ML20212G806
| ML20212G806 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/22/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212G811 | List: |
| References | |
| NUDOCS 9909300126 | |
| Download: ML20212G806 (13) | |
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lt UNITED STATES i-g
,j NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D.C. 2066H001 p
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l TXU ELECTRIC COMPANY l
COMANCHE PEAK STEAM ELECTRIC STATION. UNIT NO.1 l
DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by TXU Electr,c Company (TXU Electric) dated October 2,1998, as supplemented by letters dated July 27 and August 26,1999, l
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; i
B.
The facility will operate in conformity with the application, as amended, the
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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.
j 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-87 is hereby amended to read as follows:
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9909300126 990922 PDR ADOCK 05000445 P
PDR 1 _
2-(2)
Tpchnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. TXU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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 h A in-Robert A. Gramm, Chief, Section 1
)
Project Directorate IV & Decommissioning 1
Division of Licensing Project Manapcment j
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 4
Specifications l
Date of Issuance: September 22, 1999
90%
h-UNITED STATES 4
4 y
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
%,,.....,o TXU ELECTRIC COMPANY l
COMANCHE PEAK STEAM ELECTRIC STATION. UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 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 October 2,1998, as supplemented by letters dated July 27 and August 26,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comm!ssion'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 Fat. 51 of the Commission's regulations and all applicable reqairements have L< en 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:
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(2).
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through
. Amendment No. 71, 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 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 k
W 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: Septentber 22, 1999
ATTACHMENT TO LICENSE AMENDMENT NO. 71 l
TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 l
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.
1 Remove Insert 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15 5.0-15a 5.0-16 5.0-16 G.0-16a l
i 5.0-17 5.0-17 5.0-36 5.0-36 l
l 1
l L
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Programs and Manuals t
5.5 lI~
5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.
The provisions of SR 3.0.2 are applicable to the SG Surveillance Program test frequencies.
a.
Steam Generator Samole Selection and inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 5.5-1.
b.
Steam Generator Tube Samole Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.5-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 5.5.9d., and the inspected tubes shall l
be verified acceptable per the acceptance criteria of Specification 5.5.9e. The l tubes selected for each inservice inspection shall include at least 3% of all the expanded tubes and at least 3% of the remaining number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
1.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas; 2.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
a)
All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),
b)
Tubes in those areas where experience has indicated potential
- problems, (continued)
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l COMANCHE PEAK-UNITS 1 AND 2 5.0-13 Amendment No. 71
e Progrtms cnd Minu11s 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued) c)
A tube inspection (pursuant to Specification 5.5.9e.1.h) shall l
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, and d)
Indications left in service as a result of the application of the tube support plate voltage repair criteria shall be inspected by bobbin probe during all future refueling outages.
3.
The tubes selected as the second and third samples (if required by Table 5.5.9-2 during each inservice inspection may be subjected to a partial tube inspection provided:
I 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 i
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 tube support plate intersections down to the lowest cold-leg support with known outside diameter stress corrosion cracking (ODSCC) indications. The Determination of the lowest cold leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20% random sampling of the tubes inspected over their full length.
The results of each sample inspection shall be classified into one of the following three categories:
Cateoory inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
l (continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-14 Amendment No. 71
Programs and M:nuals 5.5 i
l 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued)
C-2 One or more tubes, but not more than 1% of the tml tubes inspected are defective, or between 5% and 10% o :he total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded l
tubes or more than 1% of the inspected tubes are defective.
Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the l
above percentage calculations.
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l c.
Steam Generator F* Tube inspection (Unit 1 oniv) - In addition to the l
minimum sample size as determined by Specification 5.5.9b., all F* tubes will l
be inspected within the tubesheet region. The results of the inspections of F*
l tubes identified in previous inspections will not be a cause for additional l
inspcetions per Tables 5.5-1 and 5.5-2.
l d.
Inspection Freauencies - The above required inservice inspections of steam l
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 shall include a specialinspection 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 l
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; 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 l
Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply l
until the subsequent inspections satisfy the criteria of Specification l
5.5.9d.1.; the interval may then be extended to a maximum of once l
per 40 months; and (continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-15 Amendment No. 71 l
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r-'-
Programs and Manuals 5.5 l
5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (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 actuatiun of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
e.
Acceptance Criteria l
1.
As used in this specification:
l a)
Imperfection means an exception to the dimensions, finish, or contour of a tube from that required by fabr' cation drawings or specifications. Eddy-current testing indicaticas below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections; j
b)
Dearadation means a service-induced cracking,
wastage, wear, or general corrosion occurring on either inside or outside of a tube; c)
Dearaded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation; d)
% Dearadation 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; 1
l (continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-15a Amendment No. 71
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued) f) Pluaoina Limit means the imperfection 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 that portion of the Unit 1 tubing that meets the l
definition of an F* tube. This definition does not apply to tube l
support plate intersections for which the voltage-based plugging criteria are being applied. Refer to 5.5.9e.1m) for the l
repair limit applicable to these intersections; 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 5.5.9d.3., above; l
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 cold leg; i) Preservice inseq.ptig_r! means an inspection of the full length 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; l
j)
F* Distance (Unit 1 oniv) is the distance of the hardroll l
expanded portion of a tube which provides a sufficient length l
of non-degraded tube expansion to resist pullout of the tube
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from the tubesheet. The F* distance is equal to 1.13 inches, l
plus an allowance for eddy current measurement uncertainty, l
and is measured down from the top of the tubesheet, or the l
bottom of the roll transition, whichever is lower in elevation; l
l k) F* Tube (Unit 1 ontv)is that portion of the tubing in the area of l
the tubesheet region below the F* distance with a) degradation l below the F* distance equal to or greater than 40%, b) which l
has no indication of degradation within the F* distance, and c) l that remains inservice; l
l (continued) l COMANCHE PEAK - UNITS 1 AND 2 5.0-16 Amendment No. 71
Programs End M nuals 5.5 5.5 Programs and Manuals l} Hard Roll Exoansion (Unit 1 oniv) is that portion of a tube l
which has been increased in diameter by a rolling process l
such that no crevice exists between the outside diameter of l
the tube and the hole in the tubesheet; and l
m) For Unit 1 ontv. the Tube Support Plate Pluaaino Limit is used for the disposition of alloy 600 steam generator tubes for continued service that are experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates and flow distribution baffle (FDB). At tube support plate intersections (and FDB), the plugging limit is based on maintaining steam generator tube serviceability as described below:
- 1. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit [1.0 volt], will be allowed to remain in service.
- 2. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with the bobbin voltage greater than the lower voltage repair limit [1.0 volt), will be repaired, except as noted in 5.5.9e.1.m)3. below.
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- 3. Steam generator tubes with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit
[1.0 volt] but less than or equal to the upper voltage repair limit *, may remain inservice if a rotating pancake coil inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than the upper repair limit ** will be plugged or repaired.
(continued)
The upper voltage repair limit is calculated according to the methodology in GL 95-05 as supplemented.
V, will differ at the TSPs and flow distribution baffle.
COMANCHE PEAK - UNITS 1 AND 2 5.0-16a Amendment No. 71
l Programs and Manuals 5.5 i
5.5 Programs and Manuals l
l 5.5.9 Steam Generator (SG) Tube Surveillance Proaram (continued)
- 4. Certain intersections as identified in WPT-15949 will be excluded from application of the voltage-based repair criteria as it is determined that these intersections may l
collapse or deform following a postulated LOCA + SSE event.
- 5. If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in 5.5.9e.1.m)1.,5.5.9e.1.m)2., and 5.5.9e.1.m)3.
l The midcycle repair limits are determined from the following equations:
Vst uuRL 1.0 + NDE + Gr ICL - at )
CL Vutat = Vuunt - NuRL - Vent) [ CL - at )
CL l
where:
Vunt = upper voltage repair limit V at = lower voltage repair limit t
Vuunt = mid-cycle upper voltage limit based on time into cycle Vuont = mid-cycle lower voltage repair limit based on j
Vutne and time into cycle 1
At
= length of time since last scheduled inspection 1
during which Vunt and V at were implemented t
l CL
= cycle length (the time between two scheduled steam generator inspections)
Vst
= structurallimit voltage Gr
= average growth per cycle NDE = 95-percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20-percent has been approved by the NRC)
Implementation of these mid-cycle repair limits should follow the same approach as in TS 5.5.9e.1.m)1.,5.5.9e.1.m)2., and 5.5.9e.1.m)3.
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.
l (continued) 1 l
l l
COMANCHE PEAK - UNITS 1 AND 2 5.0-17 Amendment No. 71 l
m Rrporting R:quirsm:nts 5.6 5.6 Reporting Requirements (continued) 5.6.7 Not used 5.6.8 PAM Report 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 report 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 Inspection Report a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or designated as an l F* tube in each steam generator shall be reported to the Commission; l
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.
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 of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-36 Amendment No. 71 l
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