ML20095G163
| ML20095G163 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/14/1995 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095G165 | List: |
| References | |
| NUDOCS 9512200054 | |
| Download: ML20095G163 (11) | |
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UNITED STATES S
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 20066 0001
- g*
ENTERGY OPERATIONS. INC.
QQCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.117 License No. NPF-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated December 6, 1993, as supplemented by letters dated May 12, August 9, and September 18, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
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; D.
The issuance of this amendment will not be inimical to the comon 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.
9512200054 951214 PDR ADOCK 05000302 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.117, and the Environmental Protection Plan 3
contained in Appendix B, are hereby incorporated in the license.
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 to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 14, 1995 5
ATTACHMENT TO LICENSE AMENDMENT NO.117 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and l
contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 4-11 3/4 4-11 3/4 4-13 3/4 4-13 3/4 4-14 3/4 4-14 3/4 4-16 3/4 4-16 B 3/4 4-2 B 3/4 4-2 l
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SURVEILLANCE REOUIREMENTS (Continued) 1.
All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).
2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.4.4a.9.)
l shall be performed on each selected tube.
If any selected l
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.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to j
i a partial tube inspection provided:
)
i 1.
The tubes selected for these samples include the tubes from 1
those areas of the tube sheet array where tubes with i
imperfections were previously found.
2.
The inspections include those portions of the tubes where t
j imperfections were previously found.
The results of each sample inspection shall be classified into one of the 4
following three categories:
I-Cateaory 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 all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
WATERFORD - UNIT 3 3/4 4-11 Amendment No.117
I REACTOR COOLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) steam generator tubes shall be performed at the fo 4.4.4.3 The first inservice inspection shall be performed af ter 6 Effective i
Full Power Months but within 24 calender months of init a.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar icality.
If two consecutive inspections following i result in all inspection results falling into the C-1 c the previous inspection.
if d
two consecutive inspections demonstrate that previously observe degradation has not continued and no additional d i
f once per 40 months.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 b.
The increase in inspection frequency f
shall apply until the subsequent inspections satisfy"the criteria o least once per 20 months.
Specification 4.4.4.3a.; the interval may then be extended to a maximum of once per 40 months.
Additional, unscheduled inservice inspections shall be performed on tion each steam generator in accordance with the fir c.
the following conditions:
Primary-to-secondary tubes leaks (not including l 1.
limits of Specification 3.4.5.2.
A seismic occurrence greater than the Operating Basis 2.
A loss-of-coolant accident requiring actuation of the 3.
engineered safeguards.
A main steam line or main feedwater line break.
4.
3/4 4-12 WATERFORD - UNIT 3
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EACTOR COOLANT SYSTEM
' SURVEILLANCE REQUIREMENTS (Continued) i 4.4.4.4 Acceptance criteria a.
As used in this Specification 1.
Tubino or tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2.
Imoerfectionmeansanexceptiontothedimensions,finishorl 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.
l 3.
Dearadation means a service-induced cracking,
wastage, wear, l or general corrosion occurring on either inside or outside of a tube.
4.
Dearaded Tube means a tube containing imperfections greater l than or equal to 20% of the nominal wall thickness caused by degradation.
5.
% Dearadation means the percentage of the tube wall l
thickness affected or removed by degradation.
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6.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a
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defect is defective.
7.
Pluacina or Repair limit means the imperfection depth at or f
beyond which the tube shall be removed from service by plugging or repaired by sleeving because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.
8.
Unserviceabh describes the condition of a tube if it leaks l
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 4.4.4.3c., above.
9.
Tube Inspection means an inspection of the steam generator l
tube from the point of entry (hot leg side) completely around the U-bend to the top support of the s:old leg.
10.
PreserviceInspectionmeansaninspectionofthefulllengthl 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 was performed prior to field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
7 WATERFORD - UNIT 3 3/4 4-13 Amendment No. 117
REACT 0ft COOLANT SYSTEM t
l SURVEILLANCE REQUIREMENTS (Continued) b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit and all tubes containing through-wall 1-cracks) required by Table 4.4-2.
Defective tubes may be repaired in accordance with CENS Report CEN-605-P, "Waterford 3 Steam Generator Tube Repair Using Leak Tight Sleeves," Revision 00-P, dated December 1992.
4.4.4.5 Renorts i
a.
'Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes
>1ugged j
or sleeved in each steam generator shall be reported to tie l
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Commission in a Special Report pursuant to Specification 6.9.2.
l b.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following completion of the inspection. This Special Report shall include:
4 1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each
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indication of an imperfection.
3.
Identification of tubes plugged or sleeved.
l c.
Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Resort to the l
Commission pursuant to Specification 6.9.2 wit 11n 30 days and i
prior to resumption of plant operation.
This report shall provide i
a description of investigations conducted to determine cause of j
the tube degradation and corrective measures taken to prevent recurrence.
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WATERFORD - UNIT 3 3/4 4-14 Amendment No.117
TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION i
The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all steam generators are performing in a like Note that under some circumstances, the operating conditions in one manner.
or more steam generators may be found to be more severe than those in other steam generators.
Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
WATERFORD - UNIT 3 3/4 4-15
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TABLE O.4-2 STEAM GENERATOR TUBE INSPECTION 15T SAAFLE M5PECTX)N 2ND SAhrLE NSPECTK)N 350 5AprLE muar-etsmJus Samede Sire Amadt Aceien Required Result Action Raoured Ammedt Asian Ameared A nunsvann of S C-1 None N. A.
N. A.
N. A.
N. A.
Tubes per S. G.
C2 Pbg er sleeve defective C-1 None N. A.
N. A.
l tubes and inspect M 2S tshes in this S. G.
C-2 Plug or sleeve defective C-1 None l
tubes and inspect W 43 tiees in this S. G.
C-2 Pbg er ateswo defeenive l
l C-3 Postenn easien ter C-3 i
easedt of Ibet esegues C3 Perform action for C 3 N. A.
N. A.
remust of first aangde C-3 hopect as tihes in this As other None N. A.
N. A.
S. G. phse or sleeve S. G.s are C-1 l
l defective tubes and i
.n.p.ct 25 tubes in each other S. G.
Notification to NRC pinouant to 150.72ttd(2) to 10CFR Part 50 Some S. G s Perform action for C-2 N. A.
N. A.
C-2 but no -
addnianal S. G. are C-3 Addmonal hopect as tubes in each N. A.
N. A.
S. G. is C-3 S. G. and plug er sleeve l
defective tihen.
Netsfiessian to SWC pusouent to 550.72the(25 of 10CPR Port to 8=
Where n is afie nunter of steem generatore Had during an inspection WATERFORD - UNIT 3 3/4 4-16 Amendment No.117
3/4.4 REACTOR COOLANT SYSTEM BASES
-3/4.4.1 REACTOR C0OLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.20 during all normal operations and anticipated transients.
In MODES 1 and 2 with one reactor coolant loop not in operation, this specification requires that the plant be in at least H0T STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.
In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops or trains (either shutdown cooling or RCS) be OPERABLE.
In MODE 5 with reactor coolant loops not filled, a single shutdown cooling train provides sufficient heat renoval capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling trains be OPERA 3LE.
The operation of one reactor coolant pump or one shutdown cooling (Iow pressure safety injection) pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.
The restrictions on starting a reactor coolant pump in MODES 4 and 5,
'with one or more RCS cold legs less than or equal to 285'F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The l
RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restricting starting of the RCPs to when the secondary water l
temperature of each steam generator is less than 100'F above each of the RCS cold leg temperatures.
3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.
Each safety valve is designed to relieve 4.6 x 105 lbs per hour of saturated steam at the valve setpoint. The relief capacity of a single safety valve is adequate to relieve any overpres-sure condition which could occur during shutdown.
In the event that no safety I
WATERFORD - UNIT 3 8 3/4 4-1 1
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REACTOR COOLANT SYSTEM BASES STEAM GENERATORS (Continued) j based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain t
surveillance of the conditions of the tubes in the event that there is i
evidence of mechanical damage o'r 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 j
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 i
chemistry is not maintained within these limits, localized corrosion may j
likely result in stress corrosion cracking. The extent of cracking during
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plant operation would be limited by the limitaties of steam generator tube i
leakage between the primary coolant system and the secondary coolant system l
(primary-to-secondary leakage - 0.5 gpm ser steam generator). Cracks having a 1
primary-to-secondary leakage less than t11s limit during operation will have an adequate margin of safety to withstand the loads imposed during normal i
o)eration and by postulated accidents. Operating plants have demonstrated j
t1at primary-to-secondary leakage of 0.5 gpm per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in j
excess of this limit will require plant shutdown and an unscheduled j
inspection, during which the leakage tubes will be located and plugged or repaired.
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 or sleeving will be required for all tubes with imperfections exceeding the plugging or repair limit as defined in Surveillance Requirement i
4.4.4.4.
Defective tubes may be repaired by sleeving in accordance with CENS Report CEN-605-P, "Waterford 3 Steam Generator Tube Repair Using Leak Tight
)
Sleeves," Revision 00-P, dated December 1992. Steam generator tube inspections of operating plants have demonstrated the capability to reliably 4
j detect degradation that has penetrated 20% of the original tube wall thickness. Sleeved tubes will be included in the periodic tube inspections
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for the inservice inspection progras j
Whenever the results of any steam generator tubing inservice inspection i
fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior the resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, i
tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
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.k WATERFORD - UNIT 3 8 3/4 4-2 Amendment No. M,117