ML20248A821

Forwards Revised TS Page B3/4.5-1 Re Licensee 980327 Submittal for Change to Licenses DPR-29 & DPR-30,App Bases Section 3/4.5.A, ECCS Operating

ML20248A821
Person / Time
Site:	Quad Cities
Issue date:	05/26/1998
From:	Pulsifer R NRC (Affiliation Not Assigned)
To:	Kingsley O COMMONWEALTH EDISON CO.
References
TAC-MA1340, TAC-MA1341, NUDOCS 9806010048
Download: ML20248A821 (6)

Text

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f May 26, 1998 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West til 1400 Opus Place, Suite 500 Downers Grove,IL 60515

SUBJECT:

TECHNICAL SPECIFICATIONS BASES CHANGE - QUAD CITIES NUCLEAR

. POWER STATION, UNITS 1 AND 2 (TAC NOS. MA1340 AND MA1341)

Dear Mr. Kingsley:

By letter dated March 27,1998, Commonwealth Edison Company (Comed) submitted a change to Facility Operating License Nos. DPR-29 and DPR-30, Appendix A - Technical Specification (TS) Bases Section 3/4.5.A, "ECCS [ Emergency Core Cooling System]- Operating." The second sentence in the seventh paragraph states, " The HPCI pump is designed to deliver greater than i ^ or equal to 5000 gpm at steam supply pressures between 1150 and 150 psig." The number 1150 was changed to 1120 to reflect the correct pressure. This change was made in the Updated Final Safety Analysis Repor1 (UFSAR) to reflect an error in a previous UFSAR update when pressure values were converted from psia to psig. It was not recognized at that time that the TS Bases need to be changed. Comed performed an evaluation pursuant to 10 CFR 50.59 and determined that an Unreviewed Safety Question does not exist. The staff has no objection to this Bases change. Enclosed, please find the revised TS page B3/4.5-1.

i Sincerely,

/s/

Robert M. Pulsifer, Project Manager Project Directorate lil-2

- Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 /

Enclosure:

TS page 3/4.5-1

[

cc w/ encl: See next page Dstnbution- Docket File . PUBLIC ..

PDill-2 r/f EAdensam, EGA1 SRichards I l CMoore RPulsifer ' OCC, 015818 ACRS, T2E26 MRing, Rlli

! ' DOCUMENT NAME: G:\CMNTSP\ QUAD \QC1340.LTR i SEE PREVIOUS CONCURRENCE

• l - To eseelve e sepy of thle i n ^ 5 " J- In sie boa: "C" = copy without enclosures *E" = Copy with enclosures "N" - No copy L OFFICE PM:PDill-2 & LA: Poll-2 R- SRXB D:PDill-2 C-NAME. RPULSIFEV# CPA%OkE TCollins* SRICHARDS 64P DATE 05/ T 2./98 05/'0 42 l98 05/14/98 05/ 9b /98 OFFICIAL RECORD COPY n;o-PDR 0048 990526 l" P

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lh6-May 26, 1998 i

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Mr. Oliver D. Kingsley, President Nuclear Generation Group 1 Commonwealth Edison Company l Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515 I

SUBJECT:

TECHNICAL SPECIFICATIONS BASES CHANGE - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA1340 AND MA1341) 1

Dear Mr. Kingsley:

By letter dated March 27,1938, Commonwealth Edison Company (Comed) submitted a change ,

to Facility Operating License Nos. DPR-29 and DPR-30, Appendix A - Technical Specification (TS) Bases Section 3/4.5.A. "ECCS [ Emergency Core Cooling System) - Operating." The second {

sentence in the seventh paragraph states, " The HPCI pump is designed to deliver greater than or equal to 5000 gpm at steam supply pressures between 1150 and 150 psig." The number j 1150 was changed to 1120 to reflect the correct pressure. This change was made in the Updated Final Safety Analysis Report (UFSAR) to reflect an error in a previous UFSAR update when pressure values were converted from psia to psig. It was not recognized at that time that tiae TS Bases need to be changed. Comed performed an evaluation pursuant to 10 CFR 50.59 and determined that an Unreviewed Safety Question does not exist.. The staff has no objection to this Bases change. Enclosed, please find the revised TS page B3/4.5-1.

Sincerely,

/s/

Robert M. Pulsifer, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation )

Docket Nos. 50-254 and 50-265 Encic sure: TS page 3/4.5-1 cc w/ encl: See next page Distribution- Docket File PUBLIC PDill-2 r/f EAdensam, EGA1 SRichards CMoore RPulsifer OGC,015818 ACRS, T2E26 MRing, Rlli 1 1

DOCUMENT NAME: G:\CMNTSP\ QUAD \QC1340.LTR SEE PREVIOUS CONCURRENCE

• l To tooelve e copy of this document,Jpeleets in the l>om: 'C' - Copy without enclosures *E' = Copy with enclosures "N" = No copy ;

OFFICE PM:PDill-2 k lA:MI-2 R- SRXB D:PDill-2 c.- {

NAME RPULSIFEW' CM% ORE TCollins* SRICHARDS 69 j 06/ % /98 DATE 05/ & 2-/98 05?'OGZ 198 05/14/98 OFFICIAL RECORD COPY 1

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& UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30506-0001

e. ,* May~26, 1998 i

Mr. Oliver D. Kingsley, President .

Nuclear Generation Group

! Commonwealth Edison Company Executive Towers West 111 l- 1400 Opus Place, Suite 500 l Downers Grove,IL 60515 iiUBJECT: TECHNICAL SPECIFICATIONS BASES CHANGE - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA1340 AND MA1341)

Dear Mr. Kingsley:

By letter dated March 27,1998, Commonwealth Edison Company (Comed) submitted a change to Facility Operating License Nos. DPR-2g and DPR-30, Appendix A - Technical Specification (TS) Bases Section 3/4.5.A. "ECCS [ Emergency Core Cooling System]- Operating." The second sentence in the seventh paragraph states, " The HPCI pump is designed to deliver greater than or equal to 5000 gpm at steam supply pressures between 1150 and 150 psig." The number

, 1150 was changed to 1120 to reflect the correct pressure. This change was made in the L

Updated Final Safety Analysis Report (UFSAR) to reflect an error in a previous UFSAR update when pressure values were converted from psia to psig. It was not recognized at that time that the TS Bases need to be changed. Comed performed an evaluation pursuant to 10 CFR 50.5g and determined that an Unreviewed Safety Question does not exist. The staff has no objection l to this Bases change. Enclosed, please find the revised TS page B3/4.5-1.

Sincerely, Robert M. Pulsifer, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265

Enclosure:

TS page 3/4.5-1 cc w/ encl: See next page -

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l

N O. Kingsley Quad Cities Nuclear Power Station .

Commonwealth Edison Company Units 1 and 2 cc:

Michael 1. Miller, Esquire Commonwealth Edison Company Sidley and Austin Site Vice President - Quad Cities One First National Plaza 22710 206th Avenue N.

Chicago, Illinois 60603 Cordova, Illinois 61242-9740 Commonwealth Edison Company Document Control Desk-Licensing Quad Cities Station Manager Commonwealth Edison Company 22710 206th Avenue N. 1400 Opus Place, Suite 400 Cordova, Illinois 61242-9740 Downers Grove, Illinois 60515 U.S. Nuclear Regulatory Commission Mr. David Helwig Quad Cities Resident inspectors Office Senior Vice President 22712 206th Avenue N. Commonwealth Edison Company Cordova, Illinois 61242 Executive Towers West lli 1400 Opus Place, Suite 900 Chairman Downers Grove, IL 60515 Rock Island County Board of Supervisors Mr. Gene H. Stanley 1504 3rd Avenue PWR's Vice President Rock Island County Office Bldg. Commonwealth Edison Company l RockIsland, Illinois 61201 Executive Towers West ll1 j 1400 Opus Place, Suite 900 lilinois Depaitment of Nuclear Safety Downers Grove,IL 60515 Office of Nuclear Facility Safety i 1035 Outer Park Drive Mr. Steve Perry Springfield, Illinois 62704 BWR's Vice President Commonwealth Edison Company Regional Administrator Executive Towers West lil U.S. NRC, Region lll 1400 Opus Place, Suite 900  ;

801 Warrenville Road Downers Grove,IL 60515 Lisle, Illinois 60532-4351 Mr. Dennis Farrar William D. Leach Regulatory Services Manager Manager- Nuclear Commonwealth Edison Company MidAmerican Energy Company Executive Towers West lll 907 Walnut Street 1400 Opus Place, Suite 500 P.O. Box 657 Downers Grove, IL 60515 Des Moines, Iowa 50303 Ms. Irene Johnson, Licensing Director Vice President - Law and Nuclear Regulatory Services Regulatory Affairs Commonwealth Edison Company MidAmerican Energy Company Executive Towers West lli One River Center Place '

1400 Opus Place, Suite 500 l 106 E. Second Street Downers Grove,IL 60515 i P.O. Box 4350 Davenport, Iowa 52808 l

.)

O. Kingsley Quad Cities Nuclear Power Plant .

Commonwealth Edison Company Units 1 and 2 Commonwealth Edison Company Reg. Assurance Supervisor- Quad Cities 22710 206th Avenue N.

Cordova, Illinois 181242-9740 Mr. Michael J. Wallace Senior Vice President Commonwealth Edison Company l Executive Towers West 111 1400 Opus Place, Suite 900 l Downers Grove,IL 60515 l

l

r EMERGENCY CORE COOLING SYSTEM B 3/4.5 I $

) , BARFR 3/4 8LA FEER Anaratinn l 3/4 sLR FEER Rhutrinwn The Core Spray (CS) system, together with the Low Pressure Coolant injection (LPCI) subsystem, is provided to assure that the core is adequately cooled following a loss-of-coolant accident (LOCA) and provides adequate core cooling capacity for all break sizes up to and including the double-ended reactor recirculation line break, and for smaller breaks following depressurization by the Automatic Depressurization System (ADS).

l The CS system is a primary source of emergency core cooling after the reactor vessel is l

1 depressurized and a source for flooding of the core in case of accidental draining.

l The surveillance requirements provide adequate assurance that the CS system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete system functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

l The Low Pressure Coolant injection (LPCI) subsystem is provided to assure that the core is I l adequately cooled following a loss-of-coolant accident. The LPCI subsystem with a minimum

- of three pumps will provide adequate core flooding for all break sizes up to and including the double-ended reactor recirculation line break, and for small breaks following depressurization by the ADS. .

The surveillance requirements provide adequate assurance that the LPCI subsystem will be l OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete system functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

The High Pressure Coolant injection (HPCI) system is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the reactor coolant system and loss of coolant which does not result in rapid depressurization of the '

reactor vessel. The HPCI system permits the reactor to be shutdown while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCI

- system continues to operate until reactor vessel pressure is below the pressure at which CS operation or LPCI subsystem ' operation maintains adequate core cooling.

The capacity of the system is selected to provide the required core cooling. The HPCI pump is l designed to deliver greater than or equal to 5000 gpm at steam supply pressures between

, 1120 and 150 psig. Suction piping for the system is provided from the condensate storage I' tank and the suppression pool. Pump suction for HPCIis normally aligned to the condensate

, - storage tank source to minimize injection of suppression pool water into the reactor vessel.

l However, if the condensate storage tank water supply is low, an automatic transfer to the suppression pool water source' ensures a water supply for continuous operation of the HPCI system.

QUAD CITIES - UNITS 1 & 2 B 3/4.5-1 ISSUED BY LETTER DATED: 05/26/98 1

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