ML19326C549
| ML19326C549 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/02/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| 1-088-2, 1-88-2, NUDOCS 8004230667 | |
| Download: ML19326C549 (3) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-313 tEC: NRE 6P4LLO /
ORO: WILLIAMS D H DOCDATE: 08/02/78
!NRC AR PWR & LIGHT DATE RCVD: 08/10/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL /
RESPONSE TO NRC REQUEST OF 06/12/78... FORWARDING VARITY OF INFO (AS LISTED)
PERTAINING TO HEAVY LOADS NEAR SPENT FUEL.
W/ATT DRAWINGS AND INFO.
PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL:
. C****************
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOO1)
FOR ACTION:
BR CHIEF ORB # (BC**LTR ONLY(7) WlG INTERNAL:
tE n FTlF*st'rD OM Vt1 D NRC PDR**LTR ONLY(1)
I & E**LTR ONLY(2)
OELD**LTR ONLY(1)
HANAUER*cLTR ONLY(1)
CORE PERFORMANCE BR**LTR ONLY(0 AD FOR SYS & PROJ**LTR ONLY(1)
ENGINEERING BR**LTR ONLY(1)
REACTOR SAFETY BR**LTR ONLY(1)
PLANT SYSTEMS BR**LTR ONLY(1)
EEB**LTR ONLY(1)
EFFLUENT TREAT SYS**LTR ONLY(12 J.
MCGOUGH**LTR ONLY(1)
EXTERNAL:
LPDR'S RUSSELLVILLE, AR**LTR ONLY(1)
TERA **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT D**LTR ONLY(16)
)
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r DISTRIBUTION:
LTR 40 ENCL /
CONTROL NBR:
-73TEW4590t. L SIZE: 2P+ GOOP
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THE END
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i ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501) 371-4CDO August 2, 1978 1-088-2 Director of Nuclear Reactor Regulation ATTN:
Mr. Victor Stello, Jr., Director Operating Reactors J
U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Power 6 Light Company Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Heavy Loads Near Spent Fuel (File:
1510)
Gentlemen:
Persuant to the request of your June 12, 1978, letter on the above subject, the following information is provided:
1.
Drawings M-2 and M-3 (attached) show the relation of the core to other fuel handling areas.
2.
Objects which may be required to be handled over an open core would include the reactor vessel head, the plenum assembly, internals handling equipment, fuel and control element assemblies, and cameras and miscellaneous hand tools. The consequences of dropping the reactor vessel head, the plenum assembly, and their handling equipment are discussed in the response to AEC Question 9.47 in the ANO-1 FSAR. The cameras and hand tools are of various shapes, but weigh less than 200 lbs. and are used as necessary. Assemblies to be relocated are moved at a maximum height of approximately 16 feet above the core. Assemblies to be removed are moved directly to the fuel tilt area at a maximum height of approximately 18 feet. These assemblies are about 14 feet in length, 8.5 inches square, and weigh about 1500 pounds.
Fuel assemblics are the only objects which are required to be moved over the fuel storage area. They are normally moved 2 to 4 feet above the storage racks.
3.
The only casks planned for use at ANO-1 at this time are 25 ton casks (50,000 lbs.) for the removal of irradiated Burnable Poison Rods. These cylindrical casks are 214 inches in length and have a 50 inch diameter.
MV dO p MEMBER MlOOLE SOUTH UT1UTIES SYSTEM
/
Mr. Victor Stello, Jr. August 2, 1978 1-088-2 4.
We have previously provided a cask drop analysis for ANO as attachment 1 in our July 19, 1978 letter.
5.
There are no heavy loads carried over equipment required for safe shutdown that is operating at the time the load is moved.
6.
No heavy loads are carried over the spent fuel pool other than fuel assemblies, and in no case are loads greater than 2000 pounds carried over fuel assemblies in the pool per ANO-1 Technical Specification 3.8.15, 7.
Spent fuel handling equipment is described in section 9.6.1 and in responses to AEC Questions 9.44-9.47 of the ANO-1 FSAR.
8 Current procedures are enclosed that cover handling of loads over or in an exposed reactor core and the spent fuel storage pool.
9.
'Ihe fuel storage facility meets the intent of Regulatory Guide 1.13, Rev. 1.
Specific bases for this statement are given in response to AEC Question 9.4 and in section 5.A.5 of Appendix 5. A to the ANO-1 FSAR.
Very truly yours, Danici H. Williams Manager, Licensing DlIW: ERG:dr
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