ML20207L751

Informs That Staff Offers No Objections to Util 990121 Change to Licenses DPR-29 & DPR-30,App a TSs Bases Sections 3/4.10.K & 3/4.10.L.Changes Clearly Identifies That RHR Scs Not Designed to Be Throttled Sufficiently to Maintain Rc

ML20207L751
Person / Time
Site:	Quad Cities
Issue date:	03/15/1999
From:	Pulsifer R NRC (Affiliation Not Assigned)
To:	Kingsley O COMMONWEALTH EDISON CO.
References
TAC-MA4595, TAC-MA4596, NUDOCS 9903180256
Download: ML20207L751 (5)

Text

_ . . . _ . _ . _ . . - . _ _ _ _ _ _ _ _ _. _ . . . _ _ _ .. _ _ _ _ _ _

March 15,1999

~ Mr. Oliver D. Kingsley, Precident Nuclear Generation Group Commonwealth Edison Company

- Executive Towers West lll 1400 Opus Place, Suite 500 - ,

. Downers Grove,IL 60515 l

SUBJECT:

TECHNICAL SPECIFICATION BASES CHANGE - QUAD CITIES NUCLEAR POWER STATION, UNITS.1 AND 2 (TAC NOS. MA4595 AND MA4596)

Dear Mr. Kingsley:

By letter dated January 21,1999, Commonwealth Edison Company (Comed, the licensee) )

submitted a change to Facility Operating License Nos. DPR-29 and DPR-30, Appar. dix A - ,

Technical Specifications (TS) Bases Sections 3/4.10.K, " Residual Heat Removal [RHR] and l Coolant Circulation - High Water Level" and 3/4.10.L, " Residual Heat Removal and Coolant i

' Circulation - Low Water Level." The licensee made administrative changes to these bases i sections to provide clarity and consistency with the RHR Shutdown Cooling system design and i with the TS footnote (e) of Section 3/4.5.A and footnote (a) of Section 3/4.5.B.  ;

This Bases change clearly identifies that the RHR Shutdown Cooling system is not designed to ,

be throttled bufficiently to maintain the reactor coolant temperature, and this system is  !

considered OPERABLE if the system can be manually aligned either remotely or locally.

These changes provide clarity to Bases sections 3/4.10.K and 3/4.10.L and consistency with the TS. The staff has no objections to this Bases change. I Sincerely, l l

ORIG. SIGNED BY I' Robert M. Pulsifer, Project Manager 9903190256 990315 ' -

PDR mst n censbg Rojed Managemed P ADOCK 05000254  ;

PDR Office of Nuclear Reactor Regulation / l Docket Nos. 50-254 and 50-265 f j

Enclosure:

Revised Bases Page I l cc w/ encl: See next page 0 l f

I l

I QlSTRIBUTION-N iiT PUBLIC PDill-2 r/f J. Zwolinski/SBl ack S. Richards C. Moore R. Pulsifer OGC,015B18  ;

G. Hill (4) . W. Beckner ACRS, T2E26 M. Ring, Rlli L. Marsh - - , _ ,_ _ _ , , _

DOCUMENT NAME: G;\PD3-2\CM\ QUAD \ BASE 4595.WPD ~~ ' ~ ~ ~~~""" "

Ta receive a copy of this document, lnd cists in the box: "C" = Copy without enclosures "E" = Copy wP.h enclosures "N" = No co)y I OFFICE PM:PDill-2 6 LA:)$lil-2 2./ SRX&Jif E D:PDill-2 C- ,

NAME LRPulsifer:sp Mut CNMRE JWEf491R SRICHARDS 54V I DATE ' 03/ 6 /99 OJ/M /99- 0 3/ 11 % wi 03/ Ik/99 i g',f % ' OFFICIAL RECORD COPY

-- --,rn v ,- ,, - -

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

SUBJECT:

TECHNICAL SPECIFICATION BASES CHANGE - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA4!,95 AND MA4596)

Dear Mr. Kingsley:

By letter dated January 21,1999, Commonwealth Edison Company (Comed, the licensee) ,

submitted a change to Facility Operating License Nos. DPR-29 and DPR-30, Appendix A- l Technical Specifications (TS) Bases Sections 3/4.10.K, " Residual Heat Removal [RHR] and Coolant Circulation - High Water Level" and 3/4.10.L " Residual Heat Removal and Coolant Circulation - Low Water Level." The licensee made administrative changes to these bases sections to provide clarity and consistency with the RHR Shutdown Cooling system design and with the TS footnote (e) of Section 3/4.5.A and footnote (a) of Section 3/4.5.B.

This Bases change cieriv identifies that the RHR Shutdown Cooling system is not designed to l be throttled and this system is considered OPERABLE if the system can be manually aligned ,

either remotely or locally.

{

These changes provide clarity to Bases Sections 3/4.10.K and 3/4.10.L and consistency with the TS. The staff has no objections to this Bases change.

Sincerely,

/

/

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:

Revised Bases Page cc w/ encl: See next page

, 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, Rlli L. Marsh DOCUMENT NAME: G:\PD3-2\C UAD\ BASE 4595.WPD Ta receive a copy of this document,ir i to Irdthe box: "C" = Copy enclosures "E" = Copy with enclosures "N" = No co.4

, OFFICE PM:PDill-2 8 LA:lilD41-2 6$Pt4 / D:PDill-2 .iN A NAME i RPulsifer:soJML- DM6QPLE LMAIRBir '~- SRICHARDS d.Ld d DATE 02/ ///99' 02/ ' l/99 Of/ /99 02/ /99 02/ / 99 OFFICIAL RECORD COPY g

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2 j NUCLEAR REGULATORY COMMISSION WASHINMON, D.c. 20066 4 001 s,*****/ March 15,1999 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West 111 1400 Opus Place, Suite 500 Downers Grove,IL 60515

SUBJECT:

TECHNICAL SPECIFICATION BASES CHANGE - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA4595 AND MA4596)

Dear Mr. Kingsley:

l By letter dated January 21,1999, Commonwealth Edison Company (Comed, the licensee) submitted a change to Facility Operating License Nos. DPR-29 and DPR-30, Appendix A -

Technical Specifications (TS) Bases Sections 3/4.10.K, " Residual Heat Removal [RHR) and Coolant Circulation - High Water Level" and 3/4.10.L, " Residual Heat Removal and Coolant Circulation - Low Watar Level." The licensee made administrative changes to these bases .

sections to provide clarity and consistency with the RHR Shutdown Cooling system design and I with the TS footnote (e) of Section 3/4.5.A and footnote (a) of Section 3/4.5.B. l This Bases change clearly identifies that the RHR Shutdown Cooling system is not designed to be throttled sufficiently to maintain the reactor coolant temperature, and this system is l considered OPERABLE if the system can be manually aligned either remotely or locally.

These changes provide clarity to Bases Sections 3/4.10.K and 3/4.10.L and consistency with the TS. The staff has no objections to this Bases change.

Sincerely, j T l 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:

Revised Bases Page cc w/ encl: See next page i

I l  !

O. Kingsley Quad Cities Nuclear Power Station -

Commonwealth Edison Company Units 1 and 2 cc:

l 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 River Center Place 106 E. Second Street U.S. Nuclear Regulatory Commission P.O. Box 4350 Quad Cities Resident inspectors Office Davenport, Iowa 52808 22712 206th Avenue N.

Cordova, Illinois 61242 Mr. David Helwig Senior Vice President 4 Chainnan Commonwealth Edison Company Rock Island County Board Executive Towers West 111 of Supervisors 1400 Opus Place, Suite 900 1504 3rd Avenue Downers Grove, Illinois 60515 Rock Island County Office Bldg.

RockIsland, Illinois 61201 Mr. Gene H. Stanley PWR Vice President Illinois Department of Nuclear Safety Commonwealth Edison Company Office of Nuclear Facility Safety Executive Towers West til 1035 Outer Park Drive 1400 Opus Place, Suite 900 Springfield, Illinois 62704 Downers Grove, Illinois 60515 j Regional Administrator Mr. Christopher Crane .

U.S. NRC, Region lli BWR Vice President l 801 Warrenville Road Commonwealth Edison Company i Lisle, Illinois 60532-4351 Executive Towers West 111 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 l

- 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 lli Cordova, Illinois 61242-9740 1400 Opus Place, Suite 500 >

Downers Grove, Illinois 60515 Ms. Pamela B. Stroebel Senior Vice President and General Counsel l Document Control Desk-Licensing Commonwealth Edison Company Commonwealth Edison Company P.O. Box 767 1400 Opus Place, Suite 400 Chicago, Illinois 60690-0767 Dowrars Grove, Illinois 60515

REFUELING OPERATIONS B 3/4.10 j BASES l

l l 1 ,

3/410.1 Sinale Control Rod Removal l

3/4.10.J Multiole Control Rod Removal These specifications ensure that maintenance or repair of control rods or control rod drives will be performnd under conditions that limihhe probability of inadvertent criticality. The requirements for simultanaous ren oval of more than one control rod are more stringent since the SHUTDOWN MARGIN specification prt.,vides for the core to remain subcritical with only one control rod fully withdrawn.

Refueling interlocks restrict the movement of control rods and the operation of the refueling equipment to reinforce operational procedures that prevent the reactor from becoming critical. These interlocks prevent the withdrawal of more than one control rod. Under these conditions, since only one control rod i can be withdrawn, the reactor core will always be shut down even with the highest worth control rod withdrawn if adequate SHUTDOWN MARGIN exists. Verification that all the other control rods are fully inserted is required to assure the SHUTDOWN MARGIN is within the limits. Verification that the five-by-five array of control rods are inserted and disarmed while the scram function for the withdrawn control rod is not availat2e is required to ensure that the possibility of criticality rem & ins precluded.

During refueling operations, no more than one control rod is permitted to be withdrawn from a core cell containing one or more fuel assemblies. When all four fuel assemblies are removed from a core cell, the control rod may be withdrawn with no restrictions. With no fuel assemblies in the core cell, the associated control rod has no reactivity control function and is not required to remain inserted. Prior to reloading fuel into the core cell, the associated control rod must be inserted to ensure that an inadvertent criticality does not occur.

3/4.10.K Residual Heat Removal and Coolant Circulation - Hiah Water Level 3/4.10.L Residual Heat Removal and Coolant Circulation - Low Water Level The requirement that at least one shutdown cooling mode loop of the residual heat removal (RHR) system be OPERABLE or that an attemate method capable of decay heat removal be demonstrated ensures that sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during REFUELING. The RHR Shutdown Cooling subsystem configuration was not designed to be throttled to sufficiently maintain constant reactor coolant temperature. Continuous or intermittent operation of one subsystem can maintain and reduce the reactor coolant temperature as required. Each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned either remotely or locally in the shutdown cooling mode.

The requirement to have two shutdown cooling mode loops of the RHR system OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating loop will not result in a complete loss of shutdown cooling capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange a large heat sink is available for core cooling. Thus, in the event of a failure of the ooersting shutdown cooling loop, adequate time is provided to initiate attemate methods capable of decay heat removal or emergency procedures to cool the core.

QUAD CITIES - UNITS 1 & 2 B 3/4.10-3 issued by letter dated March 15,1999

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