ML20209B903
| ML20209B903 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/02/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209B907 | List: |
| References | |
| NUDOCS 8609080337 | |
| Download: ML20209B903 (14) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
- j wAsmNGTON, D. C. 20555
/
COMMONWEALTH EDIS0N COMPANY i
DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.89 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated June 18, 1986, complies with the standards and 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 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 Comission'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.
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8609090337 860902 PDR ADOCK 05000249 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paranraph 3.P. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Snecifications contained in Appendix A, as revised through Amendment No. 89, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION u
John. Zwolinski, Director RWR P oject Directorate #1 Division of RWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 2,1986 i
i
ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 Revise Appendix A Technical Specifications by renoving the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.1-8 3/4.1-8 3/4.1-9 3/4.1-9 3/4.1-10 3/4.1-10 R3/4.1-19 R3/4.1-19 3
83/4.1-20 R3/4.1-20*
3/4.2-19 3/4.?-19 3/4.?-70 3/4.2-20 3/4.2-21 3/4.2-?1 B3/4.2-36 B3/4.2-36 B3/4.2-37 83/4.2-37 B3/4.2-38*
- Pagination change'omly.
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DRESDEN III DPR-25 4
Amendment ND. /> 89
-e TABLE 4.1.1 SCRAM INSTRUMENTATION FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTR. AND CONTROL CIRCUITS Instrument Channel Group (3)
Functional Test Minimum Frequency (4)
Mode Switch in Shutdown A
Place Mode Switch in Shutdown Each Refueling Outage Manual Scram A
Trip Channel and Alarm Every 3 Months IRM
- High Flux C
Trip Channel and Alarm (5)
Before Each Startup (6)
- Inoperative C
Trip Channel and Alarm Before Each Startup (6)
APRM High Flux B
Trip Output Relays (5)
Once Each Week Inoperative B
Trip Output Relays Once Each Week Downscale B
Trip Output Relays (5)
Once Each Wek High Flux (15% scram)
B Trip Output Relays Before Each Startup
, High Reactor Pressure A
Trip Channel and Alarm (1)
High Drywell Pressure A
Trip Channel and Alarm (1)
Reactor Low Water Level (2)
B (8)
(1) l High Water Level in Scram Discharge A
Trip Channel and Alarm (7)
Every 3 Months Voltanes (Float and dp Switch)
Turtpine Condenser Low Vacutsn A
Trip Channel and Alarm (1)
Main Steam Line High Radiation (2)
B Trip Channel and Alann (5)
Once Each Week l
Trip Channel and Alarm (1)
Isolation Valve Closure GeneratorLoadRejection A
Trip Channel and Alarm (1)
Turbine Stop Valve Closure A
Trip Channel and Alarm (1) l Tur' sine Control - Loss of Control A
Trip Channel and Alarm (1)
I
- 01) Pressure Notss:
(See next page) 3/4.1-8 l
3893 3122A i
DRESDEN III DPR-25 Amendment No. 7$ 89 j
NOTES:
(For Table 4.1.1) 1.
Initially once per month until exposure hours (M as defined on Figure 5
4.1.1) is 2.0x10 ; thereafter, according to Figure 4.1.1 with an interval not less than one month nor more than three months. The compilation of instrument failure rate data may include data obtained from other Boiling Water Reactors for which the same design instrument operates in an environment similar to that of Dresden Unit 3.
2.
An instrument check shall be performed on low reactor water level once per day and on high steen line radiation once per shif t.
3.
A description of the three groups is included in the Bases of this Specification.
4.
Functional tests are not required when the systems are not required to be operable or are tripped. If tests are alssed, they shall be performed prior to returning the systems to an operable status.
5.
This instrumentation is exempted from the Instrument Functional Test Definition (1.0.C).
This Instrument Function Test will consist of injecting a simulated electrical signal into the measurement channels.
6.
If reactor start-ups occur more frequently than once per week, the functional test need not be performed; i.e.,
the maximum functional test frequency shall be once per week.
7.
The Functional Test of the Scram Discharge Volume float switch shall include actuation of the switch using a water column.
8.
A functional test of the master and slave trip unit is required monthly (staggered one channel out of 4 every week). A calibration of the trip unit is to be performed concurrent with the functional testing.
3/4.1-9 3893a 3122A
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DRESDZN III DPR-25 Amendment N3. 14 ' 8 b
- r TABLE 4.1.2 SCRAM INSTRUMENTATION CALIBRATIONS MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS i
Instruwnt Channel Group (1)
Calibration Test Minirmsn Frecuency (2)
- High Flux IRM C
Conparison to APRM Every Shutdown (4) after Heat Balance High Flux APRM Output Signal B
Heat Balance Once Every 7 Days Flow Blas B
Standard Pressure and Voltage Refueling Outage Source High Reactor Pressure A
Standard Pressure Source Every 3 Months High Drywell Pressure A
Standard Pressure Source Every 3 Months Reactor Low Water Level B
Water Level (5) l Turbine Condenser Low Vacutsn A
Standard Vacutsn Source Every 3 Months o
Main Steam Line High Radiation B
Standard Current Source (3)
Every 3 Months i
Tuttine Control - Loss of Control A
Pressure Source Every 3 Months Oil Pressure High Water Level in Scram Discharge A
Water Level Once per Refueling Voltane ($ only)
Outage J
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NOTES:
(For Table 4.1.2) 1.
A description of the three groups is included in the bases of this Specification.
2.
Calibration tests are not required when the systems are not required to be operable or are tripped.
If tests are missed, they shall be performed prior to returning the systems to an operable status.
3.
The current source provides an instrument channel alignment.
Calibration using a radiation source shall be made during each refueling outage.
84.
If reactor startups occur more frequently than once per week, the functional test need not be performed; i.e., the maximum functional test frequency shall be once per week.
5.
Trip units are calibrated monthly concurrently with functional l
testing (staggered one channel out of 4 every week). Transmitters are calibrated once per operating cycle.
3/4.1-10 l3893a
'3122A
DRESDEN III DPR-g Amendment No. 7d, $7 j
4.1 SURVEILLANCE REQUIREMENT BASES (Cont'd.)
Reactor low water level instruments 3-263-57A, 3-263-57B, 3-263-58A, and 3-263-58B have been modified to be an analog i
trip system. The analog trip system consists of an analog sensor (transmitter) and a master / slave trip unit setup which ultimately drives a trip relay. The frequency of calibration and functional testing for instrument loops of the analog trip system, including reactor low water level, has been established in Licensing Topical Report NEDO-21617-A (December 1978). With the one-out-of-two-taken-twice logic, NEDO-21617-A states that each trip unit be subjected to a calibration / functional test each month (staggered one channel out of four every week). An adequate calibration / surveillance test interval for the transmitter is once per operating cycle.
5 Group (C) devices are active only during a given portion of the operational cycle. For example, the IRM is active during startup and inactive during full-power operation. Thus, the only test that is meaningful is the one performed just prior to shutdown or startup; i.e.,
the tests that are performed just prior to use of the instrument.
i Calibration frequency of the instrument channel is divided into two groups.
These are as follows:
1.
Passive type indicating devices that can be compared with like inits on a continuous basis.
2.
Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity.
Experience with passive type instruments in Commonwealth Edison generating stations and substations indicates that the specified calibrations are adequate. For'those devices which employ amplifiers, etc., drift specifications call for drift to be less than 0.19/ month; i.e.,
in the period of a month, a drift of.19 would occur and thus provide for adequate margin.
For the APRM system drift of electronic apparatus is not the only consideration in determining a calibration frequency.
Change in power distribution and loss of chamber sensitivity dictate a calibration every seven days. Calibration on this frequency assures plant operation at or below thermal limits.
B 3/4.1-19 3893a 3122A
Y
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DRESDEN III DPR-25 Amendment No. 7d, $7 gg 4.1 SURVEILLANCE REQUIREMENT BASES (Cont'd.)
A comparison of Tables 4.1.1 and 4.1.2 indicates that six instrument channels have not been included in the latter Table. These are: Mode Switch in Shutdown, Manual Scram, High Water Level in Scram Discharge Volume Float Switches, Main Steam Line Is31ation Valve Closure, Ceneettor Load Rejection, and Turbine Stop Valve Closure. All of the devices or sensors associated with these scram functions are simple on-off switches and, hence, calibration is not applicable; i.e.,
the switch is either on or off. Further, these switches are mounted solidly to the device and have a very low probability of moving; e.g.,
the switches in the scram discharge volume tank.
Based on the above, no calibration is required for these six instrument channels.
B.
The MFLPD shall be checked once per day to determine if the APRM gains or scram requires adjustment. This may normally be done by checking the LPRM readings, TIP traces, or process computer calculations.
Only a small number of control rods are moved daily and thus the peaking factors are not expected to change significantly and thus a daily check of the MFLPD is adequate.
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Tabl2 4.2.1 DRESDEN III DPR-25 MINIMUM TEST AND cal 1RRATION FREQUENCY FOR CDRE AND Amendnent No. }$, %, j8 CONIAINENT COOLING SYSTEMS INSTRUENTATION, R00 BLOCKS, AND ISOLATIONS Instrtsnent Channel Instrument Instrument Functional Test Calibration Check ECCS Instrumentation 1.
Reactor Low-Low Water Level (1)
Once/3 Months Once/ Day 2.
Drywell High Pressure (1)
Once/3 Months None 3.
Reactor Low Pressure (1)
Once/3 Months None 4.
Contalrunent Spray Interlock a.
2/3 Core Height (1) (13)
(13)
None l
b.
Containment High Pressure (1)
Once/3 Months None 5.
Low Pressure Core Cooling Punp (1)
Once/3 Months None Discharge 6.
Undervoltage Emergency Bus Refueling Outage Refuel Outage Once/3 months 7.
Sustained High Reactor Pressure (1)
Once/3 Months None 8.
Degraded Voltage Emergency Bus Refueling Outage (10)
Refuel Outage Monthly Rod Blocks 1.
APRM Downscale (1) (3)
Once/3 Months None 2.
APRM Flow variable (1) (3)
Refuel Outage None 3.
APRM Upscale (Startup/ Hot Staney)
(2) (3)
(2) (3)
(2) 4.
IRM Upscale (2) (3)
(2) (3)
(2) 5.
IRM Downscale (2) (3)
(2) (3)
(2) 6.
IRN Detector Not Fully Inserted (2)
N/A None in the Core 7.
RBM Upscale (1) (3)
Refuel Outage None 8.
RBM Downscale (1) (3)
Once/3 Months None 9.
SRM Upscale (2) (3)
(2) (3)
(2)
- 10. SRM Detector Not in Startup Position (2) (3)
(2) (3)
(2)
- 11. Scram Instrument Voltrne Level High Once/3 Months (9)
_ Containment Monitoring 1.
Pressure a.
Minus 5 in. Hg to plus 5 psig None Once/3 Months Once/ Day Indicator b.
O to 75 psig Indicator None Once/3 Months None 2.
Terrperature None Refuel Outage Once/ Day 3.
Drywell-Torus Differential None Once/6 Months (Two None Pressure (5) (6)
Channels Operable)
(0-3 psid)
Once/ Month (One Channel Operable) 4.
Torus Water Level (5) (6) a.
Plus or minus 25 in. Wide Range None Once/6 Months Indicator l
b.
18 in. Sight Glass l
Safety / Relief Valve Monitorino l
1.
Safety / Relief Valve (7)
None Once Per l
Position Indicator 31 Days l,
(Acoustic Monitor) (8) 2.
Safety / Relief Valve Position None Once every Once Per Indicator (Tenperature 18 months 31 Days Monitor (8) i 3.
Safety Valve Position Indicator (7)
None Once Per j
(Acoustic Monitor) (8) 31 Days 4.
Safety Valve Position Ir.dicator None Once every Once Per (Tenperature Monitor) (8) 18 month';
31 Days (Table cont'd next page) 3/4.2-19 3840a 3845A
Tahia 4.2.1 (Cont'd)
ORE 5 DEN III DPR-25
- T MINIMUM TEST AND CALIBRATION FREQUENCY FOR CORE AND Amendment No. p, ye, p 8 9 CONTAINMENT COOLING SYSTEMS INSTRUMENTATION, ROD BLOCKS, AND ISOLATIONS Instrunent Channel Instrunent Instrument Functional Test Calibration Check Main Steam Line Isolation 1.
Steam Tunnel High Tenperature Refueling Outage Refuel Outage None 2.
Steam Line High Flow (1)
Once/3 Months Once/ Day 3.
Steam Line Low Pressure (1)
Once/3 Months None 4.
Steam Line High Radiation (1) (3)
Once/3 Months (4)
Once/ Day Isolation Condenser Isolation 1.
Steam Line High Flow (1)
Once/3 Months None 2.
Condensate Line High Flow (1)
Once/3 Months None HPCI Isolation 1.
Steam Line High Flow (1) (11) (13)
(11) (13)
None l
2.
Steam Line Area High Tenperature Refueling Outage Refuel Outage None 3.
Low Reactor Pressure (1) (12)
(12)
None l
Reactor Building Vent Isolation and SBGTS Initiation 1.
Refueling Floor Radiation Monitors (1)
Once/3 Months Once/ Day NOTES:
(For Table 4.2.1) 1.
Initially once per month until exposure hours (M as defined on Figure 5
is 2.0 x 10 ; thereafter, according to Figure 4.1.1 with an 4.1.1) interval not less than one month nor more than three months.
The compilation of instrument failure rate data may include data obtained from other Boiling Water Reactors for which the same design instrument operates in an environment similar to thst of Dresden Unit 3.
2.
Function test calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Functional tests shall be performed before each startup with a l
required frequency not to exceed once por week. Calibrations shall be performed during each startup or during controlled shutdowns with a required frequency not to exceed once per week.
Instrument checks shall be performed at least once per week.
Instrument checks shall be I
performed at least once per day during those periods when the l
instruments are required to be operable.
I 3.
This instrumentation is excepted from the functional test definition.
j l
The functional test will consist of injecting a simulated electrical signal into the measurement channel.
See Note 4.
I 4.
These instrument channels will be calibrated using simulated electrical signals once every three months.
In addition, calibration including the sensors will be performed during each refueling outage.
(Cont'd next page) i f
3/4.2-20 3840a 3845A i
DRESDEN III DPR-25 Amendment No. 7/3, 7/, p $ 9 NOTES:
(For Table 4.2.1) (Cont'd.)
5.
A minimum of two channels is required.
6.
From and after the date that one of these parameters (...either drywell-torus differential pressure or torus water level indication)
{
is reduced to one indication, continued operation is not permissible beyond thirty days, unless such instrumentation is sooner made operable. In the event that all indications of these parameters
(...elther drywell-torua differential pressure or torus water level) is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty four hours.
7.
Functional tests will be conducted before startup at the end of each refueling outage or after maintenance is performed on a particular Safety / Relief Valve.
8.
If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however, if the reactor is in a shutdown conditionfor more than seventy-two hours, it may not be started up until all position indication is restored.
In the event that all position indication is lost on one or more valves and such indication cannot be restored in thirty days, an j-orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
9.
The Functional Test of the Scram Discharge Volume float switch shall include actustion of the switch using a water column.
10.
Functional test shall include verification of the second level undervoltage (degraded voltag6) timer bypass and shall verify operation of the degraded voltage 5-minute timer and inherent 7-second timer.
11.
Verification of time delay setting between 3 and 9 seconds shall be performed during each refueling outage.
12.
Trip units are functional tested monthly (staggered one channel out of four every week). A calibration of the trip units is to be performed concurrent with the functional testing.
13.
Trip units are functional tested monthly (staggered one division out of two every two weeks). A calibration of the trip units is to be performed concurrent with the functional testing.
3/4.2-21 3840a 3845A
DRESDEN III DPR-25 Amendment No. 7j$. 7/, $$ 69 4.2 SURVEILLANCE REQUIREMENT BASES (Cont'd.)
A more usual case is that the testing is not done independently.
If both channels are bypassed and tested at the same time, the result is shown in Curve No. 3.
Note that the minimum occurs at about 40,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, much longer than for cases 1 and 2.
Also, the minimum is not nearly as low as Case 2 which indicates that this method of testing does not take full advantage of the redundant channel.
Bypassing both channels for simultaneous testing should be avoided.
The most likely case would be to stipulate that one channel be by-passed tested and restored, and then immediately following, the second channel be bypassed, tested, and restored. This is shown by Curve No. 4.
Note that there is no true minimum. The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.
The best test procedure of all those examined is to perfectly stagger the tests. That is, if the test interval is four months, test one or the other channel every two months. This is shown in Curve No. 5.
The difference between Cases 4 and 5 is negligible.
There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.
The conclusions to be drawn are these:
1.
A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval; and 2.
More than one channel should not be bypassed for testing at l
any one time.
The analog trip system consists of an analog sensor (transmitter) and a master / slave trip unit setup which ultimately drives a trip relay. The frequency of calibration and functional testing for instrument loops of the analog system, including reactor low water level, has been established in Licer. sing Topical Report NEDO-21617-A (December, 1978).
For instruments 3-2389A, B, C, D, the one-of-two-taken-twice logic exists, and NEDO-21617-A states that each trip unit be subjected to a calibration / test frequency (staggered one channel out of four per week) of one month. An adequate calibration / surveillance test l
interval for the transmitter is once per operating cycle.
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B 3/4.2-36 l
3840a l
3845A l
- r DRESDEN III DPR-25 Amandasnt No. 76, }&, $8 gg j
4.2 SURVEILLANCE REQUIREMENT BASES (Cont'd.)
4 For instruments 3-263-73A, 73B and 3-2352, 2353, the logic downstream of the output relay contacts exhibits a one-out-of-two logic and, by utilizing the Availability Criteria identified in NEDO-21617-A, each of these trip units should also be subjected to a calibration / test frequency (staggered one division out of two per two weeks) of one month. An adequate calibration / surveillance test interval for the transmitter is once per operating cycle.
The radiation monitors in the ventilation duct and on the refueling floor which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.
The bases given above for the rod blocks applies here also and were used to arrive at the functional testing frequency.
Based on experience at Dresden Unit I with instruments of similar design, a testing interval of once every three months has been found to be adequate.
The automatic pressure relief instrumentation can be considered to
(,
be a 1 out of 2 logic system and the discussion above applies also.
The instrumentation which is required for the post accident j
condition will be tested and calibrated at regularly scheduled intervals. The basis for the calibration and testing of this instrumentation is the same as was discussed above for Protective Instrumentation in Table 4.2.4.
1 i
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l 3840a 3845A
DRESDEN III DPR-25 Amendment. No. 7), M, $,89L 10~8
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10
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-4 10 y
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10-5 CURVE 2 Id 10-7 CURVE 4 3
4 5
3p t
3,2 to 10 10 ge TEST INTERVAL (4 hows Figure 4.2.2 TEST INTERVAL VS. SYSTEM UNAVAILABILITY B 3/4.2-38 l
3840a
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