ML19273B014
| ML19273B014 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/16/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19273B012 | List: |
| References | |
| NUDOCS 7902010272 | |
| Download: ML19273B014 (2) | |
Text
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[va arcg%g UNITE D STATES y 's NUCLEAR REGULATORY COMMISSION Q@j@h 3,)
,1 l W ASHINGTON, 0. C. 20555 COMM0t1 WEALTH EDIS0ti COMPAtlY DOCKET NO. 50-295 ZION STATION UNIT NO. 1 AMETIDMENT TO FACILITY OPERATING LICENSE Amendnent No. 4l License tio. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 26, 1977, as supplementer by letter dated October 5,1978, 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, The facility will operate in conformity with the application, the B.
provisions of the Act, and the rules and regulations of the Commission; C.
i..are is reasonable cssurance (i) that the activities authorized by this amendnent 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 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 require-ments have been satisfied.
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. Accordingly, the license is amended by changes to the Technical 2.
Specifications as indicated in the attachnent to this license amendment and paragraph 2.C.(2) of Facility License No. DPR-39 is hereby amended to read as follows:
(2) Technicf]_ Specification The Technical Specifications contained in Appendices A and B, as revised through Anendnent No. 41,are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its issuance.
3.
F')R THE NUCLEAR REGULATORY COMMISSION
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- cWN W A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 16, 1979
[
S UNITED STATES
4 NUCLEAR REGULATORY COMMISSION
- I'o W ASHING TON, 0. C. 20$55 g
+....
COMMONWEALTH EDISON COMPANY 00CKET NO. 50-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. DPP,-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for anendment by Conmonwealth Edison Company (the licensee) dated October 26, 1977, as supplemented by letter dated October 5, 1978, 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 Conmission; C.
There is reasonable assurance (i) that the <
'/ities authorized by this amendment can be conducted without ei
.gering 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 amandnent 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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfied.
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,272 790201oggg
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license anendment and paragraph 2.C.(2) of Facility License flo. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendnent No. 38, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
?fzglV%lOV A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 16, 1979
ATTACliMENT TO LICENSE AMENDMEtlTS A!1ENDMENT NO. 41 TO FACILITY OPERATING LICENSE NO. DPR-39 AMErlDMENT NO. 38 TO FACIt.ITY OPERATING LICEtlSE f!0. OPR-48 00CKEI fl0S. 50-295 AND 50-304 Revise Appendix A as follows:
Remove Exi_stjng Insert Revised Page 80 Page 80 173 173 173A 173A 196 196 1
n n
J r
32.UILLAI:CE RECI?E7 ;2 LI.*/.ITISS CC..TsITIC:s FCA C?ERATION 3.3.2.
B.
The limit lines shown in Ficures 4.3.2 B.
Not Applicable 3.3.2-1 and 3.3.2-2 shall be recalculated per cdically.
C.
Th' secondary side of the steam j
C.
Not Applicsble generator must nc be pressurized above 200 psig if the temperature of the vessel is below 70 r D.
"The pressurizer heatup rate shall D.
Not Applicable not exceed 100;F/hr and the pressur-l izer cooldown rate shall not exceed C
200 P/hr".
The spray shall not be used if the temperature difference l
between the pressurizer and the spray ;
fluid is greater than 320-F.
Not Applicable C
E.
Hydrostatic Testinc f
1.
The initial reacter coolant j
system hydrostatic test shall i
be performed at a temperature i
not less than the limits of l
Figure 3.3.2-5.
l 2.
When a reactor coolant system is closr:d af ter it has been opened it shall be leak tested in accordance with Article IS-500 (Winter 1972 Addenda) of the ASME Boiler and Pressure l
Vessel Code Section XI.
The temperature at which this testing is performed shall not be less than the limits o f Figure 3.3.2-5.
Following this ;esting the system shall be depressurized i to meet the limits or Caction i
3.3.2.A for subsequent plant I
startup.
80 Amendment flo. 41, Unit 1 Amendment No. 38, Unit 2
SURVEILLANCE REQUIRIEENT LIMITING CONDITION FOR OPERATIOli 3.8.3 D.
If these conditions cannot be met 4.8.3 D.
Not Applicable the reactor shall be brought to the hot shutdown condition within four hours.
After a maximi m of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown candition, if the system is not operable the reactor shall be brought to the cold shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.
System testing of centrifugal charging, 4.
System testing of centrifugal charging, safety injection, and residual heat safety injection, and residual heat removal pump systems.
removal pump systems.
A.
A system test shall be performed A.
A system test shall be performed at each refueling outage.
The by manually initiating the safety test shall be considered injection signal to initiate operation of the centrifugal satisfactory if control board charging, safety injection, and indication and visual observa-tions indicate that all com-residual heat removal pump systems.
The centrifugal charging and safety ponents, as plant conditions injection pumps shall be blocked allow, have received the safety from starting during the test.
If injection signal and operated one of two residual heat removal satisfactorily.
pumps is not operating, it shall be blocked from starting the test.
B.
Proper valve stem position shall be verified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.
Proper E.C.C.S.
injection flows following the completion of will be maintained by verifying stroking or maintenance which valve stem positions and performing may affect the position of the following throttle valves when flow balance tests.
they are required operable:
- SI8810A, B,
C, D
- SI9003A, B,
C, D 173
- SI9013A, B,
C, D
Amendment No. 41, Unit 1 Amendment No. 38, Unit 2.
b-SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION 4.8.4.B A flow balance test shall be per-formed on the affected lines during the next refueling outage following valve stroking or maintenance or other system modifications which might alter the E.C.C.S.
flow characteristics.
E.C.C.S.
flow rates for single pump operation shall meet the following requirements under the minimum resistance configuration:
1.
Charging pump cold leg injection plus seal injection shall not exceed 550 GPM; 2.
SI pump hot or cold leg injection plus mini flow shall not exceed 650 GPM; 3.
The minimum charging pump cold leg injection through any 3 lines shall be 265 GPM; and 4.
The minimum SI pump cold leg injection through any 3 lines shall be 432 GPM.
173A Amendment No. 41, Unit 1 Amendment No. 38, Unit 2,
Basis:
"Recircualtion Sump to RIIR pump Isolation The 4.8 Complete Emergency Core Cooling Systems Valves" are stroked at a test pressure of tests cannot be performed when the re-20 psig to simulate post loss-of-coolant actor is operating because a safety accident conditions.
The valves are used injection signal causes reactor trip, during the recirculation phase approximately main feedwater isolation and containment 30 minutes after the accident.
At this time isolation.
The method of assuring the containment pressure is itss than 20 psig.
operability of these systems is therefore, to combine systems tests to be performed The purpose of these surveillance requirements during unit refueling shutdowns, with more is to provide assurance that proper E.C.C.S.
frequent component tests, which can be per-flows will be maintained in the event of a formed during reactor operation.
Maintenance of proper flow resistance LOCA.
and pressure drop in the piping system to The refueling outage systems tests each injection point is necessary to:
(1) demonstrate proper automatic operation of prevent total pump flow from exceeding runout With the Emergency Core Cooling Systems.
conditions when the system is in its minimum the pumps blocked from starting a test resistance configuration; (2) provide the signal is applied to initiate automatic proper flow split between injection points action and verification is made that the in accordance with the assumptions used in components receive the safety injection the ECCS-LOCA analyses; and (3) provide an The test signal in the proper sequence.
acceptable level of total ECCS flow to all demonstrates the operation of the valves, injection points equal to or above that pump circuit breakers, and automatic assumed in the ECCS-LOCA analyses.
circuitry.(1)
Accumulator check valve operability tests The active components (pumps and valves) are conducted to ensure that, if required, are to be tested monthly to verify that the accumulators will discharge as designed the pumps are in satisfactory running to the reactor coolant system.
The leak order and that the valves are free to move.
tightness of the valves is also checked to The test interval of one month is based on assure that the accumulators will not be the judgment that more frequent testing overpressurized during operation.
would not significantly increase the re-liability (i.e., the probability that (1)FSAR Section 6.2 the corcponent would operate when required),
and would result in increased wear over a long period of time.
The valves are fully stroked each refueling outage to verify their operability for component isolation.
Amendment No. 41, Unit 1 196 Amendment No. 38, Unit 2