ML20237G499
| ML20237G499 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/12/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G501 | List: |
| References | |
| NUDOCS 8708240106 | |
| Download: ML20237G499 (10) | |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION n
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,1 WASmNGTON, D. C. 20555
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8 LOUISIANA POWER AND LIGHT COMPANY 00CKET NO. 50-382 WATERFORD STEAM ' ELECTRIC STATION, UNI 1 3 AMEN 0HENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Louisiana Power and Light Company (the licensee) dated March 26, 1987, as supplemented by letter dated May 8, 1987, 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, 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 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.
9708240106 870012 ADOCK 0500 2
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" * ' i 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-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 22, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION G,
dei Ls-o Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 1987
ATTACHMENT TO LICENSE AMENDMENT NO. 22 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 contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert VI VI 3/4 4-9 3/4 4-9 3/4 4-9a 3/4 4-10 3/44-10(Nochange)
B 3/4 4-2 B 3/4 4-2
4 INDEX
.1
' LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE
- 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................
3/4 2-1 3/4.2.2 PLANAR RADIAL PEAKING FACT 0RS..........................
3/4 2-3 3/4.2.3 AZ IMUTHA L POWE R T I LT....................................
3/4 2-4 3/4.2.4 DNBR MARGIN.............................................
3/4 2-6 3/4.2.5 RCS FLOW RATE...........................................
3/4 2-10
' 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................
3/4 2-11 3/4.2.7 AXIAL SNAPE INDEX.......................................
3/4 2-12 3/4.2.8 PRESSURIZER PRESSURE....................................
3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION......................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................
3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION.................
3/4 3-28 INCORE DETECT 0RS.....................................
3/4 3-34 SEISMIC INSTRUMENTATION..............................
3/4 3-35 METEOROLOGICAL INSTRUMENTATION.......................
3/4 3-38 REMOTE SHUTDOWN INSTRUMENTATION......................
3/4 3-41 ACCIDENT MONITORING INSTRUMENTATION..................
3/4 3-44 1
CHEMICAL DETECTION SYSTEMS...........................
3/4 3-47 FIRE DETECTION INSTRUMENTATION.......................
3/4 3-49 LOOSE-PART DETECTION INSTRUMENTATION.................
3/4 3-54 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................
3/4 3-55 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....................................
3/4 3-60 3/4.3.4 TUR8INE OVERSPEED PROTECTION............................
3/4 3-68 WATERFORD - UNIT 3 V
INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER 0PERATION.............................
3/4 4-1 HOT STANDBY.............................................
3/4 4-2 HOT SHUT 00WN............................................
3/4 4-3 COLD SHUTDOWN - LOOPS FILLED............................
3/4 4-5 COLD SHUTDOWN - LOOPS NOT FILLED........................
3/4 4-6 3/4.4.2 SAFETY VALVES SHUTD0WN.............................................
3/4 4-7 0PERATING..................................'..........
3/4 4-8 3/4.4.3 PRESSURIZER PRESSURIZER..........................................
3/4 4-9 AUXILIARY............................................
3/4 4-9a 3/4.4.4 STEAM GENERATORS........................................
3/4 4-10 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS............................
3/4 4-17 OPERATIONAL LEAKAGE..................................
3/4 4-18 3/4.4.6 CHEMISTRY...............................................
3/4 4-21 3/4.4.7 SPECIFIC ACTIVITY.......................................
3/4 4-24 3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOP COOLANT SYSTEM...............................
3/4 4-28 PRESSURIZER HEATUP/C00LD0WN..........................
3/4 4-33 OVERPRESSURE PROTECTION SYSTEMS......................
3/4 4-34 3/4.4.9 STRUCTURii. INTEGRITY....................................
3/4 4-36 3/4.4.10 REACTOR COOLANT SYSTEM VENTS............................
3/4 4-37 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i i
3/4.5.1 SAFETY INJECTION TANKS..................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T
> 350 F..........................
3/4 5-3 avg 4
3/4.5.3 ECCS SUBSYSTEMS - T
< 350 F..........................
3/4 5-8 l
avg l
3/4.5.4 REFUELING WATER STORAGE P00L............................
3/4 5-9
)
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WATERFORD - UNIT 3 VI Amendment No. 22
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- 6 1
REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4,3.1 The pressurizer shall be OPERABLE with:
A steady-state water volume greater than or equal to 26% indicated a.
level (350 cubic feet) but less than or equal to 62.5% indicated level (900 cubic feet), and, i
b.
At least two groups of pressurizer heaters powered from Class IE buses each having a nominal capacity of 150 kW.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With only one group of the above required pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1 SURVEILLANCE REQUIREMENTS 4.4.3.1.1 The pressurizer water volume shall be determined to be within its l
limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 l
4.4.3.1.2 The capacity of each of the above required groups of pressurizer l
heaters shall be verified to be at least 150 kW at least once per 92 days.
4.4.3.1.3 The emergency power supply for the pressurizer heaters shall be l
demonstrated OPERABLE at least once per 18 months by:
a.
Verifying the above pressurizer heaters are automatically shed from the emergency power sources upon the injection of an SIAS test signal.
b.
Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.
WATERFORD - UNIT 3 3/4 4-9 Amendment No. 22
' AUXILIARY SPRAY LIMITING CONDITION FOR OPERATION 3.4.3.2 Both auxiliary spray valves shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With only one of the above required auxiliary spray' valves OPERABLE, a.
restore both valves to OPERABLE status within 30 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the 1
following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With none of the above required auxiliary spray valves OPERABLE, restore at least one valve to OPERABLE status within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The auxiliary spray valve shall be verified to have power available to each valve every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.3.2.2 The auxiliary spray valves shall be cycled at least once per 18 months.
1 i
WATERFORD - UNIT 3 3/4 4-9a Amendment No. 22
l T'
-3/4.4.4 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.4' Each steam generator shall be OPERABLE.
~
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200*F.
SURVEILLANCE REQUIREMENTS 1
4.4.4.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.
4.4.4.1 Steam Generator Sample 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 4.4-1.
4.4.4.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample-size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.4.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.4.4.
The tubes selected for each inservice inpection shall include at least 3% of the total number of tubes in all steam generators; the tubes s61ected for these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry a.
indicates critical areas to be' inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
WATERFORD - UNIT 3 3/4 4-10
3/4.4 REACTOR COOLANT SYSTEM s
BASES 3/4.4.1 REACTOR COOLANT 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 In MODES I and 2 during all normal operations and anticipated transients.
with one reactor coolant loop not in operation, this specification requires that the plant be in at least HOT STANDBY within I hour.
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 removal 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 OPERABLE.
The operation of one reactor conlant pump or one shutdown cooling (low 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 l
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 The system, which could exceed the limits of Appendix G to 10 CFR Part 50.
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 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
)
Each safety valve is designed pressurized above its Safety Limit of 2750 psia.
The to relieve 4.6 x 105 lbs per hour of saturated steam at the valve setpoint.
relief capacity of a single safety valve is adequate to relieve any overpres-In the event that no safety sure condition which could occur during shutdown.
WATERFORD - UNIT 3 8 3/4 4-1
REACTOR COOLANT SYSTEM BASES SAFETY VALVES (Continued) l valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.
In addition, the overpressure protection system provides a diverse means of protection against RCS overpressurization at low temperatures.
During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its rafet) limit of 2750 psia.
The combined relief capacity of these valves is sufficiun,.o 1 M t the cy:ta.:.
pressure to within its Safety Limit of 2750 psia following a complete loss of j
turbine generator load while operating at RGcD THERMAL POWER and assuming no reactor trip until the first Reactor Protective System tr ip setpoint (Pressurizer i
Pressure-High) is reached and also assuming no operation of the steam dump valves.
l Demonstration of the safety valves' lift settings will occur only during reactor shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
3/4.4.3 PRESSURIZER An OPERABLE pressurizer provides pressure control for the Reactor Coolant i
System during operations with both forced reactor coolant flow and with natural circulation flow.
The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure con-trol, remain covered with water to prevent failure, which could occur if the heaters were energized while uncovered.
The maximum water level in the pres-surizer ensures that this parameter is maintained within the envelope of l
operation assumed in the safety analysis.
The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble will be provided to accommodate pressure surges during operation.
The steam bubble l
also protects the pressurizer code safety valves against water relief.
The l
requirement to verify that on an SIAS test signal the pressurizer heaters are I
automatically shed from the emergency power sources is to ensure that the non-Class 1E heaters do not reduce the reliability of or overload the emergency power source.
The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability to control Reactor Coolant System pressure and establish and maintain natural circulation.
The auxiliary pressurizer spray is used to depressurize the RCS by cooling j
the pressurizer steam space. The auxiliary pressurizer spray is used during those periods when normal pressurizer spray is not available, such as the later stages of a normal RCS cooldown. The auxiliary pressurizer spray also distri-butes boron to the pressurizer when normal pressurizer spray is not available.
The auxiliary pressurizer spray is used, in conjunction with the throttling of the HPSI pumps, during the recovery from a steam generator tube rupture acci-I dent. The auxiliary pressurizer spray is also used during a natural circulation 1
l cooldown as a safety-related means of RCS depressurization to achieve shutdown cooling system initiation conditions and subsequent COLD SHUTDOWN per the require-i I
ments of Branch Technical Position (RSB) 5-1.
1 3/4.4.4 STEAM GENERATORS J
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 l
WATERFORD - UNIT 3 B 3/4 4-2 Amendment No. 22 I
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