ML20150F290
| ML20150F290 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/28/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa-Illinois Gas & Electric Co |
| Shared Package | |
| ML20150F291 | List: |
| References | |
| DPR-29-A-106 NUDOCS 8804050133 | |
| Download: ML20150F290 (7) | |
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UNITED STATES a
NUCLE AR REGULATORY COMMISSION y
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COPMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GA3 AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated November 17, 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; 4
8.
The facility will operate in conformity with the application, tne provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesautho-j rized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activ-ities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comenon defense and security or to the health and safety of the public; and E.
The icsuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulattuns and all applicable requirements have been satisfied.
I 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-29 is hereby amended to read as follows:
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2 B.
Technical Specifications i
The Technical 5pecf fications contained in Appendices A and B, i
as revised through Amendment No.106, are hereby incorporated in the license. The licenses shall operate the facility in j
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Daniel R. Huller Director Project Directorate !!!-2 Division of Reactor Projects - III IV, Y and Special Projects
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Attachment:
Changes to the Technical Specifications i
Date of Issuance: March 28,1988 i
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3 ATTACHMENT TO LICENSE AMENDMENT NO.106 i
J FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 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 marginal lines indicating the area of change.
REMOVE INSERT l
3.4/4.4-1 3.4/4,4-1 3.4/4.4-2 3.4/4.4-2 3.4/4.4-3 3.4/4.4-3 l
Figure 3.4-1 3.4/4.4-3a 1
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QUAD-CITfES OPR-29 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3 App 1tcability:
Applicability:
Applies to the operating status of the Applies to the periodic testing require-standby liquid control system.
ments for the standby liquid control system.
Objective:
Objective:
To assure the availability of an indepen-To verify the operabtitty of the standby dent reactivity control mechanism.
Itquid control system.
SPECIFICATIONS A.
Normal Operation A.
Normai Operation During periods when fuel is in the The operability of the standby liquid reactor and prior to startup from a control system shall be vertfled by cold condition, the standby liquid performance of the following tests:
control system shall be operable except as specified in Specification 1.
At least once per month 3.4.5.
This system need not be oper-able when the reactor is in the cold Domineralized water shall be shutdown condition, all control rods recycled to the test tank.
Pump are fully inserted, and Specification minimum flow rate of 40 gom l
3.3.A 15 met.
shall be vertfled against a system head of 1275 pstg.
2.
At least once during each opera-ting cycle l
Manutily initiate the system, except the explosion valves and 1
pump solution in the recircula-tion path, to demonstrate that the pump suction line from the storage tar.k is not plugged.
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Explode two of six charges or i
two of four charges manufactured in the same batch using the per-manent system wiring to verify proper function.
Then install the untested charges in the explosion valves.
1 Domineralized watir shall be injected via a test connection Into the reactor vessel to test j
that valves (except explosion i
valves) not checked by the rectrculttton test are not i
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- clogged, i
0624H 3.4/4.4 1 Amendment No, 106 1
QUAO-CITIES OPR-29 Test that the secting of the ll system pressure relief valves is between 1455 and 1545 psig.
3.
Olsassemble and inspect one explosion valve so that it can be established that the valve is not clogged.
Both valves shall be inspected in the course of 4
two operating cycles.
4 B.
Operation with Inoperable Components B.
Operation with Inoperable Components from and after the date that a redun-When a component becomes inoperable, dant component is made or found to be its redundant component shall be inoperable Specification 3.4.A shall demonstrated to be operable irredt-be considered fulfilled and continued ately and dally thereafter.
operation permitted provided that the component is rJturned to an operable l
condition within 7 days, j
C.
Liquid Poison Tank-Boron Concentration C.
Liquid Poison Tank-Boron Concentration The liquid poison tank shall contain The availability of the proper a boron-bearing solution of at least boron-bearing solution shall be vert-3733 gallons of at least 14 WT fled by performance of the following percent sodlum pentaborate tests:
Bo016 Dec4 hydrate (Na i
10H 0) at all t mes when the 1.
At least once per month 2
standby liquid control system is required to be operable and the Soron concentration shall be solution temperature shall not be determined.
In addition, the less than the temperature presented boron concentration shall be l
in Figure 3.4-2.
determined any time water or boron are added or if the 1
D.
If Specifications 3.4.A through C are solution temperature drops below not met, an orderly shutdown shall be the limits specified by Figure initiated and the reactor shall be in 3.4-2.
the cold shutdown condition within 24 I
hours.
2.
At least one per day Solution volume shall be checked.
3.
At least once per day The solution temperature shall be checked.
4 0624H 3.a/4.4-2 Amendment No. 106
l QUAD-CITIES OPR-29 a
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3.4 LIMITING CONDITIONS FOR OPEb' TION BASES
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A.
The design objective of the standby liquid control system is to provide the capability of bringing the reactor from full power to a cold, 2
menon-free shutdown assuming tnet none of the vithdrawn control rods can be inserted.
To meet this objective, the liquid control system is designed to inject a quantity of boron which produces a concentration j
of no less than 600 ppm of boron in the reactor core in approximately 83 minutes with imperfect mixing. A boron concentration of 600 ppm in the reactor core is required to bring the reactor from full power to 3%
ak or more subcritical condition considering the hot to cold reactivity swing, menon poisoning and an additional margin in the reactor core for imperfect mixing of the chemical solution in the 4
reactor water. A normal quantity of 3,321 gallons of solution having a 14% sodium pentaborate concentration is required to meet this shutdown requirement.
For a required pumping rate of 40 gpm, 3321 gallons of at least 14 WT percent solution will be inserted in approximately 83 minutes.
This insertion rate of boron solution will override the rate of reactivity I
insertion due to cool down of the reactor following the zenon peak.
Two pump operation will enable faster reactor shutdown for ATW5 events.
The monthly pump minimum flowrate test shall require a minimum flowrate of 40 gpm. This requirement, combined with the solution concentration requirements of at least 14 WT percent, will demonstrate that the Standby Liquid Control System meets the requirements of 10CFR50.62.
f Boron concentration, solution temperature, and volume are checked on a frequency to assure a high reliability of operation of the system should it ever be required.
Expertence with pump operability indicates that monthly testing is adequate to detect if failures have occurred.
i The only practical time to test the standby liquid control system is during a refueling outage and by initiatic.) from local stations.
1 Components of the system are checked periodically us described above and make a functional test of the entire system on a frequency of less j
than once each refueling outage unnecessary. A test of explosive j
charges frca one manufacturing batch is made to assure that the charges i
are satisfactory. A continual check of the firing circuit continuity j
is provided by pilot lights in the control room.
I 8.
Only one of two standby liquid control pumping circuits is needd for j
proper operation of the system. If one pumping circuit is found to be inoperable, there is no immediate threat to shutdown capability, and
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reactor operation may continue while repairs are being made. Assurance i
that th6 remaining system will perform its intended function and that j
the rel1abi11ty of the system is good is obtained by demonstrating operation of the pump in the operable circuit at least once daily. A 4
reliabilityanalystsindicatesthattheplantcanbeopera$ed;afelyin i
this manner for 7 days.
0624H 3.4/4.4 3 Amendment No.106 i
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QUAD-CITIES OPR-29 i
z The Standby Liquid Control System is operated by a five position control switch (SYS 1&2, SYS 1, OFF, SYS 2, and SYS 2&I).
The single i
pump operation positions are for operating cycle surveillance testing.
This testing demonstrates the capability of firing the explosive trigger assemblies. Also during this testing, sodium pentaborate is circulated from the storage tank, through one suction line, through a pump, and back into the storage tank.
This is done separately for each system demonstrating that both suction lines are not plugged.
The two pump operation positions will be used for the injection of the sodium pentaborate into the vessel during an ATHS event.
By using the two i
l pump operation position, the Standby Liquid Control System will be meeting the requirements of 10CFR50.62 (Requirements for reduction of risk from ATHS events for light-water-cooled nuclear power plants).
C.
The solution saturation temperature of 13% sodium pentaborate, by weight, is 59'F.
The solution shall be kept at least 100F above the l
saturation temperature to guard against boron precipitation. The 10'F margin is included in Figure 3.4-2.
Temperature and liquid level alarms for the system are annunctated in the control room.
Pump operability is checked on a frequency to assure a high reliability i
of operation of the system should it ever be required.
Once the solution has been made up, boron concentration will not vary unless more boron or more water is added.
Level indication and alarm j
indicate whether the solution volume has changed, which might indicate a possible solution concentration change. Considering these factors, the test interval has been established.
D.
Periodic tests to demonstrate two-pump flow capability are not feasible in the present system configuration and are unnecessary because the l
flow path integrity can be determined from the test of a single pump.
Comparison of single-pump test pressures with previous results and j
correlation of these data with initial two-pump tests are used to i
verify the capability of the piping, i
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e 0624H/0243Z 3.4/4.4-3a Arendment No. 106 l
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