ML20211N157
| ML20211N157 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/20/1987 |
| From: | Rajender Auluck Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211N162 | List: |
| References | |
| NUDOCS 8703020005 | |
| Download: ML20211N157 (22) | |
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og UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION
,j WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS ANil ELECTRIC COMPANY DOCKET NO. 50-?S4 00AD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. OPR-29 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 27, 1984 as supplemented iuly 22, 1986, l
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; R.
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 (1) that the activities authorized by this amendment can he conducted without endangering the health and safety of the public, and (11) 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 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 3.8. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
%#Nb 4
l'
T O B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby increporated in the license. The licensee shall operate the facility n accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
t.
LO(
M Rajender Auluck, Acting Director BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Char.ces to the Technical Specifications Date of Issuance:
February 20, 1987
wz ATTACHMENT TO LICENSE AMENDMENT NO. 101 FACILITY OPERATING LICENSE NO. DPR-29 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 3.1/4.1-8 3.1/4.1-8 3.1/4.1-9 3.1/4.1-9 3.1/4.1-10 3.1/4.1-10 3.2/4.2-11 3.2/4.2-11 3.2/4.2-12 3.2/4.2-12 3.7/4.7-10 3.7/3.7-10 3.7/4.7-18 3.7/4.7-18 3.7/4.7-19 3.7/4.7-19 l
QUAD-CITIES DPR-29 TABLE 3.1-1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS REFUEL MODE Minimum Number of Operable or Tripped Instrument Channels per Trip System (l)
Tric Function Trio level Setting Action (2) 1 Mode switch in shutdown A
1 Manual scram A
IRM 1.20/125 of full scale A
1 3
High Flux 3
Inoperative APRM(3) 2 High Flux (15% scram)
Sp,ecification 2.1.A.2 A
A 2
Inoperative 2 (per bank)
High water level in scram
-< 40 gallons per bank A
discharge volume (4) 2 High reactor pressure i 1060 psig A
l 2
High drywell pressure (5) 1 2.5 psig A
2 Reactor low water level
> 8 inches (8)
A vacuum (gondenser low
-> 21 inches Hg vacuum A
Turbine 2
')
2 Main steamline high
( 7 X normal full power A
radiation (12) background l
valve closure (7)
- 10% valve closure A
4 Main steamline isolation 3.1/4.1-8 Amendment No. $$, gg, 101 s
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QUAD-CITIES DPR-29 TABLE 3.1-2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS STARTUP/ HOT STANDBY MODE Minimum Number of Operable or Tripped Instrument Channels per Trio System (I)
Trip Function Trio Level Setting Action (2) 1 Mode switch in shutdown A
1 Manual scram A
IRM 3
High Flux 1 120/125 of full scale A
A 3
Inoperative APRM(3) 2 High Flux (15% scram)
Specification 2.1.A.2 A
A 2
Inoperative 2
High-reactor pressure i 1060 psig A
f 2
High drywell pressure (5) 1 2.5 psig A
2
- Reactor low water level
> 8 inches (8)
A 2 (per bank)
High water level in scram
- 40 gallons per bank A
i
(
discharge volume <4) vacuum (gondenser low
- 21 inches Hg vacuum A
l 2
Turbine
/)
2 Main steamline high
< 7 X normal full power A
radiation (12) background 4
Main steamline isolation
- 10% valve closure A
valve closure (7) l l
Amendment No. 00* 00s 3.1/4.1-9 101
QUAD-CITIES DPR-29 TABLE 3.1-3 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS RUN MODE Minimum Number of Operable or Tripped Instrument Channels per Trio System (l)
Trio Function Trio Level Setting Action (2) 1 Mode switch in shutdown A
1 Manual scram A
APRM(3) 2 High Flux (flow biased)
Specification 2.1.A.1 A or B 2
Inoperative A or B 2
Downscale (11)
> 3/125 of full scale A or B 2
High-reactor pressure 1 1060 psig~
A 2
High drywell pressure 1 A.5 psig A
2 Reactor low water level
> 8 inches (8)
A 2 (per bank)
High-water level in scram discharge volume 1 40 gallons per bank A
2 Turbine condenser low
> 21 inches Hg vacuum A or C vacuum 2
Main Steamline high
< 7 X normal full power A or C radiation (12) power background 4
Main steamline isolation
< 10% valve closure A or C valve closure (6)
> 40% turbine /
A or C 2
Turbine cgntrol valve fast Toad mismatch (generator iO) closure (V)
Turbine sto i 10% valve closure A or C closure (9)p valve 2
1 2
Turbine EHC control fluid
~>90bpsig A or C low pressure (9)
J Amendment No. 00' N '
3.1/4.1-10 101
QUAD-CITIES OPR-29 TABLE 3.2-1 INSTRUMENTAT!0tl THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS Minimum Number of Operable or Tripped Instrume Channels Instruments Trio Level Settino Actionil.I 4
Reactor low water (5)
>144 inches above top of A
active fuel" 4
Reactor low low water 184 inches above top of A
active fuel
- High drywell pressureIII 12.5 psig I31 A
4 16 High flow main steamline(5]
11407 of rated steam flow B 0 F B
16 High temperature matn 1200 steamline tunnel Highradiationmpgg 17 x normal rated power B
4 steamline tunnell J background 4
tow matn steam pressureI4l 1825 pstg B
of rated steam C
4 High flow RCIC steam 1tne 1300(yI flow 0
16 RCIC turbine area high 1200 F C
temperature 4
High flow HPCI steamline 1300g78gf rated steam 0
flow 0 F 0
16 HPCI area high temperature 1200 Notes j
1.
Whenever primary containment integrity is required, there shall be two operable or tripped systems for each function except for low pressure main steam 1tne which only need be available in the Run position.
2.
Action, if the first column cannot be met for one of the trip systems, that trip system shall be tripped.
If the first column cannot be met for both trip systems, the appropriate actions listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i B.
Initiate an orderly load reduction and have reactor in Hot Standby within 8 l
hours.
C.
Close isolation valves in RCIC system.
D.
Close isolation valves in HPCI subsystem.
3.
Need not be operable when primary containment integrity is not required.
4.
The isolation trip signal is bypassed when the mode switch is in Refuel or Startup/
Hot Shutdown.
5.
The instrumentation also isolates the control room ventilation system.
6.
This signal also automatically closes the mechanical vacuum pump discharge line 150-lation valves.
7.
Includes a time delay of 3 1 t i 10 seconds.
- Top of active fuel is defined as 360" above vessel zero for all water levels used in the LOCA analysis (see Bases 3.2).
3.2/4.2-11 Amendment No. hhs hh,101
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QUAD-CITIES DPR-29 TABLE 3.2-2 INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum Number of Operable or Tripped Instrume Channels Trin Function Trio Level settina Remarks 4
Reactor low low 184 inches (+ 4 1.
In conjunction with low-water level inches /-0 inch) reactor pressure inittates above top of core spray and LPCI.
active fuel
- 2.
In conjunction with high-drywell pressure 120-second time delay and low-pressure core cooling interlock initt-ates auto blowdown.
3.
4.
Initiates starting of diesel generators.
4[4]
High-drgg1= E3I HPCI. and SGTS.
12.5 pstg 1.
Initiat,es core spray. LPCI.
pressureL 2.
In conjunction with low low water level. 120-second time delay, and low-pressure core cooling interlock initiates auto blowdown.
3.
Initiates starting of diesel generators.
4.
Initiates isolation of control room ventilation.
2 Reactor low 300 psigip1350 psig 1.
Permissive for opening core pressure spray and LPCI admisston valves.
2.
In conjunction with low low reactor water level initiates core spray and LPCI.
Containment spray Prevents inadvertent operation of interlock containment spray during accident conditions.
2E3I 2/3 core height 12/3 core height 4[3]
containment 0.5 psigipil.5 psig high pressure 2
Timer auto 1120 seconds In conjunction with low low blowdown reactor water level, high-drywell pressure. and low-pressure core cooling interlock initiates auto bl ow-down.
4 Low-pressure 100 psigip1150 psig Defers APR actuation pending con-core cooling pump firmation of low-presure core discharge pressure cooling system operation.
f 2/ BUS [5]
Undervoltage on 3045 1 5% volts 1.
Initiates starting of diesel emergency buses generators, i
l 2.
Permissive for starting ECCS pumps.
3.
Removes' nonessential loads I
from buses l
4.
Bypasses degraded voltage timer.
i
- Top of active fuel is defined at 360" above i
vessel zero for all water levels used in the LOCA analysis 3.2/4.2-12 Amendment No. hhs ffs 101 i
l
QUAD-CITIES DPR-29 reopened.
- 2) The main steamline isolation valves (one at a time) shall be verified for closure time.
2.
In the event any isolation valve 2.
When an isolation valve listed specified in Table 3.7-1 becomes in Table 3.7-1 is inoperable, inoperable, reactor power opera-the position of at least one tion may continue provided at other valve in each line having least one valve in each line an inoperable valve shall be having an inoperable valve is in recorded daily.
the mode corresponding to the isolated condition.
l 3.
If Specifications 3.7.D.1 and 3.7.0.2 cannot be met, an orderly shutdown shall be initi-ated and the reactor shall be in 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 />.
4..
The temperature of the main steamline air pilot valves shall be less than 1700F except as specified in Specifications 3.7.D.5 and 3.7.D.6 below.
5.
From and after the date that the temperature of any main steam-line air pilot valve is found to be greater than 1700F reactor operation is permissible only during the succeeding 7 days unless the temperature of such valve is sooner reduced to less than 1700F provided the main steamline isolation valves are operable.
6.
If Specification 3.7,0.5 cannot be met, the main steamline isolation valve shall be considered inoperable and action taken in accordance with Specification 3.7.0.2.
3.7/4.7-10 Amendment No.07' 03" 101
~
QUAD-CITIES DPR-29 will be replaced with filters qualified pursuant to regulatory guide position C.3.d. of Regulatory Guide 1.52 Revision 1 (June 1976). Once per operating cycle demonstration of HEPA filter pressure drop, operability of inlet heaters at rated power, air distribution to each HEPA filter, and automatic initiation of each standby gas treatment system circuit is necessary to assure system performance capability).
Note: bases within parentheses will not be applicable until about December 31, 1976, when equipment modifications are completed to allow increased testing.
D. Primary Containment Isolation Valves Those large pipes comprising a portion of the reactor coolant system, whose failure could result in uncovering the reactor core, are supplied with auto-matic isolation valves (except those lines needed for emergency core cooling system operation or containment cooling). The closure times specified herein are acequate to prevent loss of more coolant from the circumferential rupture of any of these lines outside the containment than from a steamline rupture.
Therefore, this isolation valve closure time is sufficient to prevent un-cov; ring the core.
In order to assure that the doses that may result from a steamline break do no exceed the 10 CFR 100 guidelines, it is necessary ^that no fuel rod per-foration resulting from the accident occur prior to closure of the main steam line isolation valves. Analyses indicate that fuel rod cladding perforations would be avolded for main steam valve closure times, including instrument delay, as long as 10.5 seconds. However, for added margin, the technical specifications require a valve close time of not greater than 5 seconds.
For reactor coolant system temperature less than 2120F, the containment could not become pressurized due to a loss-of-coolant accident. The 2120F limit is based on preventing pressurization of the reactor building and rup-ture of the blowout panels. These valves are highly reliable, have low ser-vice requirement, and most are normally closed.
The initiating sensors and associated trip channels are also checked to demonstrate the capability for automatic isolation (reference SAR Section 5.2.2 and Table 5.2.4).
The test interval at once per operating cycle for automatic initiation re-suits in a failure probability of 1.1 x 10-7 that a line will not isolate.
More frequent testing for valve operability results in a more reliable sys-tem.
The containment is penetrated by a large number of small diameter instrument lines which contact the primary coolant system. A program for periodic testing and examination of the flow check valves in these lines is performed by blowing down the instrument line during a vessel hydro and observing the following conditions, which will verify that the flow check valve is operable:
l Amendment No. M '
3.7/4.7-18 101
-n e.--r--
--,n-,
QUAD-CITIES DPR-29 1.
a distinctive ' click' when the pappet valve seats, and
- 2. an instrumentation high flow that quickly reduces to a slight trickle.
References I.
Quad-Cities Special Report Number 4.
2.
R.E. Adams and W. E. Browning Jr. ORNL 3726
- lodine Vapor Adsorption Studies for the NS ' Savannah
- Pr6 ject. February 1965.
3.7/4.7-19 Amendment No. 35,101
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UNITED STATES
,y g
NUCLEAR REGULATORY COMMISSION c
WASHINGTON, D. C. 20555
\\...../
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS ARTT ELECTRTC COMPANY DOCKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No.98 License No. DPP-30 1.
The Nuclear Pegulatory Comission (the Commissioni has found that:
A.
The application for amendment by Commonwealth Edison Company (the licenseel dated November 27, 1984 as supplemented July 22, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended I he Act) and the Commission's rules t
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 reaulations; 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 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:
~
- z... _
b o B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, 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 h
't Q4 Rajender Auluck, Acting Director BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 20, 1987 l
l t
l l
l l
l
s.
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the page 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.
t Remove Insert l
3.1/4.1-8 3.1/4.1-8 3.1/4.1-9 3.1/4.1-9 3.1/4.1-10 3.1/a.1-10 3.2/4.2-11 3.2/4.2-11 3.2/4.2-12 3.2/4.?-1?
3.7/4.7-10 3.7/3.7-10 3.7/4.7-18 3.7/4.7-18 1
3.7/4.7-19 3.7/4.7-19 l
l
\\
l
'I.
QUAO-CITIES 5
OPR-30 TASLE 3.1-1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS REFUEL MODE Minimum Number of Operable or Tripped Instrument Channels per Trin System (I)
Trin Function Trin Level settina Action (2) 1 Mode $ witch in shutdown A
1 Manual scram A
IRM 3
High flux i 120/125 of full scale A
3 Inoperative APRM(3) 2 High flux (15% scram)
Specification 2.1.A.2 A
2 Inoperative A
2 (per bank)
High water level in scram 1 40 gallons per bank A
discharge volume ("I 2
High-reactor pressure i 1060 psig A
2 High-drywell pressure (5) i 2.5 psig A
2 Reactor low water level 1 8 inches (8)
A 2
Turbine condenser low 1 21 inches Hg vacuum A
vacuum (7I l
l 2
Main steamline high i 7 X normal full power A
radiation (III background 4
Main steamline isolation i 10% valve closure A
valve closure (7)
I t
3.1/4.1-8 Apenenent No. W 8 M' 98
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[.
- QUAO-CITIES l.,,
OPR-30 s
l.
TABLE 3.1-2 REACTOR PROTECT 10N SYSTEM ($ CRAM) INSTRUMENTATION REQUIREMENTS STARTUP/ HOT STANDBY MODE Minimum Number of Operable or Tripped Instrument Channels per Trio Svitan(I)
Trio Function Trio Level Settina Action (2)
- l 1
Mode Switch in shutdown A
1 Manual scram A
IRM 3
High flux i 120/125 of full scale A
A 3
Inoperative APRM(3) 2 High flux (15% scram)
Specification 2.1.A.2 A
A 2
Inoperative 2
High-reactor pressure i 1060 psig A
2 High-drywell pressure (5) i 2.5 psig A
2 Reactor low water level 1 8 inches (8)
A 2 (per bank)
High water level in scram i 40 gallons per bank A
discharge volumeI4) 2 Turbine condenser low 121 inches Hg vacuum A
vacuum (7I 2
Main steam 11ne high i 7 X normal full power A
radiation (III background 4
Main steamline isolation i It% valve closure A
valve closure (7)
.i i
3.1/4.1-9
- 98 Amenenent No.
=
QUAO-CITIES OPR-30
=
TABLE 3.1-3 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS RUN MODE Minimum Number of Operable or Tripped Instrument Channels per Trin Svstan(I)
Trio Function Trin Laval settina Action (2)
A 1
Mode Switch in shutdown A
1 Manual scram APRMI3I 2
High flux (flow biased)
Specification 2.1.A.1 A or 8 A or 8 2
Inoperative 2
Downscale(III 1 3/125 of full scale A or 8 2
High-reactor pressure i 1060 psig A
2 High-drywell pre'ssure i 2.5 psig A
2 Reactor low water level 1 8 inches (8I A
2 (per bank)
High-water level in scram i 40 gallons per bank A
discharge volume 2
Turbine condenser low 1 21 inches Hg vacuum A or C vacuum 2
Main stemuline high i 7 X norpul full power A or C radiation (12) background 4
Main steamline isolation i 10% valve closure A or C valve closure (6) 2 Turbine control valve fast 1 40% turbine / generator A or C closure (9) load mismatch (10) 2 Turbine stop valve i 10% valve closure A or C closure (9) 2 Turbine EHC control fluid 1 900 psig A or C low pressure (93 3.1/4.1-10 B6. 98 Amenenent No.
QUAD-CITIES 4,
DPR-30 TABLE 3.2-1 INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS Minimum Number of Operable or Tripped Instrumegt, Channel 1 W Instruments Trio Level Settina ActionbId 4
Reactor low water (5]
>144 inches above top of A
active fuel' 4
Reactor low low water 184 inches above top of A
active fuel
- High drywell pressure [5]
12.5 ssig I3}
A 4
16 High flow main steamline(5) 1140% of rated steam flow 6 0 F 8
16 High temperature main 1200 steam 11ne tunnel Highradiationggg 17 x norma 1 rated power 8
4 steam 11ne tunnell J background tow main steam pressureI43 1825 pstg 4
C 4
High flow RCIC steam 11ne 1300(})ofratedstemn flow 0 F C
16 RCIC turbine area high 1200 temperature 4
High flow HPCI steamline 1300% of rated steam 0
f10w\\ll 0 F D
16 HPCI area high temperature 1200 Malta 1.
Whenever primary containnent integrity is required, there shall be two operable or tripped systems f or each function. except for low pressure main steamline which only need be available in the Run position.
2.
Action, if the first column cannot be met for one of the trip systems, that trip system shall be tripped.
If the first column cannot be met for both trip systems, the appropriate actions listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
8.
Initiate an orderly load reduction and have reactor in Hot Standby within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Close isolation valves in RCIC system.
D.
Close isolation valves in HPCI subsystem.
3.
Need not be operable when primary containment integrity is not required.
4.
The isolation trip signal is bypassed when the mode switch is in Refuel or Startup/
Hot Shutdown.
5.
The instrumentation also isolates the control room ventilation system.
6.
This signal also automatically closes the sechanical vacuum pump discharge line iso-lation valves.
7.
Includes a time delay of 3 i t i 10 seconds.
- Top of active fuel is defined as 360" above vessel zero for all water levels used in the LOCA analysis (see Bases 3.2).
3.2/4.2 11 Amendment No. 60, 83, 98 I
QUAD-CITIES OPR-30 s
TABLE 3.2-2 INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum Number of Operable or Tripped Instrume0t.
ChannelsL.L1 Trin Function Trin Level Settina Remarks 4
Reactor low low 184 inches (+ 4 1.
In conjunction with low-water level tnches/-0 inch) reactor pressure initiates above top of core spray and LPCI.
active fuel
- 2.
In conjunction with high-drywell pressure 120-second time delay and low-pressure core cooling interlock intti-ates auto blowdown.
3.
4.
Initiates starting of diesal generators.
4I41 High-dryy 1 12.5 psig 1.
Initiates core spray. LPCI.
pressureL
2.
In conjunction with low low water level. 120-second time delay, and low-pressure core cooling interlock initiates auto blowdown.
3.
Initiates starting of diesel generators.
4.
Initiates isolation of control room ventilation.
2 Reactor low 300 psigip1350 psig 1.
Permissive for opening core pressure spray and LPCI amission valves.
2.
In conjunction with low low reactor water level initiates core spray and LPCI.
Containment spray Prevents inadvertent operation of interlock containment spray during accident conditions.
4I3l 2I3 2/3 core height 12/3 core height u
contatnment 0.5 pstgipil.5 psig high pressure 2
Timer auto 1120 seconds In conjunction with low low blowdown reactor water level, high-drywell r
l pressure, and low-pressure core cooling interlock inttiates auto blow-down.
(
4 Low-pressure 100 psigipil50 psig Defers APR actuation pending con-core cooling pump firmation of low-presure core discharge pressure cooling system operation.
2/ BUS III Undervoltage on 3045 i ST. volts 1.
Initiates starting of diesel emergency buses generators.
2.
Permissive for starting ECCS f
pumps.
3.
Removes nonessential loads from buses 4.
Bypasses degraded voltage timer.
- Top of active fuel is defined at 360" above I
l vessel zero for all water levels used in the LOCA analysts 3.2/4.2-12 Amen ment No.
f>0, 71, 98
QUAD-CITIES DPR-30 reopened.
- 2) The main steamline isolation valves (one at a time) shall be verified for closure time.
2.
In the event any isolation valve 2.
When an isolation valve listed specified in Table 3.7-1 becomes in Table 3.7-1 is inoperable, inoperable, reactor power opera-the position of at least one tion may continue provided at other valve in each line having least one valve in each line an inoperable valve shall be having an inoperable valve is in recorded daily.
the mode corresponding to the isolated condition.
3.
If Specifications 3.7.D.1 and 3.7.0.2 cannot be met, an orderly shutdown shall be initi-ated and the reactor shall be in 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 />.
4.
The temperature of the main steamline air pilot valves shall be less than 1700F except as specified in Specifications 3.7.0.5 and 3.7.0.6 below.
5.
From and after the date that the temperature of any main steam-line air pilot valve is found to be greater than 1700F reactor operation is permissible only during the succeeding 7 days unless the temperature of such valve is sooner reduced to less than 1700F provided the main steamline isolation valves are operable.
6.
If Specification 3.7.0.5 cannot be met, the main steamline isolation valve shall be considered inoperable and action taken in accordance with Specification 3.7.D.2.
3.7/4.7-10 Amendment No.6In 98
QUAD-CITIES DPR-30 will be replaced with filters quallfled pursuant to regulatory guide position C.3.d. of Regulatory Guide 1.52 Revision 1 (June 1976). Once per operating cycle demonstration of HEPA filter pressure drop, operability of inlet heaters at rated power, air distribution to each HEPA filter, and automatic initiation of each standby gas treatment system circuit is necessary to assure system performance capability). Note: bases within parentheses will not be applicable until about December 31, 1976, when equipment modifications are completed to allow increased testing.
i D. Primary Containment Isolation Valves Those large pipes comprising a portion of the reactor coolant system, whose failure could result in uncovering the reactor core, are supplied with auto-matic isolation valves (except those lines needed for emergency core ccoling system operation or containment cooling). The closure times specified herein are adequate to prevent loss of more coolant from the circumferential rupture of any of these lines outside the containment than from a steamline rupture.
1 l
Therefore, this isolation valve closure time is sufficient to prevent un-covering the core.
1 In order to assure that the doses that may result from a steamline break do no exceed the 10 CFR 100 guidelines, it is necessary that no fuel rod per-foration resulting from the accident occur prior to closure of the main steam line isolation valves. Analyses indicate that fuel rod cladding perforations would be avoided for main steam valve closure times, including instrument delay, as long as 10.5 seconds.
However, for added margin, the technical specifications require a valve close time of not greater than 5 seconds.
For reactor coolant system temperature less than 2120F, the containment could not become pressurized due to a loss-of-coolant accident. The 2120F i
limit is based on preventing pressurization of the reactor building and rup-l ture of the blowout panels. These valves are highly reliable, have low ser-l vice requirement, and most are normally closed.
The initiating sensors and associated trip channels are also checked to demonstrate the capability for automatic isolation (reference SAR Section 5.2.2 and Table 5.2.4).
l The test interval at once per operating cycle for automatic initiation re-suits in a failure probability of 1.1 x 10-7 that a line will not isolate.
l More frequent testing for valve operability results in a more reliable sys-l tem.
The containment is penetrated by a large number of small diameter instrument lines which contact the primary coolant system. A program for periodic testing and examination of the flow check valves in these lines is performed t
l by blowing down the instrument line during a vessel hydro and observing the following conditions, which will verify that the flow check valve is operable:
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3.7/4.7-18 Amendment No. E 98 1
QUAD-CITIES DPR-30 1.
a distinctive ' click' when the poppet valve seats, and 2.
an instrumentation high flow that quickly reduces to a slight trickle.
References 1.
Quad. Cities Special Report Nurnber 4.
2..
R.E. Adams and W. E. Browning Jr., ORNL 3726,' Iodine Vapor Adsorption Studies for the NS ' Savannah' Propct, February 1965.
3.7/4.7-19 Amendment tio. 34, gg