ML20148T802
| ML20148T802 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/03/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148T805 | List: |
| References | |
| NUDOCS 9707090325 | |
| Download: ML20148T802 (9) | |
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[f UNITED STATES i
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON D.C. 30666 4 001 o,s...../
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 l
WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 11, 1997, complies with the standards and i
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 applic: tion, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by J
this amendment can be conducted neithout 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 Comission's regulations and all applicable requirements have been satisfied.
i 7707090325 970703 PDR ADOCK 05000382 P
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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 i-L amended-to read as follows:
(2) Technical Snecifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through Amendment No.131, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the 2
Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance to be l
implemented within 60 days.
l FOR THE NUCLEAR REGULATORY COMISSION YAbrAJA 0?
Chandu P. Patel, Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 3, 1997 l
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ATTACHMENT TO LICENSE AMENDMENT NO.131 l
TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with i
the attached pages. The revised pages are identified by Amendment number and i
contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
4 REMOVE PAGES INSERT PAGES j
3/4 6-18 3/4 6-18 B 3/4 6-3 8 3/4 6-3 l
B 3/4 6-4 B 3/4 6-4 I
B 3/4 6-4a B 3/4 6-4a B 3/4 6-5 B 3/4 6-5 3
4 4
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l CONTAINMENT SYSTEMS SURVEILLANCERE00IREMENTSiContinued) 2.
Verifying that upon a recirculation actuation test signal, the safety injection system sum) isolation valves open and that a recirculation mode flow pati via an OPERABLE shutdown cooling i
heat exchanger is established.
3.
Verifying that each spray pump starts automatically on a CSAS test signal.
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t At least once per 10 years by performing an air or smoke flow test l
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through each spray header and verifying each spray nozzle is unobstructed.
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l WATERFORD - UNIT 3 3/4 6-17 Amendment No. 89 llDV 17 Ti&3 j
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I CONTAINMENT SYSTEMS GONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent trains of containment cooling shall be OPERABLE with two fan coolers to each train.
APPLICABlLilY: MODES 1,2,3, and 4.
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ACTION:
i With one train of containment cooling inoperable, restore the inoperable train 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 />; restore the inoperable containment cooling train to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i SURVEILLANCE REQUIREMENTS I
I 4.6.2.2 Each train of containment cooling shall be demonstrated OPERABLE:
l a.
At least once per 31 days by:
1.
Starting each operational fan not already mnning from the control room and verifying that each operational fan operates for at least 15 minutes.
l 2.
Verifying a cooling water flow rate of greater than or equal to 625 gpm to i
each cooler.
i b.
At least once per 18 months by:
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1 1.
Verifying that each fan starts automatically on an SIAS test signal.
l 2.
Verifying a cooling water flow rate of greater than or equal to 1200 gpm to each cooler.
3.
Verifying that each cooling water control valve actuates to its full open position on a SIAS test signal.
WATERFORD - UNIT 3 3/4 6-18 Amendment No. 30,131
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CONTAINMENT SYSTEMS BASES j
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM (Continued)
Leakage integrity tests with a maximum allowable leakage rate for purge supply and
-l exhaust isolation valves will provide eariy indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops. The 0.60 La 1
leakage limit shall not be exceeded when.the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
i 314 6.2 DEPRESSURIZATION AND COOLING SYSTEMS l
l 3/4 6 2.1 and 3/4 6.2.2 CONTAINMENT SPRAY SYSTEM and CONTAINMENT COOLING
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SYSTEM l
N OPERABILITY of the Containment Spray System and the Containment Cooling l
System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or MSLB for any double-ended break of the largest reactor coolant pipe i
or main steam line. Under post-accident conditions these systems will maintain the containment pressur9 below 44 psig and temperatures below 269.3*F during LOCA l
conditions or 413.5'F during MSLR conditions. The systems also reduce the containment j
pressure by a factor of 2 from its post-accident peak within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, resulting in lower i
containment leakage rates and lower offsite dose rates.
The Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere under post-LOCA conditions to maintain doses in i
accordance with 10 CFR Part 100 limits as described in Section 6.5.2 of the FSAR.
l in MODE 4 when shutdown cooling is placed in operation, the Containment Spray j
System is realigned in order to allow isolation of the spray headers. This is necessary to i
. avoid a single failure of the spray header isolation valve causing Reactor Coolant System depressurization and inadvertent spraying of the containment.' To allow for this realignment, l
the Containment Spray System may be taken out-of-service when RCS pressure is 5 400 psia. At this reduced RCS pressure and the reduced temperature associated with entry into MODE 4, the probability and consequences of a LOCA or MSLB are greatly reduced. The Containment Cooling System is required OPERABLE in MODE 4 and is available to provide depressurization and cooling capability.
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A train of Containment Cooling consists of two fans (powered from the same safety l
bus) and their associated coolers (supplied from the same cooling water loop). One j
Containment Cooling train and Containment Spray train has sufficient capacity to meet post j
accdont heat removal requirements.
Operating each containment cooling train fan unit for 15 minutes and verifying a cooling I
water flow rate of 625 gpm ensures that all trains are OPERABLE and that all associated l
controls are functioning properly. It also ensures that blockage, fan or motor failure, or excessive vibration can be detected and corrective action taken.
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l WATERFORD - UNIT 3 B 3/4 6-3 AMENDMENT NO. 80,131 i
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i CONTAINMENT SYSTEMS t
BASES t
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i 3/4 6 2.1 and 3/4.6.2.2 CONTAINMENT SPRAY SYSTEM and CONTAINMENT COOLING
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SYSTEM (con't)
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i The 18 month Surveillance Requirement verifies that each containment cooling fan actuates upon receipt of an actual or simulated SlAS actuation signal. The 18 month frequency is based on engineering judgment and has been shown to be acceptable through l
l operating experience, t
k4 Verifying a cooling water flow rate of 1200 gpm to each cooling unit provides assurance I
l that the design flow rate assumed in the safety analyses will be achieved. The safety
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analyses assumed a cooling water flow rate of 1100 gpm. The 1200 gpm requirement accounts for measurement instrument uncertainties and potential flow degradation. Also considered in selecting the 18 month frecuency were the know reliability of the Cooling Water System, the two train redundancy, and the low probability of a significant degradation of flow occurring between surveillances. The flow measurement for the 18 month test shall be done in a configuration equivalent to the accident lineup to ensure that in an accident situation f
i adequate flow will be provided to the containment fan coolers for them to perform their safety l
function.
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i Verifying that each velve actuates to the full open position provides further assurance l
that the valves will travel to their full open position on a Safety injection Actuation Signal.
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3/4 6.3 CONTAINMENT ISOLATION VALVES i
The OPERABILITY of the containment isolation valves ensures that the containment l
l atmosphere will be isolated from the outside environment in the event of a release of i
radioactive material to the containment atmosphere or pressurization of the coniainment and is consistent with the requirements of GDC 54 through GDC 57 of Appendix A to 10 CFR l
Part 50. Containment isolation within the time limits specified for those isolation valves l
des 3gned to close automatically ensures that the release of radioactive material to the j_
environment will be consistent with the assumptions used in the analyses for a LOCA.
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The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing an
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operator, who is in constant communication with control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that i
environmental conditions will not preclude access to close the valves and that this action will j
prevent the release of radioactivity outside the containment.
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" Containment isolation Valves", previously Table 3.6-2, have been incorporated into j
Plant Procedure UNT 005-026.
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3/4.6.4 COMBUSTIBLE GAS CONTROL I
The OPERABILITY of the equipment and systems required for the detection and
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control of hydrogen gas ensures that this equipment will be available to maintain the j
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WATERFORD - UNIT 3 B 3/4 64 Amendment No. ;;r4440,131 l
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j; CONTAINMENT SYSTEMS I
BASES i
j 3/4.6.4 COMBUSTIBLE GAS CONTROL (Continued) hydrogen concentration within containment below its flammable limit during post-LOCA l
conditions. Either recombiner unit is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
SURVEILLANCE REQUIREMENT SR 4.6.4.2.s requires performance of a system functional test for each hydrogen recombiner to ensure that the recombiners are operational and can attain and sustain the temperature necessary for hydrogen recombination. In particular, this SR requires verification that the minimum heater sheath temperature increases to k 700'F in :s 90 minutes. After reaching 700*F, the power is increased to maximum for approximately 2 minutes and verified to be k 60 kW.
l SURVEILLANCE REQUIREMENT SR 4.6.4.2.b ensures that there are no physical problems that could affect recombiner operation. Since the recombiners are mechanically passive, they are not subject to mechanical failure. The only credible failures involve loss of power, blockage of the intamal flow path, missile impact, etc. A visual inspection is sufficient to determine abnormal conditions that could cause such failures.
SURVEILLANCE REQUIREMENT SR 4.6.4.2.c requires performance of a resistance to ground test for each heater phase to ensure that there are no detectable grounds in any i
heater phase. This is accomplished by verifying that the resistance to ground for any heater phase is k 10,000 ohms.
3/4.6.5 VACUUM RELIEF VALVES The OPERABILITY of the primary containment to annulus vacuum relief valves with a setpoint of less than or equal + 0.3 psid ensures that the containment intemal pressure differential does not become more negative than the containment design limit for intomal pressure differential of 0.65 psi. This situation would occur, for the worst case, if all containment heat removal systems (containtnent spray, containment cooling, and other HVAC systems) were inadvertently started with only one vacuum relief valve OPERABLE.
3/4 6.6 SECONDARY CONTAINMENT 3/4.6.6.1 SHIELD BUILDING VENTILATION SYSTEM The OPERABILITY of the shield building ventilation systems ensures that containment vessel leakage occurring during LOCA conditions into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere. This requirement is necessary to meet the assumptions used in the safety analyses and limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during LOCA conditions.
WATERFORD - UNIT 3 B 3/4 6 4a Amendment No. 440,131
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CONTAINMEN SYSTEMS l
BASES 3/4.6.6.1 SHIELD BUILDING VENTILATION SYSTEM (Continued) i i
Operation of the system wb the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> continuous over a 31-l l
day period is sufficient to redur.a tne buildup of moisture on the adsorbers and HEPA filters.
t Obtaining and analyzing charrcal samples after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of adsorber operation (since the last sample and analysis) ens ira '. hat the adsorber maintains the efficiency assumed in the l
safety analyses and is consisten' with Regulatory Guide 1.52.
3/4 6.6.2 SHIELD BUILDING INTEGRITY i
SHIELD BUILDING INTEGRITY ensures that the release of radioactive materials from the primary containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with operation of the shield building ventilation system, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
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3/4.6.6.3 SHIELD BUILDING STRUCTURAL INTEGRITY i
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This limitation ensures that the structural integrity of the containment shield building will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to provide (1) protection for the steel vessel from extemal
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missiles, (2) radiation shielding in the event of a LOCA, and (3) en annulus surrounding the 4
i steel vessel that can be maintained at a negative pressure during accident conditions.
l A visualinspection is sufficient to demonstrate this capability.
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WATERFORD - UNIT 3 B 3/4 6-5 Amendment No.131
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