ML19309F916
| ML19309F916 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/11/1980 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8005010638 | |
| Download: ML19309F916 (6) | |
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April ll, 1980 Docket No. 50-213 LICENSEE: Connecticut Yankee Atomic Power Company (CYAPC0)
FACILITY: Haddam Neck Plant
SUBJECT:
SUMMARY
OF MARCH 27, 1980 PHONE CONVERSATION REGARDING THE MOVEMENT OF A SPENT FUEL CASK INTO THE SPENT FUEL P00L A conference telephone call as held on March 27, 1980, between members of the NRC headquarters staff and tne licensee's staff to discuss movement of a spent fuel cask into the Haddam Neck spent fuel pool. A list of the participants is included as Attachment 1.
On March 21, 1978, the licensee submitted a proposal to delete (from.the Haddam Neck Technical Specifications) the prohibition of spent fuel cask movement over his spent fuel pool. This prohibition was added by Amendment No. 7 on June 8, 1976, in conjunction with a change which authorized an increase in the fuel storage capability of the spent fuel pool. The staff had not acted on this request pending completion of generic task A-36, " Control of Heavy Loads".
However, the licensee recently informed us that he would like to ship several failed fuel elements from Haddam Neck to Battelle Laboratory for analysis in April 1980 before his next refueling outage, and therefore, requires evaluation of their March 1978 proposal in order to bring a spent fuel cask into the spent fuel handling buflding and lower it into the pool.
The task group which is considering the control of heavy loads as a generic issue was given this request to review for technical acceptability. This group studied the licensee request and identified several areas in which they needed further information to complete the evaluation.
The licensee was supplied with a list of the NRC staff's questions (Attachment 2) prior to the conference call.
All items in Attachment 2 were discussed, and the licensee agreed to provide additional details as listed below.
1.
The licensee will provide copies of. analyses done to verify the structural integrity of the fuel pool in the event of a cask drop. The licensee stated that analyses done for plants with fuel pools of similar design showed that the pool would not be significantly damaged by the dropping of a 100 ton cask. The NRC staff would like to know the basis and assumptions made by these other analyses and a comparison to the features at Haddam Neck.
& 2.
The licensee will use an NAC-1 cask. He will determine if the yoke is redundant and single failure proof and will investigate the availability of a single failure proof yoke.
3.
The licensee gave a value.of 2800 lbs. as the rating of the fuel cask cover lifting spider. He will verify that this rating is the design rating and not the ultimate rating.
4.
The licensee will send the NRC a detailed drawing of the fuel pool area, including the locations of all spent fuel assemblies and seismic restraints.
The drawing will also diagram.the load path of the cask, and the orientation of the cask trunion as it traverses the load path.
5.
The licensee will verify and document to the NRC staff that procedures satisfying staff criteria will be used for the movement of the cask and will verify and document the training of the crane operators in accordance with ANSI B30.2-1976.
6Property "ANSI code" (as page type) with input value "ANSI B30.2-1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
The licensee will verify that the cask handling yoke complies with ANSI N14.6-1978 and will send us a copy of the detailed analysis for the yoke.
7.
The licensee will verify and confirm that the crane used for handling of the cask has been maintained and inspected IAW ANSI B30.2-1976, and that positive motion stops or interlocks are installed to prevent improper movement of the crane used for handling the floor hatch cover, i
8.
The licensee has not completed his. evaluation of the design of the crane in comparison with ANSI B30.2-1976. When this is complete, he will for-ward it to us for review.
i 9.
The licensee will ify and document that there will be no fuel elements in the pool with U concentrations greater than 4 w/o. This is to ensure that an inadvertant criticality will not occur due to crushing and a change in fuel geometry if the cask were to drop.
The licensee indicated that he would provide the requested information quickly in order to allow the staff to complete its review.
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.,.i Ralph aruso Operating Reactors Branch #2 Division of Operating Reactors Attachments:
As stated cc w/ attachments:
See next page
. cc w/ attachments:
Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region I Office Hartford, Connecticut 06103 ATTN:
EIS C0ORDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 Mr. James R. Himmelwright Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN:
Assistant Director Research and Policy Development Department of Planning and Energy Policy 20 Grand Street Hartford, Connecticut 06106 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
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DISTRIBUTION FOR 1 R TINGFSUMMARI'ES
- et 50-213 NRC PDR 50-213 Local PDR 50-213 H. Smith TERA SEPB Reading NRR Reading H. Denton E. Case L. Shao D. Eisenhut R. Vollmer W. Russell
- 3. Grimes T. Carter T. Ippolito R. Reid G. Knighton V. Noonan A. Schwencer D. Liemann D. Crutchfield G. Lainas J. Scinto, GELD Ol&E (3)
ACRS (16)
Licensee Mr. W. G. Counsil NRC Par.ticipants D. kneth*fstall, KMC KMC R. Schaf R. Silver T. Wambach R. Caruso H. George H. Shaw F. Clemenson T. Murray, CYAPC0 R. Eppinger, CYAPC0 J. Radder, CYAPC0 A. Puri, CYAPC0 M. Pitek, CYAPC0
ATTACHMENT 1 LIST OF ATTENDEES NRC R. Caruso H. George H. Shaw F. Clemenson CYAPC0 T. Murray R. Eppinger J. Radder A. Puri it. Pitek i
ATTACHMENT 2 HADDAM NECK CASK HANDLING OPERATIONS 1.
Indicate whether a failed-fuel container will be used for movement of the damaged fuel.
If it will be, describe the path to be followed and extent to.which staff positions 1 through 5 of Enclosure 2 will be satisfied for movement of this container.
2.
Identify the model cask that will be used for shipment of the fuel.
3.
a)
Identify the weight of the. hatch cover that is moved to the roof to allow handling of the cask.
b)
Identify where this load is stored on the roof.
4.
a)
Identify the weight of the spent fuel cask cover.
b)
Identify the crane used for handling thic cover, and the defined safe load path for its movement.
5.
Identify what safety-related equipment (including cabling) is located in the area below the location where the spent fuel cask is loaded onto the transfer buggy.
6.
The response to Question 1 contained in the May 14, 1974 letter from Connecticut Yankee makes reference to analyses docketed for other plants.
Describe the assumptions and approach used for the reference analysis and by whom that analysis was made.
Describe the similarity of the assumptions made for that analysis and the working conditions in the Haddam Neck plant.
7.
Verify that procedures are developed and followed for the proper i adling of the spent fuel cask and related heavy loads (such as the hatch cover or the spent fuel cask cover), and that these procedures include:
identi-ficatie, of proper equipment and components for performing these operations; required inspections before movement of the load and related acceptance criteria; the steps and proper sequence to be followed in handling the load; definition of the safe load path; and special precautions.
8.
Verify that operators that will handle the cask and related heavy loads are trained and qualified, prior to handling these loads, and conduct themselves in accordance with Chapter 2-3 of ANSI B30.2-1976, " Overhead and Gantry Cranes".
9.
Verify that the yoke used to handle the cask satisfied the guidelines of ANSI N14.6-1978; however, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be impartea on the handling device based on the character-istics of the crane which will be used.
- 10. Verify that the slings or handling devices used for movement of the hatch cover and spent fuel cask cover'(if different from the cask yoke) are installed and used in accordance with ANSI B30.9-1971, " Slings".
. 11. Verify that the crane (s) used for handling of the spent fuel shipping cask and related heavy loads are inspected, tested, and maintained in accordanca with Chapter 2-2 of ANSI B30.2-1976, with the exception that tests and inspections should be performed prior to use where frequency of crane use for these loads is less than the specified inspection and test frequency.
- 12. Verify that.the crane design satisfies the guidance of ANSI B30.2-1976, Chapter 2-1.
Provide justification for those provisions that are not met.
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