TXX-4226, Forwards Rev 1 to Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612..., in Resolution of Open Items,Per 840618 Conference Call
| ML20090D249 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/12/1984 |
| From: | Schmidt H TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20090D251 | List: |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 TXX-4226, NUDOCS 8407180145 | |
| Download: ML20090D249 (2) | |
Text
F F
Log # TXX-4226
. TEXAS UTILITIES GENERATING COMPANY Fi1e # 10010 MKYWAY TOWEH
- 800 NOHTH OLIVE NTHEET, L.H. M B
- DALLAM,TEXAM 73208 July 12, 1984 Mr. BrJ.tYoungbloodcChief; Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 RESPONSE TO B. J. YOUNGBLOOD LETTER TO M. O. SPENCE DATED MAY 17, 1984,
" Technical Evaluation Report Regarding Control of Heavy Loads in Accordance with NUREG-0612 at CPSES"
Dear Mr. Youngblood:
As directed by your May 17, 1984 letter, a conference call was held June 18, 1984 with the NRC to resolve the open items associated with handling of heavy loads at CPSES.
Resolution was reached concerning these items and is documented by the following:
Section Resolution 2.2.1.
The safety injection pump hoist has been removed at CPSES, therefore this section is closed.
2.3.1 1)
Safe load areas are defined in CPSES plant procedures and operators training so that, to the extent practical, heavy loads are not carried over or near irradiated fuel or safe shutdown equipment.
2)
Safe load area sketches are provided in the appropriate plant procedures.
l 3)
Electrical interlocks are utilized on the Fuel Building Overhead Crane ar.d are discussed in t
the appropriate plant procedures.
4)
The signalmen and crane operators at CPSES have been trained to use hand signals.
These signals are discussed in the appropriate plant procedures.
2.3.2 Closed 0
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A DEVENION OF TEXAN l'TELETIEN ELECTRIC COMPANY
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2.3.3 Closed 2.3.4 1)
Reactor vessel head and reactor internal lifting rigs meet the intent of ANSI 14.6-1978 and NUREG-0612 for design, fabrication, assembly and operation. Refer to Section 6 of the enclosed WCAP-10156, Rev. 1.
2)
A detailed analysis of an alternate load verification, testing, and stress design factor is included in Attachment B of WCAP-10156, Rev. 1.
2.3.5 The unit of hoist speed used for calculating the dynamic load in the formula (load X 0.005 X hoist speed + max. static load) is feet / minute.
2.3.6 Closed 2.3.7 The CPSES Final Response to NUREG-0612 was submitted to the NRC by letter TXX-3659 dated June 8, 1983.
1)
All loads in Table A-4 of this report which are less than 2150 poun'ds are not considered heavy loads, therefore no action is taken with those items.
2.4.1 Not applicable to CPSES.
2.4.2 Closed 2.4.3 Closed If.you have questions, please call.
Sincerely, H. C. Schmidt RWH/grr Enclosure cc - Mr. John J. Stefano Mr. Pete Hearn
'Mr. Amarjit Singh
..