ML13198A272
| ML13198A272 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 07/02/2013 |
| From: | Heacock D Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 13-228A | |
| Download: ML13198A272 (35) | |
Text
FDomi nioNi Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com July 2, 2013 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT. INC.
Serial No.
NSSL/MAE Docket No.
License No.
13-228A RO 50-423 NPF-49 MILLSTONE POWER STATION UNIT 3 SUPPLEMENT TO LICENSE AMENDMENT REQUEST FOR CHANGES TO TECHNICAL SPECIFICATION 3/4.7.5. "ULTIMATE HEAT SINK" By letter dated May 3, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3).
The proposed amendment would modify Technical Specification (TS) 3/4.7.5, "Ultimate Heat Sink," to increase the current ultimate heat sink (UHS) water temperature limit from 75°F to 80°F and change the TS Action to state, "With the ultimate heat sink water temperature greater than 80 0F, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." DNC requested approval of the LAR by May 5, 2014 with implementation within 60 days of issuance.
In a letter dated June 26, 2013, the NRC provided DNC an opportunity to supplement the LAR identified above.
During a clarification call between the NRC and DNC on June 20, 2013, DNC agreed to provide the information to the NRC by July 3, 2013. provides DNC's response to the NRC's request. The associated detailed information requested by the NRC is provided in Enclosures 2 and 3.
If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.
Sincerely, David A. Heacock, President and Chief Nuclear Officer VICKI L. HULL Notary Public Commonwealth of Virginia 140542 My Commission Expires May 31. 2014 COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A.
Heacock, who is President and Chief Nuclear Officer of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 64-day of 2013.
My Commission Expires:
t
/
Notary'Public 4
m Commitments made in this letter: None
/-ý- 00 (
W2Z
Serial No. 13-228A Docket No. 50-423 Page 2 of 2
Enclosures:
- 1. Supplement to License Amendment Request for Changes to Technical Specifications 3/4.7.5, "Ultimate Heat Sink."
- 2. DNC Response for Items Al through Al0
- 3. DNC Response for Item B cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 James S. Kim Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No 13-228A Docket No. 50-423 ENCLOSURE 1 SUPPLEMENT TO LICENSE AMENDMENT REQUEST FOR CHANGES TO TECHNICAL SPECIFICATIONS 3/4.7.5, "ULTIMATE HEAT SINK" Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement, Page 1 of 2 By letter dated May 3, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3).
The proposed amendment would modify Technical Specification (TS) 3/4.7.5, "Ultimate Heat Sink," to increase the current ultimate heat sink (UHS) water temperature limit from 750F to 80°F and change the TS Action to state, "With the ultimate heat sink water temperature greater than 80°F, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."
In a letter dated June 26, 2013, the NRC provided DNC an opportunity to supplement the LAR identified above. The NRC requested; A) The following information for each safety related heat exchanger cooled by service water:
- 1)
Design heat load
- 2)
Design fouling factor
- 3)
As-tested fouling factor
- 4)
Tube plug allowance
- 5)
Actual number of plugged tubes
- 6)
Calculated heat removal capability
- 7)
Design minimum flow rate
- 8)
Actual flow rate
- 9)
Vendor supplied heat exchanger specification sheet
- 10) Description of Generic Letter 89-13 testing/cleaning program for each heat exchanger.
B) An 18 x 24 size piping and instrumentation diagram of service water system, and C) A statement as to whether or not the increase in service water temperature from 75 °F to 80 OF will result in a derating of the emergency diesel generators.
DNC Response (Items Al through A10)
The requested information for items Al through A10 identified above in support of operation at a UHS of 80°F, are provided in Enclosure 2 for the following service water cooled, safety-related, heat exchangers:
Reactor Plant Component Cooling Water Heat Exchangers (3CCP*E1A, 3CCP*E1B, 3CCP*ElC)
" Charging Pump Coolers (3CCE*E1A, 3CCE*E1B)
Safety Injection Pump Coolers (3CCI*E1A, 3CCI*E1B)
" Emergency Diesel Generator Heat Exchangers (3EGS*E1A/E2A, 3EGS*E1B/E2B)
" Control Building Chiller Heat Exchangers (3HVK*CHLIA, 3HVK*CHL1B)
ESF Air Conditioning Unit Heat Exchangers (3HVQ*ACUS1A, 3HVQ*ACUS1 B, 3HVQ*ACUS2A, 3HVQ*ACUS2B)
" MCC/Rod Control Air Conditioning Unit Heat Exchangers (3HVR*ACUIA, 3HVR*ACU 1B)
Recirculation Spray Heat Exchangers (3RSS*E1A, 3RSS*E1B, 3RSS*EIC, 3RSS*E1 D)
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement, Page 2 of 2 Physical plant changes have been implemented following the UHS license amendment submittal to correct HVR booster pump (flow) performance deficiencies identified in the submittal (LAR Commitment 13). The corrective actions entailed a change to a flow restricting orifice size in the Service Water to HVR piping subsystem. This change corrected the HVR booster pump flow deficiency and also resulted in small changes to the delivered flow calculated to some of the other heat exchangers in the SW system. Any information provided in this response which is different from the values provided in the UHS license amendment submittal dated May, 3, 2013, are flagged to indicate the value which has been updated to address the recent restricting orifice change. Note that the tabulation of actual flows in the May 3 submittal only identifies the lower of the two trains' flow. In this submittal, both trains' flowrate are identified. These are not flagged as changes.
DNC Response (Item B)
A 17 x 22 size piping and instrumentation diagram of the MPS3 service water system is provided in Enclosure 3 as Drawing No. 25212-26933.
DNC Response (Item C)
The increase in service water temperature from 75°F to 80°F does not require derating of the MPS3 emergency diesel generators.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement ENCLOSURE 2 DNC Response for Items Al through A10 Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 1 of 18 Reactor Plant Component Cooling Water Heat Exchangers Item 3CCP*EIA 3CCP*EIB 3CCP*EIC Al) Design heat load 117.8 E+6 Btu/hr 117.8 E+6 Btu/hr 117.8 E+6 Btu/hr A2) Design fouling factor 0.001609 0.001609 0.001609 A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 10% (114 of 1148 Tubes) 10% (114 of 1148 Tubes) 10% (114 of 1148 Tubes)
A5) Actual number of plugged tubes 63 79 88 A6) Calculated heat removal capability See Attachment 1 See Attachment 1 See Attachment 1 LOP(') - 3634 gpm LOP - 3634 gpm A7) Design minimum flow rate SIS(2) - 2139 gpm SIS - 2139 gpm SGCS - 7388 gpm SGCS(3) - 7388 gpm SGCS - 7388 gpm LOP - 763714) gpm LOP - 7661 (4 gpm A8) Actual flow rate SIS - 63784 gpm SIS - 6207(4)gpm SGCS - 7412 gpm SGCS - 76231 gpm SGCS - 764614) gpm A9) Vendor supplied specification sheet See Figure 1 See Figure 1 See Figure 1 A10) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) LOP: Loss of Power.
(2) SIS: Safety Injection Signal.
(3) SGCS: Safety Grade Cold Shutdown.
(4) Updated value.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 2 of 18 Figure I d C c
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Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 3 of 18 Charging Pump Coolers Item 3CCE*EIA.
3CCE*EIB Al) Design heat load 81,100 Btu/hr 81,100 Btu/hr A2) Design fouling factor*
0.00654 hr-ft2-°F/Btu 0.00654 hr-ft2-OF/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 0%, Total Number of Tubes 1 0%, Total Number of Tubes 1 A5) Actual number of plugged tubes N/A N/A A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate 31.2 gpm 31.2 gpm A8) Actual flow rate 40.8 gpm 44.2 gpm A9) Vendor supplied specification sheet N/A(1)
N/A(1)
Al 0) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) Heat exchanger was specially manufactured on site.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 4 of 18 Safety Injection Pump Coolers Item 3CCI*EIA 3CCI*E1 B Al) Design heat load 27,850 Btu/hr 27,850 Btu/hr A2) Design fouling factor-0.00256 hr-ft2-OF/Btu 0.00256 hr-ft2-OF/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 0%, Total Number of Tubes 1 0%, Total Number of Tubes 1 A5) Actual number of plugged tubes N/A N/A A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate 19.62(2) gpm 19.62(2) gpm A8) Actual flow rate 22.7 gpm 27.2 gpm A9) Vendor supplied specification sheet N/A(1)
N/A(1)
Al 0) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) Heat exchanger was specially manufactured on site.
(2) Updated value.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 5 of 18 Emergency Diesel Generator Heat Exchangers Design Parameter 3EGS*EIAIEIB 3EGS*E2A/E2B Al) Design heat load 4,210,000(") Btu/hr 8,445,000 Btu/hr A2) Design fouling factor-0.000959 hr-ft2-°F/Btu 0.000959 hr-ft2-OF/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 5.0 % (16 Tubes) 5.0 % (16 Tubes)
A5) Actual number of plugged tubes 0 Tubes 0 Tubes A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate 1444 gpm 1444 gpm A8) Actual flow rate 1738 gpm 1714 gpm A9) Vendor supplied specification sheet See Figure 2 (a)
See Figure 2 (b)
Al 0) Description of Generic Letter 89-13 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) This is the required heat load for the intercooler heat exchanger (3EGS*EIA/EI B).. Since the jacket water cooler (3EGS*E2AIE2B) is more limiting, and the heat exchangers are in series, at the jacket water cooler required flow, the intercooler heat load is 4,725,000 Btu/hr. This design minimum flow rate is based on the jacket water cooler..
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 6 of 18 Figure 2 (a)
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ANALYSIS.
25212-39241 SH. 69
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 7 of 18 Figure 2 (b)
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Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 8 of 18 Control Building Chiller Heat Exchangers Item 3HVK*CHLIA 3HVK*CHLIB Al) Design heat load 2,800,000 Btu/hr 2,800,000 Btu/hr A2) Design fouling factor-0.00461291 hr-ft2-OF/Btu 0.00461291 hr-ft2-OF/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 15.0% of 240 Tubes 15.0% of 240 Tubes A5) Actual number of plugged tubes 22 Tubes 18 Tubes A6) Calculated heat removal capability-See Attachment 1 See Attachment 1 A7) Design minimum flow rate 303 gpm 303 gpm A8) Actual flow rate 315 gpm 329 gpm A9) Vendor supplied specification sheet See Figure 3 See Figure 3 Al0) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
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Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 10 of 18 i
ESF Air Conditioning Unit Heat Exchangers Item 3HVQ*ACUSIA 3HVQ*ACUSI B Al) Design heat load 360,600 Btu/hr 360,600 Btu/hr A2) Design fouling factor*
0.00244395 hr-ft2-OF/Btu 0.00244395 hr-ft2-°F/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 10.0% of 106 Tubes 10.0% of 106 Tubes A5) Actual number of plugged tubes 0 Tubes 2 Tubes A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate 25.0 gpm 25.0 gpm A8) Actual flow rate 29.6 gpm 25.2 gpm A9) Vendor supplied specification sheet See Figure 4 See Figure 4 Al0) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 11 of 18 Figure 4 Rev.
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NONCONDENSABLES n/HR.
FLUID*,.'..,"
,ONDENSED v,
i R
5760 STEAM CONDENSED
"'HR.
GRAVITY - LIOUID j
VISCOSITY - LIOUID MOLECULAR WEIGHT - VAPORS
- 86. 5
- 86. 5 IOLECULAR WEIGHT - NON - CONDENSIBLES SPECIFIC HEAT BTU/"'F THER/, ALCOmCUCT.;VITy.
LATENT HEAT I
TEMPERAUREC(COND.
105 F.)
-F 1
95
{
80 1
95.7 INLET PRESSURE PSIG 215 o10 NUMBER OF PASSES PER SHELL
-ONE Two "
VELOCITY FT.._SEC....
3.0 PRESSURE DROP - ALLOA.CALC PSI 4__
4_
6 FOULING RESISTANCE
,3TU*HR SO.FT.,F CONSTRUCTION OF ONE SHELL SKETCH ?BUNDLE NOZZLE OREPIT.
____________PRESSURE_____
SHELL SIDE TUBE SIDE DESIGN/TEST PRESSURE PSIG 30a 450 150i 225 ORIENTATION PERI'D.RAWING DESIGN TEMPERATURE
-F
.200 200 NU-C-1056-1 CORROSION ALLOWANCE IN
.063"
.003" CONNCTIONSN 1-*'/.4'1 VP 21-1509R.F.
SIZE&
OU1-1/4"NP 2"-150#R.F.
RATING I
TUBE NO.
106 oD 5/8" IN.
THK(MIN *.QA
.049 IN.
LENGTH 11 -- 0" TUBE MATERIAL fitfSNMLS)
SB-359 90/10 CUNi PITCH 25/32" IN,
- 30 10 SHELL SA-106 Gr..B ID.
D. 10" IN.
SHELL.COVER (INTEG.)
(REMOV I MSMI12M BONNET SB-402 90/10 Cu-Ni **
CHANNEL '%VER TUBESHEET-STATIONARY SB-171 90/10 Cu-Ni TUSESHEET - FLOATING FLOATING HEAD COVER IMPINGEMENT PROTECTION SA-240 TP 304 BAFFLES-CROSS SA-285 Gr.C TYPE Segmental
%CUT 20%
SPACING.
4" (4)
BAFFLES, LONG SA-285 Gr.
C Subcooling WeirTUBESUP"ORTS SA-285 Gr. C TUBE SHEET JOINTS SHELL Welded CHANNEL Flanged TUBES Expanded GASKETS - SHELL None FLOATING HEAD CHANNEL Neoprene CODE REOUIREMENTS ASME Section III Class 3 (Tubeside)
TEMA CLASS R
WEIGHTSiSHELL - SHIPPING 1200 FLOODED 1660 LBS.
REMARKS'
- ASME Section VTTT D,.7 (Shellside) 1974 Edition S74 t..'-
- 'Flanges are SB-402 90/10 Cu-Ni Plate Type A.
"5I
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 12 of 18 ESF Air Conditioning Unit Heat Exchangers Item 3HVQ*ACUS2A 3HVQ*ACUS2B Al) Design heat load 396,400 Btu/hr 396,400 Btu/hr A2) Design fouling factor-0.00211819 hr-ft2-OF/Btu 0.00211819 hr-ft2-OF/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 10.0% of 106 Tubes 10.0% of 106 Tubes A5) Actual number of plugged tubes 0 Tubes 0 Tubes A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate 33.2 gpm 33.2 gpm A8) Actual flow rate 35.7 gpm 35.5 gpm A9) Vendor supplied specification sheet See Figure 4 See Figure 4 A10) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 13 of 18 MCC/Rod Control Air Conditioning Unit Heat Exchangers Item 3HVR*ACUIA 3HVR*ACUIB Al) Design heat load 560,700 Btu/hr (DBA(1))
560,700 Btu/hr (DBA) 507,000 Btu/hr (BTP CMEB 9.5-1(2))
507,000 Btu/hr (BTP CMEB 9.5-1(2))
A2) Design fouling factor 0.016642 hr-ft2-OF/Btu 0.016642 hr-ft2-°F/Btu A3) As-tested fouling factor See Item 5 of Attachment 2 See Item 5 of Attachment 2 A4) Tube plug allowance 5.5 % (3 of 54 Tubes per Row - 4 5.5 % (3 of 54 Tubes per Row - 4 Rows)
Rows)
A5) Actual number of plugged tubes 2
2 A6) Calculated heat removal capability See Attachment 1 See Attachment 1 A7) Design minimum flow rate BTP CMEB 9.5 75 gpm BTP CMEB 9.5 75 gpm All Others - 122 gpm All Others - 122 gpm A8) Actual flow rate BTP CMEB 9.5 96" gpm BTP CMEB 9.5 i00(3) gpm All Others - 140(3) gpm All Others - 134) Urnpm A9) Vendor supplied specification sheet See Figure 5 See Figure 5 Al 0) Description of Generic Letter 89-13 testing/cleaning See Attachment 2 See Attachment 2 program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) DBA: Design Basis Accident.
(2) BTP CMEB 9.5-1: Fire protection guidelines, Branch Technical Position CMEB 9.5-1. These are conditions during a postulated fire that disables the associated booster pump.
(3) Updated value.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 14 of 18 Figure 5 - Page 1 Atachment No. 1 NNECO Cadculation No. 90-069-011311W, Rev. 1 SELECTION OF AEROFIN AIR-COOLING COILS Job Name :
MILLSTONE Quote Number H
NO TUBES PLUGGED System Id Date :
10/18/94 Coil Information Coil Type z R
Fin Material : Copper Coil Circuit : FULL Tube Size a 5/80 x 0.049" wall OPTIf Rev H 06/01/94 Number Tube In Face Face 2
27 Casing Height 43.0" Nominal Tube Length 96.0" Fine/
Inch 8.50 Rowe 4
Dry Wt lbs 1079 System Face Area t Performance Air Side Elevation Standard Pressure z Standard Airflow ;
Standard Face Velocity':
Entering Dry Bulb Temperature Entering Wet Bulb Temperature Leaving Dry Bulb Temperature Leaving Wet Bulb Temperature Sensible Heat Load Total Heat Load 3 Outside Surface Fouling i Fluid Side Fluid I
Entering Temperature i
Leaving Temperature s
Flow Rate :
Tube Velocity Inside Surface Fouling t
Losses Air Friction Fluid Pressure Drop 49.51 sq ft 0
29.92 26000 525 2
120.0 91.0 100.7 2
87.3 568.0 568.0 0,00000 ft in Hg cfm fpm FP FF HBH hr-ft^2-F/Btu SEA WATER 75.0 F 96.4 F 55.0 gpm 1.5 fpe 0.00200 hr-ftA2-F/Btu 0.30 in vg vg Notes Non standard tube face; special pricing/lead time required.
Coil weight shown is for one coil.
Fluid propertiesi Ea-1.025 VI= 0. 850 CP= 0. 940 TKx 0.340.
0
/~~Cf 9~-,,
Proto-Power Calc: 99-114
Attachment:
A Rev: A Page 2 of 4
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 15 of 18 Figure 5 - Page 2 PROTO-POWER CORPORATION 591 POQUONNOCK ROAD GROTON, CT 06340 (860) 446-9725 TELEPHONE MEMORANDUM DATE OF CALL:
9/16/99 TIME OF CALL: -11:00 AM PERSON CALLING:
Merid Above PERSON CALLED: Brian Elliott Proto-Power Aerofin Corp.
860-446-9725 804-528-6208
SUBJECT:
Millstone Unit 3 MCC Control Rod Area AC unit (3HVR*ACUIA/B)
COMMENTS:
Called Aerofin Corporation (Manufacturer of Subject Air Coil unit) to obtain missing physical information. Namely, The coil's Fin Thickness, Fin Height, and Longitudinal and Transverse tube pitches.
Mr. Elliott provided me with the following information.
Fin Thickness: 0.012" Fin Height: 3/8" above tube outer surface Transverse Tube Pitch: 1 25/64".
In addition, he mentioned that the tubes are arranged in an equilateral triangle configuration and that the longitudinal pitch can be derived from the geometry.
Proto-Power Cato: 99-114
Attachment:
A Rev: A Page 3 of 4
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 16 of 18 Figure 5 - Page 3 3HC'-XA13 5l
,268 Coampact Heat Exchangers Fig. IG-69 Finned c*OLL Muee, euhlace CF-9.06-3/4J. (Deta of Jonv.art)
Tube otvilde dlrmeter - 0.774 In - 19.68 x 10- m Fin pitch - 9.05 per In - 356 ipe m Fin thicdnes - 0.012 in - 0,306 x 10Wm Fin areatotal area.
0.917 Flow paage hvdydaulic A
a dhlner, 4t,-
0.01681 0.02685 5.131 x 103 8.179.10-3 C
0 E
0,0445 0.01587 0.02108 it 113.69x 110Y 4.9 46.1 0s 8.428XO 10m Free-.low areulfroetal free. a.
"est transfr area/
total volume, c,
0.455 0.572 0.688 0.537 0.572 108 86.1 61.9 135 tO1 ft2/ftl 354 279 203 443 354 fti/ml Note: Minimum free-flow area In all cases ooc4is In the spaces transverse to tihe flow, except (or ID, In which the trmlmrnli area is Itn the diagonals.
7U 00- 01//3///?3 2i Proto-Power Cab: 99-114
Attachment:
A Rev: A Page 4 of 4
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 17 of 18 Recirculation Spray Heat Exchangers Design Parameter 3RSS*E1A 3RSS*EI B 3RSS*EI C 3RSS*E1 D Al) Design heat load'1) 184,534,533 Btu/hr 184,534,533 Btu/hr 184,534,533 Btu/hr 184,534,533 Btu/hr A2) Design fouling factor (shell/tube side) 0.0010 0.0010 0.0010 0.0010 hr-ft2-_F/Btu hr-ft2_OF/Btu hrft2 -OF/Btu hr-ft2_OF/Btu See Item 5 of See Item 5 of See Item 5 of See Item 5 of A3) As-tested fouling factor A4) Tube plug allowance 69 (5%) of 1380 69 (5%) of 1380 69 (5%) of 1380 69 (5%) of 1380 A5) Actual number of plugged tubes 3
3 6
3 A6) Calculated heat removal capability See Attachment 1 See Attachment 1 See Attachment 1 See Attachment 1 A7) Design minimum flow rate 5400 gpm 5400 gpm 5400 gpm 5400 gpm A8) Actual flow rate 5493(2) gpm 5753(2) gpm 5479(2) gpm 5641(2) gpm A9) Vendor supplied specification sheet See Figure 6 See Figure 6 See Figure 6 See Figure 6 Al 0) Description of Generic Letter 89-13 See Attachment 2 See Attachment 2 See Attachment 2 See Attachment 2 testing/cleaning program
- This is the total fouling factor used in the analysis of record to determine required service water flow rate.
(1) Design heat load data comes directly from the heat exchanger vendor data sheet. Actual heat transfer values based on Loss of Coolant Accident (LOCA) conditions with 80°F service water temperature vary with time based on containment sump temperature and therefore, were not specifically documented within design bases analysis documents. These calculations were done using the NRC-approved GOTHIC methodology.
(2) Updated value.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 18 of 18 Figure 6 TECHNICAL DATA FURNISHED BY BIDDER/SELLER STONE., WEBSTER ENGINEERING CORPORATION TUBULAR HEAT EXCHANGER DATA ci(.r, Northeast Utilities Service Company PIoi... and Lo.,io.rMilltone Nuclear Power Station - Unit 3 Oat. 1 /k/76 oXAK S...I..
Coniomrnb Na c!tVS-ElA
/ C Mfr.
S'..
36 -- 432
.fr a Tap.
installotion -Marl. El
- 4.
ea,.ri..
Each Cao.i.*.t a
1 Poarallel S.
Ba 1
Sh.el. in
-VSar]
8082 S ft. per shelf 1
sl.
D,, Batt.,y 8082 sq, i. prr e0411.y PERFORMANLE OF ONE BATTERY SHELL SIDE TUBE SIDE Fluid Circlated Rpeirauv ated Wateir Seryn Watr Total Fluid Ent..ing MW 1,932,299 lb/i.
MW 3,244,278 lb/hr
'V.o.1 MW lb/h, MW Ib/ia Lquald MW
-b932*99 lb/i, Mw 3,2 4,278 1b1/1 Steam lb/h Ib/br N-oaodl.lfbl.e MW lb/h, MW lb/h'
-* Ian~t
& Vslaaa
)l it Hi Ci a it 01 Fat Ci at F
- Op. Hi. b Subble PaIn at FE F
at F.
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F&
F at F
Fluid Vop. L,. Cand.
ib/hr Ib/lia WoIntHot BTU/lb at of F
BTU/Ib of i
T.Tp. In out 201.5 F&
106.0 t
75 F.
131.88 F
Oitrotin. P,..,..00--
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n" 1751 N..0005 n1 1751 3-6
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i=
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- i.
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1-i**i-.
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00 p3,OPsi 53 Ran°ab Shell aide-Class.2, Tube_.side-..lass 3 4
.**At.5,000-gpm
.9 At.7,o-r.00O-aq.-W
-_K 50 0?
35 59 60,v.,.....
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ITH '. :,
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement ATTACHMENT 1 CALCULATED HEAT REMOVAL CAPABILITY Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Calculated Heat Removal Capability Service water cooled heat exchanger calculations (using Proto-HXTM ) use the design heat load (or an assumed heat load greater than the design) and fouling factor, the heat exchanger characteristics (geometry, tube plugging limits, materials, etc.), process side parameters, and temperature of the sea water to determine the required seawater flow rate. The service water system flow calculation (using Proto-floTM) then determines the available flow. There is no separate calculation of heat removal capability - it's presented as the same as the design heat load. The difference between the required flow and the available flow demonstrates the margin. Additionally, margin also exists in the difference between the actual number of tubes plugged and the number of tubes assumed plugged (plugging allowance) and the difference between the actual service water pump performance and the assumed degraded pump in the flow analysis. While these numbers can change over time, they are monitored to ensure that equipment is repaired or replaced before system margin is challenged.
For Plant Component Cooling Water (CCP), heat removal capability depends on the system alignment under consideration. From a safety standpoint, the most limiting system alignment is a safety grade cold shutdown (SGCS). It is limiting because it has the least amount of associated flow margin with respect to the other CCP flow alignments.
Heat removal capability is calculated as a function of various parameters. To name a few, it is a function of CCP temperature limitations, time to cold shutdown requirements, CCP flow rates, service water (SW) flow rates, and is a function of time due to decay heat removal.
SGCS which involves CCP and the residual heat removal system is analyzed using calculation specific code and is analyzed in time steps. For each time step, various parameters of interest, many of which are interdependent and must be solved simultaneously/iteratively for each time step, are calculated. Among those parameters is the CCP heat removal capability, which varies over time.
The SGCS analysis is defined as the limiting CCP heat exchanger heat transfer case because it has the highest safety-related component heat load and the lowest margin between minimum required and available SW flow. The SGCS analysis is a transient analysis that models multiple systems to simulate the plant cooldown process. The SGCS analysis uses a representative fixed CCP heat exchanger proportionality constant (UA) and a 7388-gpm SW flow rate to simulate the plant cooldown process.
The representative UA value is 3.93 x 106 (BTU/hr-*F) and this UA is determined in a supporting CCP heat exchanger heat transfer calculation. SGCS analysis cases have a peak 117.8 x 106 BTU/hr CCP heat exchanger heat removal rate and this peak occurs when the CCP heat exchanger shell side inlet temperature is 142.4 F. This heat removal rate is reported as the CCP heat exchanger "design heat load" in Enclosure 2.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement ATTACHMENT 2 DESCRIPTION OF GENERIC LETTER 89-13 TESTING/CLEANING PROGRAM Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 1 of 3 Description of Generic Letter (GL) 89-13 Testing/Cleaning Program GL 89-13 Elements Five items were required by GL 89-13. They are summarized below:
- 1) Implement and maintain an ongoing program of surveillance and control techniques to significantly reduce the incidence of flow blockage problems as a result of biofouling. This program includes:
- a. Inspect the intake structure for macrofouling due to organisms, sediment and corrosion. Remove fouling accumulations.
- b. Continuously chlorinate the service water (SW) system.
- c. Flush and flow test infrequently used cooling loops and fill stagnant loops with chlorinated water prior to layup.
- 2)
Conduct thermal performance testing of safety related heat exchangers to verify design heat transfer capability.
- 3)
Perform routine inspection and maintenance on piping and components to ensure that corrosion, erosion, protective coating failure, silting and biofouling cannot degrade the performance of safety related systems cooled by service water. This program should include:
- a. Remove excessive accumulations of biofouling agents, corrosion products and silt.
- b. Repair defective coatings and corroded service water system piping and components that could adversely affect a safety related function.
- 4)
Confirm the service water system will perform its intended function per the licensing basis for the plant.
- 5)
Confirm that maintenance practices, operating and emergency procedures and training that involve the service water system are adequate to ensure that safety related equipment cooled by the service water system will function as intended and that operators of this equipment will perform effectively.
Dominion Nuclear Connecticut Response Millstone Unit 3 complies with GL 89-13 as follows. Note that item numbers below correspond to the requirements of GL 89-13 listed above.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 2 of 3 Item 1:
- a. The intake structure is inspected annually using divers and videotape during the annual intake bay outages in the winter.
- b. The Service Water system is chlorinated by injecting hypochlorite immediately downstream of the strainer of the running SW pump.
- c. The infrequently used cooling loops in the SW system are the supply lines to the four Containment Recirculation Spray (RSS) heat exchangers which are normally maintained dry, the SW piping to the diesel heat exchangers, and the SW piping to the engineered safety feature (ESF) Air Conditioning Unit Heat Exchangers (HVQ) heat exchangers. Service Water is flushed through the RSS heat exchangers twice per year, followed by a fresh water flush and then drained. The diesel heat exchangers get chlorinated water continuously via a flow orifice which allows flow around a normally closed isolation valve and they are tested weekly at full flow for macrofouling. Service Water to the HVQ is flowed once per day for 15 minutes via the bypass outlet valve in order to maintain chlorinated water in the heat exchangers and each of these heat exchangers is subject to a weekly macrofouling surveillance. Layup of heat exchangers and stagnant piping requires components to be placed in fresh water layup if they are idle for greater than three days. Removing the salt water significantly reduces the possibility of fouling and thus additional chlorination is not needed.
Item 2:
Thermal performance testing of heat exchangers has been conducted per NRC commitments made in NU letter B17205 of May 6, 1998 (Reference 1) as modified by Northeast Utilities (NU) letter B18331 of February 28, 2001 (Reference 2). Millstone Power Station Unit 3 committed to the NRC (in letter B17205) to develop and implement a heat exchanger testing program to satisfy Item 2 of GL 89-13. This testing program required three baseline thermal performance tests and periodic retests be done on each safety related SW-cooled heat exchanger except the four RSS heat exchangers. The RSS heat exchangers are maintained dry and are flushed with fresh water after surveillances which flow salt water through the tubes. These actions prevent fouling. In 2001, attempts to test Reactor Plant Component Cooling Water (CCP) heat exchangers were discontinued due to impracticality of obtaining meaningful test data. Commitments related to CCP heat exchanger testing were cancelled by NU Letter B18331 of February 28, 2001. For the other safety related heat exchangers, baseline thermal performance tests were used to establish a cleaning frequency that ensures that microfouling will not proceed to a point that exceeds the assumptions in the heat exchanger analyses.
Subsequent testing has confirmed that this cleaning frequency remains adequate to maintain required heat transfer capability. For the CCP heat exchangers, an annual cleaning frequency was established. The cleaning frequency has subsequently been changed to twice per year to prolong heat exchanger life (silt accumulation was found to increase the rate of tube pitting).
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement Page 3 of 3 Item 3:
Inspection and maintenance of SW system components includes direct visual examination of accessible piping and heat exchangers, inspection by remote camera of piping, components and heat exchangers (as needed), cleaning and eddy current testing of heat exchangers, and ultrasonic testing to determine wall thickness of susceptible piping. The results of the inspections determine the necessary maintenance on the affected components so that the safety related function of the Service Water system is maintained.
Item 4:
The ability of the SW system to perform as licensed has been confirmed and reported in NU letter B14643 of November 5, 1993 (Reference 3). Regular maintenance of the heat exchangers, as well as control over design changes (including analyses and tests to verify the design) ensure that the system will continue to perform as licensed.
Item 5:
Maintenance practices, procedures, and training have been confirmed to adequately ensure that Service Water cooled equipment will perform as designed and that operators will operate the equipment effectively to maintain the safety related function of the system.
The thermal performance tests described in item 2 above were used to determine a rate of change of fouling factor with respect to time to determine the adequacy of the cleaning frequency. Therefore, there is no direct correlation between the tested and the design fouling factors. The tested fouling factor is extrapolated to the end of the cleaning interval to demonstrate that the fouling factor remains less than the design.
References:
- 1. M. L. Bowling to NRC, "Millstone Station, Unit No. 3, Service Water System -
Generic Letter 89-13 (TAC No. 74027), May 6, 1998.
- 2. R. P. Necci to NRC, "Millstone Nuclear Power Station, Unit No. 3, Commitment Changes Associated with Service Water System - Generic Letter 89-13 (TAC No. 74027), February 28, 2001 (ML010660034).
- 3. J. F. Opeka to NRC, "Millstone Nuclear Power Station, Unit No. 3, Service Water System-Generic Letter 89-13 (TAC No. 74027), November 5, 1993.
Serial No 13-228A MPS3 Ultimate Heat Sink Supplement ENCLOSURE 3 DNC Response for Item B Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit
THIS PAGE IS AN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:
PIPING & INSTRUMENTATION DIAGRAM SERVICE WATER WITHIN THIS PACKAGE... OR, BY SEARCHING USING THE DOCUMENT/REPORT DRAWING NO. 12179-EM-133A D-01
THIS PAGE IS AN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:
PIPING & INSTRUMENTATION DIAGRAM SERVICE WATER WITHIN THIS PACKAGE... OR, BY SEARCHING USING THE DOCUMENT/REPORT DRAWING NO. 12179-EM-133B D-02
THIS PAGE IS AN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:
PIPING & INSTRUMENTATION DIAGRAM SERVICE WATER WITHIN THIS PACKAGE... OR, BY SEARCHING USING THE DOCUMENT/REPORT DRAWING NO. 12179-EM-133C D-03
THIS PAGE IS AN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:
PIPING & INSTRUMENTATION DIAGRAM SERVICE WATER WITHIN THIS PACKAGE... OR, BY SEARCHING USING THE DOCUMENT/REPORT DRAWING NO. 12179-EM-133D D-04X