ML19317E968
| ML19317E968 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/27/1972 |
| From: | Peltier I US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001070763 | |
| Download: ML19317E968 (5) | |
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j ,~ 310 at] DEC 2 71972
- 1. C. DeToung, Assistant Director for Pressurized Water Reactors, L THRU A. Schwencer, Chief, Pressurized Water Reactors Branch No. 4, L SITE VISIT TO DUKE COMPANT OCONEE NUCLEAR STATION - DECDGER 20, 1972 a
Enclosed is a report of the site visit made to the Oconee Nuclear d Station on December 20, 1972 for the purpose of discussing vibration testing of vessel internals during hot functional testing and to view other safety related plent features. Also enclosed is a copy of principal contacts made. Original Signed by Irving A.Peltiet 1
- 1. A. Peltier Project Manager PWR-4 Enclosuret-
~~ '~ Site Visir Report cct RSBoyd DISTRIBUTION DSkovholt HH100Dy Subject File DKnuth RP Reading RMaccary L Reading RTedesco PWR-4 Reading HDenton EIGoulbourne PWR Branch Chiefs RWKlocker MRosen RO (3) DFLange CGLong IAPaltier \\ orrict > --_ LWR-4.. A ~.: zu.w I' v sumur > 4APalt.ier4kaf- --A encer---- .12 M /Z2,_,_,,__,,,,12 h 72 i q,,_.,$? ; cart > -{ r Arc ns(Rev.9-53) ABCM 0340 5
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O O s'e Y
SUMMARY
OF SITE VISIT TO DUKE POWER COMPANY OCONEE NUCLEAR STATION - DECEMBER 20, 1972 1. The Keowee hydrostation water intake gate was visited to cbtain a better understanding of the features and method of operation. The gate is used to plug the intake duct to the hydrostation; whenever, it is desired to de-water the penstocks or to shut down the hydro-turbines in an emergency if the normal flow gates fail to close. The gate is a 39 ft. cylinder which is lowered and raised by-a permanent overhead crane. In its lowered position it plugs _the side flow through the intake screens to the vertical intake duct. The gate weighs about 120 tons and will go down by gravity to its ~ lowered position without power on the crane at about 1 or 2 ft. per minute (requires about 25 minutes for full travel according to Duke personnel). The gate is held in its upper position by a mechanical brake on the crane hoist drum. The normal position of l i l h ',.':7 the brake is "on" and it requires e ectr c power to re ease t e brake. For emergency purposes, the brake release can be energized from the Keowee station, Oconee station and the gate pier. Power for raising the gate can be controlled only from the gate pier. Our interest in this gate centers.around the fact that the Keowee hydro units are the on-site power source for the Oconee plant. In this regard, the lowering of the gate is enunciated in both the Keowee and Oconee stations and a control room pancl light indicates when the gate is in the lowered position according the Duke. Apparently there are no safety related interlocks. 2. I reviewed Dukes' schedule of key events between now and the time the plant would be ready for power escallation. They are as follows: Event Date System cool down 12-27-72
- w' Hot Functionals C,omplete 12-31-72 Drain System 1-1-73 Detentioning of head 1-2-73 Set head off 1-6-73 Plenum out 1-7-73 Core support out 1-9-73 Steam Cencrator Tube..aspection (critical item) start 1-3-73 Steam Generator tube Inspection complete latest 1-24-73 Fuel loading start 1-28-73 Fuc1 loading complete 2-12-73 Zero power physics complete 3-5-73 15% power start 3-10-73 to 3-17-73 t.
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w e . The above schedule does not take into consideration any over The schedule also does take into consideration all assumption that they are parallel activities.as ECCS such restrictor installation will be 1-9-73 and will be complete inThe start seven days. ....2 u. 3. lines frem every location practical.I viewed the Oconee ~ er ' ~ ~ ' " One main steam-line leaves the containment penetration and outdoors all the way to the turbine building. runs the containment penetration inside of the penetraEionThe~other' leaves the corner of the room, makes a couple of right anglroom near ~ leaves the penetration room and runs outdoors from there t e turns, turbine building room is about as shortThe run of steam line inside the penetration o the t-3 , l,7,",' turns. _ Outside the steam lines run parallel over the the loading dock and are well constrained in this area over the loading dock. The relief valves are The two main feedwater lines have long runs (80 ft inside the penetration room prior to entering the co t i . or more) The main check valves are in the penetration room close t n a nment. containment wall (about 10 f t.). o the The penetration room contains safety related fluid syst the low pressure service water, low pressure injecti ems such as high pressure injection system and building spray syste on system, It also contains all of the electrical cabling to the rea t m piping. building. penetration room (izmediate levels) and there d c or to be a common wall with the control room although th e do overlap. e elevations a 47 I viewed the data acquisition, recording and monitoring ^ being used by B&W to study the fluid equipment internals response during the hot functional tests' forcing functions and v data have been acquired and all internal c9mponents of i All essential except the thermal shield have exceeded 10 nterest According to E&W the stress levels are low, the 'systemcycles of vib f to be tight and loss of instrumentation was minimu appears m (about 10%). + 2 ',
- -?3 G-72 20 a-L?-Ts e,
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.g: i PRINCIPAL PERSONS CONTACTED Duke Power Company J. Ansell T. Summerlin - M. McIntosh i Babcock and Wilcox E. Hooker D. Thoren Region II (AEC) I F. Jape ( ~ ,s.1 *- AEC Licensing D. Lange I. Peltier i i l i ..w' . a. 1 I l 6 e ) 1
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