ML20055D717
| ML20055D717 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/27/1990 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055D718 | List: |
| References | |
| NUDOCS 9007090329 | |
| Download: ML20055D717 (8) | |
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UNITED STATES
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NUCLEAR RECULATORY COMMISSION l
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f COMMONWEALTH EDISON COMPANY AND 10WA-ILLIN01$ GAS'AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 License No. OPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (thelicensee)datedMay 19, 1990, 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 t1e Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 it 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. DPR-29 is hereby amended to read as follows:
9007090329 900627 PDR ADOCK 05000254 P
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B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.125, are hereby incorporated in the i
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 COMMIS$10N p /A' Rich d. Barrett, Director Project Directorate !!!-2 Division of Reactor Projects - 111 IV,YandSpecialProjects Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: June 27, 1990 t
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ATTACHMENT TO LICENSE AMENDMENT N0.125 FACILITY OPERATING LICENSE NO. DPR-29 l
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 i
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3.7/4.7-3 3.7/4.7-3 3.7/4.7-4 3.7/4.7-4 3.7/4.7-5 3.7/4.7-5 i
3.7/4.7-40 3
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QUADCITIES i
L, DPR-29
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TECHNICAL SPECIFICATIONS APPENDIX A LIST OF TABLES Number Title Page 3.1-1 Reactor Protection System (Scram)
Instrumentation Requirements-Refuel Mode 3.1/4.1-11 3.1-2 ReactorProtectionSystem(Scram) Instrumentation Requirements-Startup/ Hot Standby Mode 3.1/4.1-12 3.1-3 Reactor Protection System (Scram) Instrumentation Requirements-Run Mode 3.1/4.1-13 3.1-4 Notes for Tables 3.1-1, 3.1-2 and 3.1-3 3.1/4.1-14 4.1-1 ScramInstrumentationandLogIcSystemsFunctional Test-Minimum Functional Test frequencies for Safety Instrumentation, Logic Systems and Control Circuits 3.1/4.1-15 4.1-2 ScramInstrumentCalibration-MInimumCalibration Frequencies for Reactor Protection Instrument Channels 3.1/4.1-17 3.2-1 Instrumentation that Initiates Primary Containment Isolation Functions 3.2/4.2-15 3.2-2 Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 3.2/4.2-17 3.2-3 Instrumentation that Initiates Rod Block 3.2/4.2-19 3.2-4 Postaccident Monitoring Instrumentation Requirements 3.2/4.2-21
-3.2-5 Radioactive Liquid Effluent Monitoring Instrumentation 3.2/4.2-24 3.2-6 Radioactive Gaseous Effluent Monitoring Instrumentation 3.2/4.2-25 4.2-1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks and Isolation 3.2/4.2-27 4.2-2 Postaccident Monitoring Instrumentation Surveillance Requirements 3.2/4.2-30 4.2-3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3.2/4.2-32 4.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3.2/4.2-33 t
4.6-1 Inservice Inspection Recuirements for Quad-Cities 3.6/4.6-34 4.6-2 Revised Withdrawal Schecule
- 3. U4. 6-43 3.7-1 Primary Containment Isolation
- 3. '//4. 7-33 3.7-2 Primary Containment Leakage Test i'enetrations 3.7/4.7-39 4.7-1 Temocrarily Untested Pathways 3.7/4.7-40l 4.8-1 Radioactive Gaseous Waste Sampling ana Analyti. Program 3.8/4.8-27 v
Amendment No.
125
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QUADCITIES DPR-29 2.
Primary containment integrity 2.
The c otainment leakage rates shall be maintained at all times shall oe demonstrated at the I
when the reactor is critical or following test schedule, and when the reactor water shall be determined in temperature is above 212'F and confomance with the criteria i
fuel is in the reactor vessel specified in Appendix J of 10 except while perfoming low CFR 50 using the methods and power physics tests at provisions of ANSI N45.4 (1972)..
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atmospheric pressure at power levels not to exceed 5 MWt.
a.
When primary containment a.
Three Type A tests (Overall
-integrity is required Integrated Containment primary containment leakage Leakage Rate) shall be e
rates shall be limited to:
conducted at 40 110 month intervals during shutdown at
- 1) An overall integrated either P 48 psig or at leakage rate of:
P 25pilgduring,each 1
16,yearserviceperiod.
The a) < L, 1.0 percent by third test of each set shall weilhtofthe be conducted during the containment air per shutdown for the 10-year 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 48 plant inservice inspection.
i psig, or i
b) < L, 1.0 percent by l
weihhtofthe containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P, 25 psig.
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- 2) A combined leakage rate t
of < 0.60 L for all penetrationiandvalves, except the main steam isolation valves, and the M01-220-1 valve (whileitis inoperable), subject to Type 8 and C tests when pressurized to Pvalve $.
The M01-220-1 111 be restored to oper-ability no later than startup after the first Cold Shutdown following a 30-day period after December 21, 1982. Also temporarily excluded are those pathways specified in Section 4.2.d.5).
3.7/4.7-3 Amendment No.125 m am
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QUAD CITIES DPR-29
- 3) 11.5 scf per hour for any one main steam isolation valve when tested at 25 psig, b.
With the measured overall b.
If any periodic Type A test integre.ted containment fails to meet either 0.75 L*
leakage rate exceeding 0.75 or 0.75 L, the test.
scheduleforsubsequentType L or 0.75 L as a$plicable,h,storethe A tests shall be reviewed.
overall integrated leakage and approved by the rate (s) to < 0.75 L or Commission.
If two consecu-
< 0.75 L asapplilable.
tive Type A tests fail to Temporarhyexcludedare meet either 0.75 L or those pathways specified 0.75L,aTypeAtestshall in Section 4.2.d.5).
beperformedateachshutdown for refueling or a;> proximately every 18 months, w11chever occurs first, until two consecu-tive Type A tests meet either 0.75 L or 0.75 L, at which timetheaboveteltschedule may be resumed.
c.
With the measured combined c.
The accuracy of each Ty>e A leakage rate for all test shall be verified >y a penetrations and valves, supplemental test which; except for main steam isolationvalves,subjectto
- 1) Confirms the accuracy of Type B and C tests exceeding the test by verifying 0.60 L, restore the that the difference combinldleakageratefor between the supplemental-all penetrations and valves, data and the Type A test except for main steam data is within 0.25 L*
isolationvalves,subjectto or 0.25 L.
Type B and C tests to g
0.60 L.
Also temporarily
- 2) Has a duration excludIdarethosepathways sufficient to establish specifiedinSection4.2.d.5),
accurately the change in leakage rate between the Type A test and the supplemental test.
3.7/4.7-4 Amendment No. 125 I
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i QUAD-CITIES DPR-29 1
- 3) ~ Requires the quantity of gasinjectedintothe-j eentainment or bled from i
the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P 4
25pNg.8psig,orP' t
d.
Leakage shall be limited to d.
Type B and C tests shall be a leakage rate of less than conducted at P, 48 osig, at or equal to 3.75 percent of intervalsnogfeater.than24 L for any one air lock when months except for tests pfessurizedto10psig.
involving:
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- 1) Air locks which shall be i
tested at 10 psig at least once per 18 months, and s
- 2) Main steam isolation valves which shall be leak tested at least once per operating cycle, of a frequency not to exceed 24 months, at a pressure of 25 psig.
- 3) Bolteddouble!asketed l
seals which sh 11 be l'
tested at a pressure of 48 psig whenever the seal is closed after being opened and each 5
operating cycle.
- 4) While valve M01 220-1 is inoperable, valves M01-220-2, M01-220-3, and M01-220-4 shall be VERIFIED closed after l-each closure.
- 5) The pathways identified in Table 4.7-1, which will not be tested until the end of cycle 11 refueling outage.
3.7/4.7-5 Amendment No. 125
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I QUAD-CITIES DPR-29 i
TABLE 4.7-1 TEMPORARILY UNTESTED PATHWAYS
- System Penetration No.
Line No.
Instr. Air X216 47138-1/2" Instr. Air X22 47200-2"
.P.8CCW X23 3769-10"
.RBCCW X24 3747-10" Core Spray X168 1404-10" Core Spray X16A 1403-10" SBLC X47 1102-1 1/2" Clean Domin. Water X20 4309-3"
- Local Leak Rate Testing not required until End of Cycle 11 refueling outage.
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i 3.7/4.7-40 Amendment No.
125
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