ML17219A704
| ML17219A704 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 07/16/1987 |
| From: | Tourigny E Office of Nuclear Reactor Regulation |
| To: | Woody C FLORIDA POWER & LIGHT CO. |
| References | |
| TAC-65587, NUDOCS 8707250027 | |
| Download: ML17219A704 (6) | |
Text
~
~4' Ce g July 16, 1987 Docket No. 50-335 Mr. C. 0.
Woody Group Vice President Nuclear Energy Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408 DISTRIBUTION NRC PDR Local PDR PD22 Rdg.
S.
Yarga G. Lainas D. Miller E. Tourigny OGC-Bethesda E. Jordan J. Partlow J. Ridgely ACRS (10)
Gray File
Dear Mr. Woody:
SUBJECT:
RE(UEST FOR ADDITIONAL INFORMATION (TAC NO. 65587)
In conducting our review of your June 12, 1987 submittal relating to expanding the spent" fuel pool storage capacity at the St. Lucie Plant, Unit No. 1, we have determined that we will need additional information identified in the enclosure to continue our review.
, In order for us to maintain our review schedule, your response is requested within 45 days of your receipt of'his letter.
We are also prepared to meet with your staff to discuss the responses to expedite our review.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Please contact me at (301) 492-9786 if you have any questions concerning this letter.
Sincerely,
/s/
Enclosure:
Request for Additional Information E.
G. Tourigny, Senior Project Manager Project Directorate II-2 Division of Reactor Projects-I/II cc w/enclosure:
See next page DM er 7/~)/87 PM:PD2~ 0 ETourignyc:hc LRubenstein 7////87 7/ IG/87 0027 8707 fg -,,n R
ADQCN 05000ggs.
t',
I PDR
~
~
M 4
M I'I '
44 I
A I ~
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL CAPACITY EXPANSION ST.
LUCIE UNIT 1 DOCKET NUMBER:
50-335 2.
3 ~
4 ~
5.
6.
7.
In the June 12, 1987 submittal, Table 3-11 specifies the coolant flow rate for the spent fuel pool cooling systems to be 3560 gpm.
Indicate whether this is the flow rate with one spent fuel pool cooling system pump running or with both pumps running.
The submittal specifies that the spent fuel pool cooling system consists, in part, of two spent fuel pool cooling system pumps and one heat exchanger.
Since all heat exchangers require maintenance at some point in time, it is not clear how the spent fuel pool will be cooled during the time that the single spent fuel pool cooling system heat exchanger is out of service for maintenance.
Provide a discussion of how the spent fuel pool is cooled and the temperature is maintained below the Technical Specification temperature limit for the following conditions:
I)
The heat exchanger is out of service for plugging of failed tubes.
2 The heat exchanger is out of service for cleaning of the tubes.
3 The heat exchanger is out of service for replacement.
Provide a drawing (or drawings as necessary) which shows the arrangement of the spent fuel pool cooling system piping fn and around the spent fuel pool.
Page 4-28 states that the fuel assembly drop accident was evaluated with the dropped assembly being positioned 36 inches above the top of the spent fuel storage racks.
It is not clear that this represents the maximum height that the fuel assembly will be carried over the spent fuel storage racks.
Specify the maximum carrying height for fuel assemblies within the spent fuel pool area and discuss the physical design features which prevent a fuel assembly from being carried higher than the specified height, or verify that the fuel assembly drop accident analysis is bounding by assuming total failure of all effected fuel assemblies.
Provide drawings which show the movement of both the existing and the new racks throughout their entire path of travel from outside of the fuel handling building until their final location in the spent fuel pool (and the reverse for the existing racks).
For each step in the replacement of the racks, provide drawings which show the location of the spent fuel and the movement of the fuel which demonstrates that no heavy load will be carried over spent fuel or over any rack which contains spent fuel.
{Note:
This information can be placed on the set of drawings provided in response to question 5).
Provide additional discussion on the temporary crane that will be used to handle the spent fuel storage racks within the fuel building.
As part of the discussion, specify I) whether the crane is single failure proof;
I
Mr. C. 0. Woody Florida Power 5 Light Company St. Lucie Plant CC:
Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.
NRC 7585 S.
Hwy AIA Jensen Beach, Florida 34957 State Planning 5 Development
~ Clearinghouse Office of Planning 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Harold F. Reis, Esq.
Newman E Holtzinger 1615 L Street, N.W.
Washington, DC 20036 Norman A. Coll, Esq.
McCarthy, Steel, Hector and Davis 14th Floor, First National Bank Building Miami, Florida 33131 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis, County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 Mr. Charles B. Brinkman, Manager Washington - Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue
- Bethesda, Maryland 20814 Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Executive Director for Operations 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323
- 2) whether the temporary crane will be carried over the spent. fuel pool; and 3) the load path that the fuel building crane will take to carry the temporary crane.
Provide drawings of the temporary crane and pertinent details which demonstrate the crane's compliance with the guidelines of NUREG-0612 and NUREG-0554. If the temporary crane is not single failure proof, provide the results of the analysis which demonstrates that the appropriate safety factors have been applied to the crane and that load handling by the crane will be in accordance with the guidelines of NUREG-0612.
8.
Provide drawings of the lifting rigs.
Verify that the lifting rigs are single failure proof and meet the guidelines of NUREG-0612.
9.
Assuming that a rack is dropped, provide a discussion of how it will be verified that no damage has been done to the pool liner, spent fuel pool cooling system piping in the spent fuel pool, or to other racks.
Assuming that the dropped load was the result of the lifting attachment, describe how you would provide a new lifting attachment that makes the liftsingle failure proof.
Provide a discussion of the potential splashing effects from the dropped rack on the loss of suction for the spent fuel pool cooling system and with respect to the effects on plant personnel in the area.