ML20024F583
| ML20024F583 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/02/1983 |
| From: | Kanga B GENERAL PUBLIC UTILITIES CORP. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| 410-83-L-0205, 410-83-L-205, NUDOCS 8309090493 | |
| Download: ML20024F583 (5) | |
Text
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GPU Nuclear Corporation U Nuclear m' age 8:48 S
Middletown. Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:
September 2,1983 4410-83-L-0205 TMI Program Office Attn:
Dr. B. J. Snyder Program Director US Nuclear Regulatory Commission Wash!ngton, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Polar Crane Additional Information Attached for your review and approval is additional information intended to supplement that provided to you in GPUNC's letter 4410-83-L-0175 from Mr. B. K. Kanga to Dr. B. J. Snyder dated August 16, 1983. This letter provides additional input to Questions 1, 3, 10, and 11 from your letter to Mr. B. K. Kanga dated July 18, 1983. Supplemental information on crane travel limits is also provided.
If you have any questions or desire further information, please contact Mr. J. J. Byrne of my staff.
Sincere y, B. K. Kanga Director, TMI-2 BKK/RBS/jep Attachment CC:
Mr. L. H. Barrett, Deputy Program Director'- TMI Program Office I \\
8309090493 830902 PDR ADOCK 05000320
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P PDR GPU Nuclear Corporation is a subsidiary of the Gen
' Public UtMties Corporation
I PCLAR GANE LOAD TEST - StPR.LM:NTAL INFORt4T10N
- (The numbering corresponds to that used in the response to the NRC letter of July ~18,1953)
ITEM 1 (page 4) '
Approximate weights of kr;own heavy lifts made by the polar crane are stated below:
'(Weights in Tons)
Pressurizer 15 2 Core Flood Tanks 39 Reactor Coolant Piping (Inlet Piping) 112 (C1Jtlet Pipiry) 105 Reactor Coolant RJmps 56 Reactor Loolant Pump Motors 51 P&H Electric H/draulic trane (75T capacity) 25 R.V. Head tw/o Service Structure) 81
>R.V., Service Structure (Bare) 17
' Upper R.V. Internals w/shippiry canisters 55
-Lower R.V. Internals w/ shipping canisters 110 R.V. head, Service Structure, WLM cssemblies
- 146 Missile Shields - (Reactor Vessel) 40 (Pressurizer)
.These lif ts were made generally during initial plant construction ano start-up. -
Not includirg the 6 ton tripod liftirg assembly, which would brity the total weight on the hook to approximately 152 tons.
ITEN 3 (page 7)
The corrective action taken as a consequence of the Quality Deficiency Paport (LDR) regarding administrative issues of the polar crane refurbishnent program are delineated as follows:
Corrective action was taken in three areas. First GPU Iesponded to Quality Deficiency Report No. LHi-11-83 by statirg that all future plant modifications would be made via the applicable lhit 2 procedures.
Second, the software program for irecontainment work has been revised to eliminate use of or reference to Work Packages ano/or Work Packages attached to Unit Work Instructions. Sirce receipt of the IJJR, all wurk has been done in accordance with approved Unit Work Instructions per GPU Unit 2 procedures.
4 Thirdly, corrective action was taken to identify documentation of modifications that were performed without the fully approved ergineeriry documents.
For each modification, Design Engineerity icentified the approviry Engineering documents as follows:
Work Package Design Engineeriny Remons_e M-0024 ELM's will not be backfittea for polar crate (Installation of refurbistynent. Sufficient " design documents" were Jib Lrane) attachea to DERG-0002 for D.E. to approve the jib crane installation.
No design drawirys are needed.
E-0046 Same response as for M-0024 for ELN.
D.E. reviewed (Pendant, Cable, and approved with comments the field purchase Festoon Lable) requisitions for the materials per DLSE-0028.
Itwever, subsequent fielo installation did not agree with field FR and no prior approval was requested of D.E. by PLTG. Subsequently, D.E. reviewed and approved with comments the installation as part of an in@ection report per DERO-0070. Design drawing 2-EOR-1302 was updated (Rev.1).
E-0055 & E-0059 Same response as for N-0024 for ECM. Drawirg (Trolley Power /
2-LOR-1302 was issued for the installation ano Control Bypass) subsequently included in work packages E-0055 and E-0059. Both work packages were reviewed by D.E. per DE5E-0032 and DESE-0029, Iespectively.
E-0037 The correct title for work package E-0037 is Polar (Polar Crane Crane Bridge Control Functional Test which was Control Labinets) reviewed and approved by Design Lngineering per DESE-0012. No further engineering action required.
No oesign drawing needs to be upoated.
ITEM 10 (page 13)
A discussion of non-oestructive examinations as well as visual and dimensional c3 %Imance checks perfoImed on the load test assembly structural 1.Lewats is presented in the report entitled Polar Crane Load Test Ac;:. 2Qt aluation forwarded under separate cover. Especially pleast n lyr '
Issues 3, 6, and 8.
(.
g ITEM 11 (page 14)
A quantitativa dose estimate for performing the load test and a comparison of it to dose estimates associateo with a load test which includes optional activities suggested (but not required) by ANS1 B30.2 is presenteo below. A dose estimate comparing the load test frame to ANSI N14.6 is presented as well.
The dose estimate for the proposed
- load test is approximately 30 man The dose estimate for performance of a test that includes optional rem.
activities suggested (but not required) by ANSI B30.2 ranges from 84 man-rem up to 97 man-Iem.
The reason for the exposure rartje span of 13 man-rem is that the test load may have to be supplemented by as much as 13 tons (which equates to 13 man-rem) in cruer to meet the minimum test load suggesteo by At61 B30.2.
This is due primarily to uncertainties regarding the exact weight of the missile shields which comprise the bulk of the test load weight.
Test elements and their dose estimates are as follows:
- Non-oestructive Testirt; (NbT) Main Hook 4.5 man-rem 50 Ton Load Test 50.0 man-Iem NDT of Main Hook 4.5 man-rem
- 200 Ton (Minimum) Load Test 20.5 man-Iem
- NDT of Main Hook 4.5 man-rem 84 man Iem 13 ton contingency 13 man-rem 97 man-rem Note that exceptions are taken to full travel of bridge and trolley with test load suspended. These exceptions are taken for prudent safety reasons, ie., driving the test load over the incore seal table is not considered prudent or safe hence, man-rem exposures for these activties have not been estimated.
A quantitative dose estimate comparing the load test frame presently in the reactor building with ANSI N14.6 is as follows:
Man-Rem Decontamination of frame ano preparation for 1-2 removal from reactor building Remove frame 10-11 (At this point, the frame could conceivably be reassembled, tested to 1506, and examined with no expenditure of man-rem)
Replace frame in reactor building 10-11 21-24 M
M l
It should be noted that this evolution would waste the 10.5 man-Iem already expendeo in placing the frame in the reactor bulloiry at elev.
347 where it now Iests.
HUDITIONAL INFORmTION ITEM A The polar crane load test SER, as amenced, clearly defines areas in the teactor building which have been analyzed and determined to be safe.
The polar crane operating procedure requires that all load movements (including the unloaoed hook / block) be restricted to these areas.
Lompliance with the operating procedure statements regaruing load movements will be ensured by trained operating personnel making visual comparisons between the boundaries of the analyzed safe area ano the actual physical position of the loads.
Notwithstanding the above, a system of visual markers will be placed inside the reactor building to alert the operator that the bridge is approachirt an area of limitation and that caution should be used in movement of the tIolley lest a load be moved into an especially hazardous are a.
Furthermore, it should be noted that the safety of load movement cepenas tpon staying within an analyzed area and not Lpon a specific, precise path within the area. Accordingly, the load path orawirth presented in ammendment 1 to the SER are intended to show approximate and general travel paths for specific loads, and should not be construed to represent precise lines of movement. !
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