ML20029D058
| ML20029D058 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/20/1994 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029D059 | List: |
| References | |
| NUDOCS 9405030353 | |
| Download: ML20029D058 (11) | |
Text
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.7h UNITED STATES
-[g.lg]l_f)t[j NUCLEAR REGULATORY COMMISSION p
y wASPNGTON, D.C. FM0001
\\..a...f WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 A_t1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendmert by Wisconsin Electric Power Company (the licensee) dated Februaiy 26, 1993, complies with the standards and requirements cf the Atomic Energy Act of 1954, as amended (the Act), :nd th'.e Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities author 1.
by this amendment can be conducted without endangering the health and safet v of the public, and (ii) that such activities will be conduct-compliance with the Commission's regulations; D.
The issuance of thi ' 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.
l 9405030353 940420 PDR ADOCK 05000266 P
./ 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 147, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'I0'? l Allen G. Hansen, Project Manager
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/
Project Directorate III-3 j
j Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: t
'l 20, 1994 i
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,t UNITED STATES
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j NUCLEAR REGULATORY COMMISSION
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o WASHlNoToN, D.C. 20565-0001 f
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RISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.151 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated February 26, 1993, 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.
G
-]
2.
Accordingly, the license'is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 151, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Vl 5
pg S 77 t-a
~
Allen G. Hansen, Project Manager j
/ Project Directorate III-3
~ /
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 20, 1994
')
ATTACHMENT TO LICENSE AMENDMENT NOS.147 AND 151 T9 FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 15.3.4-2 15.3.4-2 15.3.4-2a 15.3.4-2a 15.3.4-2b 15.3.4-2b i
15.3.4-2c 15.4.8-1 15.4.8-1 15.4.8-2 z
3.
A minimum of 13,000 gallons of water per operating unit in the condensate storage tanks and an unlimited water supply from the lake via either leg of the plant Service Water System, 4.
System piping and valves required to function during accident conditions directly associated with the above components operable.
5.
Both atmospheric steam dump lines shall be operable.
If either of the atmospheric steam dump lines is determined to be inoperable, restore the inoperable line to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If operability cannot be restored, be in hot shutdown within six hours and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
The iodine-131 activity on the secondary side of the steam generator shall not exceed 1.2 pCi/cc.
C.
During power operation the requirements of 15.3.4. A.2.a and b may be modified to allow the following components to be inoperable for a specified time.
If the system is not restored to meet the requirements of 15.3.4. A.2.a and b within the time period specified, the specified action must be taken.
If the requirements of 15.3.4. A.2.a and b are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the appropriate reactor (s) shall be cooled down to less than 350 F.
3.
Two Unit Operation - One of the four operable auxiliary feedwater pumps may be out-of-service for the below specified times. A turbine driven auxiliary feedwater pump may be out of service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine driven auxiliary feedwater pump cannot be restored to service within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period the assoc ~iated-reactor shall be in hot shutdown within the next'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A motor driven auxiliary feedwater pump-may be out of service for up to 7 days.
If the inoperable motor driven auxiliary feedwater pump cannot be restored to service within the 7 day time period both of the reactors shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Unit 1 - Amendment No. J39,147 Unit 2 - Amendment No. 134,151 15.3.4-2
l 2.
Single Unit Operation - One of the three operable auxiliary feedwater pumps associated with a unit may be out-of-service for the below specified timer. The turbine driven auxiliary feedwater pump may be l.
out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine driven auxiliary feedwater pump cannot be restored to service within that 72-hour time period, the reactor shall be in hot shutdown within the next'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Either one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days.
If the motor driven auxiliary feedwater pump cannot be restored to service within that 7-day period the operating unit shall b:: in not shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l D.
The crossover steam dump system shall be operable.
If the crossover steam dump system is determined to be inoperable, reduce power to less than 480 MWe (gross) within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
E.
During power operation, at least one of the turbine overspeed protection systems that trip the turbine stop valves or shut the turbine governor valves shall be operable.
If all three systems are determined to be inoperable, isolate the turbine from the steam supply within the next six hours.
F.
Should one of the turbine stop valves or governor valves be declared inoperable, restore the inoperable valve to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If operability cannot be restored, perform one of the following actions:
1.
Shut the affected valve within the next six hours.
2.
Isolate the turbine from the steam supply within the next six hours.
Basis A reactor shutdown from power requiras removal of core decay heat.
Immediate decay heat removal. requirements at. normally satisfied by the steam bypass to the condenser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the capability to return feedwater flow to Unit 1 - Amendment No. JA7,147 Unit 2 - Amendment No. A77,151 15.3.4-2a
the steam generators is provided by operation of the turbine cycle feedwater system.
The eight main steam safety valves have a total ccmbined rated capability of u
6,664,000 lbs/hr.
The total full power steam flow is 6,620,000 lbs/hr, therefore eight (8) main steam safety valves will be able to relieve the total full-power steam flow if necessary.
In the unlikely event of complete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the availability of either the steam-driven auxiliary feedwater pump or one of the two' motor-driven auxiliary steam generator feedwater pumps, and steam discharge to the atmosphere via the main steam safety valves or atmospheric relief valves.
One motor-driven auxiliary feedwater pump can supply sufficient feedwater for removal of decay heat from a unit.
The minimum amount of water in the condensate _ storage tanks ensures the ability to maintain each unit in a hot shutdown condition for at least one hour concurrent with a loss of all AC power.
An unlimited supply is available from the lake via either leg of the plant service water system for an indefinite time period.
ll Each of the AFW pumps possesses a low suction pressure trip that will protect it should a loss of feedwater occur. Additionally, should a steam generator tube rupture occur, the motor-operated steam admission valves for the turbine-driven AfW pumps serve as isolation boundaries for the affected steam generator.
The crossover steam dump system is designed to prevent the turbine from exceeding 132% of rated speed following a unit trip. The system is armed at approximately 430 MWe.
The system receives input from, and is actuated when the turbine
{
auxiliary governor and/or the Independent Overspeed Protection System (IOPS) senses an overspeed condition.
The system consists of four pilet-operated dump
'l valves, with only three valves being necessary to achieve the required overspeed protection. However, in order to meet single failure criteria, the crossover steam dump system shall be declared inoperable if any one of the four dump valves is declared inoperable.
l Unit 1 - Amendment No. J)) 147 Unit 2 - Amendment No. J77,151 15.3.4-2b
'l
T In addition to the crossover steam dump system, there are three other systems that protect the_ turbine from an overspeed condition.
The first feature is the mecnanical overspeed trip mechanism which consists of-an eccentric weight located in the turbine rotor extension shaft.
The second feature uses the turbine
. auxiliary governor to sense turbine overspeed using the auxiliary speed tachometer.
The third feature is 10PS. This system monitors turbine speed electrically and consists of three independent speed channels.
The actuation of two of three channels will generate a trip signal.
The mechanical overspeed trip mechanism and 10PS cause the turbine stop valves to trip and the turbine governor valves to shut, while the auxiliary governor causes only the governor valves to shut. A turbine stop valve shall be declared inoperable if it does not trip shut following a valid overspeed signal. A turbine governor valve shall be declared inoperable if it does not respond properly following a valid overspeed signal.
The atmospheric steam dump lines are required to be operable because they are relied upon, following a steam generator tube rupture coincident with a loss of A.C. power, to cool down the Reactor Coolant System to RHR entry conditions. An atmospheric steam dump line is considered operable if it is capable of providing-the controlled relief of main steam flow necessary to perform the RCS cooldown.
Isolating an atmospheric steam dump line does not render it inoperable if the line can be unisolated and the RCS can still be cooled down to RHR entry conditions, through local or remote operation, within the time period required by the applicable FSAR accident analyses.
J s
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1 l
Unit 1 - Amendment No. 173,147 Unit 2 - Amendment No. 137,151 15.3.4-2c
. ~.
Y 15.4.8 AUXILIARY FEEDWATER SYSTEM ellR icability l
Applies to periodic testing requirements of the turbine-driven er.d a
motor-driven auxiliary feedwater pumps.
i Ob.iective To verify..the operability of the Auxiliary Feedwater System and its ability to respond properly when required.
j jnecification 1
1.
a.
Each motor driven auxiliary feedwater pump will be started
-l quarterly.
.j b.
Each steam turbine driven auxiliary feedwater pump will be started quarterly provided steam is available.
If the test I
comes due when not at power operation, the test shall be performed during the subsequent startup within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering power operation.
The auxiliary feedwater pumps discharge valves and the service c.
water supply valves on the suction side will be tested by operator action quarterly.
2.
These tests shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have operated properly.
Basis The quarterly testing of the auxiliary feedwater pumps will verify their operability. The quarterly test of the steam driven pumps will be a fast start test with no prior warmup.
Proper functioning of the steam turbine admission valves and the start of the feedwater pumps will demonstrate j
the integrity of the steam driven pumps.
The ability to both open and shut l
1 Unit 1 - Amendment No. p 3.147 15.4.8-1 Unit 2-AmendmentNo.}T.151 1
(]
the turbine-driven AFW pump motor-operated steam admission valves will be demonstrated since these valves serve as isolation boundaries should a steam generator tube rupture occur. Verification of correct operation will be made both from instrumentation within the main control room and direct visual observation of the pumps.
Reference FSAR - Sections 10.4 FSAR - Section 14.1.7 FSAR - Section 14.2.5 j
Unit 1 - Amendment No. A4),147 15.4.8-2 Unit 2 -' Amendment No. J37,151 e