ML20206N981
| ML20206N981 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/19/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206N984 | List: |
| References | |
| TAC-61775, TAC-61776, NUDOCS 8608270047 | |
| Download: ML20206N981 (11) | |
Text
_ =.
4 UNITED STATES O
'n NUCLEAR REGULATORY COMMISSION i
h
,j WASHINGTON, D. C. 20555 2
DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDM'ENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
~
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Cuke Power Company (the licensee) dated June 24, 1986, as revised August 5,13 and 18,1986 and supplemented July 1 and 23, 1986 complies with the standards and requireinents of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; i
D.
The' issuance of this amendment will nct be inimical to the cor.inon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8608270047 863819 DR ADOCK 05000369 PDR i
i
~
\\
- 4 2.
Accordingly, the license is hereby amended by page changes to the Technical i-Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications 4
The Technical Specifications contained in Appendix A, as revised through Amendment No.59, are hereby incorporated into the license.
i; The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its'date of issuance.
1 j
FOR THE NUCLEAR REGULATORY COMMISSION
\\S \\
1 Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes i
D, ate of Issuance: August 19, 1986 5
Dsli (h
PWR#4/0PWR-A P,WR kPWR-A
/GC-Beg PWR#4/0PWR-A J030h fBJYoungblood DHood/ rad Mbtf n
08/g/86 08/j /86 08/l /86 08/jf/86 i
@ fd (f
p f '}
[
'o UNITED STATES
~,,
- [
n NUCLEAR REGULATORY COMMISSION L
-p WASHINGTON, D. C. 20555
\\...../
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. NPF-17 1.
The Nuclear Regulatory Ccmission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, i
Unit 2 (the facility) Facility' Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated June 24, 1986, as revised, August 5, 13, and 18, 1986 and supplemented July 1 and 23, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations if the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
f
l i
t 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license arrendment, i
and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
5 (2) Technical Specifications r
The Technical Specifications containee in Appendix A, as revised through Amendment No. 4Q are hereby ir.corporated into the license.
5 The licensee shall operate the facility in accordance with the Technical Specifications and the_ Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COP 91ISS' ION
[
\\M Darl Hood,, Project Manager PWR Project Directorate #4 l
Division of PWR Licensing-A
Attachment:
Technical Specification l
Changes j
i f
Cate of Isstance: August 19, 1986 I
r i
i r
3)$h h
PWR#4/0PWR-A PWR 4 C-B th PWR#4/DPWR-A N0dn(Ea/(lPWR-A Y
%Q pBJYoungblood DHood/ rad 08/g/as 08/l6 /8s n/ss Os/,t/86
i l
ATTACHMENT TO LICENSE AMENDMENT NO. 59 l
l FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 40 FACII.ITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Overleaf Page Page 3/4 4-12 3/4 4-11 3/4 4-14 3/4 4-13 3/4 4-15 B 3/4 4-3 4
4 1
i I
Y
..__.._,_j f
O 1
+
3/4.4.5 STEAM GENERATORS f
t LIMITING CONDITION FOR OPERATION
\\
3.4.5 i
Each steam generator shall be OPERABLE.
t APPLICABILITY: MODES 1, 2, 3 and 4.
\\
ACTION:
i
)
With one or more steam generators inoperable, restore the inoperable generator (s)
I j
to OPERABLE status prior to increasing T,yg abcve 200 F.
i I
SURVEILLANCE REQUIREMENTS
(
f j
4.4.5.0 Each steam generator shall be demonstrated OPERABLE b'y performance of the following augmented inservice inspection program and the requirements of Specificaticn 4.0.5.
s i
j 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator i
shall be determined OPERABLE during shutdown by selecting and inspecting at
{
least the minimum number of steam generators specified in Table 4.4-1.
j 4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam i
generator tube minimum sample size, inspection result classification, and the
[
j corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generatcr tubes shall be performed at the fre-j i
quencies specified in Specification 4.4.5.3 and the inspected tubes shall be i
}
verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The j
tubes selected for each inservice inspection shall include at least 3% of '.he j
total number of tubes in all steam generators the tubes selected for these I
inspections.shall be selected on a random bas s except:
t Where experience in similar plants with similar water chemistry a.
i indicates critical areas to be inspected, then at least 50% of the-
?
j tubes inspected shall be from these critical areas; b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice insp~ectior.) of each steau generator l
9 shall include:
[
1
?
l i
l i
j l
McGUIRE - UNITS 1 and 2 3/4 4-11 i
I
_._-.... _._ =..
= _ - -.. - -.
l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) l 1)
All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),
2)
Tubes in those areas where experience has indicated potential problems, and f
3)
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall i
be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube i
inspection, this shall be recorded and an adjacent tube shall j
be selected and subjected to a tube inspection!
f c.
In addition to the 3% sample, all F* tubes will be inspected.
i i
l d.
The tubes selected as the second and third samples (if required by l
l Table 4.4-2) during each inservice inspection may be subjected to a 1
j partial tube inspection provided:
1)
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with l
imperfections were previously found, and i
2)
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the j
following three categories:
l l
Category Inspection Results C-1 Less than 5% of the total tubes inspected are i
j degraded tubes and none of the inspected tubes are defective.
l C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
I C-3 More than 10% of the total tubes inspected are j
degraded tubes or more than 1% of the inspected tubes are defective.
t Note:
In all inspections, previously degraded tubes must exhibit i
significant (greater than 10%) further wall penetrations j
to be included in the above percentage calculations, i
4 i
McGUIRE - UNITS 1 and 2 3/4 4-12 Amendment No. 59 (Unit 1) l Amendment No. 4o(Unit 2) 4
-m
__.-_.__v_,_.__,.._
..____.___.-...,__,-,...~..~,-_._r.-...
SEACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
The first inservice inspection shall be performed after 6 Effective a.
Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two l
consecutive inspections demonstrate that previously observed degra-dation has not continued and no cdditional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; b.
If the results of the inservice inspection of a steam generator conducted in accordance'with Table 4.4-2 at 40-month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3a; the interval may then be extended to a maximum of once per 40 months; and Additional, unscheduled inservice inspections shall be performed on c.
each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
1)
Reactor-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, 2)
A seismic occurrence greater than the Operating Basis Earthquake, 3)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, and 4)
A main steam line or feedwater line break.
McGUIRE - UNITS 1 and 2 3/4 4-13 a
)-
(
SURVEILLANCE REQUIREMENTS (Continued) i 4.4.5.4 Acceptance Criteria j
a.
As used in this specification:
1)
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or l
l specifications.
Eddy-current testing indications below 20% of f
j the nominal tube wall thickness, if detectable, may be
~
considered as imperfections; r
2)
Degradation means a service-induced cracking, wastage, wear or I
i general corrosion occurring on either inside or outside of a f
j tube; l
r t
i 3)
Degraded Tube means a tube containing imperfections greater' l
l than or equal to 20% of the nominal wall thickness caused by degradation; j-4)
% Degradation means the percentage of the tube wall thickness l
affected or removed by degradation; 1
j 5)
Defect means an imperfection of such severity that it exceeds the plugging limit.
A tube containing a defect is defective; t
j 6)
Pluggina Limit means'the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of i
the nominal tube wall thickness.
This definition does not apply to the area of the tubesheet region below the F* distance pro-i vided the tube is not degraded (i.e., no indications cf cracking) t within the F* distance.
{
i t
7)
Unserviceable describes the condition of a tube if it leaks or l
1 contains a defect large enough to affect its structural integ-f i
rity in the' event of an Operating Basis Earthquake, a loss-of-j coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c, above, 1
t l
8)
Tube Inspection means an inspection of the steam generator tube j
from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg; and j
i f
l NOTE 1:
The application of F* expires at the end of the fifth fuel cycle for each respective unit.
i j
McGUIRE - UNITS 1 and 2 3/4 4-14 Amendment No.59 (Unit 1)
Amendment No.40 (Unit 2) i l
\\-
j
~
SURVEILLANCE REQUIREMENTS (Continued) r 9)
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by addy' current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION j
using the equipment and techniques expected to be used during j
subsequent inservice inspections.
10)
F* Distan:e is the distance into the tubesheet from the top face of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively chosen to be 2 inches.
i 11)
F* TUBE is a tube with degradation equal to or greater than 40%,
+
l below the F* distance and not degraded (i.e., no indications of j
cracking) in the F* distance.
b.
The steam generator shall be determined OPERABLE after completing j
the corresponding actions (plug all tubes emceeding the plugging limit and all tubes containing through-wall cracks) required by
}
Table 4.4-2.
a 4.4.5.5 Reports l
a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam j
generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; b.
The complete results of the steam generator tube inservice inspection shall he submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1 1)
Number and extent of tubes inspected, 1
2) location and percent of walb thickness penetration for each indication of an imperfection, and i
j 3)
Identification of tubes plugged.
j c.
The results of inspections of F* tubes shall be reported to the l
Commission in a report to the Director, ONRR, prior to the restart 1
of the unit following the inspection.
This report shall include:
1)
Identification of Fa tubes, and 2)
Location and size of the degradation.
}
McGUIRE - UNITS I and 2 3/4 4-15 Amendment No.59 (Unit 1) i Amendment No.40 (Unit 2) 1 1
0 l
r
REACTOR COOLANT SYSTEM BASES 3/4.4.4 RELIEF VALVES The power-operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump.
Operation of the PORVs minimizes i
the undesirable opening of the spring-loaded pressurizer code safety valves.
Each PORV has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained. The program for inservice inspection of. steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the Reactor Coolant System and the Secondary Coolant System (reactor-to-secondary leakage = 500 gallons per day per steam generator).
Cracks having a reactor-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated acciderts.
Operating plants have demonstrated that reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, durir.g which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demoastrated the capability to I
reliably detect wastage type degradation that has penetrated 20% of the origi-nal tube wall thickness.
For tubes with degradation below the F* distance, and not degraded within the F* distance, plugging is not required.
Amendment NoS9(Unit 1)
McGUIRE - UNITS 1 and 2 B 3/4 4-3 Amendment NoA0(Unit 2)
_ _ _ _ - _ _