ML20212G836
| ML20212G836 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/22/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212G840 | List: |
| References | |
| NUDOCS 9909300132 | |
| Download: ML20212G836 (14) | |
Text
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 gs...../
TXU ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by TXU Electric Company (TXU Electric) dated February 12,1999, as supplemented by letter dated June 14,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is arnended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows:
l 9909300132 990922 DR ADOCK 05000445 PDR
s 4
I
.g.
1 (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Electric shall operate the facility in accordance with the Technical Specifications and the i
Environmental Protection Plan.
l 3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
l k
h Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 22, 1999 l
l l
l l
l p racy a"
-i UNITED STATES j
.j NUCLEAR REGULATORY COMMISSION
'f WASHINGTON. D.C. 20666 4 001
.....,o TXU ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF 89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by TXU Electric Company (TXU Electric) dated February 12,1999, as supplemented by letter dated June 14,1999, complies i
with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 rules and regulations of the Commission; 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 comp!!ance with the Commission's regulations; D.
The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF 89 is hereby amended to read as follows:
.g.
(2)
Technical Specif! cations and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through 4
l Amendment No. 70, and the Environmental Protection Plan contained in l
Appendix B, are hereby incorporated into this license. TXU Electric 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ht A A-Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
September 22, 1999 i
ATTACHMENT TO LICENSE AMENDMENT NO. 70 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove insert 3.4-33 3.4-33 5.0-14 5.0-14 5.0-15 5.0-15*
5.0-15a*
5.0-16 5.0 16 5.0-16a 5.0-17 5.0-17 5.0-36 5.0-36 5.0-36a
- no change - overflow page
RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:
- a. No pressure boundary LEAKAGE;
- b. 1 gpm unidentified LEAKAGE;
- c. 10 gpm identified LEAKAGE;
- d. 1 gpm total primary to secondary LEAKAGE through all steam generators for Unit 2 (SGs); and l
- e. 150 gallons per day for Unit 1 and 500 gallons per day for Unit 2 l
primary to secondary LEAKAGE through any one SG.
APPLICABILITY:
MODES 1,2,3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limits for reasons other than within limits.
B. Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> QB Pressure boundary LEAKAGE exists.
COMANCHE PEAK - UNITS 1 AND 2 3.4-33 Amendment No. 70
Programs and M:nu Is 5.5 5.5 Programs and Manuals 5.5.g Steam Generator (SG) Tube Surveillance Proaram (continued) c)
A tube inspection (pursuant to Specification 5.5.9.4a.8 shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
d)
Indications left in service as a result of the application of the l
tube support plate voltage repair criteria shall be inspected by l
bobbin probe during all future refueling outages.
l l
3.
The tubes selected as the second and third samples (if required by 1
Table 5.5.9-2 during each inservice inspection may be subjected to a partial tube inspection provided:
a)
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and b)
The inspections include those portions of the tubes where imperfections were previously found.
4.
Implementation of the steam generator tube / tube support plate repair
]
criteria requires a 100% bobbin coil inspection for hot-leg and cold-leg l
tube support plate intersections down to the lowest cold-leg support l
with known outside diameter stress corrosion cracking (ODSCC) l indications. The Determination of the lowest cold leg tube support l
plate intersections having ODSCC indications shall be based on the l
performance of at least a 20% random sampling of the tubes l
inspected over their fulllength.
l (continued)
I COMANCHE PEAK UNITS 1 AND 2 5.0-14 Amendment NO. 70 o
Progrcms end Minuils 5.5 5.5 Programs and Manuals 0.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued)
The results of each sample inspection shall be classified into one of the following three categories:
Cateaorv insoection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
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.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note: In allinspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
c.
Insoection Freauencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
1.
The first inservice inspection shall be performed after 6 Effective Full Power Months (EFPM) and before 12 EFPM and shallinclude a special inspection of all expanded tubes in all steam generators.
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, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months-l 2.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 5.5-2 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
{
5.5.9.3a.; the interval may then be extended to a maximum of once per 40 months; and l
(continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-15 Amendment No. 70 1
l a
l
Programs and MInuals 5.5 5.5 Programs and Manuals 5.o.9 -
Steam Generator (SG) Tube Surveillance Prooram (continued) 3.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 5.5-2 during the shutdown subsequent to any of the following conditions:
a)
Primary-to secondary tube leaks (not including leaks originating from tube-to-tube sheet welds)in excess of the limits of Specification 3.4.5.2, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
d.
Accentance Criteria 1.
As used in this specification:
)
a)
Imoerfection means an exception to the dimensions, finish, or contour of a tube from that required by fabrication drawings or specifications. - Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections; I
b)
Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside j
of a tube; c)
Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by.
degradation; d)
% Deoradation means the percentage of the tube wall thickness affected or removed by degradation; e)
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective; (continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-15a Amendment No. 70
m l
Programs end Manutls 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued) f) Pluggina Limit means the imperk. tion depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness. This definition does l
not apply to tube support plate intersections for which the j
voltage-based plugging criteria are being applied. Refer to l
5.5.9.d.1.] for the repair limit applicable to these intersections; l
g) Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 5.5.9.3c, above; h) Tube insoection means an inspection of the steam generator tube from the tube end (hot leg side) completely around the U-bend to the top support of the coid leg; i) Preservice insoection means an inspection of the fulllength of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections; and I
j) For Unit 1 ontv. the Tube Sucoort Plate Plugging Limit is used
[
for the disposition of alloy 600 steam generator tubes for l
continued service that are experiencing predominantly axially l
oriented outside diameter stress corrosion cracking confined l
within the thickness of the tube support plates and flow l
distribution baffle (FDB). At tube support plate intersections l
(and FDB), the plugging limit is based on maintaining steam l
generator tube serviceability as described below:
l l
- 1. Steam generator tubes, whose degradation is attributed to l
outside diameter stress corrosion cracking within the l
bounds of the tube support plate with bobbin voltages less l
than or equal to the lower voltage repair limit (1.0 volt], will l
be allowed to remain in service.
l l
l (continued) l l
COMANCHE PEAK-UNITS 1 AND 2 5.0-16 Amendment NO. 70 l
Programs and Manuals l
5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued)
I
- 2. Steam generator tubes, whose degradation is attributed to l
outside diameter stress corrosion cracking within the l
bounds of the tube support plate with the bobbin voltage l
greater than the lower voltage repair limit (1.0 volt], will be l
repaired, except as noted in 5.5.9.d.1.J.3 below.
l I
- 3. Steam generator tubes with indications of potential I
degradation attributed to outside diameter stress corrosion l
cracking within the bounds of the tube support plate with a l
bobbin voltage greater than the lower voltage repair limit l
[1.0 volt] but less than or equal to the upper voltage repair l
limit *, may remain inservice if a rotating pancake coil l
inspection does not detect degradation. Steam generator l
tubes, with indications of outside diameter stress corrosion l
cracking degradation with a bobbin voltage greater than j
the upper repair limit" will be plugged or repaired.
l l
- 4. Certain intersections as identified in WPT-15949 will be l
excluded from application of the voltage-based repair l
criteria as it is determined that these intersections may l
collapse or deform following a postulated LOCA + SSE l
event.
l (continued)
The upper voltage repair limit is calculated according to the methodology in GL 95-05 as l
supplemented.
l Vunt will differ at the TSPs and flow distribution baffle.
l COMANCHE PEAK - UNITS 1 AND 2 5.0-16a Amendment No. 70
[
n
~
L Programs and Minu:Is L
5.5 5.5_ Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Prooram (continued)
- 5. If an unscheduled mid-cycle insoection is performed, the j
following mid-cycle repair limits apply instead of the limits l
identified in 5.5.9.d.1.J.1,5.5.9.d.1.J.2, and 5.5.9.d.1.J.3.
l The midcycle repair limits are determined from the l
L following equations:
l l
W I
v,wa =
l 1.0 + NDE + Gr (CL - at j l
CL l
l Vuta = Vuunt - (Vunt - V at) [ a - at j l
t CL l
l where:
l l
Vug = upper voltage repair limit l
V,a = lower voltage repair limit l
Vuun = mid-cycle upper voltage limit based on time into l
cycle l
Vuta = mid-cycle lower voltage repair limit based on l
Vuta and time into cycle l
at
= length of time since last scheduled inspection l
during which Vug and V g were implemented l
t CL
= cycle length (the time between two scheduled
[
steam generator inspections) l Vst
= structurallimit voltage l
Gr
= average growth per cycle l
NDE o 95-percent cumulative probability allowance for l
nondestructive examination uncertainty (i.e, a l
value of 20-percent has been approved by the l
NRC) l l
Implementation of these mid-cycle repair limits should follow l
the same approach as in TS 5.5.9.d.1.J.1,5.5.9.d.1.J.2, and l
5.5.9.d.1.J.3.
l 2.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 5.5-2.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-17 Amendment No. 70
~
T.
l' R porting Requirzments j
5.6 I
l 5.6 Reporting Requirements (continued) i 5.6.7 Not used 5.6.8 PAM Reopd When a report is required by the required actions of'LCO 3.3.3," Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The rep 6rt shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.9 Not used 5.6.10 Steam Generator Tube insoection Reoort a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission; b.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a report within 12 months following the completion of the inspection. This report shallinclude:
1)
Number and extent of tubes inspected, 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identification of tubes plugged.
c.
Results of steam generator tube inspections which fall into Category C-3 shall be reported to the Commission pursuant to 10 CFR 50.72(b)(2) within four hours of initial discovery, and in a report within 30 days and prior to resumption of plant operation. This report shall provide a description ofinvestigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
(continued)
I COMANCHE PEAK - UNITS 1 AND 2 5.0-36 Amendment No. 70 t.
R: porting Requir:ments 5.6 5.6 Reporting Requirements (continued) 5.6.10 Steam Generator Tube insoection Reoort (continued) i d.
For implementation of the voltage based repair criteria to tube support l
j plate intersections, notify the staff prior to returning the steam generators l
4 to service should any of the following conditions arise:
l l
4 1.
If estimated leakage based on the projected end-of-cycle (or if not l
practical, using the actual measured end-of-cycle) voltage l
j distribution exceeds the leakage limit (determined from the l
'icensing basis dose calculation for the postulated main steam line l
break) for the next operating cycle.
l l
2.
If circumferential crack-like indications are detected at the tube l
support plate intersections.
l l
3.
If indications are identified that extend beyond the confines of the l
tube support plate.
l l
4.
If indications are identified at the tube support plate elevations that l
are attributable to primary water stress corrosion cracking.
l l
S.
If the calculated conditional burst probability based on the projected l end-of-cycle (or if not practical, using the actual measured end-of-I cycle) voltage distribution exceeds 1 x 102, notify the NRC and l
provide an assessment of the safety significance of the occurrence.
l COMANCHE PEAK - UNITS 1 AND 2 5.0-36a Amendment No. 70