SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage

Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage

ML20209C282
Person / Time
Site:	Quad Cities
Issue date:	06/30/1999
From:	Dimmette J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-99-139, NUDOCS 9907090237
Download: ML20209C282 (4)

Text

i' Commonwealth 1:dbon Comlun)

, Quad Cities Generating Wion

/ , 22710 36th Asenue Nonh cordova. !!. 612 6247 to ,

reiw a u2a June 30,1999 l SVP-99-139 l

U. S. Nuclear Regulatory Commission I ATTN: Document Control Desk Washington, D C 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Clarification to Technical Specification Change Request Technical Specifications Section 3/4.6.G Leakage Detection Systems

References:

(1) Letter (SVP-99-38) from J. P. Dimmette, Jr. (Comed) to USNRC,

" Technical Specification Change Request, Technical Specifications Section 3/4.6.G, Leakage Detection Systems,"

dated March 30,1999.

(2) Teleconference between R. M. Pulsifer (USNRC) and Commonwealth Edison (Comed) Company, dated June 16, 1999.

In Reference (1) Commonwealth Edison (Comed) Company proposed a change to Technical Specifications (TS) Section 3/4.6.G, " Leakage Detection Systems," of Facility Operating Licenses DPR-29 and DPR-30. The proposed change provides an alternate methodology for quantifying Reactor Coolant System (RCS) leakage when the normal RCS leakage detection system is inoperable.  !

During a recent teleconference, Reference (2), the NRC requested the proposed wording for TS 3/4.6.G, ACTION 2, be changed to describe the specific alternate method for determining drywell floor drain sump leakage. The revised ACTION 2 and associated TS Bases changes are provided in the attachment. Comed has reviewed the proposed changes and has determined they are administrative in nature and do not affect the information supporting a finding of no significant hazards provided in i I

Reference (1).

/ !

9907090237 990630  !'

PDR ADOCK 05000254 P PDR o0I a Q[

A i'nkom conyuny

i a

• June 30,1999

. U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. W.J. Beck at (309) 654 2241, extension 3100.

Resp tfully, Mtnnl/$f -

oel P. Dimmette, Jr !  :

Site Vice President Quad Cities Nuclear Power Station ,

Attachment:

Revised Technical Specification 3/4.6.G, ACTION 2 and Associated >

Bases cc: Regional Administrator- NRC Region 111 NRC Senior Resident inspector- Quad Cities Nuclear Power Station i

i__--_ ___:-_-_- _ __-_ - _ - -

ATTACHMENT Quad Cities Nuclear Power Station Revised Technical Specification 3/4.6.G, ACTION 2 And Associated Bases ORIGINAL 3/4.6.G, ACTION 2 With the drywell floor drain sump monitoring system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> establish an alternate method of determining drywell floor drain sump flow rates, AND within 30 days restore the drywell floor drain sump monitoring system to an OPERABLE status; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

REVISED 3/4.6.G, ACTION 2:

With the drywell floor drain sump monitoring system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> establish an alternate manual method of determining drywell floor drain suinp flow rates by  ;

calculating flow rates using sump pump i run times, AND within 30 days restore the 1 drywell floor drain sump monitoring system to an OPERABLE status; otherwise, be in at ,

least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> andin COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Original Proposed Bases for TS Section 3/4.6.G:

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. Limits on leakage from the reactor coolant pressure boundary are required so that appropriate action can be taken before the integrity of the reactor coolant pressure boundary is impaired. Leakage detection systems for the reactor coolant system ,

are provided to alert the operators when leakago rates above the normal I background levels are detected and also to supply quantitative measurement of leakage rates. Leakage from the reactor coolant pressure boundary inside the drywell is detected by at least one or two independently monitored variables, such as sump level changes and drywell atmosphere radioactivity levels. The means of quantifying leakage in the drywell is the drywell floor drain sump pumps. With the drywell floor drain sump monitoring system inop~"'e an alternative method, such as measuring sump run-times for quanti, y leakage may be employed for up to 30 days under administrative controls. Primary containment atmosphere sampling for radioactivity can provide indication of changes in leakage rates.

Revised Proposed Bases for TS Section 3/4.6.G:

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. Limits on leakage from the reactor coolant pressure boundary are required so that appropriate action can be taken before the integrity of the reactor coolant pressure l boundary is impaired. Leakage detection systems for the reactor coolant system 1 are provided to alert the operators when leakage rates above the normal background levels are detected and also to supply quantitative measurement of leakage rates. Leakage from the reactor coolant pressure boundary inside the drywell is detected by at least one or two independently monitored variables, such as sump level changes and drywell atmosphere radioactivity levels. The means of quantifying leakage in the drywell is the drywell floor drain dump pumps. With the drywell floor drain sump monitoring system inoperable an alternative method )

using measured nump run-times for quantifying leakage can be employed for up l to 30 days under administrative controls. Primary containment atmosphere sampling for radioactivity can provide indication of changes in leakage rates.

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