ML20203H918
| ML20203H918 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/18/1999 |
| From: | Pulsifer R NRC (Affiliation Not Assigned) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| TAC-MA4182, TAC-MA4183, NUDOCS 9902230148 | |
| Download: ML20203H918 (6) | |
Text
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February 15,1999 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove, IL 60515
SUBJECT:
TECHNICAL SPECIFICATION BASES CORRECTION LETTER - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA4182 AND MA4183) i
Dear Mr. Kingsley:
By letter dated January 5,1998[9], the NRC staff addressed Bases changes to Technical Specifications (TS) Sections 3/4.2.D, " Reactor Core Isolation Cooling Actuation
-- Instrumentation" and 3/4.5.D, " Reactor Core isolation Cooling."
The revised Bases pages were inadvertently omitted. Enclosed please find revised pages B3/4.2-2 and B3/4.5-3.
Sincerely, SIGNED:
R. Palsifer Robert M. Pulsifer, Project Manager Project Directorate 111-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
TS Bases pages cc w/ encl: See next page Distnbution Docket File PUBLIC PDlli-2 r/f J. Zwolinski S. Richards -
C. Moore R. Pulsifer OGC, 015818 i
G. Hill (4)
W. Beckner ACRS, T2E26 M. Ring, Rll!
l DOCUMENT NAME: G:\\PD3-2\\CM\\ QUAD \\ CORRECT.WPD To receive a copy of this document. Indiceth the box: "C" = Copy without enclosures "E" = Copy with enclosures "N* = No copy OFFICE PM:PDill-2 6
l.AW lil-2 6
D:PDill-2 C-NAME
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February 18, 1999 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
TECHNICAL SPECIFICATION BASES CORRECTION LETTER - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA4182 AND MA4183)
Dear Mr. Kingsley:
By letter dated January 5,1998[9), the NRC staff addressed Bases changes to Technical Specifications (TS) Sections 3/4.2.D, " Reactor Core Isolation Cooling Actuation Instrumentation" and 3/4.5.D " Reactor Core Isolntion Cooling."
The revised Bases pages were inadvertently omitted. Enclosed please find revised pages 83/4.2-2 and B3/4.5-3.
Sincerely, SIGNED:
R. Palsife'r Robert M. Pulsifer, Project Manager Project Directorate 111-2 Division of Licensing Project Management i
Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 i
Enclosure:
TS Bases pages cc w/ encl: See next page l
Distribution:
Docket File PUBLIC PDill-2 r/f J. Zwolinski S. Richards C. Moore R. Pulsifer OGC,015B18 G. Hill (4)
W. Beckner ACRS, T2E26 M. Ring, Rill DOCUMENT NAME: G:\\PD3-2\\CM\\ QUAD \\ CORRECT.WPD Ta receive e copy of this document, Indicat4 the box: "C" = Copy without enclosures *E" = Copy with enclosures *N' = No copy OFFICE PM:PDill-2 6
AW 111-2 6
D:PDill-2 C-NAME
/RPULSIFER:spXA ClyIDQRE SRICHARDS W
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g February 18, 1999 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
TECHNICAL SPECIFICATION BASES CORRECTION LETTER - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA4182 AND MA4183)
Dear Mr. Kingsley:
By letter dated January 5,1998[9], the NRC staff addressed Bases changes to Technical Specifications (TS) Sections 3/4.2.D, " Reactor Core Isolation Cooling Actuation Instrumentation" and 3/4.5.0, " Reactor Core Isolation Cooling."
The revised Bases pages were inadvertently omitted. Enclosed please find revised pages B3/4.2-2 and B3/4.5-3.
Sincerely, p
/
Pobert M. Pulsifer, koject Manager Project Directorate ill-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
TS Bases pages cc w/enci: See next page
i d
O. Kingsley Quad Cities Nuclear Power Station.
l Commonwealth Edison Company Units 1 and 2 cc:
Commonwealth Edison Company.
Vice President - Law and Quad Cities Station Manager Regulatory Affairs 22710 206th Avenue North MidAmerican Energy Company Cordova, Illinois 61242-9740 One R!ver Center Place 106 E. Second Street l
U.S. Nuclear Regulatory Commission P.0, Box 4350 Quad Cities Resident inspectors Office Davenport, Iowa 52808
. 22717. 206th Avenue N.
[
Cordova, Illinois 61242 Mr. David Helwig Senior Vice President Chairman Commonwealth Edison Company Rock Island County Board Executive Towers West lli of Supervisors 1400 Opus Place, Suite 900
)
j 1504 3rd Avenue Downers Grove, Illinois 60515 Rock Island County Office Bldg.
RockIsland, Illinois 61201 Mr. Gene H. Stanley PWR Vice President l
Illinois Department of Nuclear Safety Commonwealth Edison Company Office of Nuclear Facility Safety Executive Towers West lli 1035 Outer Park Drive 1400 Opus Place, Suite 900 Springfield, Illinois 62704 Downers Grove, Illinois 60515 Regional Administrator Mr. Christopher Crane U.S. NRC, Region ll1 BWR Vice President 801 Warrenville Road Commonwealth Edison Company Lisle, Illinois 60532-4351 Executive Towers West til 1400 Opus Place, Suite 900 William D. Leach Downers Grove, Illinois 60515 Manager - Nuclear MidAmerican Energy Company Commonwealth Edison Company 907 Walnut Street Site Vice President - Quad Cities P.O. Box 657 22710 206th Avenue North Des Moines, Iowa 50303 Cordova, Illinois 61242-9740 Mr. R. M. Krich Commonwealth Edison Company Vice President - Regulatory Services Reg. Affairs Manager-Quad Cities Commonwealth Edison Company 22710 206th Avenue N.
Executive Towers West 111 Cordova, Illinois 61242-9740 l
1400 Opus Place, Suite 500 l
Downers Grove, Illinois 60515 Ms. Pamela B. Stroebel Senior Vice President and General Counsel Document Control Desk-Licensing Commonwealth Edison Company j
Commonwealth Edison Company P.O. Box 767 j
1400 Opus Place, Suite 400 Chicago, li;inois 60690-0767 i
Downers Grove, Illinois 60515 i
1 0
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INSTRUMENTATION B 3/4.2 o
BASES 3/4.2.B Emeroency Cqre Co6na Svstem Actuation Instrumentation The emergency core cooling system (ECCS) instrumentation generates signals to automatically actuate those cafety systems which provide adequate core cooling in the event of a design basis transient or accident. The instrumentation which actuates the ECCS is generally arranged in a one-out of-two taken twice logic circuit. The logic circuit is composed of four CHANNEL (s) and each CHANNEL contains the logic from the functional unit sensor up to and including all relays which actuate upon a signal from that sensor. For core spray and low pressure coolant injection, the divisionally powered actuation logic is duplicated and the redundant components are powered from the other division's power supply. The single-failure criterion is met through provisions for j
redundant core cooling functions, e.g., sprays and automatic blowdown and high pressure coolant injection. Although the instruments are listed by system, in some cases the same instrument is used to send the actuation signal to more than one system at the same time.
For effective emergency core cooling during small pipe breaks, the high pressure coolant injection (HPCI) system must function since reactor pressure does not decrease rapidly enough to allow either core spray or the low pressure coolant injection (LPCI) system to operate in time. The automatic pressure relief function is provided as a backup to HPCl, in the event HPCI does not operate. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation. The trip settings given in the specification are adequate to assure the above criteria are met. The specification preserves the effectiveness of the system during periods of maintenance, testing or calibration and also minimizes the risk of inadvertent operation, i.e., only one instrument CHANNEL out-of service.
3/4.2.C ATWS - RPT Instrumentation The anticipated transient without scram (ATWS) recirculation pump trip (RPT) provides a means of limiting the consequences of the unlikely occurrence of a failure to scram concurrent with the associated anticipated transient.19e response of this plant to this postulated event f alls within the bounds of study events in General Electric Company Topical Report NEDO-10349, dated March 1971 and NEDO24222, dated December 1979. Tripping the recirculation pumps adds negative reactivity by increasing steam voiding in the core area as core flow decreases.
3/4.2.D Reactor Core isolation Coolina Actuation Instrumentation The reactor core isolation cooling system provides makeup water to the core in the event of a postulated isolation of the reactor from the main condenser with a loss of feedwater. The system automatically initiates upon receipt of a reactor vessel low-low water level signal utilizing level indicating switches in a one-out-of-two taken twice logic scheme. The system may also be manually started.
QUAD CITIES - UNITS 1 & 2 B 3/4.2-2
EMERGENCY CORE COOLING SYSTEM B 3/4.5
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BASES 3/4.5.C Suooression Chamber The suppression chamber is required to be OPERABLE as part of the ECCS to ensure that a sufficient supply of water is available to the HPCI and CS systems and the LPCI subsystem in the event of a LOCA. This limit on suppression chamber minimum water volume ensures that sufficient water is available to permit recirculation cooling flow to the core. The OPERABILITY of the suppression chamber in OPERATIONAL MODE (s) 1,' 2 or 3 is also required by Specification 3.7.K.
Repair work might require making the suppression chamber inoperable. This specification will
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4 permit those repairs to be made and concurrently provide assurance that the irradiated fuel has an adequate cooling water supply when the suppression chamber must be made inoperable, including draining, in OPERATIONAL MODE (s) 4 or 5.
In OPERATIONAL MODE (s) 4 and 5 the suppression chamber minimum required water volume is reduced because the reactor coolant is maintained at or below 212*F. Since pressure suppression is not required below 212*F, the minimum water volume is based on net positive suction head (NPSH), recirculation volume and vortex prevention plus a safety margin for conservatism. With 4
the suppression chamber water level less than the required limit, all ECCS subsystems are inoperable unless they are aligned to an OPERABLE condensate storage tank. When the suppression chamber level is less than 8.5 feet, the CS system or the LPCI subsystem is considered OPERABLE only if it can take suction from the condensate storage tank, and the condensate storage tank water level is sufficient to provide the required NPSH for the CS or LPCI e
pumps. Therefore, a verification that either the suppression chamber water level is greater than or equal to 8.5 feet or that CS or LPCI is aligned to take suction from the condensate storage tank and the condensate storage tank contains greater than or equal to 140,000 gallons of make-up water, i
available to the reactor pressure vessel.
3/4.5.D Reactor Core Isolation Coolina i
The Reactor Core Isolation Cooling (RCIC) system is provided to supply continuous makeup water 4
to the reactor core when the reactor is isolated from the main condenser with a loss of reactor feedwater. Under these conditions, the pumping capacity of the RCIC system is sufficient to maintain the water level above the core without any other water system in operation. If the water level in the reactor vessel decreases to the RCIC initiation level, the system automatically starts.
The system may also be manually initiated at any time. The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig even though the LPCI mode of the residual heat removal (RHR) system provides adequate core cooling up to 350 psig.
The RCIC system specifications are applicable during OPERATIONAL MODE (s) 1,2 and 3 when i
reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS source of core cooling when the reactor is pressurized.
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j QUAD CITIES - UNITS 1 & 2 B 3/4.5-3 f
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