|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20078E2051995-01-20020 January 1995 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20078Q6061994-12-12012 December 1994 Proposed TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20064J3181994-03-11011 March 1994 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20059A7321993-12-20020 December 1993 Proposed Tech Specs 1.1/2.1-1 Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8301993-10-21021 October 1993 Proposed Tech Specs Deleting Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20116J7091992-11-0606 November 1992 Corrected Proposed TS 3.2/4.2-8 Re Administrative Changes ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits ML20099D7791992-07-29029 July 1992 Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity 1999-08-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] |
Text
.
QUAD-CITIES DPR-30
, 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Applicability: Applicability:
Applies to the operating status of the Applies to the periodic testing require-ctendby liquid control system. monts for the standby liquid control system.
Objective: Objective:
To assure the availability of an indepen- To verify the operability of the standby
'dtnt reactivity control mechanism. liquid control system.
SPECIFICATIONS A. Normal Operation A. Normal 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 verified 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.B. This system need not be oper-able when the reactor is in the cold Demineralized water shall be shutdown condition, all contro1~ rods recycled to the test tank. Pump are fully inserted, and Specification minimum flow rate of 40 spm l 3.3.A is met. shall be verified against a
- system head of 1275 psig.
- 2. At least once during each opera-ting cycle Manually initiate the system, except the explosion valves and pump solution in the recircula-tion path to demonstrate that the pump s ction line from the storage taak is not plugged.
Explode two of six charges or two of four charges manufactured in the same batch using the per-manent system wiring to verify proper function. Then instal?,
the untested charges in the 8611070271 861028 explosion valves.
PDR ADOCK 05000265 P PDR Domineralized water shall be injected via a test connection into the reactor vessel to test
,that valves (except explosion valves) not checked by the recirculation test are not clogged.
0624H 3.4/4.4-1 Amendment No.
.- . - - ~. . - . _
QUAD-CITIES DPR-30 Test that the setting of the system pressure relief valves is between 1455 and 1545 psig.
- 3. Disassemble 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 two operating cycles.
B. Operation with Inoperable Conditions B. Operation with Inoperable Components From and after the date that.a redun- When a component becomes inoperable, i its redundant component shall be dant component is made or found to be inoperable, Specification 3.4.A shall demonstrated to be operable immedi-
- be considered fulfilled and continued ately and daily thereafter.
operation permitted provided that the
- component is returned to an operable condition within 7 days.
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 veri-3321 gallons of at least 14 WT fled by performance of the following
- . percent sodium pentaborate tests:
Decahydrate (Na2 B10 016 -
10H2 0) at all times when the 1. At least once per month standby liquid control system is
, required to.be operable and the Boron concentration shall be solution temperature shall not be determined. In addition, the less than the temperature presented boron concentration shall be in Figure 3.4-2. determined any time water or boron are added or if the 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 2. At least one per day Solution volume shall be checked.
j' 3. At least once per day The solution temperature shall be checked.
t 0624H 3.4/4.4-2 Amendment No.
g -
,-m- , - -,--o y v p-, , -aww,,-. v.v-----r---.---,--.-n,w-,m<,wa-enwm.,,,,,,m,,w,,e ,-m,. ., we-,,-.,----,,e-, ,aw,,,-w_,e- , .. ena ~
~
QUAD-CITIES OPR-29 3.4 LIMITING CONDITIONS FOR OPERATION BASES 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, xenon-free shutdown assuming that none of the withdrawn 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 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, xenon 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 gpm. 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.
Components of the system are checked periodically as described above and make a functional test of the entire system on a frequency of less tha.n once each refueling outage unnecessary. A test of explosive charges from one manufacturing batch is made to assure that the charges are satisfactory. A continual check of the firing circuit continuity is provided by pliot lights in the control room.
B. Only one of two standby liquid control pumping circuits is needed for proper operation of the system. If one pumping circuit is found to be 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 that the reliability of the system is good is obtained by demonstrating operation of the pump in the operable circuit at least once daily. A reliability analysis indicates that the plant can be operated safely in this manner for 7 days.
0624H 3.4/4.4-3 Amendment No.
'l i
0680H
QUAD-CITIES DPR-30 C. The solution saturation temperature of 13% sodium pentaborate, by weight, is 59 0F. The solution shall be kept at least 10 F 0above the saturation temperature to guard against boron precipitation. The 100 F margin'is included in Figure 3.3-1. Temperature and liquid level alarms for the system are annuciated 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, vhich 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.
i r
l 0624H 3.4/4.4-3a Amendment No.
.---,.-,w- , , . - .,,,-..----,..--n,,,.,- _ - , - , , . . _ , ,
QUAD-CITIES DPR-30
, l 4875 gal 9.75 '
'O ~
'(ft40RE DELET~2D ~
?.1 5-11 -
w I
E VOLUME CONCENTRATION REQUIREMENT 13 -
3470 gal em 16 3000 3500 4000 4500 5000 5500 VOLUME OF SOLUTION (gal)
FIGURE 3.4-1 STANOBY LIQUID CONTROL SOLUTION REQUIREMENTS
. AMENDMENT NO.
DPR-30
-g e ,
u S U 5
W f
M k L 2
w 5
8 i . $
d.
\ g
' \\ 5 g
t' e-s . . _ _ . _ -
\T 5 N 5w 5 Weid '
wgo $
bok ,
--e xam 5 \ o~
l N S"$r 5lW3
\
o 8 8 8 3 s.=. - -
(3.) 3V01VU3dW31
(
FIGURE 3.4-2 SODIUM PENTABORATE SOUJTION TEMPERATURE REQUIREMENTS AMENDMENT NO.
l .
- ATTACIGENT 2 NO SIGNIFICANT HAZARDS CONSIDERATION EVALUATION
! DESCRIPTION OF PROPOSED CHANGE c--nwealth Edison '(Ceco) proposes to modify the Quad Cities Unit 2 Technical Specifications to support a planned modification to the Standby Liquid control System (SBLC) to meet the requirements of 10 CPR 50.62. The specific changes to the' Technical Specifications involve replacing the boron concentration versus solution volume curve (Figure 3.4-1) with a minimum allowable volume of 3321 gallons of solution at a minimum concentration of 14 weight percent. The required SBLC pump flow rate is increased from 39 to 40 gpm. Also the allowable setpoint band for the system pressure relief valves has been increased from the current 1400 to 1490 psig to a band of
]
1455 to 1545 psig to reflect the increased pump discharge pressure during
- two pump operation. Finally, the Technical Specification bases have been revised to reflect the above changes.
DISCUSSION 10 CFR 50.62(c)(4) requires a SBLC system with a minimum flow capacity and boron content equivalent to 86 gpm of 13 weight percent sodium pentaborate solution. For Quad Cities Unit 2, this is being accomplished by modifying the SBLC system to allow dual pump operation (80 gym combined flow rate) and revising the_ Technical Specifications to require a 14% minimum concentration. The minimum required volume of solution in the Technical Specifications is revised from the previous 3,470 gallons of 13.4% solution I (from Figure 3.4-1) to 3,321 gallons of 14% solution. This preserves the original amount of boron injection.
As a result of two pump SBLC system operation discharge pressures will be higher. Accordingly, the allowable system pressure relief valve setpoints have been increased by approximately 55 psig.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION commonwealth Edison has evaluated the proposed Technical Specification changes and determined they do not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92(c), operation of Quad Cities in accordance with the proposed amendment will not:
- 1. Involve a significant increase in the probability or_ consequences of an accident previously evaluated because the proposed changes maintain the total amount of boron injection previously required by the Technical Specifications thereby maintaining the previous shutdown reactivity capability. The proposed changes are needed to implement the requirements of 10 CFR 50.62 and have no impact on systems or equipment that could potentially initiate or impact the probability of an accident.
l
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated because the changes involve a system whose
-only function is to provide a backup shutdown capability. The changes do not affect any systems or equipment which could initiate an accident.
- 3. Involve a significant reduction in the margin of safety because the overall shutdown reactivity capability (i.e. total boron injection) of the SBLC system is not reduced by these changes. The proposed amendment supports required modifications which will increase the SBLC system injection rate, thereby increasing the margin of safety for Anticipated Transient without Scram events.
Based on the above discussion, commonwealth Edison concludes the proposed Technical Specification changes do not represent a Significant Hazards Consideration.
i l
l l
2200K
. - . - - - _ - _ . . , , . . _ _ . _ - _ _ . . . _ - _ _ _ _ _ - _ _ _ _