ML20043C024
| ML20043C024 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/23/1990 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043C025 | List: |
| References | |
| NUDOCS 9006010209 | |
| Download: ML20043C024 (19) | |
Text
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98" UNITED STATE $
'n NUCLEAR HEGULATORY COMMISSION
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I WASHING TON, D. C. 20555
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10WA-ILLIN015 GAS AND ELECTRIC COMPAN'f DOCKET NO. 50-254 00AD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 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 October 11, 1989, 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; B.
The facility will operate in cor<formity with the application.
the provisions of the Act, and the rules and regulations of the.
Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi11 be conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements 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 Operating License No. DPR-29 is hereby amended to read as follows:
9006010209 900323 PDR ADOCK 05000254 P
upa. 1 B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, 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.
FOR THE NUCLEAR REGULATORY COMMISSION M
Richard F. Dudley, Acting Director Project Directorate 111-2 Division of Reactor Projects - Ill, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 23,1990 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 124 l
FACILITY OPERATING LICENSE NO. DPR-29 i
DOCKET NO. 50-254 l
l l
Revise the Appendix A Technical Specifications by removing the pages l
identiffed below and inserting the attached pages. The revised pages are l
identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT l
3.6/4.6-9 3.6/4.6-9 3.6/4.6-10 3.6/4.6-10
?
3.6/4.6-11 3.6/4.6-11 3.6/4.6-12 3.6/4.6-12 3.6/4.6-13 3.6/4.6-13 3.6/4.6-23 3.6/4.6-23 J
+
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1
QUAD-CITIES DPR-29 G.
Jet Pumps G.
Jet Pumps 1.
Whenever the reactor is in the 1.
Whenever there is recirculation Startup/ Hot Standby or Run flow with the reactor in the modes, all-jet pumps shall be Startup/ Hot Standby or Run intact, and all operating jet modes, jet pump integrity and-pumps shall be operable.
If it operability shall be checked is determined that a jet pump is daily by verifying that two of inoperable, an orderly shutdown the following conditions do shall be initiated and the not occur simultaneously:
reactor shall be in a cold shutdown condition within 24 a.
The recirculation pump flow hours.
differs by more than 10%
from the established speed-flow characteristics.
b.
The. indicated total core-flow is more than 10%
greater than the core flow value derived from established core plate DP core flow relationships.-
c.
Individuel jet pump flow for
' l each jet pump does not differ by more than 10% from estab-lished flow to average loop jet pump flow character,istics.
2.
Flow indication from 19 of the 2.
Additionally, when operating 20 jet pumps shall be verified with one recirculation pump with prior to initiation of reactor the equalizer valves closed, the startup from a cold shutdown diffuser to lower plenum condition, differential pressure shall be checked daily, and the differential pressure of any jet pump in the idle. loop shall not vary by more than 10% from established patterns.
3.6/4.6-9 Amendment No. -124 ' I n
.c,
QUAD-CITIES DPR-29 3.
The indicated core flow is the 3.
The baseline data required to sum of the flow indication from evaluate the conditions in each jet pump with operable flow-Specifications 4.6.G.1 and indication.
In addition, for 4.6.G 2 will be acquired each any jet pump with inoperable operating cycle.
flow indication, the flow indication from the companion jet pump on the same jet pump riser shall be summed a second time to compensate for the flow through the jet pump with inoperable flow indication.
If flow indication failure occurs for three or more jet pumps, immediate corrective action shall be taken.
If flow indication for all but two jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
4.
If flow indication failure occurs for both jet pumps on the same jet pump riser, immediato corrective action shall be taken.
If flow indication for
~
at least one of the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
If flow indication failure occurs for both calibrated (double-tap) jet pumps on the same recirculation loop,
, immediate corrective action shall be taken.
If flow indication for at least one of.the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall in cold shutdown I
condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6/4.6-10 Amendment No.124 I
i
.s QUAD-CITIES DPR-29 H.
Recirculation Pump Flow limitations H.
Recirculation-Pump Flow Limitations 1.
Whenever both recirculation pumps are in operation, pump Recirculation pumps speed shall be speeds shall be maintained checked daily for mismatch.
within 10% of each other when i
power level is greater than 80%
and within 15% of each other when power level is less than 80%.
2.
If Specification 3.6.H.1 cannot
-be met, one recirculation pump shall be tripped.
3.
During Single Loop Operation for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the following restrictions are required:
a.
The MCPR Safety Limit shall be increased by 0.01 (T.S.
1.1A);
b.
The MCPR Operating Limit. as r
I specified in the CORE OPtHAT-ING LIMITS REPORT, shall be increased by 0.01 (T.S. 3.5.K);
c.
The flow biased APRM Scram and Rod Block Setpoints I
shall be reduced by 3.5% to read as follows.
T.S. 2.1.A.1; S 1 58WD + 58.5 T.S. 2.1.A.1;*
S 1 (.58WD + 58.5) FRP/MFLPD l
T.S. 2.1.B; i
S 1 58WD + 46.5 T.S. 2.1.B;*
i S 1 (.58WD + 46.5) FRP/MFLPD T.S. 3.2.C (Table 3.2-3);*
l APRM Upscale 1 (.58WD + 46.5)
FRP/MFLPD
3.6/4.6-11 Amendment No.
124
QUAD-CITIES l
DPR-29 d.
The flow biased RBM Rod Block setpoints, as'specified in the CORE OPERATING LIMITS REPORT, shall be reduced by i
4.0%.
e.
The suction valve in the idle loop shall be closed and electrically isolated except when the idle loop is being prepared for return to service.
l I.
Shock Suppressors (Snubbers) 1.
Shock Suppressors (Snubbers)
The following surveillance require -
ments apply to all snubbers on safety-related piping systems.
1.
During all modes of operation
=1.
Visual inspections shall be except Shutdown and Refuel.all performed in accordance with the snubbers on safety-related piping following. schedule utilizing the systems shall be operable except acceptance criteria given by as noted in 3.6.I.2 following.
Specification 4.6.I.2.
l l
Number of Snubbers Found Inoperable Next During Inspection
- Required, or During Inspec-Inspection tion Interval Interval l
L 0
18 months t2S%
1 12 months t25%
2 6 months 125%
3,4-124 days t25%
5,6,7 62 days t25%
>8 31 days 125%.
The. required inspection interval shall not k lengthened more than one rcep at a time, r
3.6/4.6-12 Amendment No'..
124
I QUAD-CITIES i
OPR-29 r
1.
(Cont'd) i Snubbers may be categorized in t
two groups, ' accessible' or
' inaccessible' based on their accessibility for inspection during reactor operation.. These two groups may be inspected independently according to the above schedule.
Snubber service life moni-t toring shall be followed by the snubber surveillance inspection records and maintenance history records. - The above record retention method shall.be used to prevent the snubbers from exceeding a service life.
2.
From and after the time that a 2.
Visual inspections shall. verify:
snubber is determined to be inoperable, continued reactor a.
There are no visible-operation is permissible during indications of damage or the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if impaired operability, and i
the snubber is sooner made
- operable, b.
Attachments to the foundation or supporting structure are secure.
3.
If the requirements of 3.6.I.1 3.
Once each refuel'ing cycle a and 3.6.I.2 cannot be met, an representative sample of 10% of I
orderly shutdown shall be the total of each type of.-
initiated and the reactor shall snubber in~ use-in the plant be in a cold shutdown condition
~ hall be functionally tested s
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, either in place or in a bench test.
For each snubber that does not meet the functional test criteria, an additional 10%
of that type of snubber shall be functionally tested.
-i l
3.6/4.6-13 Amendment No. 124
R QUAD-CITIES OPR-29 l
G.
Jet Pumps Failure of a jet pump nozzle assembly holddown mechanism, nozzle assembly, and/or riser increases the cross-sectional flow area for blowdown following the postulated design-basis double-ended recirculation line break.
Therefore, if a failure occurs, repairs must be made to assure the validity of the calculated consequences.
Maintenance of jet pump integrity is required to demonstrate that the core can be reflooded to two-thirds core height i
following a large recirculation line break loss-of-coolant accident.
The following factors form the basis for the surveillance requirements:
1.
A break in a jet pump decreases the flow resistance characteristic of the external piping loop causing the recirculation pump to operate at a higher flow condition when compared to previous i
operation.
2.
Agreement of indicated core plate dp/ core flow relationships provides assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps.
3.
The change in flow rate of the failed jet pump produces a change in the indicated flow rate of that pump relative to.the other pumps in that loop.
Comparison of the data with a normal relationship or pattern provides the indication necessary to detect a failed jet 4
pump.
Comparison of individual jet pump flows to average. loop jet pump flow is the most sensitive indicator of significant jet pump performance degradation.
The individual jet pump flow deviation from established patterns will clearly indicate jet pump displacement since the indicated flow of the jet pumps on the affected riser changes by 45% and 67%.
Failure of a jet pump with-lost flow indication would be indicated by a change in the flow to average loop jet pump flow ratio of the companion jet pump on the same jet pump riser.
' Plant operation with loss of flow indication for both jet pumps on the same riser is not permitted.
If this should occur, there is no method for ensuring jet pump integrity is being maintained for the affected jet pumps.
Plant operation with loss of flow indication for both calibrated (double-tap) jet pumps on a recirculation loop is not permitted.
If this should occur, uncertainties introduced into core flow calibration exceed the value assumed in the derivation of the Safety Limit Minimum Critical Power Ratio.
I A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true.
The lack of any 1
substantial stress in the jet pump body makes failure impossible without an initial nozzle riser system failure.
3.6/4.6-23 Amendment No. 124
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UNITED STATES 8
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,e NUCLEAR REGULATORY COMMISSION v...m h I wAsHiNotoN, D. C. 20655 COMMONWEALTH EDISON COMPANY MD, IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 121 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company-(the licensee) dated October 11, 1989, 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; B.
The facility will o)erate in conformity with the application.
the provisions of tie Act, and the rules and regulations of the-Commission; y
Thereisreasonableassurance(1))thattheactivitiesauthorized C.
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 1
comon defense and security or to the health and. safety of the 1
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 is 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-30 is hereby amended to read as follows:
to B.
Technical Specifications j
i
-The Technical Specifications cont 61ned in Appendices A and B as l
revised through Amendment No.121, are hereby incorporated In the
-license. The licensee shall operate the facility in accordance l
with the Technical Specifications.
I 3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION Y
I Richard F. Dudley, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
+
Attachment:
Changes to the Technical Specifications Cate of Issuance:
May 23, 1990 v
2 9
P b
4
~
d A1TACHMENT TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-30 l
DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages l
identified below and inserting the attached pages. The revised pages are-l identified by the captioned amendment number and contain marginal lines i
indicating the area of change.
REMOVE INSERT
.i
- ii ii l
\\
3.6/4.6-5 3.6/4.6-5 3.6/4.6-Sa 3.6/4.6-5a 3.6/4.6-5b 3.6/4.6-5b 3.6/4.6-5c 3.6/4.6-13 3.6/4.6-13 3.6/4.6-13a 3.6/4.6-13a b
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OPR-30 i
s, TABLE OF CONTENTS (Cent'd)
Page j
3.5/4.5 CORE CONTAINMENT COOLING SYSTEMS 3.5/4.5-1
+
A.
Core Spray Subsystems and the LPCI Mode of the RHR System 3.5/4.5-1 B.
Containment Cooling Mode of the RHR System 3.5/4.5-3 C.
HPCI Subsystem-3.5/4.5-4 D.
Automatic Pressure Relief Subsystems 3.5/4.5-5 i
E.
Reactor Core Isolation Cooling System
-3.5/4.5-6 I
F.
Minimum Core and Containment Cooling System Availability 3.5/4.5-6 G.
Maintenance of Filled Discharge Pipe 3.5/4.5-7 H.
Condensate Pump Room Flood Protection 3.5/4.5-8
.l I.
Average Planar Linear Heat Generation Rate (APLHGR) 3.5/4.5-9 J.
Local LHGR 3.5/4.5-9 K.
Minimum Critical Power Ratto (MCPR) 3.5/4.5-10 t
1 3.5 Limiting Conditions for Operation Bases 3.5/4.5-11 i
4.5 Surveillance Requirements Bases 3.5/4.5-16 3.6/4.6 PRIMARY SYSTEM BOUNDARY 3.6/4.6-1 A.
Thermal Limitations 3.6/4.6-1 i
i B.
Pressurization Temperature 3.6/4.6-1 C.
Coolant Chemistry 3.6/4.6-2 D.
Coolant Leakage 3.6/4.6-3 E.
Safety and Relief Valves 3.6/4.6-4 F.
Structural Integrity 3.6/4.6-4 G.
Jet Pumps:
3.6/4.6-5 i
H.
Recirculation Pump Flow limitations 3.6/4.6-Sa I.
Shock Suppressors (Snubbers) 3.6/4.6-Sc 3.6 Limiting Conditions for Operation Bases 3.6/4.6-8
[
.3.7/4.7 CONTAINMENT SYSTEMS 3.7/4.7-1 i
A.
Primary Containment 3.7/4.7-1 B.
Standby Gas Treatment System 3.7/4.7-7 i
C.
Secondary Containment 3.7/4.7-8 0.
Primary Containment Isolation Valves 3.7/4.7-9 3.7 Limiting Conditions for Operation Bases 3.7/4.7-11 4.7 Survelliance Requirements Bases
-3.7/4.7-15 l
3.8/4.8 RADIOACTIVE EFFLUENTS 3.8/4.8-1 i
i A.
Gaseous Effluents 3.8/4.8-1 B.
Liquid Effluents 3.8/4.8-6a C.
Mechanical Vacuum Pump 3.8/4.8-9 D.
Environmental Monitoring Program 3.8/4.8-10 E.
Solid Radioactive Waste 3.8/4.8-13 F.
Miscellaneous Radioactive Materials Sources 3.8/4.8-14 H.
Control Room Emergency Filtration System 3.8/4.8-14a 3.8/4.8 Limiting Conditions for Operation and Surveillance Req. Bases 3.8/4.8-15 1631B/0600Z 11 Amendment No. 121 7
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[G.
Jet Pumps G.
Jet Pumps 1.
14henever the reactor is in the 1.
14henever there is recirculation Startup/ Hot Standby or Run flow with the reactor in the modes, all jet pumps shall be Startup/ Hot Standby or Run modes, intact, and all operating jet jet pump integrity and pumps shall be operable.
If 1t operability shall be checked is determined that a jet pump daily by verifying that two of is inoperable, an orderly the following conditions do not shutdown shall be initiated and occur simultaneously:
the reactor shall be in a cold shutdown condttion within 24 a.
The recirculation pump flow-
- hours, differs by more than 10%
from the established speed-flow character 1$ tics.
b.
The indicated total core flow is more than 10%
greater than the core flow value derived from established core plate DP/ core flow relationships.
c.
Individual jet pump flow for each jet pump does not differ by more than 10% from established flow to average loop jet pump flow characteristics.
2.
Flow indication from 19 of the l
2.
Additionally, when operating wtth 20 jet pumps shall be verified one recirculation pump with the prior to initiation of reactor equalizer valves closed, the startup from a cold shutdown diffuser to lower plenum condition.
differential pressure shall be checked daily, and the differential pressure of any jet pump in the idle loop'shall not-vary by more than 30% from established patterns.
3.
The indicated core flow 1s the 3.
The baseline data required to sum of the flow indication from evaluate the conditions in each jet pump with operable Specifications 4.6 G.1 and flow indication.
In addition, 4.6.G.2 will be acquired each for any jet pump with operating cycle, inoperable flow indication, the flow indication from the companion jet pump on the same jet pump riser shall be sumned a second time to compensate for the flow through the jet pump with inoperable flow indication.
If flow indication failure occurs for three or
-1631B/0600Z 3.6/4.6-5 Amendment No. 121 l
4 4
~
QUAD-CITIES l
3 OPR-30 "O
more jet pumps, immediate corrective action shall be 8
taken.
If flow Indication for all but two jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
If flow indication failure occurs for both jet pumps on i
the same jet pump riser, immediate corrective action i
shall be taken.
If flow indication for at least one of the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall 4
be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
If flow indication failure occurs for both calibrated (double-tap) jet pumps on the same recirculation loop, immediate corrective action shall be taken.
If flow l
indication for at least one of i
the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be l
initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
H.
Recirculation Pump Flow Limitations H.
Recirculation Pump Flow Limitations 1.
Whenever both recirculation Recirculation pumps speed shall be pumps are in operation pump checked daily for mismatch.
speeds shall be maintained t
within 10% of each other when power level is greater than 80%
and within 15% of each other t
when power level is less than 801.
e 2.
If Specification 3.6.H.1 cannot be met, one recirculation pump shall be tripped.
16318/06002 3.6/4.6-Sa
. Amendmtnt No. 1 21 P
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QllAb-CITIES i
DPR-30 3.
Prior to Single Loop Operation for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the following restrictions are required:
a.
The MCPR Safety Limit shall be Increased by 0.01.
(T.S. 1.1A);
5 b.
The MCPR Operating Limit, ac specified in the CORE OPERATING LIMITS REPORT, shall be increased by 0.01 (T.S. 3.5.K);
c.
The flow biased APRM Scram and Rod Block Setpoints shall be reduced by 3.5% to read as i
follows:
T.S. 2.1.A.1;
' S 1 58HD + 58.5 T.S. 2.1.A.1;*
S 1 (.58HD + 58.5) FRP/MFLPD T.S. 2.1.B:
S 1 58HD + 46.5 T.S. 2.1.B;*
S 1 (.58HD + 46.5) FRP/MFLPD T.S. 3.2.C (Table 2.1-3);*
APRM upscale < (.58HD + 46.5)
~
FRP/MFLPD l
In the event that MFLPD exceeds FRP.
1 d.
The flow biased RBM Rod Block setpoints, as specified in the CORE OPERATING LIMITS REPORT, shall be reduced by 4.0%.
e.
The suction valve in the idle loop shall be closed and electrically isolated except when the idle loop is being prepared for return to service.
4 1
1976H/0615Z 3.6/4.6-Sb Amendment No. 121
QUAD-CI?lES DPR-30 Shock Suppressors (Snubbers) 1.
Shock Suppressors (Snubbers)
The following-surveillance requirements apply to all snubbers on
?
safety related piping systems.
1.
During all modes of operation 1.
Visual inspections shall be except Shutdown and Refuel, all performed in accordance with the snubbers on safety related following schedule utilizing the t
piping systems shall be operable acceptance criteria given by except as noted in 3.6.I.2 Specification 4.6.I.2.
following.
2.
From and after the time that a Number of Snubbers snubber is determined to be.
Found Inoperable Next inoperable, continued reactor During Inspection Required operation is permissible during or During Inspec-Inspection the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if
' tion Interval Interval
-the snubber is sooner made i
0 18 months t
+25%
3.
If the requirements of 3.6.I.1
~
and 3.6.I.2 cannot be met, an 1
12 months orderly shutdown shall be
+25%
initiated and the reactor shall
~
be in a cold shutdown condition 2
6 months within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
225%
4.
If a snubber is determined to be 3.4 124 days inoperable while the reactor is
+25%
In the Shutdown or Refuel mode,
~
the snubber shall be made 5,6,7 62 days operable prior to reactor 125%
5 startup.
28 31 days 225%
The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, ' accessible' or
' inaccessible' based on their accessibility for inspection during reactor operation.. These two groups may be inspected independently according to the above schedule.
1631B/0600Z 3.6/4.6-5c Amendment No.121 w-
,m.. _,,
.y-
l
. QUAD-CITIES DPR-30 L'..
G.
Jet Pumps I *;.
Failure of a jet pump nozzle assembly holddown mechanism, nozzle assembly, and/or riser increases the cross-sectional flow area for blowdown following the postulated design-basis double-ended recirculation line break.
Therefore, if a failure occurs, repairs must be made to assure the validity of the calculated consequences. Maintenance of jet pump Integrity is required to demonstrate that the core can be reflooded to two-thirds core height following a large recirculation line break f
loss-of-coolant accident.
The following factors form the basis for the surveillance requirements:
1.
A break in a jet pump decreases the flow resistance I
characteristic of the external piping loop causing the recirculation pump to operate at a higher flow condition when 1
compared to previous operation.
2.
Agreement of indicated core plate dp/ core flow relationships provides assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps.
l 3.
The change in flow rate of the failed jet pump produces a change
(
in the indicated flow rate of that pump relative to the other i
pumps in that loop.
Comparison of the data with a normal relationship or pattern provides the indication necessary to.
detect a failed jet pump.
Comparison of individual jet pump flows to average loop jet pump flow is the most sensitive indicator of significant jet pump performance degradation. -The individual jet pump flow deviation from established patterns will clearly indicate jet pump displacement since the indicated flow of the jet pumps on the affected riser changes by 45% and 67%.
Failure of a jet pump with lost flow indi' cation would be indicated by a change in the flow to average loop jet pump flow ratio of the companion jet pump on the same jet pump riser.
Plant operation with loss of flow indication for both jet pumps on the same riser is not permitted.
If this should occur, there is no method for ensuring jet pump integrity is being maintained for the affected jet pumps.
Plant operation with loss of flow indication for both calibrated (double-tap) jet pumps on a recirculation loop is not permitted.
If this should occur, uncertaintles introduced into core flow calibration exceed the value assumed in the derivation of the Safety Limit Minimum Critical Power Ratio.
A nozzle-riser system failure could also generate the coincident failure of 4 jet pump body; however, the converse is not true.
The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle riser system failure.
16318/0600Z 3.6/4.6-13 Amendment No.
121 5
QUAD-CITIES DPR-30 l<
l..
H.
Recirculation Pump Flow Limitation l
l The LPCI loop selection logic is described in the SAR Section 6.2.4.2.5.
For some limited low probability accidents with the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection.
For these limited conditions, the core spray itself is adequate to prevent fuel temperatures from exceeding allowable limits.
However, to limit the probability even further, a procedural limitation has been placed on the allowable variation in. speed i
between the recirculation pumps.
The licensee's analyses indicate that above 80% power the loop select. logic could not be expected to function at a speed differential of 15%.
Below 80%
power, the loop select logic would not be expected to function at a speed differential of 20%.
This specification provides a margin of 5% in pump i
speed differential before a problem could,arise.
If the reactor is operating on one pump, the loop select logic trips that pump before making.the loop selection.
Analyses have been performed which support indefinite single loop operation provided the appropriate restrictions are implemented within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />..The MCPR Safety Limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used.in the statistical analysis of the safety limit.
The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, has also been increased by 0.01 to maintain the same margin to
+
the safety limit as during Dual Loop operation.
The flow biased scram and rod block setpoints are' reduced to account for uncertainties associated with backflow through the idle jet pumps when the operating recirculation pump is above 20-40% of rated speed.
This assures that the flow biased trips and blocks occur at conservative neutron flux levels for a given core flow.
The closure of the suction valve in the idle loop prevents the loss of LPCI flow through the idle recirculation pump into the downcomer, j
l l
l 2760H 3.6/4.6-13a Amendment No.121
.