ML19317F098
| ML19317F098 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/25/1973 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jennifer Davis US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001080787 | |
| Download: ML19317F098 (4) | |
Text
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UNITED STATES o
ATOMIC ENERGY COMMISSION 5 I 'q l DIRECTORATE OF~ REGULATORY OPERATIONS I
T REGION ll - SUIT E 818
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f-2M PE AC HT R E E ST R E ET. NORT HwEST 814rgg o' AT L ANT A. GEoRGa A 30303 September 25, 1973 John G. Davis, Deputy Director for Field Operations Directorate of Regulatory Operations, Headquarters DUKE POWER COMPANY (OCONEE 2) OUTSTANDING ITEMS LIST Enclosed for your information is an updated list of outstanding items at Oconee 2 as of September 25, 1973.
A new item has been added to the list. Questions have been raised regarding the integrity of the electromatic relief valve. This item may require a restriction to the license. The baseline inspection has not been completed. A meeting with DPC and B&W is tentatively scheduled for October 1-2, 1973, to discuss the inspectors questions.
The hot functional test program is essentially completed.
Examination of reactor internals is currently underway.
l Norman C. Moseley
~ Director
Enclosure:
Outstanding Items cc w/ encl:
RO:HQ Files T
'DR Central Files
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t, TRANSMITTED VIA MAG CARD 9/26/73 10:30 a.m.
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I OUTSTANDING ITEMS LIST, OCONEE 2, SEPTEMBER 6, 1973 1.
Welding' Program Deficiencies A draf t of the licensee's report on voiding deficiencies was reviewed and according to the draft report all items have been resolved.
No deficiencies were noted in the drnft report. Final resolution will be documented upon receipt of the, complete report.
2.
Baseline Data RO's review of the baseline data for Oconee 2 is currently underway. Several questions regarding the baseline report have been raised by the inspector. Resolution of these questions should not delay issuance of an operating license, but should i
be resolved prior to initial criticality. A meeting is tentatively scheduled for October 1-2, 1973,. with DPC and B&W personnel to discuss the baseline report.
3.
Licensee's Approval of Test Results The licensee has not completed all preoperational testing, reviewed the test results nor has he approved. all. testing as being acceptable.
At the present time, the results of 34 test procedures and 37 instrument procedures remain to be approved by the plant superintendent or responsible gr5up head. Most of the cests are in progress or have been conducted. The final review and acceptance is actively in progress by DPC and RO expects to find all tests accepted by initial fuel loading date.
4.
Reactor Coolant Pump Flow Determination An unresolved item 73-4/1, " Reactor Coolant Pump Flow," is
- currently being carried for Oconee ly, Since Oconee 2 ib similar in design, this same problem may occur in Oconee 2.
A report on Unit 1 RC flow determination was received from Duke Power Company on August 23,1973..The resuli c, of Unit 2 RC. Flow testing currently being done during hot 'Eunctional testing will be
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compared kith the Unit I report.
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RO is expecting to find that Unit 2 RC flow, will begreater than design flow presented in the FSAR by about 8 per cent.
In this event, Headquarters guidance will be requested.
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- 5. ~ Health Physics The following items are currently underway-but. remain to be completed:
a.
Calibration of process and area monitoring system.
b.. Verification of hood air flow in Unit 2. sampling room.
RO's understanding is thac these three itema will be completed prior to the licensing date.
6.
Physical Security Plan This item remains unchanged from the previous report. RO has reviewed the physical security plan for-Oconee 2 and twenty-two items were identified as incomplete. A followup i
inspection is tentatively scheduled for the, week of October 1, 1973.
Results should be available by October 4, 1973.
7.
RO's Review of Preoperatfanal Tests RO's review of preoperational tests is as fol. lows:
Percent of Percent of Test Procedures Test Results Category Reviewed Reviewed Remarks 35
'R0 inspection is 1
40 continuing. Will be completed prior to
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initial fuel loading 2
37 26 RO inspection program
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effort completed 3
52 35 RO inspection program 7-effort completed 1,
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8.
Operations QA Plan RO's review of the QA plan for operations has been completed.
However, a similar audit conducted previously for Oconee 1 had revealed many deficient items (RO Inspection Report 50-269/73-7).
Dukes response to the violations for Oconee 1 has been received and is being evaluated.
Preliminary icview indicates DPC's response is considered satisfactory.
One item regarding manipulation of control rods with an air hoist remains open.
Further discussions on this item'will be held with DPC management to clarify this item.
9.
Electromatic Relief Valve During the review of valve wall thickness, the stress analysis for the electromatic relief valve, 2-RC-66, was identified as not being in agreement with applicable codes. Reactor operation N
at design conditions with this valve in service has not been resolved. This question may require a restriction on operation until the valve analysis can be verified.
Closure of block valve RC-4 effectively removes RC-66 from service.
Licensee presently considering replacing the electromatic 4
relief valve.
If stress analysis indicates that valve walls are not adequate for the service, then restriction should be imposed to require block valve RC-4 to be normally closed when plant is in operation until the problem of the, thin wall valve is resolved.
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