ML20116H156
| ML20116H156 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/04/1992 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116H161 | List: |
| References | |
| NUDOCS 9211120324 | |
| Download: ML20116H156 (8) | |
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/y,ni NUCLEAR REGULATORY COMMISSION UNITED STATES
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E WASHINGTON, D.C. 20%5
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COMMONWEALTH EDISON COMPANY UD l0WA-ILLINOIS GAS AND.[LECTRIC COMPANY DD_(UT NO. 50-?,M QUAD CITIES NUCLEAR POWER STATION. UNIT 1 MENDMENT TO J.AQ1LITY OPERATING LICENSE Amendment No.139 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Com"ny (the licensee) dated July 6, 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 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 securit/ 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 l
Specifications as indicated in the attachment tc this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereb/
l amended to read as follows:
l 9211120324 921104 DR ADOCK 0500 4
L
2-B.
Technical Specifications The Technical Specifications contained in Ap)endices A and B as revised through Amendment No.139, are here sy incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This liter,se at 'ndment is effective immediately, to be implemented during the twel th refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION O I-OG James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
Noveraber 4,1992 v-,
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ATTACHMENT TO llCENSE AMENDMEf4T NO.139 FACllllY OPERATING llCENSE NO. OPR-29 Q.CKET NO. 50-254 0
Revise the A mendix 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 marginal lines indicating the area of change.
REMOVf EdfM 3.2/4.2-8 3.2/4.2-8 3.2/4.2-8a 3.2/4.2-8a 3.2/4.2-15 3.2/4.2-15 3.7/4.7-37
'a.7/4.7-37 3.7/4.7-38 3.7/4.7-38
i QUAD-CITIES q
'i setting of 140% of rated steam flow. in conjunction with the flow limiters and main steamline valve closure, limits the mass inventory loss such that fuel is not uncovered, fuel temperatures remain less than 1500'F, and release of radiocctivity to the environs is well below 10 CFR 100 guidelines t
L (reference SAR Sect.ons 14.2.3.9 and 14.2.3.10).
Ttmperature monitoring instrumentation is provided in the main steamline tunnel to detect leaks in this area.
Trips are provided on this instrumentation and when exceeded cause closure of Group 1 isolation L
valves.
Its setting of 200'F is low enough to detect leaks of the order of 5 to 10 ppm; thus it is capabie of covering the entire spectrum of breaks.
l For large breaks, it is a backup to high-steam flow instrumentation f
discussed above, and for small breaks with the resulting small release of radioact.vity, gives isolM ion before the guidelines of 10 CFR 100 are exceeded.
High radiation monitors in t.he main steamline tunnel have been provided 1.0 detect gross fuel failure.
This instrumentation causes closure of Group 1 valves, the only valves required to clos >: for this accident. With the established setting of_If times normal background (without hydrogen addi-tion) and main steamline isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this 1
accident (reference SAR Section 14.2.1.7).
Pressure instrumentation is provided which trips when main steamline
- pressure drops below 825 psig.
A trip of this instrumentation results in closure of Group 1 isolation valves.
In the Refuel and Startup/ Hot Standby modes this trip function is bypassed.
This function is provided primarily to provide protection against a pressure regulator malfunction which would cause the control and/or bypass valve to open. With the trip set at 825 psig, inventory loss is limited so ' hat fuel is not uncovered and peak cladding temperatures are much 1 css than 1500'F; thus, the're are no fission produc+s available for release other than those in the reactor water (refer rce SAR Section 11.2.3h The RCIC and the HPCI high flow and temperature instrumentation are provided to detect a break in their respective piping. A trip of this instrumentation i
results in closure of the RCIC or HPCI steam supply isolation valves.
The trip legic for this function is similar to that for the main-steamline isolation valves, thus all sensors are required to be operable or in a tripped condition to meet single-failure criteria.
The trip settings of 170'F and 300% of design flow and valve closure time are such that core t
uncovery is prevented and fission product release is within limits.
In addition, the steam supply valves for each system are c?osed on lov steamline pressure te provide primary containment isolation when the reactor pressure, as sensed in the' system steamlines, is below the required pressure for turbine operation.
Operation of the HPCI turbine will continue as long as reactor pressure is above;150 psig.
When the reactor pressure falls below 150 psig, the speed of' the turbine pump unit will decrease and gradually be slowed due to stop 6
3.2/4.2-8 Amendment No. 139 y9e 9 y
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QUAD-CITIES OFR-29 friction and windage losses at low reactor pressures.
The low reactor pressure isolation setpoint was developed in accordance with NEDC-31336,
" General Electric Instrument Setpoint Methodology," dated October 1986.
The trip setpoirt of greater than or equal to 100 psig was calculated such that the isolatic1 will occur on decreasing reactor pressure to p** vide' primary containment isolation when the reactor pressure, as sensed '
.he system steamlines, is below the required pre'.sure for turbine opera.on.
The external vacuum breaker line for the HPCI turbine will isolate on low steamline pressure concurrent with high dryvell pressure signals.
The instrumentation and controls ensure thi proper HPCI and primary containment response to a HPCI steamline break (isolation of the stea: aline supply valves only), a large break inside the containment (closure o'
'a steam supply and vacuum relief isolation valves) and a small or interme-size break inside containment (steam supply and vacuum breaker isolatio-
.es remain open for HPCI operation).
i 3.2/4.J 8a Amendment No.
139
f QUAD-CITIES DPR-29 TABLE 3.2-1 INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS Minimum Number of Operable or Tripped Instrument Channele fy Instruments Trip Level Setting Action [2]'
4 Reactor low water [5]
>144 incher above top of A
active fuel
- 4 R'sctor low low water
>84 inches above top of A
active fuel
- 4 High drywell pressure [5]
12.5 psig [3]
A 16 High flow main steamline[5]
1140% of rated steam flow B 16 High temperature main
<200*F B
steamline tunnel High radiation main
<15 x normal rated power B
steamline tunnel [6]
Eackground (without hydrogen addition)
Low main steam pressure [4]
1825 psig B
a i
High flow RCIC steamline
<300% of rated steam C
T10w[7]
4 RCIC turbine area high 1170 F C-temperature 2
High flow HPCI steamline
<300% of rated steam D
Tlow[7]
4 HPCI area high temperature 1170 F D
4 HPCI Steamline pressure 1100_psig 0
Notes
[1] Whenever primary containment integrity is required, there shall be two operable or tripped systens for each function, except for low pressure main steamline which only need be available in the Run position.
3.2/4.2-15 Amendment No. 139
QUAD-CITIES DPR-29 TABLE 3.7-1.(Cont'd)
PRIMARY CONTAINMENT ISOLATION Valve Number Number of.
Maximum for Power-0perated Operating Normal.
Action on Isolation Valve Units Va?ves Time Operating Initiating Group Identification 1 and 2 Inboard Outboard (sec)
Position Signal Reactor Water Cleanup 3
Pump suction isolation valve M0-1201-2 1
530 0
GC 3
Pump suction isolation valve M0-1201-5 1
530 0
GC HPCI 4
Steam isolation valve M0-2301-4 1
550 0
GC 4
Steam isolation valve M0-2301-5 1
550 0
GC 4
Vacuum breaker isolation M0-2399-43 1
550 0
GC 4
Vacuum breaker isolation MO-2399-41 1
550 0
GC
,PCIC 5
Turbine steam supply M0-1301-16 1
525 0
GC 5
Turbine steam supply M0-1301-17 1
525 0
GC 3.7/4.7-37 Amendment No.139
i 1
QUAD-CITIES OPR-29 TABLE 3.7-1 (Cont'd)
Key:
0:
open C:
closed SC:
stays closed GC:
goes closed Note:
Isolation groupings are as follows:
Group 1:
The valves in Group 1 are closed upon any one of the following conditions:
1.
Reactor low-low-water level 2.
Main steamline high radiation 3.
Main steamline high flow 4.
Main steamline tunnel high temperature 5.
Main steamline low pressure Group 2:
The actions in Group 2 are initiated by any one of the following conditions:
Reactor low water level 2.
High drywell pressure Group 3:
Reacto' low water level alone initiates the following:
1.
Cleanup demineralizer system isolation Group 4:
The steam supply isolation valves in the high pressure coolant injection system (HPCI) are closed upon any one of the following signals:
1.
HPCI steamline high flow 2.
High temperature in the vicinity of the HPCI steamline 3.
Low reactor pressure The turbine exhaust vacuum breaker isolation valves close when both of the following signals are present (simultaneously):
1.
High drywell pressure 2.
Low reactor pressure Group 5:
Isolation valves in the reactor core isolation cooling system. (RCIC) are closed upon any one of the following signals:
1.
RCIC steamline high flow 2.
High temr, :ture in the vicinity of the RCIC steamline 3.
Low re*: tor pressure 3.7/4.7-38 Amendment No. 139
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