ML19317F185
| ML19317F185 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/06/1974 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Goller K, Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001080899 | |
| Download: ML19317F185 (5) | |
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AM 6 W4 Docket No. 50-287 K. Collar Assistant Director for Operating Reactors, I.icensing V. Moore, Assistant Director for Light Water Reactors. Group 2. Licensing TRANS7ER OF OCONEE NUCLEAR STATION, U'IIT 3 FROM LWR 2-3 TO ORB-1 Effective immediately, the Regulatory licensing responsibility for oconee Muclear Station, Unit 3 (Docket !!o. 50-287) is transferred from LWR Branch 2-3 to Operating Reactors Eranch ?!o. 1.
Oconee Unit 3 received a full-tcrn, full-power operating license, DPR-55, on July 19, 1974. The pisnt is currently in startup and there are no operating power restrictions.
The LECT 3D (Attachment 1) defines the generic item categories. The status of the safety review for econce Unit 3 13 sumarized in Attach-ment 2.
The attachment includes the status of generie ice-s as well as items specific to Oconee. You will note that Attsch-ent 2 is comon to all three Oconec Unita.
By copy of this memo, TR, RO, OPS, Regulatory Files. EP, 000. Public Infor=ation and Public Proceedings are being notified of the following changes:
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Project Manager I. A. Peltier L. V. 'tcDonough Branch Chief A. Schwencer R. A. Purple Assistant Director V. A. Moore K. Coller
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Licensing Assistant E. Coulbourne S..,Sheppard Origtn! sierd by Roger S.Boyd A. Ciambusso Deputy Director for Reactor Projects Directorate of Licensing i
Attachments and ecs:
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@ Attachments:
1.
The LEGDID 2.
Status of Review Items ecs: TR ADe TR BCs 9 (3)
OPS HThompson, EP HWilchins, OGC CMiles FKaras i
DISTRIBUTION:
Dockets LWR 2-3 Reading L Reading AGiambusso VAMoore ASchwencer RPurple IPeltier LMcDonough EGoulbourne STeets RSBoyd KGoller H-6<tA'W L
AGJambusso-Y42 174 L:C/ LWR 2-3 L:0RB-1, L:C/ORBg l,
L:ADOR c7886/g 2-3 o g'h RAPurple AM.
_et._ _ KGoller
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7hbl74 7/}I0/74 7/Q(J74
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ATTACIfMENT 1
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LEGEND A.
This item has been evaluated in light of current requirements and the status has been evaluated as acceptable.
(This does not necessarily mean that the status fully meets current requirements.)
J B.
This item has been evaluated in light of current requirements and measures have been initiated that will make the status acceptable.
C.
This item has not been evaluated in light of current requirements; however, the Project Manager's judgment is that the status is probably acceptable.
(This judgment should include consideration of (a) whether Regulatory requirements have been changed much since the item was evaluated, (b) whether the item has been evaluated at other plants with this item similar, (c) whether there would be a substantial effect on public health and safety even if current requirements were not met and any other relevant information known to the Project Manager.)
D.
This item has not been evaluated in light of current requirements.
It is the Project Manager's judgment that the status is probabl.y unacceptable.
E.
This item has not been evaluated in light of current standards.
The Project Manager cannot express a judgment concerning acceptability of the status.
(This category included items for which the Regulatory requirements have not been determined.)
NA This item is not applicable tc the facility.
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A ATTACHMENT 2 STATUS OF REVIEW ITEMS, OCOMEE NUCLEAR STATION A.
Generic Items Which Have Been Resolved and Require No Further Licensing Actions Item Reference 2
1.
-Instrumentation-for Earthquake (SG 1 )
Page 5-11 SER 7/6/73 2.
Quality Assurance for Operations Page 12-6 SER 7/6/73
- 3.
Steam Lin'e Break Page.4-2 SER Suppl. 3 7/10/73 Page 7-45 SER 7/6/73 4.
Protection Against Pipe Whip Inside Containment Page 7-38 SER 7/6/73 5.
Combustible Gas in Containment Post-Accident Control Page 7-45 SER 7/6/73-6.
Adequacy of Post-Accident Monitoring Page 54 SER 12/29/70 Page 9-17 SER 7/6/73 7.
Post-Accident Control Room Habitability Tech Spec 4.12 8.
Reliability for Containment Isolation
-Valve Closure Page 45 SER 12/29/70 9.
Main Steam Isolation Valve Leakage Tech Spec 4.8 10.
Instrumentation Lines Penetrating Con-tainment (SG-ll)
Tech Spec 4.4 11.
Adequacy of Inservice Inspection Program Page 29 SER 12/29/70 Page 5-11 SER 7/6/73
- 12. Adequacy of Tornado Protection Page 6-1 SER 7/6/73
- 13. Adequacy of Flood Protection Page 3-10 SER 7/6/73 14.
Operability of Safeguards Equipment Page 5-4 SER 12/29/70 in Accident Environment
- 16. Adequacy of Testing When Pisabling Vital Equipment Page 8-1 SER 7/6/73 17..
Adequacy of Power and Control (IEEE 279, 308, GDC 17, SG 6)
Page 8-1 SER 7/6/73
- 18. Primary and Secondary Systems Safety
'and Relief Valve Support Adequacy Page 5-9 SER 7/6/73 19.
Fuel Densification SER Suppl. 1 8/2/73 SER Suppl. 3 7/10/73 20.
Internal Flooding of Critical Equipment Page 7-34 SER 7/6/73
- 21. Primary Coolant Leakage-Limits and Detection Capability Page 32 SER 12/29/70 22.
Furnace Sensitized Stainless Steel Page 5-6 SER 7/6/73 23.
Seismic Design Adequacy Page 5-10, 6-1 SER 7/6/73 3
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- 24. Fluence Damage to Reactor Vessel Page 5-7 SER 7/6/73
- 25. Reporting Requirements (SG -16 & 21)
- 26. Adequacy of Emergency Plan (App. E)
Page 12 3 SER 7/6/73
- 27. Hydraulic Pipe Snubbers Tech Specs Table 4.1-2
- 28. High-Energy Line Modifications Page 7-38 SER 7/6/73
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B.
Geueric Items Which Have Been Evaluated In Light of Current Requirements And Measures Have Been Initiated That Will Make The Status Acceptable.
Item Reference 1.
Adequacy of Industrial Security Page 12-4 SER 7/6/73 March 21, 1974 letter to applicant requested reevaluation of security plan per RG 1.17.
Applicant revised 4/17/74. OSB has reviewed revision and found it acceptable.
,2. Performance of Effluent Treatment Systems Page 9-1 SER 7/6/73 (ALAP)
Applicant is revising waste management system.
Preliminary design will be submitted for AEC review about mid 1974.
3.
Adequacy of Environmental Monitoring Program Page 9-18 SER 7/6/73 Tech Spec 4.11 AEC is requesting modification to Environmental Monitoring Tech Spec. Revised Specs were completed June 19, 1974.
4.
Evaluation of R'efueling Cask Drop OR will re-review this matter in mid 1974.
Legend C, D, E, NA Items NA Items were not included on~ lists i
l Legend C Items 1.
Turbine overspeed 2.
Rod Drop Accident Analysis 3.
ECCS Water-Hammer Legend D Items 1.
Anticipated Transients Without Scram 'ATWS), Page 7-37 SER 7/6/73 2.
Main Coolant Pump Overspeed SER Suppl. 2 10/1/73 Legend E Items None Items Specific to Oconee - Legend B Category Item Refer:ence Iodine Filters in Spent Fuel Building Page 10-1, 11-2 SER 7/6/73 l
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