L-91-176, Application for Amends to Licenses DPR-31 & DPR-41, Modifying Tech Spec 4.7.2 Re Component Cooling Water Sys Surveillance Requirements to Permit Verification of HX Surveillance Curves Via Tests Under Plant Conditions
| ML17348A965 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/21/1991 |
| From: | Bohlke W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17348A966 | List: |
| References | |
| L-91-176, NUDOCS 9107030301 | |
| Download: ML17348A965 (18) | |
Text
, ACCELERATED D TRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9107030301 DOC.DATE:~ 91/06/21 NOTARIZED: YES
'OCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION BOHLKE,W.H.
Florida Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
-Application for amends t'o Licenses DPR-31 6 DPR-41, modifying -Tech Spec 4.7.2 re component coolinq water sys'urveillance requirements to permit verification of HX
'urveillance curves via tests under plant conditions..
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTRl ENCL L SIZE:
TITLE: OR Submittal:
General Distribution NOTES R
D RECIPIENT ID CODE/NAME PD2-2 LA AULUCK,R INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/~FM EG FIL'E EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 1
1 1
0 1
1 1
1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS3 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
0 1'
1
~ '
D R
D NOTE TO ALL"RIDS" RECIPIENTS:
A D
D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL 16
\\ ~
P
~
1 0
0 J
~
k'g c \\
I
P.O. Box '14000, Juno Beach, FL 33408-0420 JU5g 2 1 Is9)
L-91-176 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Proposed License Amendment Com onent Coolin Water S stem Surveillances In accordance with 10 CFR 50.90, Florida Power
& Light Company (FPL) requests that Facility Operating License DPR-31 and DPR-41 be amended to modify Turkey Point Units 3
and 4
Technical Specifications.
The section to be modified is Technical'pecification 4.7.2, Component Cooling Water System Surveillance Requirements.
The purpose of this amendment is to revise the above section to permit the verification of the heat exchanger surveillance curves by performing Component Cooling Water heat exchanger performance tests under plant conditions which improve the accuracy of the test results.
FPL has determined that the proposed license amendment.
does not involve a
significant hazard pursuant to 10 CFR 50.92.
A description of the amendment request is provided in Attachment 1.
The no significant hazards determination in support of the proposed Technical Specification change is provided in Attachment 2.
Attachment 3 provides the proposed revised Technical Specification changes.
In accordance with 10 CFR 50.91(b)(1),
a copy of this proposed License Amendment is being forwarded to the State Designee for the State of Florida.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
Should there be any questions on this request, please contact us.
Very truly yours, W. H.
Boh e
Vice President Nuclear Engineering and Licensing WHB/GS 9107030301 910621 PQR ADOCK 05000250 p
L-91-176 Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Attachments cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr.
Jacob Daniel
- Nash, Florida Department of Health and Rehabilitative Services
STATE OF FLORIDA
)
) ss.
COUNTY OF PALM BEACH
)
Robert E. Grazio being first duly sworn, deposes and says:
That he is Director, Nuclear Licensing, of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert ED Gr io Subscribed and sworn to before me this
~(~ day of 1991.
NOTEDLY FU LIC, in and for t County of Palm Beach,. State of Florida Notary Public, State of Rorirfa Ny Commission Expires June 1, 1993 My COmmiSSiOn eXpireS aoadod rhru rcoy rala. losucsnce lac.
II r
I' iL
,'/, ~
ATTACHMENT 1 DESCRIPTION OF AMENDMENT REQUEST
~
~
L-91-176 Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 DESCRIPTION OF AMENDMENT RE VEST The proposed amendment revises the Turkey Point Technical Specifications to permit the verification of the heat exchanger surveillance curves by performing Component Cooling Water (CCW) heat exchanger performance tests under plant conditions which improve the accuracy of the test results.
The description of this change is provided below.
A note will be added to surveillance 4.7.2.b, stating that "Technical Specification 4.7.2.b(2) is not applicable for entry into MODE 4 or MODE 3, provided that:
1) surveillance 4.7.2.b(2) is. performed no later than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reaching a Reactor Coolant System Tgyg of 547 F, and 2)
..MODE 2 shall not be entered prior to satisfactory performance of this surveillance."
Turkey Point monitors Intake Cooling Water (ICW) temperatures and CCW heat exchanger performance to assure that adequate heat removal capability is maintained.
CCW heat exchanger performance tests are accomplished by measuring a temperature differential across each CCW heat exchanger for both ICW and CCW.
Heat exchanger fouling and allowable ICW temperatures are then calculated using the differential temperatures (delta-T) and ICW flow rates.
This process is satisfactory when the average Reactor Coolant System temperature is at least 547 F and the heat load on the heat exchanger is sufficient to produce delta-Ts of adequate magnitude.
Magnitude is significant because even at 100% power the heat load is only 10-154 of the design heat load of 60 x 10 Btu/hr per heat exchanger (assuming three CCW heat exchanger operation).
The corresponding delta-Ts are approximately 2 F for ICW and 4 F for CCW.
During mode 5 conditions (i.e.,
below 200 F) the heat load and consequent delta-T values are very small.
Under these circumstances, the plant may provide a heat load of less than 1.1 x 10 Btu/hr per CCW heat exchanger.
The ICW delta-T under this condition is approximately
.3 F.
L-91-176 Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 The magnitude of the potential errors associated with the measurement uncertainties in the instrumentation approaches the actual delta-T values at very low heat loads.
This results in calculated minimum ICW temperatures which are unreliable.
To assure CCW operability and satisfactory heat exchanger performance upon entry into mode 4, Turkey Point will clean the CCW heat exchangers prior to mode 4 operation when TS 4.7.2.b would otherwise prohibit entry into mode 4.
Heat exchanger performance curves following heat exchanger cleaning, based on historical data, have been generated.
CCW operability will be confirmed in accordance with TS 4.7.2.a by verifying that the ICW temperature is below the limits identified by these curves prior to entry into mode 4.
By performing heat exchanger performance tests prior to entry into mode 2, CCW operability and satisfactory heat exchanger performance's confirmed prior to reactor criticality.
The proposed change does not affect the initiator of any accident evaluated in the FSAR nor the mitigation of any accident.
Based on the above, there is no significant increase in the probability or consequences of an accident previously evaluated.
2 of,2
ATTACHMENT 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION
L-91-176 Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The Commission has provided standards for determining whether a
significant hazards consideration exists (10 CFR 50.92(c)).
A proposed amendment to an operating license for a facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
1 ~
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
This change does not revise any minimum equipment requirements nor any plant operating parameters.
CCW heat exchanger performance monitoring will continue to assure CCW system operability.
Prior to the performance of the heat exchanger performance test, the satisfactory performance every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of the surveillance described in Technical Specification 4.7.2.a verifies the CCW system's capability to remove the design basis heat loads.
Verification of CCW heat exchanger performance prior to entry into mode 2 ensures that sufficient.
cooling capacity is available for continued operation of safety-related equipment during accident conditions as described in,the FSAR.
Therefore, the proposed change does not affect the probability or consequences of accidents previously analyzed.
2 ~
Operation of the facility in accordance with the proposed amendment would not create the possibility of a
new or different kind of accident from any accident previously evaluated.
No new types of equipment are added by this change.
The proposed change introduces no changes in operation or new modes of operation.
The ability of the CCW system to provide the appropriate heat removal capability is maintained.
1 of 2
L-91-176 Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 3 ~
Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a
margin of safety.
CCW heat exchanger performance upon entry into mode 4 is confirmed by verifying that the ICW temperature is below the limits identified by heat exchanger performance curves based on historical post-cleaning data.
. By performing heat exchanger performance tests prior to entry into mode 2,
CCW operability and satisfactory heat exchanger performance is confirmed prior to reactor criticality.
Prior to the performance of the heat exchanger performance
- test, the satisfactory performance every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of the surveillance described in Technical Specification 4.7.2.a verifies the CCW system' capability to remove the design basis heat loads.
Based on the above, the proposed amendment does not involve a significant reduction in a margin of safety.
2 of 2
II