ML20198E342
| ML20198E342 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/23/1992 |
| From: | Samworth R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198E348 | List: |
| References | |
| NUDOCS 9212070040 | |
| Download: ML20198E342 (14) | |
Text
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%b UNITED STATES O"
t NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LI{DLSE A'nendment No.136 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 September 7, 1990, as supplemented May 10, 1991 and September 11, 1992, 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 f th in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the AG, 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.
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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136 are hereby incorporated in the license.
The licensee shall operate the facilo in accordance with the Technical Specifications.
9212070040 921126 PDR ADOCK 05000266 P
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3.
This license amendment is effective ime11ately upon issuance. The Technical Specifications are to be irapleciented no later than December 31, 1992.
FOR THE NUCLEAR REGULATORY COMMISSION Robert B. S mworth, Sr.
roj ct ager Project Directorate 111-3 Division of Reactor Projects ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: Noverher 23. 1992 a
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UNITED STATES 8'
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NUCLEAR REGULATORY COMMISSION e
HASHING TON, 0. C. 206M
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WISCONSIN ELECTRIC POWER COMPANY j
DOCKET NO. 50-301 i
POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACillTY OPERATING LICENSE Amendment No. < 40 j
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 September 7,1990, as supplemented May 10, 1991 and September 11, 1992, complies with the standards and requirements o< 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 tIie-application, the provisiens of the Act, and the rules-and regulations of the l
Comission; i
e C.
There'is reasonable assurance (1) that the activities authorized by t
this ameridment 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.
2.
Accordingly, the license is amended by changes to tha Technical Specifications as indicated in the attachment to this license amendment, and paragraph.3.8 of Facility Operating License No. DPR-27 is hereby l-amended to read as follows:
l-B.
Technical Soecifications
-The Technical Specifications contained in Apaendices A and B, as i
revised through Amendment No. 140, are heresy incorporated in the -
L license.
The licensee shall operate the facility in accordance with L
the Technical Specifications.
1
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-.- _,_.._ _. ~ _ _
. 3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented no later than December 31, 1992.
FOR Tile NUCLEAR REGULATORY COMMISSION fp 9
obertB.Smworth,Sr.9rojectH[_ager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation 2
Attachment:
Changes to the Technical Specifications Date of issuance: November 23, 1992 J
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_ _ -. _ - _ _ - _ _ ~ _ _ - -. - _ - -. _.
ATTACHMENT TO LICENSE AMENDMENT N05.136 AND 140 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 QQCKET N05. 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 15.3.7-1 15.3.7-1 15.3.7-2 15.3.7-2 15.3.7-3 15.3.7-3 15.3.7-5 15.3.7-5 15.3.7-6 15.3.7-6 15.4.6-2 15.4.6-2 15.4.6-3 15.4.6-3 15.4.6-4 15.4.6-4 l
~, _ _
_. _.. ~..
15.3.7 AUXILIARY ELECTRICAL SYSTEMS
@flicability Applies to the availability of off-site and on-site electrical power for plant power operation and for the operation of plant auxiliaries.
0Alective To define those conditions of electrical power availability necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing availability of engineered safeguards.
Specification A.1 Under normal conditions neither one nor both reactors shall be made critical unless the following conditions are met:
a.
At least two 345 KV transmission lines are in service, b.
The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the reactor (s) to be taken critical are in service; or one 345/13.8 KV station auxiliary transformer and the associated 13.8/4.16 KV station auxiliary transformer (s) are in service with the gas turbine operating.
c.
4160 Volt unit supply buses A03 and A04 for the unit to be taken critical are energized from their normal supply, d.
4160 Volt safeguards buses A05 and A06 for the unit (s) to be taken critical are independently energized from their normal supply and both units' A05/A06 bus tie breakers are removed from their cubicles.
e.
480 Volt buses B03 and B04 for the unit (s) to be taken critical are independently energized from their normal supply and both units' B03/B04 tie breakers are open with control power removed, f.
A fuel supply of 11,000 gallons is available; and both diesel generators are operable.
9 Four of the five safety-related station batteries and all four of the main DC distribution systems are operable.
h.
Four battery chargers are operable with one charger carrying the DC loads on each DC main distribution bus: D01, 002 D03 and 004.
Ur,1 - Amendment No.EA,87, 134, 136 15.3.7-1 Unit 2 - Amendment No.BE.92, JJS, 140
A.2 Under abnormal conditions including Black Plant startup, one reactor may be maoe critical providing the following conditions are met:
a.
One 345 KV transmission line is in service; or the gas turbine is operating, b.
The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the unit to be taken critical are in service; or the associated 13.8/4.16 KV station auxiliary transformer is in service and the gas turbine is operating.
c.
Peactor power level is limited to 50% rated power until 2 or more transmission lines are restored to service, d.
4160 Volt buses A03 and A04 for the unit to be taken critical are energized from their normal supply.
e.
4160 Volt safeguards buses A05 and A06 for the unit to be taken critical are independently energized from their normal or emergency power supply and both units' A05/A06 bus tie breakers are removed from their cubicles.
f.
480 Volt safeguards buses B03 and B04 for the unit to be taken critical are independently energized f a - +Seir normal or emergency power supply and both units' B03/B04 bus le beu ar< wren with control power removed.
g.
A fuel supply of 11,000 0 10 6 f.uji? scie; and both diesel generators 4
are operable.
h.
Four of the five safety-telated Ftation batteries and all four of the main DC distribution systems are operable.
i.
Four battery chargers are operable with one charger carrying the DC loads of each main DC distribution bus:
D01, 002. 003 and 004.
I B.1 During power operation of one or both reactors, the requirements of 15.3.7.A.1 may be modified to allow the following arrangements of systems and components:
a.
if the 345 KV lines are reduced to only one, any operating reactor (s) must be promptly reduced to, and limited to. 50% power.
If all 345 KV lines are lost, any operating reactor (s) will be reduced to supplying its auxiliary load, until one or more 345 KV transmission lines are again available.
b.
If both 345/13.8 KV auxiliary transformers are out of service and only the gas turbine is operating, only one reactor will remain operating and it will be limited to 50% power.
The second reactor will be placed in the hot shutdown condition.
l Unit 1 - Amendment No. 84,87.734.136 15.3.7-2 Unit 2 - Amendment No. 88.92.738, 140 I
c.
If the 13.8/4.16 KV auxiliary transformers are reduced to only one, the reactor associated with the out of service transformer must be placed in the hot shutdown condition.
d.
Either bus A03 or A04 may be out of service for a period not exceeding 7 days provided both diesel generators are operable and the associated diesel generator is operating and providing power to the engineered safeguard bus normally supplied by the out of service bus.
e.
With a unit in cold or refueling shutdown, one pair of buses. A05 and A06 or 803 and B04, for that shutdown unit, may be tied together through their common tie breaker for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
If the tie breaker cannot be opened or the conditions of 15.3.7.B.1.f met within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the operating unit shall be placed in the hot shut-down condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
f.
With a unit fully defueled, one pair of buses for the defueled unit, A05 and A06 or 803 and B04, may be tied together through their common tie breaker in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided:
- 1) An evaluation is performed to show that the loads that remain or can be energized by the buses will not cause a potential overload of the associated diesel generator.
The applicable Limiting Conditions for Operation of the equipment removed from service shall be entered for operating unit.
- 2) A single train of spent fuel cooling is adequate to cool the spent fuel pool.
9 One diesel generator may be inoperable for a period not exceeding 7 days provided the other diesel generator is tested daily to ensure operability and the engineered safety features associated with this diesel generator shall-be operable.
This LCO shall not be allowed in conjunction with e. or f. above, h.
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.
l Unit 1 - Amendment No. BA.87, M4,136 15.3.7-3 Unit 2 - Amendment No. 88,92, M38'140 -
I
could result in an overload and a loss of the associated diesel generator.
The LCOs permit abnormal power 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 l
conditions.
For example, when a unit is fully defueled, safeguards and safe j
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 diesel generator due to over-loading 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 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, 0105, j
D106) and a battery charger.
In addition to these bus-specific power supplies, a swing safety-related battery (D305) is installed which is capable of being connected to any one of the four main DC distribution buses.
Swing battery chargers are_also provided. Under normal circumstances, one battery and one battery charger are connected in each main DC distribution bus.
The battery i
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 j
batteries is returned to service within the time periods specified in Specifica-tion 15.3.7.B.l.f.
These limiting conditions for operation ensure that adequate DC power will always be available for starting the emergency generators and other emergency uses.
The emergency generator sets are General Motors Corporation. Electro-Motive Division, Model 999-20 Units rated at 2580 KW continuous 0.8 power factor 900 RPM, 4160 volts 3 phase, 60 cycle and consume.- 205 gallons of fuel per hour.
Thus the 11,000 gallon supply in the Emergency Fuel Tank provides sufficient Unit 1 - Amendment No, 84,87.734 136 15*3*7-5 Unit 2 - Amendment No. 88,92 J38,140 l
~
fuel to operate one diesel 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 />.
In addition.
l it will be normal for Point Beach to keep one, or the equivalent of one, bulk storage tank full at all times (55.000 gallons which is equal to about 10 days' supply).
They are each capable of providing 3050 KW for a 30 minute period.
The gas turbine is capable of providing 20,000 KW.
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 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 transfonners 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 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 transnibsion system reliability only and are not dictated by safety system requirements.
l References FSAR Section 8.
Unit 1 - Amendment No. BA.E7.13A 136 15.3.7-6 Unit 2 - Amendment No. BB,92.73E.140
1 3.
Each diesel generator shall be given an inspection, at least annually, following the manufacturer's recommendations for j
this class of stand-by service.
4.
Each fuel oil transfer pump shall be run monthly.
The above tests will be considered satisfactory if all applicable equipment operates as designed.
B.
Safety-Related Station Batteries These surveillance specifications are applicabie to all four safety-related station batteries: DOS, D06, D105, and D106; and the safety-related station swing battery 0305.
1.
Every month the voltage of each cell (to the nearest 0.05 volt).
the specific gravity and temperature of a pilot cell in each battery and each battery voltage shall be measured and recorded.
2.
Every 3 months the specific gravity, the height of electrolyte, and the amount of water added, for each cell, and the temperature of every fi"th cell, shall be measured and recorded.
3.
At each time data is recorded, new data shall be compared with old to detect signs of abuse or deterioration.
4.
Each Safety-Related Station Battery shall be demonstrated OPERABLE:
a.
At least once per 18 months (SERVICE TEST) by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulr+,ed emergency loads for the design duty cycle.*
b.
At least once per 60 months (PERFORMANCE TEST) by verifying that the battery capacity is at least 80% of the manufacturer's rating. This performance discharge test may be performed in lieu of the battery service test.*
c.
Annual performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has
- Service and Performance testing to begin subsequent to installation of the swing safety-related battery (0-305) which is expected by the end of 1992.
Unit 1 - Amendment No.2.JJ0,136 15*4*6-2 Unit 2 - Amendment No.2 JJ3.140
reached 85% of the service life exoected for the application.
Degradation is -indicated when the battery capacity drops more than 10% of rated capacity from its previous performance test, or is below 90% of the manufacturer's rating. When performance tests are required, they may be perfonned in lieu of the battery service test.*
Basis The tests specified are designed to demonstrate that the diesel generators will provide power for operation of equipment. They also assure that the emergency generator system controls and the control systems for the safeguards equipment will function automatically in the event of a loss of all normal AC station service power.
The testing frequency specified will be often enough to identify and correct any mechanical or electrical deficiency before it can result in a system failure.
The fuel supply and starting circuits and controls are continuously monitored and any faults are alarm indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators themselves on test.
i Station batteries will deteriorate with time, but precipitous failure is extremely unlikely.
The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
If a battery cell has deteriorated or if a connection is loose, the voltage under load will drop excessively indicating replacement or maintenance.
A Service Test, performed at least every 18 months, demonstrates adequate battery j
capacity to supply power to loads required during the most demanding duty cycle.
This design duty cycle occurs upon an actuation of safeguards loads in one unit coincident with a loss of off-site power.
The design duty cycle is defined further-in FSAR Section 8.2.
A Performance Test will also be conducted at least every 60 months. The Performance Test is a constant discharge rate capacity test which allows comparison with the manufacturer's rating of the battery. This test is the best indicator of the effects of aging'on battery capacity.
Provisions are made in
- Service end Performance testing to begin subsequent to installation of the swing safety-related battery (D-305) which is expected by the end of 1992.
Unit 1- - Amendment No.136 15.4.6-3
-Unit 2 - Amendment No. 140
these specifications to change the test periodicity to annual when the battery is degraded or when the battery reaches that point in its service life at which capacity degradation with time is accelerated.
Operability is satis-factorily demonstrated by achieving a capacity of at least 80% of the manufacturer's rating.
Since the Performance Test entirely bounds the battery loads applied during a Service Test, when a Performance Test is conducted, the Service Test for that battery's current test cycle may be omitted.
These surveillance specifications are applicable to all five of the safety-related station batteries: DOS, D06. D105 D106, and the swing battery D305.
Reference FSAR, Section B.2 Unit 1 - Amendment No.136 15.4.6-4 Unit 2 - Amendment No.140 l
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