ML20207N284
| ML20207N284 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/30/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207N286 | List: |
| References | |
| NUDOCS 8701140099 | |
| Download: ML20207N284 (8) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
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e E WASHINGTON, D. C. 20555 r,
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-265 00AD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 93 License No. OPR-30 1.
The Nuclear Reculatory Commission (the Commissioni has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 78, 1986, 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 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 CFP Part 51 of the Commission's regulations and all applicable reouirements 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 Operatino license No. DPR-30 is hereby amended to read as follows:
870214o099 861230 PDR ADOCK 05000265 P
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_2 B.
Technical Specifications The Technical Specifications contained in '..pendices A and B, as revised through Amendment No. 93, 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.
FORTHENtfCLEARREGULjTORY(, COMMISSION.
d John. Zwolinski, Director BWR P oject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 30, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 93
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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 amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT vi vi 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 3.4/4.4-4 FIGURE 3.4-1 t
QUAD-CITIES DPR-30 TECHNICAL SPECIFICATIONS APPENDIX A LIST OF FIGURES 4
Number Title 2.1-1 APRM Flow Reference Scram and APRM Rod Block Settings 2.1-2 Deleted 2.1-3 APRM Flow Bias Scram Relationship to Normal Operating Conditions 4.1-1 Graphical Aid in the Selection of and Adequate Interval Between Tests 4.2-1 Test Interval vs. System Unavailability 3.4-1 Deleted 3.4-2 Sodium Pentaborate Solution Temperature Requirements 3.5-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs. Planar Average Exposure 3.5-2~
K factor 3.6-1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 4.6-1 Chloride Stress Corrosion Test Results at 5000F 4.8-1 Locations of Fixed Environmental Radiological Monitoring Stress 6.1-1 Corporate Organization 6.1-2 Station Organization Chart 6.1-3 Minimum Shift Manning Chart f
4 4
Amendment No. 84, 93 vi
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i QUAD-CITIES DPR-30 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRSMENTS 4
l Applicability:
Applicability:
Applies to the operating status of the Applies to the periodic testing require-ctcadby liquid control system.
monts for the standby liquid control 1
system.
Objective:
Objective:
To assure the availability of an indepen-To verify the operability of the standby d:nt reactivity control mechanism.
liquid control system.
i SPECIFICATIONS A.
Normal Operation A.
Normal Operation During periods when fuel is in the The operability of the standby liquid
.t reactor and prior to startup from a control system shall be verified by
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cold condition, the standby liquid performance of the following tests:
control system shall be operable i
except as specified in Specification 1.
At least once per month l
3.4.B.
This system need not be oper-j able when the reactor is in the cold Domineralized water shall be l
shutdown condition, all control rods recycled to the test tank. pump are fully inserted, and Specification minissem flow rate of 40 spa 3.3.A is met.
shall be verified against a y
system head of 1275 psig.
i 2.
At least once during each opera-ting cycle Manually initiate the system, except the explosion valves and pump solution in the recircula-i tion path, to demonstrate that the pump suction line from the storate tank is not plugged.
l Explode two of six charges or i
two of four charges manufactured l
in the same batch using the per-manent system wiring to verify l
Proper function. Then install the untested charges in the i
explosion valves.
i Domineralized water shall be i
injected via a test connection into the reactor vessel to test
.that valves (except explosion j
ve.1ves) not checked by the recirculation test are not clogged.
3.4/4.4-1 Amendment No. 93 i
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QUAD-CITIES DPR-30 Test that the setting of the system pressure relief valves is between 1455 and 1545 pois.
3.
Disassemble and inspect one emplosion valve so that it can be established that the' valve is not clogged. Both valves shall be inspected in the course of two operating cycles.
B.
Operation with Inoperable Components B.
Operation with Inoperable Components From and after the date that a redun-When a component becomes inoperable, dont component is made or found to be its redundant component shall be inoperable, Specification 3.4.A shall demonstrated to be operable immedi-be considered fulfilled and continued stely and daily thereafter.
operation permitted provided that the I
component is returned to an operable l
condition within 7 days.
t.
.C.
Liquid Poison Tank-Boron Concentration C.
Liquid poison Tank-Boron Concentration The liquid poison tank shall contain The availability of the proper l
a boron-bearing solution of at least boron-bearing solution shall be veri-3321 gallons of at least 14 WT fled by performance of the following percent sodium pentaborate tests:
Decahydrate (Na2 310 016 -
10H 0)'at all times when the 1.
At least once per month 2
l standby liquid control system is required to be operable and the Boron concentration shall be solution temperature shall not be determined. In addition, the i
less than the temperature presented boron concentration shall be in Figure 3.4-2.
determined any time water or j
boron are added or if the l
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.
I the cold shutdown condition within 24 I
hours.
2.
At least one per day l
Solution volume shall be checked.
3.
At least once per day The solution temperature shall l
be checked.
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3.4/4.4-2 Amendment No. 93
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QUAD-CITIES
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0 DPR-30 3.4 LIMITING CONDITIONS FOR OPERATION BASES A.
The design objective of the standby 11guld control system is to provide the capability of bringing the reactor from full power to a cold.
xenon-free shutdown assuming that none of the withdrawn control rods can be inserted.
To meet this objective, the 11guld control system is designed to inject a quantity of boron which produces a concentration 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 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 insertion due to cool down of the reactor following the zenon peak.
Two pump operation will enable faster reactor shutdown for ATHS events.
The monthly pump minimum flowrate test shall require a minimum flowrate of 40 gom.
This requirement, combined with the solution concentration requirement of at least 14 WT percent, will demonstrate that the Standby Liquid Control System meets the requirements,of 10CFR50.62.
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.
Experience with pump operability indicates that monthly testing is adequate to detect if failures have occurred.
The only practical time to test the standby liquid control system is during a refueling outage and by initiation from local stations.
l Components of the system are checked periodically as described above and make a functional test of the entire system on'a frequency of less than once each refueling outage unnecessary. A test of explosive charges from one manufacturing batch is made to assure that the charges 4
are satisfactory. A continual check of the firing circuit continuity l
15 provided by pilot lights in the control room.
8.
Only one of two standby liquid control pumping circuits is needed for l
proper operation of the system. If one pumping circuit is found to be l
Inoperable, there is no immediate threat to shutdown capability, and reactor operation may continue while repairs are being made. Assurance that the remaining system will perform its intended function and tnat the reliability of the system is good is obtained by demonstrating operation of the pump in the operable circuit at least once daily. A l
reliability analysis indicates that the plant can be operated safely in this manner for 7 days.
l 3.4/4.4 3 Amendment No.EJ 93 0680H i
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O QUAD-CITIES DPR-30 C.
The solution saturation temperature of 13% sodium pentaborate, by
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weight, is 590F. The solution shall be kept at least 10*F above the saturation temperature to guard against boron precipitation. The 0
10 F margin is included in Figure 3.3-1.
Temperature and liquid level alarms for the system are annunciated in the control room.
Pump operability is checked on a frequency to assure a high reliability 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 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 flow path integrity can be determined from the test of a single pump.
Comparison of single-pump test pressures with previous results and correlation of these data with initial two-pump tests are used to verify the capability of the piping.
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- 3. 4 /4. 4-4 Amendment No. 93 I
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