ML19339A887
| ML19339A887 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/14/1976 |
| From: | French J YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19339A886 | List: |
| References | |
| WYR-76-95, NUDOCS 8011050644 | |
| Download: ML19339A887 (3) | |
Text
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h to Telephons 617 366-9011 TWX 7s0-390 0739 YANKEE ATOMIC ELECTRIC COMPANtegulatory Docket Elle
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20 Turnpske Rood Westborough, Mossochusetts 0158
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September 14, 1976
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United States Nuclear Regulatory Commission u5 h d >,/yf Washington, D.C. 20555
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License No. DPR-3 (Dockii ho. 50-29)
Reference:
(a)
(b) YAEC letter, DJS to DEV, dated March 6, 1974.
YAEC letter, DEV to DOL, dated September 13, 1974.
(c)
YAEC letter, LHH to DOL, dated November 5, 1974.
(d)
YAEC letter, LHH to DOL, dated January 13, 1975 N l g' (e)
NRC letter, KRG to GCA, dated February 7, 197
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YAEC letter, JLF to DOL, dated March 31, 197
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YAEC letter, JLF to DOL, dated March 3,197 2/
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(i) NRC letter, RAF to RHG, dated May 3, 1976. 2 sgp 20BB >
z,q (j) YAEC letter, JLF to NRR, dated May 17,197e g (k) NRC letter, AS to RHG, dated August 5, 1976
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Dear Sir:
I C3 Ynnkee Atomic Electric Company was requested in Reference (b) to from a dropped spent investigate the consequences which could result The results of our investigation were sunnitted fuel shipping cask.
in References (c), (d), and (e), and provided all of the information During a meeting with your staff on that was available at the time.
Yankee' discussed its previous submittals and agreed January 22, 1975, to investigate the f easibility. of incorporating a number of design f eatures into the Yard Crane modifications.
Subsequent to that meeting, Reference (f) requested Yankee to cubmit the details of the Yard Crane 28, 1975.
In Reference (g), Yankee indicated modifications by March that the feasibility of the proposed modifications was still being Details of the modifications were submitted as a point by evaluated.
point response to Branch Technical Position APCSB 9-1 in Reference (h).
Reference (i) requested additional information concerning the proposed That information was submitted in Reference (j).
That information is attached modifications.
Reference (k) requested further information.
to this letter.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
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J.L. French y~
Manager of Operations lam Kg,g 8011050
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ADDITIONAL INFORMATION YARD CRANE MODIFICATIONS
. YANKEE NUCLEAR POWER STATION (YANKEE - R0WE).%. g N DOCKET NO. 50-29
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.T G-q" 1.A. NRC OUESTION Your proposal to employ only administrative controls for limiting spent fuel cask crane movement while handling critical loads is not acceptable.
We will require control devices which, as a minimum, will activa.e an audible alarm when the crane violates the safe travel path boundaries Therefore, established for critical load (spent fuel cask) handling.
provide a discussion on the control devices you will use to Include the number, type, and location of as the spent fuel cask.
Discuss any administrative controls and how they will function.
procedures to be used and how they will be used in conjunction with the control' system.
B. YAEC RESPONS__
E Control devices will be installed which in conjunction with administrative procedures will prevent spent fuel cask movement over stored fuel.
the spent fuel cask At Yankee Rowe, the Yard Crane is used to transport from the area between spent fuel pit and the decontamination building (north of the spent fuel pit) to the north side access hatch of the spent fuel pit roof where it is lowered into the cask loading area of the pit.
The cask loading area encompasses about 25 percent of the pit floor The area south of the cask loading area is used space on north side.Af ter the cask has been loaded, the Yard Crane retrieves the cask through the roof hatch and carries it in a northerly for fuel stcrage.
direction (opposite to the direction required for povement over stored fuel) for decontamination and shipping.
Limit suitches will be used which will sound audible alarms if the the point at which the cask is icwered operator drives the bridge past Limiting through the north side access hatch of the spent fuel pit.
bridge novement to the area north of this point will prevent cask movement The switches will be the proximity type with the over stored fuel.
proximi:y sensors located on the bridge and the actuating bracketsThe located on the bridge rails.
will be redundant.
The cask handling procedure will require that the alarm system is tested before handling _the spent fuel cask by actually driving the bridge to the If the alarm sounds during point at which the alarms should sound. actual cask handling 3
h immediately stop bridge motion and then direct t e direction away from the area over the stored fuel.
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SiON DOCKET NUM;E R 50-29
- a. x, NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL
'TO: NRC FROM: Yankee Atomic Elec. CO.
DATE OF DOCUMT *.
Westborough, Mass. 01581 9-16-76 R.H. Grece DATE RECDVED 9-20-76
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