ML20024J186
| ML20024J186 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/29/1994 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20024J187 | List: |
| References | |
| NUDOCS 9410110207 | |
| Download: ML20024J186 (11) | |
Text
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es erco UNITED STATES g2-j NUCLEAR REGULATORY COMMISSION r
WASHINGTON, D.C. 20566 4001 9.....,d 4
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266
)
i POINT BEACH NUCLEAR PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.154 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated July 18, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
r and the Commission's rules and regulations set forth in 10 CFR 7
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
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 j
conducted in compliance with the Commission's regulations; P
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 i
been satisfied.
[
i i
1 i
I 9410110207 940929 PDR ADOCK 05000266 P
PDR I
. 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-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.154, 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 45 days from the date of issuance.
FOR THE NUCLEAR RECULATORY COMMISSION 7
Allen G. Hansen, Project Manager Project Directorate III-3 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 29, 1994 t
s MC o
+
UNITED STATES y
y-j NUCLEAR REGULATORY COMMISSION r
WASHINGTON, D.C. 20555 4001
....+
WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NVCLEAR PLANT. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 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 July 18, 1994, 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 witn the application, the provisions of the Act, and the rules and regulations of the i
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 amer.dment will not be inimical to the common defense and security or to the health and safety of the public; and j
E.
The issuance of +h'.s amendment is in accordance with 10 CFR Part 51 of the Commiss.sn's regulations and all applicable requirements have been satisfied.
~
6 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to thic 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. 158, 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 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ff'
- l Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 29, 1994 i
i
ATTACHMENT TO LICENSE AMENDMENT N05.154 AND 158 TO 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 TS 15.3.7-4 through TS 15.3.7-4 through TS 15.3.7-8 (4 pages)
TS 15.3.7-9 (6 pages)
generator is supplying the affected 4160/480 Volt buses. After 7 days, both units will be placed 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 /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
1.
One of the four connected safety-related station batteries may be inoperable for a period not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided four battery chargers remain operable with one charger carrying the DC loads of each main DC distribution bus.
j.
If an operating safety-related inverter is rendered inoperable and the associated loads transfer to a non-safety-related power source, the loads shall be transferred back to an operable safety-related inverter within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in hot shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> of inverter inoperability.
k.
If any safeguards bus is deenergized, the applicable LCOs will be j
entered for the affected equipment.
1.
One of the four connected battery chargers may be inoperable for a t
period not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
If an operable battery charger is not.
connected to the affected DC distribution bus within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the operating unit (s) shall be sequentially placed 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 /> and 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> respectively, and placed in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Basis This two unit plant has four 345 KV transmission line interconnections. A 20 MW gas turbine generator, two original and two additional diesel generators are installed at the plant. All of these energy sources will be utilized to provide depth and reliability of service to the Engineered Safeguards equipment through redundant station auxiliary power supply systems.
The electrical system equipment is arranged so that no single contingency can inactivate enough safeguards equipment to jeopardize the plant safety. The 480-volt equipment is arranged on 4 buses per unit. The 4160-volt equipment 1
is supplied from 6 buses per unit.
L Two separate outside sources can serve either unit's low voltage station auxiliary transformer. One is a direct feed from the unit's high voltage station auxiliary transformer and the second is from the other unit's high voltage station auxiliary transformer or the gas turbine via the 13,800' volt 15.3.7-4 gig-gendment No. B4 B7,734, Unit 2 - Amendment No. 88,92,73B,752, JEE,158
I system tie bus H01. The normal power supplies for the A05 and A06 buses are the A03 and A04 buses, respectively.
Separation is maintained in the 4160-volt system to allow the plant auxiliary equipment to be arranged electrically so that redundant items receive their power from the two different buses.
For example, the safety injection pumps are supplied from the 4160 volt buses 1-A05 and 1-A06 for Unit No. I and 2-A05 and 2-A06 for Unit No. 2; the six service water pumps are arranged on 480-volt buses as follows:
two on bus 1-803, one on bus 1-804, one on bus 2-803 and two on bus 2-B04; the four containment fans are divided between 480-volt buses 1-803 and 1-B04 for Unit No. I and 2-B03 and 2-804 for Unit No. 2 and so forth. Redundant valves are supplied from motor control centers 1-B32 and 1-B42 for Unit No. I and 2-832 and 2-B42 for Unit No. 2.
The specifications for the 480 volt safeguards buses, 803 and B04, and the 4160 volt safeguards buses, A05 and A06, direct an independent lineup of power distribution, specifically stating that a normal lineup must be achieved (ali safeguards buses associated with a unit are powered through their normal supply breaker with all safeguards bus tie-breakers open) prior to taking a unit critical and during subsequent power operation.
Operability of the safeguards buses is based on maintaining at least one train of on-site emergency power operable during accident conditions coincident with an assumed loss of offsite power and a single failure in the other train of on-site emergency power.
This includes a failure of a tie-breaker to trip, which under certain conditions could result in an overload and a loss of the associated diesel generator. The LCOs permit abnormal electrical distribution lineups for periods of time in order to facilitate such items as maintenance of normal supply breakers or transformers.
In such cases, bus independence may be relaxed under the conditions specified in the LCO.
Extended use of safeguards bus tie-breakers is allowed under specified, controlled conditions.
For example, when a unit is fully defueled, safeguards and safe shutdown systems and equipment dedicated to that unit are not required. However, spent fuel pool cooling must be maintained.
By limiting the loads supplied by the cross-connected buses, the potential for loss of a Unit 1 - Amendment No. /)4,/,AAA, 15.3.7-5 JBb,)AB,hb2,154 Unit 2 - Amendment No.
,S/,AA,)Ap,
/lla,A46,158
diesel generator due to overloading caused by the failure of a tie-breaker to open is minimized. Operability of shared safeguards systems such as auxiliary feedwater and service water must be maintained as required by their applicable LCOs.
The bus tie-breaker specifications have provisions that the required redundant j
decay heat removal for the shutdown unit and the required redundant shared engineered safety features for the other unit are operable. The specification that applies only to the defueled condition does not have the provision for the required redundant decay heat removal for the shutdown unit.
It has provision for verifying the adequacy of a single train of spent fuel pool cooling in lieu of the consideration of decay heat removal for a reactor in cold shutdown.
The Point Beach DC electrical system has been modified so that each of the four main DC distribution buses, which are shared between the two units, has its own power supplies consisting of a safety-related station battery (DOS, D06, DIOS, D106) and a battery charger.
In addition to these bus-specific power supplies, a swing safety-related battery (0305) is installed which is capable of being connected to any one of the four main DC distribution buses.
Swing battery chamers are also provided. However, one of the four connected battery chargers may be inoperable for up to two hours to allow the transfer to a standby battery charger or return the inoperable battery charger to service. The 2-hour outage time is based on Regulatory Guide 1.93 and reflects a reasonable time to assess plant status and either connect an operable battery charger to the affected bus or prepare to effect an orderly and safe shutdown of the operating unit (s). Under normal circumstances, one battery and one battery charger are connected in each main DC distribution bus. The battery charger normally shall be in service on each battery so that the batteries will always be at full charge in anticipation of a loss-of-AC power incident. Under unusual circumstances, two of the five safety-related batteries may be out of service for a limited period of time provided one of the two out-of-service batteries is returned to service within the time periods specified in Specification 15.3.7.B.I.i.
These limiting conditions l
Unit 1 - Amendment No.gf,B/,J34,J26,15.3.7-6 fnit F Einement No.es,92.Jaa,Jee, J
/N.JE6,158
4 I
for operation ensure that adequate DC power will always be available for starting the emergency generators and other emergency uses.
1 The emergency diesel generators are the sources of standby emergency power.
The support systems necessary to be operable to ensure the operability of the emergency diesel generators (EDGs) are the EDG starting air system, EDG fuel oil system, EDG ventilation system, and EDG DC control power. The standby emergency power supply for a 4160 Volt and associated 480 Volt safeguards bus consists of an operable EDG, including all required support systems, and an operable output breaker to that 4160 Volt safeguards bus.
The LCOs for the standby emergency power supplies require the redundant j
standby emergency power supplies to be started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into these LCOs.
If the standby emergency power supply LC0 is exited within 24
}
hours, then starting of the redundant standby emergency power supplies is not required.
If the LC0 was entered due to a standby emergency power supply failure and the LC0 was exited within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then an evaluation must be completed as soon as possible within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into the LC0 to show that the redundant standby power supplies are not susceptible to that failure f
4 by common cause or the redundant standby emergency power supplies must be started to prove that failure by common cause does not exist within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into the LCO.
I The EDG starting air system is considered operable when 1) all starting air bottles in each bank are operable, 2) the starting air banks can be maintained i
at a minimum pressure of 165 psig, 3) the air bank crossconnect valve is shut unless bank pressures are being equalized and an operator is stationed at the valve during pressure equalization, and 4) all four starting air motors and their associated valves and relays are operable, l
I The EDG fuel oil system is considered operable when I) 11,000 gal. of fuel oil l
I is initially available in the fuel oil storage tank which supplies the diesel generators (Because the EDGs consume approximately 205' gallons of fuel per l
hour when fully loaded, the 11,000 gallon fuel supply in the emergency fuel i
Unit 1 - Amendment NoJR,JE2,154 15.3.7-7 Unit 2 - Amendment No. JB2,JEf>,158
.~
tank provides sufficient fuel to operate one EDG at design load for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.), 2) the EDG day tank for that EDG is operable and for G-01 and G-02 the associated motor-operated fill valve is operable, 3) for G-01 and G-02, at least one of the two base-mounted sump tank fuel oil transfer pumps is operable, and 4) the fuel oil transfer system associated with the EDG is operable. However, the fuel oil transfer system is allowed to be out-of-service for four hours for G01 and G-02 due to a combined four-hour supply of fuel oil in the diesel base and day tanks which do not require a fuel oil transfer pump for flow to the associated EDG. The fuel oil transfer system is allowed to be out-of-service for two hours for G-03 and G-04 due to a two-hour supply of fuel oil in the day tank. The transfer system may be out-of-service f
for longer periods if an appropriate alternate source of fuel is made available to the diesel generators.
The EDG ventilation system is considered operable when diesel room temperature can be maintained s120*F with the diesel engine operating at full load.
Temperature will be maintained s120 *F if 1) all gravity-operated louvers are operable, and 2) both diesel room exhaust fans are operable E for G-01 and G-02; one diesel room exhaust fan is operable and outside air temperature is
$80*F.
I Normal DC control power must energize all DC circuits for the associated EDG to be operable.
The original AEC Safety Evaluation for PBNP states, "0nsite fuel storage capacity is sufficient for a minimum of seven days' operation of the required safety feature loads which is acceptable." Therefore, to satisfy this requirement, at least 34,500 gallons of fuel oil will be maintained available for the emergency diesel generators at Point Beach at all times when EDG operability is required.
If only one 345 KV transmission line is in service to the plant switchyard, a temporary loss of this line would result in a reactor trip (s) if the reactor (s) power level were greater than 50%.
Therefore, in order to maintain Unit 1 - Amendment No.JE2,154 15.3.7-8 Unit 2 - Amendment No.756,158
1
~
l continuity of service and the possibility of self sustaining operations, if only one 345 KV transmission line is in service to any operating reactor (s),
the power level of the affected reactor (s) will be limited to 50%.
If both 345/13.8 KV station auxiliary transformers are out of service, only one reactor will be operated.
The gas turbine will be supplying power to operate safeguards auxiliaries of the operating reactor and acts as a backup j
supply for the unit's normal auxiliaries.
Therefore, to prevent overloading the gas turbine in the event of a reactor trip, the maximum power level for the operating reactor will be limited to 50%. These conservative limits are set to improve transmission system reliability only and are not dictated by safety system requirements.
References FSAR Section 8.
i Unit 1 - Amendment No.154 15.3.7-9 Unit 2 - Amendment No. 158
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