ML20154G149
| ML20154G149 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/10/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20154G152 | List: |
| References | |
| DPR-29-A-107, DPR-30-A-102 NUDOCS 8805240262 | |
| Download: ML20154G149 (12) | |
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION
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-E WASHINGTON, D. C. 20$55
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COMNONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES hUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 6, 1987 and supplemented on December 16, 1987, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Cocinission; I
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the puLlic, and (ii) that such activities will be conducted in compliance with the Cocinission's regulations; D.
The issuance of this amendment will not be inimical to the corrnon i
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.
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. OPR-29 is hereby amended to read as follows:
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2 B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.107. 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 Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, 4
IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: May 10,1988 1
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i ATTACHMENT TO LICENSE AMENDMENT NO. 107 I
FACILITY OPERATING LICENSE NO, DPR-29 I
1 i
DOCKET NO. 50-254 4
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain merginal'11nes j
indicating the area of change, i
REMOVE INSERT 3.2/4.2-10a 3.2/4.2-10e 3.2/4.2-11 3.2/4.2-11 3.2/4.2-17 3.2/4.2-17 l
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QUAO-C878ES OPR-29 w
s Reactor water level instruments 1-263-73A & S. HPCI high steam flow instruments 1-2352 & 1-2353, and HPCI steam line low pressure instruments 4
i 1-2349A-0 have been modified to be analog trip systems.
The analcg 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 testino for instrument loops of the analoa trip system has been established in Licensing Topical Report NEDO-21617-A (Decemcer 1978).
With the one-out-of-two-taktn-twice logic, NEDO-21617-A states that each trip unit be subjected to a calibration / functional test i
frequency of one merith.s An adequate calibration /survelliance test interval for the transmitter is once per operating cycle. s The radiation monitors in the ventilatton duct and on the refueling floor which laitiate building isolation and standby gas treatment operation are arranged in two one-out-of two logic systems.
The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency.
Based on experience at Oresden Unit I with instruments of similar design, a testing interval of once every 3 months has been found to be adequate.
The automatic press 6re relief instrumentation can be considered to be a one-cut-of-two logic system, and the discussion above applies to it also.
The instrumentation which is required for the postaccident condition will be tested and calibrated at regularly scheduled intervals.
The basis for the calibratten and testing of this instrumentattort is the same as was discussed above for the reactor protection system and the emergency core cooling systems.
Peferences 1.
B. Epstein and A. Shlff, "Improving Availability and Readiness of Field 4
Eculement Through Periodic Inspection", UCRL-50451, Lawrence Radiation Lateratory, p 10. Equation (24), July 16, 1968 i
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074CS 3.2 / 4.24 0a Acenc e': No.
i 107
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eUa0.C2 Tit $
l OPR 29 TAllt 3.2 1 INSTRUMENTATICN THAT INITI ATE $ PRIMARY CCNTAthMENT !$CLAf!CN FUNCTICMS MininJa Number of CperaDie of Tripped Char.reli w fastru ents IIl2_ level fett9sa Actienlld Instrumep$,
Reactor low water (Il slaa inches above top of A
a active fuel' 4
Reactor low 1cw water 184 inches above top of A
active fuel' Mign drywell pressure [5]
12.5psigI33 A
4 High flow main steamline(Il 1140% of rated steam flow 8 16 16 Migh tercersture main 1200* F 8
steunline tunnel High radiation Ngg 17 norwul rated power 8
4 steamline tunnell J background Low main.steun pressureE8}
1825 psig 8
4 C
2 High flow RCIC stenmline 1300())of rated steam flow 16 RCIC turbir.e area high 1200' F C
toegerature D
2 Migh flow MPCI siekmline 13JC}?of rated steam f10ws l 16 MPCI area high tencerature 1200' F 0
12181 bmemover primary containment integrity is required, there shall be two operable or 1.
trippeJ systems for each f anction except f or low pressure main stenmline which only need be available in the Run position.
2.
Action, if the first columa cannot be set for one of the trip systep4. that trip system shall be tripped.
If the first colunn cannot be met for botn '. rip systems, the appropriate actions listed below shall be taken, A.
Initiate an orderly shutdown and have the reactor in Cold $hutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have reacter in Mot Standby within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Close isolation valves in RCIC system.
D.
Close isolation valves in HPCI subsystem.
3.
Need not be operable wnen primary containment integrity is not required.
4.
The isolation trip signal is bypassed when the ecde switch is in Refuel or startup/
Hot $%utdown.
S.
The instrumentation also isolates the control room vantilation system.
6.
This signal also automatically closes the rechanical vacuum pump discharge line iso-14tton valves.
7.
Includes a time delay of 3 i t i 9 seconds.
- Top of active fuel is defined as 360* above vessel aero for all water levels used in the LOCA analysis (see Bases 3.2).
noenament no.107 of408 3.2/4.2-11
l OUaD-C17!! $
OPR 39 TaBtt 4.2-1 (Cont'd) r Instrument Instr nt Instrument Funct) anal Test i!)
calibratien(I)
CheckgI chaenet HPCI ! solation 1.
Steamline high flow (1) (9)
Once/3 months None 2.
Steamline area hign temperature Refueling outage Refueling outage None 3.
Low reactor pressure (1)
Once/3 months None Reactor Building Ventilation $ystem Isolation and Standby Treatment System Initiation 1.
Refueling floor radiation (1)
Once/3 months once/ day renitors Steam Jet Air Ejector off-Gas ! solation 1.
Off-gas radiation montters (1) (4)
Refueling outage Once/ day Control Room vent 11atten System Isolation 1.
Reactor low water level (1)
Once/3 renths Once/ day 2.
Crywell high pr3ssure (1)
Once/3 months None 3.
Main steam 11me hign flow (1)
Once/3 renths Once/ day 4
Tonic gas analy:ers (chlorine.-
Once/ Month once/18 months once/ cay amnonta, sulphur dioside)
Notes:
Initially on$e per month untti exposure hours (M as defined on Figure 4.1-1) 1.
tnereafter, according to Figure 4.1-1 with an interval not are 2.0 x 10 less than 1 month nor rcre than 3 rcnths. The compilation of instrument f ailure rate data may include data obtained from other boiling water reactors for =hich the same design instrueent operates in an environment similar to that of Guad Cities Units 1 and 2.
2.
Functional tests, calterations. 4nd instrument checks are not required when these instruments are not required to be 0;erable or tripped.
3.
This instrumentation is encepted f rom the functional test definition. The function test small consist of injecting a simulated electric signal ti.to the reasurement channel.
4 This instrument channel is escepted f rom the functional test definitions and shall be ca11erated using strulated electrical signals on:e every 3 renths.
5.
Functional tests shall be performed before each startup with a required frecuency not to enceed once per meek. Calterations shall te performed during each startup or during controlled shutdowns with a required frequency not to esteed once per weet.
6.
The positioning rechanism shall te calierated every refueling cutage.
7.
Logic system functional tests are performed as specified in the applicable section for these systems.
I 8.
Functional tests shall include verification of operation of the degraded voltage. 5 minute timer and 7 second inherent tirer.
9.
Verification of the time delay setting of 31 t i 9 seconds shall be perf ormed caring each refueling outage, g
i 0844B/03802 3.2/4.2-17 Amenoment No.
107 j
/ sa ucq'o UNITED STATES
^g NUCLEAR REGULATORY COMMISSION e
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W ASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY s
AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amenda,ent No. 102 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated November 6,1987 and supplemented on December 16, 1987, 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.
Tne facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this arendment can be conducted without endangerthg 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 tnis 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 amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and e'l opp 11 cable 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 3.8 of Facility Operating License l
No. DPR-30 is hereby arended to read as follows:
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2-i B.
Technical Specifications
)
The Technical Specifications contained in Appendix A and B, as i
revised through Amendment No.102. are Mreby incorporated in this license. The licensee shall opery the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, j
FOR THE NUCLEAR REGULATORY COMMISSION Y /d' Y/7 Daniel R. Muller, Director Project Directorate Ill-2 utvision of Reactor Projects - III, t
IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications i
Date of Issuance: May 10,1988 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 102 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendnent number and contain marginal lines indicating the aret of change.
REMOVE INSERT 3.2/4.2-10 3.2/4.2-10 3.2/4/2-11 3.2/4.2-11 3.2/4.2-17 3.2/4.2-17
CuaD-C!t!ES DPR-30 Optimizing each channel indepen6ently may not truly optimize tiie system
.s considering the overall rules of system operation. However, true system optimization is a complex problem. The optimums are broad, not sharp, and optimizing the irdividual channels is generally adequate for the system.
The formula given 4t'ove minimizes the unavailability of a single channel which us? ee bypassed dt, ring testing. The minir'iration of the unavatlatility is illustrated by curve 1 of Figure 4.2-2, which assumes' that 6
a channel has a fatture rate of 0.1 x 10 / hour and 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> is required to tegtit. The unavailability is a mintrum at a test interval 1. of 3.6 x 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
If two similar channels are used in a ene-out-of-two configuration, the test interval for mir.imum availability changes as a function of the rules for testing. The simplest case is to test each one independent of the other.
In this case, there is assumed to be a finite probability that both may be bypassed at one time. This case is shown by curve 2.
Note that the unavailability is lower, as expectec f or a reduneant system, and the mininum occurs at the sa.me test interval. Thus, if the two channels are tested independently, the equation above yields the test interval for minimum unavailability.
. A more usual case is that the testing is not done independtatly. If both channels are bypass 2d and tested at the same time, the result is shown in curve ).
Note that the mininum occurs at About 40.000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, ruch 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 struitaneous testing should be avoided.
The ecst likely case would be to stipulate that one channel be bypassed, tested and restored, and then infaediately following the second channel be bypassed, tested. and restored. This is shown of curve 4 Note that there 15 not true mtntrum. The curve does have a definite knee, and very little reduction in system unavailability is achieved by testing at a sho*ter interval than computed by the ecuation for a single chanr.e1.
The best test procedure of all those erwined is to cerf ectly stagger the tests. This is, if the test interval is 4 months, test one of the other enannels every 2 months. This is shown in curve 5.
The difference between Cases a and 5 is negligible. There may be other arguments however, that more strengly support the perfectly staggered tests, including reductions in human error.
The conclusions to be drawn are these:
a.
A one-cut-of-n system may be. eated the same as a single channel in terms of choosing a test interval, b.
More than'one channel shoulo not be bypassed for testing at any one time.
Reactor water level instruments 2-263-73A&B, HPCI high steam flow instruments 2 2352 & 2-2353. and HPCI steam 11ne low pressure instruments 2-23891-0 have been modified 14 be analog trip systems The analog trip system consists of an analog sensor ' transmitter) and a master / slave trip unit setup which ultimately drives a trip relay. The frecuency of calibration and function testing for instrument loops of the analog trip system has been established in Licensing Topical Report NEQQ-21617-A (Decemoer 1978). With the one-out-of-two-taken-twice logic. N(00-21617-A states that each trip unit be subjected to a calibration / functional test frecuency 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 one out-of two lo d systems. The bases given above for the a
rod blocks apply here also and weia used to arrive at the functional testing frecuency.
07408 3.2/4.2-10 Amendment No.
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DPR-30 7ABLE 3.3-1 INSTRUMENTATION Thai INITIATES Pe! MARY CONTAINMENT 250LA?!CN FUNC7!CNS Mintmun Numter of Operable or Tripped Instrumeot.
chamreisW fastrueents Tria tevel settino ActionbIl Reactor low water (5)
>144 inches above top of A
4 active fuel' 4
Reactor low low water 184 inches above top of A
active fuel' High drywell pressure ($]
12.5 psig (33 A
4 16 High flow main steamitne(5]
1140* of rated steam flow 8 16 High temperature main 1200* F 8
steamitne tunnel 17 x nurmal rated power 8
High radiationsteamline tunnel ggbackground 4
J Low main steam presserel4}
1825 psig 8
4 C
2 High flow RCIC steam 1tne 1300(*I)of rated steam flow 16 RCIC turbine area high 1200* F C
temperature 2
High flow HPCI steamline 1300*(IIgf rated steam D
110w 16 HPCI area high temcerature 1200* F D
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Notes 1.
Whenever primary containment integrity is required, there shall be two operable or trip;ed systems for each function. except for low pressure main steamline which only need be available in the Run position.
2.
Action. if the first column cannot be Pet for one of the trip systems, that trip system shall be tripped.
If the first column cannot be met for both trip systems the appropriate actions i
listed below shall be taken.
1 A.
Initiate an orderly shutdowr. and have the reactor in CC1d $hutdown co9dition in 24 neurs.
6.
Initiate an orderly load reduction and have reactor in Hot Standby within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Close isolation valves in RCIC system.
D.
Close isolation valves in HFCI subsystem.
3.
Need not be operable when primary containeent integrity is not required.
4 The isolation trip signal is bypassed when the rede switch is in Refuel or Startup/
Het $hutdown.
5.
The instrumentation also isolates the control room ventilation system.
6.
This signal also autanatically closes the mechanical vacuum pump discharge line iso-lation valves.
7.
Includes a time delay of 3 1 t i 9 seconds.
- Top of active fuel is defined as 360' above vessel zero for all water levels used in the LOCA analysis (see Bases 3.2).
07408 3.2/4.2-11 Amenoment No.102
QUAD-CITfES OPR-30 s
TABLE 4.2-1 (Cont'd)
Instrument Instrument Functgnal Calibratien(2)
ChecktII Instrymant Test
)
channel HPCI Isolation 1.
Steamline high flow (1) (9)
Once/3 renths None 2.
Steamline area high temperature Refueling outage Refueling outage None 3.
Low reactor pressure (1)
Once/3 ncnths None Reactor Building Ventilation System Isolation and Standby Treatment System Initiation 1.
Refueling floor radiation (1)
Once/3 months On:d/ day renitors Steam Jet Air Ejector Off-Gas Isolation 1.
Off-gas radiation monitors (1) (4)
Refueling outage Once/ day Control Room ventilation System Isolation 1.
Reactor low water level (1)
Once/3 mo9ths Once/ day 2.
Drywell high pressure (1)
Once/3 months None 3.
Main steamline high f1c=
(1)
Once/3 months Once/ day 4.
Toxic gas analyzers (chlorine, Once/Menth once/18 echths Once/ day arrenta, sulphur dicxide)
Nctes 1.
Initially once per month until exposure hours (M as defined on Figure 4.1-1) are 2.0 X 108; thereaf ter, according to Figure 4.1-1 with an interval not less than 1 month nor more than 3 months. The comotlation 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 Quad Cities Units 1 and 2.
2.
Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or tripped.
3.
This instrumentation is excepted from the functional test definitton. The function test shall consist of injecting a simulated electric signal into the measurenent channel.
J.
This instrument channel is excepted from the functional test definitions and shall be calibrated using strulated electrical signals once every 3 months.
5.
Functional tests shall be performed before each startup with a reautred frequency not to exceed once per week. Calibration $ shall be performed during each startup or during controlled shutdowns with a required frecuency not to exceed once per week.
6.
The positioning mechanism shall be calibrated every refueling outage.
7.
Logic sy; ten functional tests are perfortred as specified in the applicable section for these systems.
8.
Functional tests shall include verification of operation of the degraded voltage. 5 minute timer and 7 second inherent timer.
9.
Verification of the time delay setting of 31 t i 9 seconds shall be performed during each refueling outage.
0844B/0380Z 3.2/4.2-17 Amen $ ment No.
102