L-82-514, Forwards Inservice Insp Relief Requests 6 & 7,originally Transmitted 790918 & Clarified W/Addl Info,In Response to NRC 820316 & 0614 Requests
| ML17341B509 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/18/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-82-514, NUDOCS 8211230412 | |
| Download: ML17341B509 (19) | |
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REGULATORY IN RMATION DISTRIBUTION SYST
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AGGE'SSION NBR:8211230412 DOC ~ DATE: 82/11/18 NOTARIZED:
NO FACIL:50 250 Turkey Point Planti Unit 3i Florida <<Power and Light 'C 50 251 Turkey Point <<I'lanti Unit 4i Florida, Power and Light C
AUTHiNANE AUTHOR AFFILIATION UHRIGiR~E ~
Florida Power 5 Light Co.
REC IP, NAt]E RECIPIENT AFFILIATION EISENHUTiD,G ~
Di,vision of Licensing
SUBJECT:
Forwards inservice insp -relief Requests 6
8 7 originally transmitted 790918 5 clarified w/addi iqfoqin response to NRC 820316 8
0614 requests, DISTRIBUTION 'CODE!
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OX 14000, JUNO BEACH, FL 3340B FLORIOA POWER & LIGHTCOMPANY November 18, 1982 L-82-514 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dea r Mr.
Ei senhut:
Re:
Turkey Point Units 3 5 4 Docket No. 50-250 5 50-251 Inservice Inspection Relief Request Please find attached relief requests 6
5 7 originally transmitted by L-79-261 dated September 18, 1979 and clarified with additional information in response to your questions of March 16, 1982 by L-82-245 dated June 14, 1982.
These requests are being transmitted following discussions with your staff.
Very truly yours, o rt E. Uhrig Vice President Advanced Systems 5 Technology R EU/J EM/mvt Attachme nt s cc:
Mr. James P. O'Reil ly, Region II Mr. Harold F.
Rei s, Esquire 821 f2304i2 8211 18
'PDR ADOCK 05000250 GPDR
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FLORIDA POWER & LIGHT COMPANY Turkey Point Unit No.
4
'RELIEF REQUEST NO. 6/7 A.
Com onent Classification:
Class 1
Code Examination Category 1)
B-L-1, (Item No.
B5 ~ 6) 2)
B-L-2, (Item No. B5.7)
B..
Examination Re uirement:
1)
Code Item No. B5.6 - Volumetric.examination, to include 100% of pressure retaining welds, of one pump in each group of pumps performing similar functions in a system.
The examinations shall be performed during each inspection interval, and maybe performed at or near the end of the inspection interval.
2)
Code Item No. 'B5.7 Visual examination. of the 'interval pressure boundary surfaces on one pump in each of the group of pumps performing similar functions in the system during each inspection interval.
The examinations maybe perform d at or near the end of the inspection interval.
C.
Relief Re ues ted:
Reactor Coolant 'Pum (s
In lieu of Volumetric Examinations, Florida Power 8 Light Co.
proposes to perform:
1) 100% visual examination of the external surfaces only of one pump casing welds to the extent and, frequency of Examination Category B-.L-2.
2)
Partial surface examination. of the external casing weld {s) of only one pump, conditions permitting - to the frequency of Examination Category B-'-2.
D.
Basis for.Relief:
1 1)
State-of-the-Art Ultrasonic Techniques have not. been developed to meet the Code requirements.
In the event that an ultrasonic examination technique is developed that meets the Code requi rements, the i ntent of the Code will"be followed.
Florida Power 8 Light Company has representation on ASNE Code committees, and keeps abreast of, State-of-the-Art developments in all aspects of nondestructive examination methods in the industry.
Oi
~ ~
I
Turkey Point Unit No.
4 RELIEF REQUEST NO; 6/7 2) 3)
4)
Radiographic examination is not possible without the complete disassembly of'he pump (see figure I).
To perform this examination, large expenditures of manhours and man-rem are required with essentially no compensating increase in plant safety.
Based on actual data compiled from the radiographic examination of the Turkey Point Unit No.
3 reactor coolant pump casing welds and'isual examination of the internal pressure boundary surfaces on one pump, in excess of 5900 man-hours and 46 man-rem exposure was expended in the disassembly, examinations and reassembly of the pump.
These examinations are conducted under somewhat adverse conditions which have far reaching effects as depicted in Figure 2 thru Figure 5.
There is a very low probability, based upon industry experience, to disassembly pump(s) for maintenance purposes.
There is no requirement by the pump manufacture (Westinghouse) to disassemble the pump('s) as part of normal maintenance or inspection.
Accordingly, Florida Power 5 Light Company's procedures do not require disassembly of the pump(s) for maintenance. of inspection purposes.
There are no reported failures within the pump casings with these model pump(s).
It's note worthy to mention that removal of the pump impeller does not provide access to the casing internal surfaces which would still prohibit the inspection (visual and volumetric) of the pump to Code requirements.
See Figure I for items to be removed for Code ISI examination compl iance.
Florida Power 5 Light Company feels that adequate safety margins are inherent in the basic pump design.
The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime.
The reactor coolant pump casing material.,
cast stainless steel (ASTH A35I'F8g)., is widely used in the nuclear industry and has performed extremely well.
The presence of some delta ferrite (typically 51 or more) substantially increases resistance to intergranular corrosion. and stress corrosion cracking.
The delta ferrite also results in improved resistance to pitting corrosion.
5)
Florida Power 5 Light Company feels that the sati s factory inspecti on results achieved in February 1982 (See D.2), coupled with the same inspections conducted by three (3) other utility company's and employing the same manufactures model
- pumps, provides additional assurance as to the pump's casing integrity.
i'
Turkey Point Uni-t No.
4 RELIEF RE/VEST NO. 6/7 E.
Alterna te Exami na tions:
1)'anufacture' Shop Radi ographs, ASME Secti on III.
2)
Hydrostatic Tests, ASME Section XI.
3)
Surface Examinations, ASME Section XI.
4)'isual Examinations, ASME Section XI.
5)
The extent of surface coverage to be achieved, and the, alternate exami,nations and tests,,provide assurance of an acceptable level of quality and safety.
F.
Im,l'ementati on Schedule:
At or near
-the end'f the Inspection Interval.
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