ML18227C821
| ML18227C821 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/27/1974 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Case E US Atomic Energy Commission (AEC) |
| References | |
| Download: ML18227C821 (20) | |
Text
AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)
CONTROL NO: 10176 FILE FROM: Plorida Power 6 Light C Miami, Pla.
33101 Nr. R.E. Uhri TO:
E.G. Case CLASS UNCLASS PROPINFO XXX DATE OF DOC 9-27-74 ORIG 3 signed INPUT XXX DATE R EC'D 10-2-74 CC OTHER NO CYS REC'D 40 LTR TWX RPT OTHE R SENT, AEC PDR XXX SENT LOCAL PDR DOCKET NO:
0-250 251 DESCR IPTION:
Ltr notarized 9-27-74...trans the following..
~ ~ ~ ~ ~ ~
ENCLOSURES:
Proposed changes-toi'the~
tech"-s1IeC'5...
ZCKNOWLKDGKD (40 cys encl rec'd)
PL'ANT NAIVIE: Turkey Point 3
& 4 FOR ACTION/INFORMATION DO NOT RKMOVFi 10-8-74 JB BUTLER (L)
W/ Copies CLARK (L)
W/ Copies PARR (L)
W/ Copies KNIEL (L)
W/ Copies SCHWENCER (L)
W/ Copies STOLZ (L)
W/ Copies VASSALLO (L)
W/ Copies PURPLE (L)
W/ Copies ZIEMANN(L)
REGAN (E)
W/ Copies W/ Copies DICKER (E) v LEAR (L)
W/ Copies W//Copies KNIGHTON (E)
W/ Copies W/ Copies YOUNGBLOOD (E)
W/ Copies W/ Copies INTERNAL DISTR IBUTION
~REG FILE
+OGC, ROOM P-506A
+ MUNTZING/STAFF CASE GIAMBUSSO BOYD MOORE (L) (BWR)
DEYOUNG (L) (PWR)
SKOVHOLT (L)
~GOLLER (L)
P. COLLINS DENISE gREG OPR FILE & REGION (3)
MOR RIS STEELE TECH REVIEW SCHROEDER MACCARY KNIGHT PAWLICK I SHAO STELLO HOUSTON NOVAK ROSS IPPOLITO TEDESCO LONG LAINAS BENAROYA VOLIMER DENTON G R IMES GAMMILL KASTNER BALLARD SPANGLER ENVIRO MULLER DICKER KNIGHTON YOUNGB LOOD REGAN ROJ CT,LDR CCleveland HAR LESS LIC ASST DIGGS (L)
GEAR IN (L)
GOULBOURNE (L)
KREUTZER (E)
LEE (L)
MAIGRET (L)
REED (E)
SERVICE (L)
SHEPPARD (L)
SLATER (E)
SMITH (L)
~ TEETS (L)
WI LLIAMS(E)
WI LSON (L)
A/T IND B RAITMAN SALTZMAN B. HURT PLANS MCDONALD CHAPMAN DUBE w/input
~ E. COUPE
~. Sch'em'el ~
D. THOMPSON (2)
KLECKER EISENHUT EXTERNALDISTRIBUTION
~1 LOCAL PD R~om~e'ad~+la..
<1 TIC (ABERNATHY)
(1)(2)(10) NATIONALLABS v'1 NSIC (BUCHANAN) 1 ASLBP(E/W Bldg, Rm 529) 1 ASLB 1
W. PENNINGTON, Rm E-201 GT Newton Anderson 1
B&MSWINEBROAD, Rm E-201 GT X16 ACRS A'4$KS(RQ( Sent to 1
CONSULTANTS Teats NEWMARK/BLUME/AGBABIAN.
10-8-74 1 P D R-SAN/LA/NY 1 BROOKHAVEN NAT LAB 1 G. ULRIKSON, ORNL 1 AGIVIED (RUTH GUSSMAN)
Rm B-127 GT 1 R. D. MUELLER, Rm E-201 gW
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.O. BOX 3100 MIAMI,FLORIDA 33IOI gegIIlatary OOCket File S
+i>+
0 C
Mr. Edson G. Case, Acting Director Directorate, of Licensing Office of Regulation U. S. Atomic Energy Commission Washington, D. C.
20545
Dear Mr. Case:
FLORIDA POWER 8, LIGHT COMPANY September 27, 1974 CD s
0QX q4'g+@<
Re:
TURKEY POINT T UNITS 3 AND 4 DOCKET NOS.~50-250 AND 50-251 PROPOSED AbfBNB TO THE FACILITY OPERATING LICENSES DPR-31 AND'PR-41 In accordance with 10 CFR 50.30, Florida Power G Light. Company sub-mits herewith three signed originals and forty (40) conformed copies of a request to amend the Facility Operating Licenses DPR-31 and DPR-41.
This submittal is in response to Mr. Karl Goller's letter of July 18, 1974, in which we were rectuested to submit a proposed change to our Technical Specifications establishing requirements for a program of steam generator tube inspection.
On August 28,
- 1974, we advised Mr. Goller that we were working with the reactor vendor in this regard and we would submit an inspection program by October 1, 1974.
The program which we have established essentially conforms with the level of inspection required by Regulatory Guide 1.83," Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes.
How-
- ever, the program does not address the subject of baseline inspection.
We believe that the extensive inspections performed on the Unit, No.
4 steam generators constitutes a sufficient basis for baseline in-spections.
Based on the Unit No.
4 results, the Unit No.
3 steam generators will also be extensively inspected during the upcoming refueling outage.
The changes we are requesting are shown on the attached revised pages of the Technical Specifications (Appendix A of the Facility Operating Licenses).
These changes consist of a revision to Table 4.2-1 and to Section B4.2 of the Bases.
We have reviewed this program and have concluded that it meets or exceeds the requirements of Regulatory Guide 1.83.
We have also j.Ug'po HELPING BUILD FLORIDA
0 e
b h
r
Mr. Edson G. Case, Acting Director Page Two September 27, 1974 concluded that it, does not involve a significant hazards considera-tion and there is reasonable assurance that the health and safety of the public will not be endangered.
Very uly yours, Ro ert E.
hrig Vice President REU/DWR/cpc Attachment cc:
Jack R.
Newman, Esquire STATE OF FLORIDA )
)
COUNTY OF DADE
)
ROBERT E.
UHRIG, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foreg'oing instrument; that the state-ments made in this said instrument.'are true and correct to the best of his knowledge, information and bel'ief;.
and that he is-authorized to execute the instrument. of said Licensee.
ert E. Uhrig Subscribed and sworn to before me this c~A Way of September, 1974.
Not r Public in and for the Coun of Dade, State of Florida
'I Notosy Poblis, Sate,of'Florih at luge 5'ommission Exp'ues,Oct. 30, l974
- loaA4 av. ~saa tea 4 ~AxQa.~
1
BOX 013100, MIAMI, FLORIDA 33101 iyQl/P~
$5@
~ri'., i ~
J FLORIDA POWER 5 LIGHT COMPANY September 27, 1974 Mr. Edson G. Case, Acting Director Directorate of Licensing Office of Regulation U. S. Atomic Energy Commission Washington, D. C.
20545
Dear Mr. Case:
Re:
TURKEY POINT PLANT UNITS 3 AND 4 DOCKET NOS.
50-250 AND 50-251 PROPOSED AMENDMENT TO THE FACILITY OPERATING LICENSES DPR-31 AND DPR-41 OCT 3 3974
'I.S.
P1.,",l" '.;,;T R J.Bi,,,lI U)1l SAi;3 In accordance with 10 CFR 50.30, Florida Power 6 Light Company sub-mits herewith three signed originals and forty (40) conformed copies of a request to amend the Facility Operating Licenses DPR-31 and DPR-41.
This submittal is in response to Mr. Karl Goller's letter of July 18, 1974, in which we were requested to submit a proposed change to our Technical Specifications establishing requirements for a program of'steam generator tube inspection.
On August 28,
- 1974, we advised Mr. Goller'that we were working with the reactor vendor in this regard and we would submit an inspection program by October 1, 1974.
The program which we have established essentially conforms with the level of inspection required by Regulatory Guide 1.83, Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes.
How-
- ever, the program does not address the subject of baseline inspection.
We believe that the extensive inspections performed on the Unit No.
4 steam generators constitutes a sufficient basis for baseline in-spections.
Based on the Unit No.
4 results, the Unit No.
3 steam generators will also be extensively inspected during the upcoming refueling outage.
The changes we are requesting are shown on the attached revised pages of the Technical Specifications (Appendix A of the Facility Operating Licenses).
These changes consist of a revision to Table 4.2-1 and to Section B4.2 of the Bases.
We have reviewed this program and have concluded that it meets or exceeds the requirements of Regulatory Guide 1.83.
We have also col'i'6 HELPING BUILD FLORIDA
t
'1~
Mr. Edson G. Case, Acting Director Page Two September 27, 1974 concluded that it does not involve a significant hazards considera-tion and there is reasonable assurance that the health and safety of the public will not be endangered.
Very uly yours, Ro ert E.
hrig Vice President REU/DWR/cpc Attachment cc:
Jack R.
Newman, Esquire STATE OF FLORIDA )
)
COUNTY OF DADE
)
ROBERT E.
UHRIG, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing instrument; that the state-ments made in this said instrument are true and correct to the best of his knowledge, information and belief; and that he is authorized to execute the instrument of said Licensee.
R ert E. Uhrig Subscribed and sworn to before me this c~A Way of September, 1974.
Not r Pubis.c xn and for the Coun of Dade, State of Florida Notary, Publis, 54ta,ol Florida at Lang Ny Commission Expies,Ost. 30, 1974
. 'IoasQ ay. rrrsaSNa 5s 4 Qw&aQsr.~
M
by a factor of 2.1.
Thus, this capsule provides information for approximately a four-year exposure to the vessel.
Capsule No.
2 is scheduled to be removed at the fourth region replacement.
This capsule leads the vessel maximum exposure by a factor of 0.8 and thus will provide data for a four-year exposure to the vessel.
This sample also contains weld metal which is not present in Capsule No. l.
Capsule No.
3 leads the vessel maximum exposure by a factor of 2.2 and is scheduled to be removed after twenty years.
- Thus, sample No.
3 will provide data for an exposure to the vessel of approximately forty years.
Capsules No.
4 and 5 lead the maximum vessel exposure by factors of 0.7 and 0.5, respectively.
- Thus, Capsule No. 4, which is scheduled to be removed after thirty years, provides data for a vessel exposure of twenty-one year's and Capsule No. 5, which is scheduled to be re-moved at forty years, provides data for a vessel exposure of twenty years.
In addition to the capsules discussed
- above, there are three spares.
Item 7.3 Steam Generator Tubes 1)
Sample Selection and Testing Each steam generator shall be in-spected during shutdown as follows:
a)
During each inservice inspection (at frequencies specified in Item 7.3.2),
a representative sample of at least 3 percent of the total, number of steam generator tubes shall be eddy current inspected.
Inspections subsequent to the first two inservice inspections of the steam generator tubes shall routinely concentrate on the hot-leg side of the steam generator.
The tubes selected for -each inservice inspection shall include:
B4.2-13 10/'1/74
O.
1.
All tubes,(except plugged tubes) in which wall penetrations of >20 p'ercent were revealed during previous inspections.
2.
Tubes in those areas (including the cold-leg side) where design and experience have indicated potential problems.
b)
As a minimum, an additional 3 percent of the steam generator tubes shall be eddy current inspected if more than 10 percent (all tubes previously identified as having wall penetrations
>20 percent and exhibiting further wall penetrations of >5 percent shall be included in this 10 percent) of the tubes inspected per l)a above, have wall penetrations of >20 percent or if one or more of t'e inspected tubes require plugging as defined in 3)a.
At least 75 percent of these additional tubes selected for eddy current inspection shall be from tubes in those areas of the tube sheet array where tubes with defects were found.
c)
As a minimum, an additional 3 percent of the steam generator tubes shall be eddy current inspected if more than 10 percent of the tubes inspected per l)b above, have wall penetrations of >20 per-cent or if one or more of the inspected tubes require plugging as defined in 3)a.
These additional tubes selected for eddy current inspection shall be from tubes in those areas of the tube sheet array where tubes with defects were found.
2)
Ins ection Fre uencies The above inservice inspections of steam tubes shall be performed at the following frequencies:
a)
At intervals of not less than 12 or more than 20 calendar
- months, except the first scheduled inservice inspection shall be performed at the first extended outage after 6 months of operation.
If two consecutive inservice inspections of steam generator tubes show no additional tubes with wall penetrations of >20 percent and no significant
(>5 percent) further penetration of tubes with previous defect indications, the inspection frequency for hot-leg tubes may be extended to at least once per 40 months.
If two consecutive B4.2-14 10/1/74
inservice inspections of the cold-leg tubes of the steam generator
"'how no additional tubes with wall penetrations
>20 percent and no significant
(>5 percent) further penetration of tubes with previous defect indications, the inspection frequency for cold-leg tubes may be extended to at least once per 10 years.
b)
During the shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary leakage in excess of 1 gpm.
2.
A seismic occurrence greater than the Operating Basis Earth-quake.
3.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
4.
A steam line or feed water line break requiring a reactor shutdown.
3)
Acce tance Criteria a)
Any tubes with an eddy current indication of 50% or greater wall penetration shall be plugged before the steam generator is re-turned to service.
b) If in the inspections performed under Item 7.3.1, less than 10% of the total tubes inspected have detectable wall penetration
(>20%) and no tubes require plugging per Acceptance Criterion 3)a~
plant operation shall be resumed and the inspection results shall be reported in the semi-annual operating reports covering the periods of operation in which these inspections were completed.
c) If in the inspections performed under Item 7.3.1, less than 10% of the total tubes inspected have detectable wall penetration
(>20%) and no more than 3 tubes require plugging per Acceptance B4.2-15 10/1/74
I 1
Criterion 3)a, plant operation shall be resumed after corrective action given in Acceptance Criterion 3)b has been taken.
The results of these inspections and corrective actions shall be reported in the semi-annual operating reports covering the periods of operation in which these inspections were completed.
d) If in the inspections performed under Item 7.3.1, more than 10% of the total tubes inspected have detectable wall penetrations
(>20%), or more than 3 of the tubes inspected require plugging, the situation will be assessed by the plant operator and appro-priate action will be taken prior to plant operation and the event shall be reported to the Commission as an abnormal occurrence.
B4.2-16
0 0
TABLE 4 2-1 (cont ed)
Item No.
Examination caCte Co Components and Parts To Be Examined Method Extent of Examination (Percent in 10 Year Interval Extent of Examination (Percent in 5 Year Interval)
Remarks 6.5 G-2 Pressure-retaining bolt Visual and Volumetric 100X 33X Exception is taken for valves which are not accessible.
6.6 6.7 K-1 K-2 Integrally-welded supports Supports and Hangers Visual Not Applicable 100X Not Applicable 33X Exception is taken for supports and hangers which are not accessible.
7.1 Reactor coolant pump Flywheel 100X for (2)
In place at bore, Keyway, and tapped holes for (1).
The flywheels shall be visually examined at the first refueling and at the end of each 10 year interval.
The outside surface shall be examined by ultra-sonic methods on the following schedule:
(1) During second re-fueling all 3, (2) At the
- seventh, eighth and ninth re-fueling' one different fly-wheel each refueling (3) Re-peat (2) within 10 years.
7.2 Irradiation Specimen Schedule Tensile and See Remarks Charpy V
Notch (Wedge Open Loading)
See Remarks Capsule 1 shall be removed and examined at the first region replacement Capsule 2 shall be removed and examined at the fourth region replacement.
Capsule 3 shall be removed and ex-amined after twenty years of operation.
Capsule 4 shall be removed and examined after thirty years of operation.
Capsule 5 shall be removed and examined after forty years of operation 7.3 Steam Generator Tubes Eddy Current See Bases See Bases See Bases
4 0