ML20087M186
| ML20087M186 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/20/1984 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NLS-84-094, NLS-84-94, NUDOCS 8403290083 | |
| Download: ML20087M186 (2) | |
Text
a e
CP&L Carolina Power & Light Company MAR 2 01984 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR ADDITIONAI. INFORMATION - CONTROL OF HEAVY LOADS
Dear Mr. Vassallo:
Following a phone conversation with your staff on February 21, 1984, Carolina Power & Light Company was asked to provide some additional information concerning load testing on the special lifting devices at the Brunswick Steam Electric Plant Unit Nos. I and 2.
Attached please find our responses to the questions asked by your staff.
Should you have any question concerning this letter please do not hesitate to contact a member of our Licensing Staff.
Yours very truly, S. R. Zimmerma Manager Nuclear Licensing Section PPC/ccc (9579PPC)
Attachment ec:
Mr. D. O. Myers (NRC-BSEP) l Mr. J. P. O'Reilly (NRC-RII) i Mr. M. Grotenhuis (NRC) 0403290083 840320 PDR ADOCK 05000324 P
PDR 411 Fayetteville Street
- P. O.. Box 1551
- Raleigh, N. C. 27602 gI
5 QUESTION It appears that the special lifting devices have never been load tested.
Does the program being developed for compliance with ANSI N14.6 Article 5.3.1 provide for a load test of these devices?
If it doesn't, what justification can be provided for having never completed an overload test.
(See synopsis Guideline 4, Exception 2).
RESPONSE
Initial load testing was performed for the following lifting devices:
Head Strongback The initial load test for the Head Strongback was performed at the time of manuf actare of the equipment to 100 tons (25 tons applied simultaneously to each leg).
Dryer Separator Sling-The initial load test for the Dryer Separator Sling was performed at the time of manuf acture of the equipment to 104 tor.s (26 tono applied simultaneously to each leg).
Spent Fuel Cask Yoke The Spent Fuci Cask Yoke was originally load tested to 200% of rated load.
In 1980 the Spent Fuel Cask Yoke was modified and retested to 200% of rated load.
Initial load testing has not been performed for the Stud Tensioner Frame and the Invessel Service Platform Strongback.
However, a load test for these two special lif ting devices will be perforined in accordance with ANSI N14.6 Section 5.3.1.(1) by August 31, 1984. The Shielded Personnel Lif ting Apparatus is already being load teated at BSEP. As mentioned in our February 3, 1984 letter, the load test presently being performed will be upgraded to meet the requirements of ANS1 N14.6 Section 5.3.1.(1).
The acceptance testing and maintenance program being developed for the Shielded Personnel Lif ting Apparatus, Head Strongback, Dryer Separator Sling, Stud Tensioner Frame and the Invessel Service Platform Strongback will provide for load testing of these devices in accordance with ANSI N14.6-t Section 5. 3.1. ( 1), 5. 3. 2, 5.3. 3, 5. 3.4 and 5. 3. 5.
The spent fuel cask yoke will not be load tested; however,_the acceptance _ testing _and maintenance program presently used for this lif ting device already meets the conditions of.
ANSI N14.6 Section 5.3.1.(2) per the manufacturer's recommendations. CP&L~
will continue to use the existing acceptance testing and maintenance program for the Spent fuel case yoke.
L
.