ML19344A864
| ML19344A864 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/05/1978 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220379 | |
| Download: ML19344A864 (6) | |
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AlabamaPower t~e sea ec vec:rc. :e-December 5, 1978 3o - 3+8 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Mr. Albert Schwencer
Dear Mr. Schwencer:
Attached is Alabama Power Company's response to your request for additional information concerning control of heavy loads near spent fuel requested in your letter of September 23, 1978.
If you have questions, please advise.
Yours very truly, l
.s F.3. k N A
,e Clayton, ;Jr.
j F1.CJr/TNE:bhj Attachment cc:
Mr. R. A. Thomas w/ Attachment Mr. G. F. Trowbridge w/ Attachment i
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ENCLOSURE
RESPONSE
FOR NRC QUESTIONS PERTAINING TO CONTROL OF HEAVY LOADS NEAR SPENT FUEL l
i
Question #1:
Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.
Response:-
FSAR Figures 1.2-2,1.2-8, and 1.2-10 show the plant general arrangements and the physical relationships between the reactor vessel, the fuel transfer canals, and the spent fuel pool.
Enclosed is a set of drawings D-175050,175054, and 175067 which contain more detailed information than the FSAR figures.
Question #2:
Provide a list of all objects that are required to be moved o't:s the reactor For each object core (during refueling), or the spent fuel storage pool.
listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying height) and the frequency of movement.
Response
Ob-Objects that are lifted over the reactor core are listed on Table 1.
jects that 'are moved over the spent-fuel pool are listed on Table 2.
Drawing D-17505 has been marked to indicate the movement paths of objects moved over the reactor core and.the spent fuel pool.
TABLE 1 OBJECTS MOVED DVER REACTOR CORE Weight Height Item (lbs.)
(ft.)
Frequency Size Reactor Head-229,000 25 2
25' x 16' Dia Upper. Internals
'103,500 20 2
15' x 13' Dia G
2,500 15 220 35' x l-1/2' Dia p9e(i Fue As em ly TV Camera & Support s 50 25 Scan Small Movable Lights s 10 25 Various Snell
Response #2 (Continued):
TABLE 2 OBJECTS MOVED OVER SPENT FUEL POOL Weight Height Item (lbs.)
(ft.)
Frequency Size Spent Fuel Handling Tool 375 5'
Approx. 55 l' x l' x 15' Spent Fuel Assembly 1400 5'
Approx. 55 l ' x l ' x 15 '
Question #3:
f What are the dimensions and weights of the spent fuel casks that are or l
will be used at your facility?
Response
At' this time, no decision has been made on the type of spent fuel cask that will be utilized at FNP. However, as stated in the FSAR, the spent fuel cask crane has a 125-ton design rated load capacity which is capable of handling any currently licensed spent fuel cask.
Question #4:
i Identify any heavy load or cask arop analyses performed to date for your i
facility. Provide a copy of all such analyses not previously submitted to the NRC staff.
4
Response
FSAR Section 9.1 presents the des.;n of the single failure proof spent fuel cask crane utilized at FNP. The use of a single failure proof l
crane eliminates the rLauirement to analyze the damage created by a cask drop accident.
- Question *5:
Identify any heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved.
. Identify what equipment could be affected in the event of a heavy load 3
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Question #8:
Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.
Response
'The procedures listed below limit, instruct, or test objects moved or devices used to move objects over the reactor core or the spent fuel pool.
FNP-1-FHP-5.13 Manipulator Crane FNP-0-FHP-5.18 Spent Fuel Bridge Crane FNP-1-FHP-5.4 Spent Fuel Handling Tool FNP FHP-7.0 Limitations and Precautions for Handling Fuel Assemblies Reactor Vessel Head Removal and FNP-1 -MP-1.8 a.
- /
Installation g.f Internals Lifting Rig Procedures FNP-1-MP-1.9 FNP-0-MP-ll.4 i Reactor Polar Crane - Operating Instructions FNP-1-STP-601.0 Manipulator Crane Cutoff and Load Test It is the policy of Alabama Power Company to make procedures available at the Farley Nuclear Plant for review. The above listed procedures are, therefore, not attached.
Question #9:
Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December,1975) regarding Spent Fuel Storage Facility Design Basis.
Response
Conformance to Regulatory Guide 1.13, Revision 0 is discussed in FSAR Appendix 3A. The design complies with the revised position of Regulatory Guide 1.13, Revision 1.
3 handling accident (piping, cabling, pumps, etc.) and discuss the feasibility of such an accident affecting this equipment.
Describe the basis for your conclusion.
Response
The path of the spent fuel cask as it is transferred to and from the building (shown on FSAR Figure 9.1-16) passes over the spent fuel pool
-cooling system pumps, heat exchangers, and associated piping.
Possible damage to this equipment due to a postulated cask drop accident was eliminated by the use of a single failure proof cask crane.
Inside the containment, heavy loads, i.e., the reactor vessel head and internais are moved to the Elev.155' operating deck and into the refueling cavity respectively during refueling or maintenance.
During refueling, RHR system operation is required to cool the core. This piping is protected from load drops by the Elev.155' concrete floor.
Question #6:
If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to uncover the spent fuel.
Describe the basis for your conclusions.
Response
The spent fuel cask crane is prohibited from carrying loads over the scent fuel pool.
This physical design, coupled with the use of a single failure proof cask crane, eliminates the potential for a cask crane load drop into the spent fuel pool. A load carrying accident inside the containment, which could possibly create severe leakage from the refueling canal, would not result in a loss of water from the reactor vessel nor uncover the fuel in the reactor vessel.
Question #7:
Describe any design features of your facility which affect the potential for a heavy load handling accident involving spent fuel, e.g., utilization of a single failure-proof crane.
Response
The design of the FNP single failure proof spent fuel cask crane is de-scribed in FSAR Section 9.1.
._.