. M. Koehler - Technical Support Engineer R. L. Wilson - Performance Engineer G. W. Cage - Assistant Operating Engineer i
0. S. Bradham - Instru:'ent and Control Engineer L. R. Schlazer - Jr. Engineer l
E. F. Hood - Test Coordinator J. N. Pope - Shift Supervisor (SIO)
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2.
General
i The inspection of April 28 and 30,1973, was conducted to determine that the power ascension test procedures were adequate, that they had been reviewed and approved by DPC, and that prerequisites
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for the power ascension test program had been completed.
3.
Zero Pcwer Physics Tests (ZPPT)
f DPC should complete z(ro power physics testing approximately May 1,
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1973. Both B&W and DPC test coordinators have been reviewing test results on a daily basis. B&W has complet.ed a review r.nd
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evaluation of preliminary test results and has approved them.
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The ZPPT preliminary results have been reviewed by the Station j
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Review Comittee (SRC). The plant superintendent informed the
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program. The inspecter found no evidence to the contrary.
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10 Rpt. No. 50-269/73-5 I-2
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The inspector witnessed part of the ZPPT on April 27,1973, and observed the measurement of the worth of a dropped rod, CRA 6-5 (step 12.14.11.7 of TP-710/1).
4.
Power Ascension Test Procedures./
The licensee's power asce sion test program is described in 31 test procedures. During the inspection of March 4-7, 1973, the inspector reviewed TP-800/23, " Controlling Procedure for Power Escalation Sequence," and 17 other power ascension test procedures and discussed his coments on the procedures.
As a result of one of the inspector's comments, DPC has rereviewed all power ascension test procedures. Seventeen procedures have been retyped after changes were made and one more will be retyped.
Changes have been made to seven other procedures but they did not require retyping. The inspector reviewed twelve of DPC's revised power ascension test precedures.
(Eight of which had been reviewed by the inspector during the March 4-7 inspection.) The inspector found that CPC has taken action on all of the inspector's previous comments (paragraph 5) and comitments have been received that should resolve all new coments (paragrgh 6).
DPC's power ascension test program meets the requirements of the FSAR and other applicable documents.
5.
Resolution of Inscector's Previous Coments on Power Ascension Test Procedures The inspector's previous comments / were resolved as follows:
At 15% of full power, the overpower trip will be set at 35%
a.
instead of 50% of full power.
b.
The accaotance criteria stated in the abstract of TP-800/23 in the FSAR have been included in the test procedure.
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Test procedure TP-800/3, " Biological Shield Survey," requires c.
neutron surveys at each power plateau, d.
B&W indicated their comments have been incorporated into the power ascension test procedures.
The inspector reviewed 12 of the seventeen retyped procedures.
e.
"5mments were resolved during the inspection. DPC action remains to be taken on three of them.
(See paragraph 6)
1/ See RO Inspecticn Report No. 50-269/73-3, Details I, paragraph 3.
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RD Rpt. No. 50-269/73-5 I-3
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Step 6.3 of TP-800/5, " Reactivity Coefficients at Power,"
was revised.
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Teut procedure TP-800/10, " Xenon Reactivity Worth and Rapid Depletion Test," was revised to include more detail.
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The maximum and minin.2 acceptable flows in the reactor coolant system were specified. The acceptance criterion for the comparison of neasured to calculated flew was not added.
(See paragraph 6.)
6.
Review of Revised Power Ascension Test Procedures
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The inspector reviewed the following revised pcwer ascension tests and dicussed his comments with representatives of DPC:
" Reactivity Coefficients at Power" - Enclosures 4 and 5 did not contain sufficient information
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for the reactor inspector to understand hcw they were to he used. DPC revised both enclosures on April 29, 1973. One contained several typographical errors which DPC will correct.
TP-800/10, " Xenon Reactivity Worth and Rapid Depletion Test."
TP-800/13, " Unit Loss of Electrical Load."
TP-800/16, " Reactivity Depletion Vs. Burnup."
TP-800/18, " Induced Power Oscillation Test" - The test pro-cedure did not explain how the operators were to verify that any oscillations prior to initiating the perturbation were within the required +3%.
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DPC agreed to add an enclosure to specify the method and instrumentation P.o be used in determining this requirement.
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TP-800/19, " Rod Worth at Power."
"NSS Heat Balance" - DPC agreed to add acceptance criteria for use in comparing calculated flow with measured flow or else they will discuss the actions that will be taken if flows are not in agreement.
TP 800/28, " Unit Load Steady State."
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10 Rpt. No. 50-269/73-5 I-4
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TP-800/30, "Ioss of Control Room."
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TP 800/31, " Pseudo Control Rod Ejection Test."
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T'/-800/32,
TP-800/33, " Dropped Control Rod Test."
The inspe'ctor's coments were discussed during the management interview. In addition to the above comments, the plant superintendent confirmed that TP-800/26 would be retyped.
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Resolution of Preccerational Test Deficiencies 1/
7.
DPC has prepared a summary of the resolution of the deficiencies which are described in the sumary of the results of TP-600/1,
" Controlling Procedure for Hot Functional Testing." All deficiencies have been resolved.
The only item remaining from the preoperational testing program is the repeat of TP-110/2, " Penetration Room Flow Pressure Drop and Filter Tests," which will be rerun at 1000 cfm.
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l If Site RO Inspection Report No. 50-269/73-3, Details I, paragraph 10.
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