ML20101M599
| ML20101M599 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/02/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-92-2077, NUDOCS 9207080302 | |
| Download: ML20101M599 (2) | |
Text
-.
J MNQQIgf GPU Nuclear Corporation Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 I
TELEX 84 2386 Writer's Direct Dial Nurnber:
(717) 948-8005 July 2, 1992 C311-92-2077 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
ihree Mile Island Nuclear Station, Unit 1 (TMI 1)
Operating License No. OPR-50 Docket No. 50-289 Spent Fuel Pool Rerack This letter ct. firms the substance of a teleconference between GPUN and the NRC staff on.May 21, 1992, regarding clarification of the NRC Safety Evaluation Report
- iR) for Technical Specific & tion Amendment No.164, issued April L. 1992. The following describes the GPUN clarifications noted and discussed
1.
Use;of divers - SER Page 4 states that the use of a diver is not planned at this time.
It was clarified that although this statement was consistent with the original plan, as stated in the Rerack Licensing Report (HI-89407), subsequent inspection of the existing rack structural connections has confirmed that divers will be required.
HOLTEC's evaluation has confirmed that use of divers will result in lower exposure to the crew as compared to using long handled tools to remove bolts and other interferences.
It was also indicated that GPUN F id completed the radiological review for the use of divers and had confirmed that the total person-rem projected for the entire project remained between the originally estimated 3-10 person-rem.
mm
-ggg 2.
Boral Blackness Test - SER Page 7 states that surveillance coupons bo containing Boral and blackness testing of Boral panels will provide time-
,;$2.
pool. It was clarified that the blackness test is only being performed as related informatien of the actual behavior of Boral in the spent fuel r
So l tw an initial test after rack installation and that this test provides a l SQ' 88; baseline for future analysis of the neutron absorbing capability of the Boral. The coupon program will provide the time related information which
, to will detect potential degradation. Blackness testing could be utilized in l om the future to confirm any potential Boral degradation detected through the lgg.
coupon surveillance program.
A{
0 k,j Q (J O [ 1 GPU Nuclear Corporation is a subsidia / of General Puchc Utikties Corporation
C311-92-2077 Page'2 3.
FHB Crane Inspection and Maintenance - SER Page 11 states the licensee plans to relubricate the moving parts of the fuel handling crane prior to the start of reracking.
Finally, the licensee plans to load test the crane prior to use in reracking. It was clarified that only the FHB crane daily / monthly inspection will be performed if the yearly inspection was performed less than 6 months ago. If the crane was inspected 6 months ago or lenger, the yearly inspection will be performed. Both inspections are performed in accordance with Preventive Maintenance Procedure E-14. Gear box oil levels are inspected as part of the daily / monthly inspection and the yearly inspection requires checks, samples, analysis, and replenishing of lubricant as needed. It was also clarified that the FHB crane (110 ton capacity) is not subject to periodic load tests and need not ba load tested prior to its use in the rerack project.
The special lift rig designed for rack handling will be load tested prior to use for the rerack project and prior to future use /$ase 2 rerack) following long-term storage.
4.
Heavy Loads Handling - SER Page 17 implies that the heavy load handling system may be considered single-failure proof. It was clarified that the FHB crane, rack lifting devices, and 40 ton intermediate boist are not classified as single-failure proof (with the exception of the special rack lifting rig), but satisfy the alternate criteria using ultimate strength as defined in GPUN letter C311-92-2054, dated April 24, 1992.
5.
Spent Fuel Pool Cooling - SER Page 18 states that the licensee intends to operate the SFP cooling system with two trains which will result in a maximum SFP bulk coolant temperature of 129.7 F.
The NRC's concern was that the 158.4 F calculated for normal batch discharge into a fully loaded pool and on? SFP cooling train in operation could be a long-term condition and potentially result in concrete dearadation.
It was clarified that normally one train of SFP cooling
's in operation and that the determination to place two trains of SFP cooling in operation is based on the temperature demand of the SFP.
Two trains of SFP cooling would be placed into operation under such circumstances to precluce a long-term SFP adverse temperature condition from occurring.
GPUN is proceeding with instaliation of the new spent fuel pool storage racks based on the clarf fications noted above. As a result of our discussion with NRC on May 21, 1992, GPUN concludes these clarifications do not affect the SER conclusions.
Sincerely, h5 kk T. G. Brou ton Vice President and Director, TMi-1 DJD/amk 4
cc Region I, Administrator TMI-l Senior Resident Inspector TMI-l Senior Project Manager