ML17340A752
| ML17340A752 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/17/1981 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102250336 | |
| Download: ML17340A752 (10) | |
Text
ACCESSION NBR:
FAGIL:50 250 50 251 AUTH BYNAME UHRIGP R ~ E ~
REL IP ~ NAME VARGAPS ~ AD REGULATORY NFORMATION DISTRIBUTION SY EM (RIDS) 8102250336 DOC ~ DATE 81/02/17 NOTARI ED NO Turkey Point Planti Unit 3s Florida Power and Light C
Turkey Point Planti Unit 4P Florida Power and Light C
AUTHOR AFFILIATION Florida Power L Light Co, RECIPIENT AFFILIATION Operating Reactors Branch 1
DOCKET 05000250 05000251
SUBJECT:
Forwards 'addi info re steam generator repairsiin response to NRC 810129 1,tr,Dlawing of steam generator leg assembly encl.
DISTRIBUTION CODE:
ABOIS COPIES RECEIVED:LTR Q ENCL+
SIZE:
TITLE: General Distribution for after Issuance of Oper ating License NOTES:
REC IP? ENT 10 CODE/NAME, ACT'ID'ARGAPSB 04 INTERNAI.
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EXTERNAL: ACHS ASIC 09 05 16 16 1
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J~fVv 1 ~4% W FLORIDA POWER BL LIGHTCOMPANY February 17, 1981 L-81-40 Office of Nuclear Reactor Regulation Attention:
Mr ~ Steven.A. Varga, Chi ef Operating Reactors Branch,81 Division of Licensing U.
S. Nuclear Regulatory Commission l<ashington, D.
C.
20555
Dear Mr. Varga:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and'0-251 Steam Generator Re airs Attached you will find Florida Power and L'ight Company's responses to the requests for additional information which were enclosed with your letter of January 29, 1981.
Please notify us if we can supply additional information.
Very truly yours, R.
E. Uhrig Vice President Advanced Systems 8 Technology REU/LFR/ah Attachment cc:
Neil Chonin, Esquire Norman A. Col,l,,Esquire Henry Harnage, Esquire Mark P.
Oncavage J.
P,. O'Rei lly, Director., Region II Harold F. Reis, Esquire Burt L. Saunders, Esquire 810 225 0 PEOPLE... SERVING PEOPLE
(1)
The drawing of the steam generator assembly SGRR figure 3.3-7 does not have dimensions of the steam generator assembly.
Provide the dimensions necessary to calculate the volume of the assembly.
~Res onse A drawing of the SGLA is attached with the necessary dimensions and the weight
.,written in.
PLAN 3 PLATE I2'- l0" l2.L2" STEAM GCNFRATOR 0I I
BRCAK LIME I
I b
ROUGH CV LINE FINAl CUT LINC s/
A/e//Aic ~tS',S I ~I/
JIC~QV= (a 't q g //
d( rr~kr = l D 7 m I2'0 Ci 0
C III rD 0
Z0 IV Ill u~.gL+ ~IN P4.ksss"0 T~~s
~ 0 /lAc c-~A'lJ 2: ( g.
SECTION 8
DET TOP CL I
I Co EXC.
GC'N CUT LINE SUPPORT LUG~i
~C,"'
II CD 0
I CP TITLE rTTOM BLOWOOWN ITTOM BLOWOOVIN IELL ORAIN NS RANGE LCVEl TAP ELEVATION SIZE CLOSURE DETAIL CLO'SURE MATERIAI ASTM A-3G I I
~
I rl SECTiON A
DE BOTTOM 0 XNOHOLE (SECCNOARV)
C" I.O.
XODHOl E {EECONOARV)
)P CUT OPENING 8T'TOM CVT OPENING G I.O, M/A M/A
~
~
(2)
The:number of workers given in the SGRR on p.
6-.1 is 300.
If that is not the total work force on the repair program, provide the total number of workers, i.e.,
anyone that is issued a film badge and, dosimeter.
~Res onse This number (300 workers) is not the total work force on the repair.
This is a conservative average daily number of people (both FPL and contractor) who may obtain some radiation exposure inside and outside containment.
Of these, approximately 190 are craft:personnel and 1-10 are supervisory, health physics, quality assurance/quality control, etc.
The total number of people who are issued a film badge and dosimeter is difficult to estimate with accuracy because there will be a turnover due to workers completing their assigned work and being no longer required, and to workers quitting or being discharged; In'addition, it is projected that some workers may reach their quarterly'adiation exposure limit, in which case they may be reassigned to work"not involving radiation exposures until the end of the quarter, or until they are again required after the end of the quarter.
Further, non-craft and management persons may be present on an irregular basis.
A rough approximation to the total number of'eople issued a badge and dosimeter during the repair of one unit can be calculated as follows:
It is assumed that the period for the repair of one unit is approximately 9 months working two ten-hour shifts per day, six days per week.
It is also assumed that, for the reasons indicated above, approximately 60 new persons are issued a badge and dosimeter during each 30-day period.
That is, after the first 30-day period, 360 persons would have been issued a badge and dosimeter, 420 persons after the second period, and so on.
This would result in a total, which we believe to be conservative, of '840 different workers issued a badge and dosimeter for work in connection with the repair of one unit.
(3)
The analysis of the drop of the steam generator indicated the maximum drop is 12 feet.
However, according to D-l-l of the SGRR the assemblies will be lowered into the storage facility which apparently has 22 foot high walls.
Clarify the apparent discrepancy.
~Res onse The analysis of the drop of the steam generator was provided in connection with our "Environmental Evaluation of Offsite Shipment of the Turkey Point Steam Generator Lower Assemblies",
which was submitted with our Letter L-80-364, R.
E. Uhrig to Steven A. Varga,.October 31, 1980, as revised by our Letter-80-386, R.
E. Uhrig to Steven A. Varga, November 21, 1980.
The 12 foot drops (at either the Turkey Point or. the Barnwell sites) discussed therein.are the maximum drops that can be postulated if the alternative is chosen to ship the steam generators offsite.
The possibility of accidents in connection with the onsite storage al.ternative was previously analyzed in the Steam Generator Repair Report, Section 3.4.7, "Accident Considerations Associated with Onsite Storage."
At the time this section was written, it was planned to build three walls and the floor of the steam generator storage compound (SGSC), slide the steam generator lower assemblies (SGLA's) into the
- SGSC, then build the fourth wall and the roof.
Consequently, no analysis of a drop was performed.
- However, we believe this approach may not maintain radiation doses to personnel as low as reasonably achievable (ALARA). Therefore, we presently plan, if the onsite storage alternative is chosen, to build all four walls and floor of the SGSC, lift the SGLA's into the
- SGSC, then install the roof.
The walls of the SGSC would be approximately 22 feet high.
(See p. D..l..l, Steam Generator Repair Report).
The probability of dropping an SGLA during such a lift is extremely low. If, nevertheless, we assume that an SGLA is dropped, the welds 'sealing the cover plates could be breached.
However, the extent of such a breach would be limited because the cover plates for the SGLA will be approximately three inches thick and they will then be attached with 13; inch fillet welds, and because the fill surrounding the SGSC is not an unyielding surface.
The doses at the Turkey Point North site boundary may be calculated, with large factors of conservatism, as follows:
It is assumed that the accident occurs approximately 80 days 'after reactor shutdown..
The proposed location of the SGSC is about 1,470 meters from the North site boundary, and the corresponding X/g is 1.66 x 10 4 sec/m3.
It is fur ther assumed that 15 of the activity within the SGLA escapes, becomes
- airborne, and floats (in the calm conditions inherent in the given X/g) 1,470 meters to the site boundary.
Under these assumptions, the resultant dose to the lung of a teenager standing for two hours"at the North site boundary would be approximately 138 millirem.
This is well below l,imits,for accidental releases.
~
~
Contention 5e refers to condenser retubing cost.
Page A-19-1 of the SGRR indicates that the main condensers have already been retubed with Titanium tubes.
,When was this done?
What was the cost?
Is there another
retubing of the condenser imminent?
~Res ense The total cost of retubing of, the condensers with titanium tubing was approximately
$8,000',000.
This was previously reported in our response to Intervenor's interrogatory 11-15.
The dates on which retubing was performed are as follows.
Turke Point Unit 3 Water Box A North Water Box B North Water Box A South Water Box B South Turke Point Unit 4 Outa e Dates Nov. 16, 1976 Jan.
20, 1977 Dec. 1, 1978 - Feb.
6, 1979 Nov. 24, 1977 - Feb.
17, 1978 Dec. 1, 1978 - Feb.
6, 1979 Outa e Dates Hater Box A North Water Box B North Water Box A South Water Box B South Aug. 13, 1978 - Oct. 5, 1978 Apr
. 18, 1976 June 10, 1976 Apr. 5, 1979 June 22, 1979 Apr. 26, 1980 - June 16, 1980 It is not expected that another retubing will be required in the foreseeable future.
Please note that the Licensing Board has numbered the pertinent contention as contention lie., not 5e.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of FLORIDA POWER AND LIGHT COMPANY (Turkey Point Nuclear Generating Unit Nos.
3 and 4)
Docket No. 50-250-SP 50-251-SP (Proposed Amendments to Facility Operating License to Permit Steam Generator Repairs)
CERTIFICATE OF SERVICE I HEREBY CERTIFY THAT copies of the letter of this date addressed to the members of the Board and the foregoing "Testimony of Frederick G. Flugger, Habib H. Jabali, and P.
K.
Wan Relating to Contention 4B" were served on the individuals whose names appear on the attached service list by deposit in the United States mail, first class, properly stamped and addressed, on the date shown below.
Additional service by hand or courier was made upon the individuals next to whose name an asterisk
(*) appears.
Ha old F. Reis Lowenstein,
- Newman, Reis 6 Axelrad 1025 Connecticut
- Avenue, N.W.
Washington, D.C.
20036 Telephone:
(202) 862-8410 May 15, 1981
Attachment:
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
FLORIDA POWER
& LIGHT COMPANY
)
)
(Turkey Point Nuclear
)
Generating Unit Nos.
3 and
)
4)
)
Docket Nos.
50-250-SP 50-251-SP (Proposed Amendments to Facility Operating Licenses to Permit Steam Generator Repair)
SERVICE LIST
- Marshall E. Miller, Esq., Administrative Judge
- Chairman, Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555
- Dr. Emmeth A. Luebke, Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- Dr. Oscar H. Paris, Administrative Judge Atomic Safety and Licensing Board Panel U.S'. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Mark P.
Oncavage 12200 S.W. 110th Avenue Miami, Florida 33176 Norman A. Coll, Esq.
- Steel, Hector 6 Davis Co-counsel for Licensee 1400 Southeast First National Bank Building Miami, Florida 33131
- Steven C. Goldberg, Esq.
Office of the Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Service List Docketing and Service Section Office of the Secretary U.S. Nuclear Regula"ory Commission Washington, D.C.
20555
- Burt Saunders,
- Esq, Assistant Dade County Attorney 1626 Dade County Courthouse Miami, Florida 33130
- Neil Chonin, Esq.
1400 AmeriFirst Building One Southeast Third Avenue Miami, Florida 33131
- Henry H. Harnage, Esq.
Peninsula Federal Building 10th Floor 200 S.E. First Street Miami, Florida 33131 May 15, 1981
- Additional Service by Hand or Courier