ML20205T363

Proposed Changes to Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks

ML20205T363
Person / Time
Site:	Grand Gulf
Issue date:	06/05/1986
From:	MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20205T347	List: AECM-86-0176, Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl ML20205T363
References
TAC-57619, NUDOCS 8606130122
Download: ML20205T363 (11)

Text

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DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.2-1.

N 5.6 FUEL STORAGE h$

8 v's CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a. A k,ff equivalent to less than or equal to 0.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 4.3 of the FSAR.

(4.n e

b. A nominal e inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maint'ained to prevent inadvertent draining of the pool below elevation 202'5 1/4".

CAPACITY y

5.6.3 The spent fuel storage M(capaed.

is designed and shall be ::!9t !ned '!th *

t: =;; ::; =!t, limited torn: ::r th= 1270 fuel :::: 511:0.

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5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1-1.

a., 4 m.re f6 2524

• sped fuel a.wmblies 'in w sped fuel pel, b.N.m.re h doospe,i+ avi e.wmn.t.o 'in %e y emkiwd pool .

e The phpia.1 f.mW 'is 4548. The 23M 1;mM reNb The nuar of Spd fuel awmW;,i, wk.A can be siemd h% sp.4 (sel pool weed 6.crevive re r.ece en RHt Swie,.e4 coot.% ; i.e. , Gr e. 4'i m e peM in encen of c. nor M r e 4 ,e f. o g o (u r a di % .

8606130122 860605 PDR ADOCK 05000416 P PDR GRAND GULF _-UNIT __1 _.

5-6 __. _ _ _ _

_ _ _ _ Amsawayrf._ _

PLANT SYSTEMS 3/4.7.9 SPENT FUEL STORAGE POOL TEMPERATURE LIMITING CONDITION FOR OPERATION 3.7.9 The spent fuel storage pool temperature shall be maintained at less than or equal to 4608F.

i+o APPLICABILITY: Whenever irradiated fuel is in the spent fuel storage pool.

ACTION: With th; ;;;nt fuel ;ter;;; p;;l t;;p;r;tur; gr;;t;r then 100"i for 1;ngcr then 72 h;ur;, pr;por; and ;;bmit Sp;;iel R; pert pur;;;nt to Sp;;ific; "'~~

tien 5.0.2 within th; next I? days outlining th; ;;u;; cf the high t;;p;r;tur;

ndition, ;nd the plan; for r;;tering th; ;p;nt fuci ; tor;;; p;;i t;;;;r;tur; t; n;r cl f;r en!; ting plant ;;nditions.

1NSERI~

SURVEILLANCE REQUIREMENTS 4.7.9.1 The spent fuel storage pool temperature shall be verified to be less than or equal to 456*F at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. l 14 0 4.7.9.2 Start each fuel pool cooling and cleanup pump not already running at least once per 92 days and run each pump for at least 15 minutes, r

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GRAND GULF-UNIT 1 3/4 7-34 MMENoMper No.

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INSERT TO 3.7.9 ACTION:

0 ACTION: With the speng fuel storage pool temperature greater than 140 F but less than 210 F, perform the following:

a. Restore the pool temperature to less than or equal to 140 F within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 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 />, and

b. If at any time after exceeding 140 0F an extrapolated temperaturgplotindicatesthatthepooltemperaturewill exceed 210 F in less than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

J10 MISC 86060402 - 1

Attachment to NLS-84/05 RESPONSE TO NRC CONCERNS REGARDING THE SPENT FUEL P00L BULK TEMPERATURE ANALYSIS FOR THE HIGH DENSITY SPENT FUEL RACKS Concern #1: The NRC could not confirm that MP&L had correctly calculated the decay heat loads in accordance with BTP ASB 9-2, Rev. 2 Response: A. Base Offload Schedule The high density spent fuel rack thermal hydraulic analyses are based on the fuel offload schedule presented in FSAR Table 9.1-10. This schedule (assemblies offloaded per cycle) is consistent with Table 1.1 of the Licensing Report on High Density Spent Fuel Racks, submitted by MP&L on May 6, 1985 (AECM-85/0143). This offload schedule is based on a twelve month operating cycle and consists of a discharge rate of 280, 240, and 208 assemblies for the first three cycles, with an equilibrium value of 228 assemblies discharged thereafter. In fact, for the initial refueling outage, MP&L plans to discharge 264 assemblies.

MP&L is currently considering the implementation of an eighteen month operating cycle. Prior to implementation, the associated revised offload will be evaluated in accordance with 10CFR50.59.

Specifically, the required analyses will be repeated to ensure that the results presented here are bounding and that the technical specifications are not impacted.

B. Revised Offload Schedule For Comparison of Heat Loads In checking decay heat loads, the NRC assumed that all spent fuel storage locations were filled. The above discussed base offload schedule, however, will not completely fill all storage locations. MP&L has, therefore, calculated decay heat loads assuming the discharges listed in Tables 3 and 4 to match NRC analytical assumptions. Based on discussions with the NRC staff, MP&L understands that the resulting heat loads are consistent with NRC results indicating that the heat loads used in the bulk temperature analyses are correct.

J16PMI86051201 - 1

Attachment to NLS-84/05 Concern #2: The NRC required MP&L to perform a bulk pool temperature analysis assuming the failure of a spent fuel pool heat exchanger train at a time when RHR was not available to supplegentfuelpoolcoolingtodemonstratethatthelimit of 140 F was not exceeded.

Response: Analysisindicatesthatonefuelpoolheatexchangercanremovg g

11.3 million 8tu/hr from the pool with 140 F pool water and 95 F cooling water entering the heat exchanger (heat exchanger data sheets are provided in the attached Figures 1 and 2). Heat load analysis of the thirteenth refueling outage shows that the heat load 830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> after shutdown, when RHR assist is assumed to be cutoff, is 11.288 million Btu /hr. Tables 1 and 2 provide the refueling scenario and heat loads for the thirteenth projected refueling outage. Therefore, the bulk spent fuel pool temperature limit of 140 F0 would not be exceeded under the above described conditions.

The above discussed analysis indicates that heat loads associated with thirteen refueling outages are within the capability of one fuel pool heat exchanger given the scenario prescribed. As discussed with the NRC, an interim limit on spent fuel pool capacity will be conservatively limited to ten refueling outages.

Specifically, the number of spent fuel assemblies which can be discharged to the spent fuel pool will be limited to the projected number of assemblies to be discharged through the tenth refueling outage (2324 assemblies-based on discharge rates presented in Tables 1 & 2). This limit will be observed until an engineering solution has been determined which provides or substantiates heat removal capability to accommodate larger amounts of spent fuel ang still maintain bulk pool temperatures less than or equal to 140 F. The engineering solution will be defined prior to startup following the third refueling outage and any associated design or operational changes will be implemented prior to restart following the fifth refueling outage.

J16PM186051201 - 2 t

TABLE I Heatloads for the First 12 Protected Fuel Cycles on the Eve of the Thirteenth Refueling Outage Batch Shutdown No. of Fuel Heat Load / Bundle Batch Heat Load l No. Time (yrs) Bundles (Btu /hr) (Btu /hr) 1 12 280 1337.7 374556 2 11 240 1370.2 328848 3 10 208 1403.8 291990 4 9 228 1438.8 328046 5 0' 228 1476.3 336596 6 7 228 1518.6 346240 7 6 228 1572.2 358462 8 5 228 1652.9 376861 9 4 228 1801.5 410742 10 3 228 2122.0 483816 11 2 228 2896.9 660493 12 1 228 5312.4 1211227 TOTAL

• 5507877 i

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• All fuel is assumed to have 4 years of reactor operating operating time and 12 month fuel cycles.

I TABLE 2 Decay Heat loads of 228 Fuel Bundles for Shutdown Times UD to 1000 Hours Shutdown Decay Heat Load

• Time (Hours) (Btu /hr x 10-6 )

0 322.70 50 18.33 100 14.01 150 11.78 200 10.48 250 9.63 300 9.00 350 8.50 400 8.07 450 7.69 500 7.36 550 7.06 600 6.78 650 6.53 700 6.29 750 6.08 800 5.88 850 5.70 900 5.53 950 5.37 1000 5.22 l

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• All fuel is assumed to have 4 years of reactor operating time and 12 month fuel cycles.

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TABLE 3 Heat Load Analysis of the Normal Discharce Scenario Prescribed by the NRC Batch Shutdown No. of Fuel Batch Heat load

• No. Time (Years) Bundles (BTU /Hr) 1 18 252 291967 2 17 240 284808 3 16 208 252803 4 15 228 283834 5 14 228 290700 6 13 228 297768 7 12 228 304996 8 11 228 312406 9 10 228 320066 10 9 228 328046 11 8 228 336596 12 7 228 346241 13 6 228 358462 14 5 228 376861 15 4 228 410742 16 3 228 483816 17 2 228 660493 18 1 228 1211227 19 150 Hrs 228 11780000 TOTAL 4348 TOTAL 18931832 i

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• All fuel is assumed to have 4 years of reactor operating operating time and 12 month fuel cycles.

TABLE 4 Heat Load Analysis of the Abnormal Discharge Scenario Prescribed by the NRC

Batch Shutdown No. of Fuel Batch Heat Load

• No. Time (Years) Bundles (BTU /Hr) 1 16 128 155576 2 15 228 283834 3 14 228 290700 4 13 228 297768 5 12 228 304996 6 11 228 312406 7 10 228 320066 8 9 228 328046

9 8 228 336596 10 7 228 346241 11 6 228 358462 12 5 228 376861 13 4 228 410742

14 3 228 483816 15 2 228 660493 16 1 228 1211227 17 150 Hrs 800 41330000 TOTAL 4348 TOTAL 47807830 i

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• All fuel is assumed to have 4 years of reactor operating operating time and 12 month fuel cycles.

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FIGURE 1 p.,

L-A Fuel Pool Heat Exchanger Data Sheets  ;

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1 Beat Ezehanter - CoolinE - CCW. '

3 -

i 4 FLANT LOCATION Crand Gulf I & 2 DATE 12/29/75 5 SERVICE OF UNIT Fuel Fool ITEM NO. G41-BQ01 6 SIZE 26-252 TYPE CEU CONNECTED IN '

7 SURFACE PER UNIT 2087 EFF. SHELLS PER UNIT 1 SURFACE FER SHELL 2087 EFF. l 8 . PERFORMANCE OF ONE UNIT (PRIMARY) i

, 9 9 . .

SHELL SIDE TUBE SIDE 10 FLUID CIRCULATED Pool Water - Cooling Wer-Como Cooling Wtr

. 11 TOTAL FLUID ENTERING 550000.000 (11 GPM) 500000.000 (1000 GPM) 12 VAPOR 13 LIQUID l 14 STEAM 15 MON-CONDENSABLES

, 16 FLUID VAPORIZED OR CONDENSED 1

17 STEAM CONDENSED 18 LIQUID DENSITY -

61.801 62.006 19 VISCOSITY-LIQUID -

0.561 1 0.659 20 MOLECUIAR WEIGHT-VAPORS

!! SPECIFIC REAT-LIOUIDS 1.000 BTU /d '

l.000 BTU /F 22 LATINT HEAT-VAPORS BTU /f BTU /F 23 TEMPERATURE IN 125.000 'F 95.000 'F

! 24 . TEMPERATURE OUI 111.273 'F 110.100. F 2 ., !!0PERATING FRESSURE 150.000 f/So, In. 150.000 f/SO. IN.

NUMBER OF PASSES

• 1 2

• , VELOCITY l 2.738 Ft.Sec. 3.820 FT./SEC.

.8 FRESSURE DROP 9.991 #/Sc. In. 2.688 f/SO. IN.

9 FOULING RESISTANCE 0.00050 u 0.00057 l 10 THERMAL CDNDUCTIVITY 0.371 1 0.364 11 BEAT EXCHANGER - BTU /HR. 7550000.000 .

M.T.D (CORRICTED) 13.025

!12 TRANSFER RATE-SERVICE 277.746 CLEAN 395.193 13 CONSTRUCTION i 4 DESIGN PRESSURE 250.000 #/So. In. 150.000 f/SO. IN. '

5 TEST FRESSURE 375.000 f/Sc. In. 225.000 (/SO. IN.

. 6 DESIGN TEMPERAWRE 150.000 'T '

150.00 'F l.7 TUBES S$316L SA249 NO. 253 0.D. .750 BWG 18 M.W. LENGTH 21.00 PITCH .9375 TRI.

8 SNELL CS SA-1068 Seam I.D. O.D. 26 THICKNESS 0.375

;9 SNELL COVER CS SA516 (cRADE 70) FLOATING HEAD COVER

!O CRANNEL CS SA-1068 SEAM AND SA-105 CRANNEL COVER CS SA516-70

-l 1 TUBE SMEETS - STATIONARY SS316L SA-240 F14ATING

,2 ,

SAFFLES-CROSS CS SA-36 TYPE SPLIT SEG @ 10.00 THICKNESS 3/16 l ,3 BAFFLE-LONG TYPE THICKNESS 4 TU3E SUPPORTS THICINESS I5 GASEETS DOUBLE JACEETED ASBESTOS 6 CDIstECTIONS-SHELL-IN

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$ OUT S SERIES 150 f ASA

'7 CMANNEL-IN 8 OUT S SERIES 150 f ASA

'8 CDRADSION ALLOWANCE-SHELL SIDE 0.05 TUBE SIZE 0.08 6 .005 on Tube 9)CODEREOUIREMNTSSEC.III.SUBSEC.ND,C1.3 TEMA CLASS C

'dEIGHTS-EACH SHELL 9198 BUNDLE A995 FULL OF WATER 14.092

, (1TNud:

INDICATE AFTER EACH FART WHETHER STRESS RELIEVED (S.R. ) AND WHETHER (C'_ RADIOGRAFRED (Z. R.)

REMARKS:

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- ---- n-.,- _..,... . .- . - - - ~ - - - - , - - - - - . . - - - - - , - - - . ~ , . . . - , . -

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FIGURE 2 Fuel Fool Best Exchanger Data Sheets '

El neae Ezehenner - Cooling 'ESv. '\

' 2g 2

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\ PLANT LOCATION Crand Culf 1 & 2 DATE 12/29/75 1 5 SERVICE OF UNIT Puel Pool ITEM NO. G41-8001 l 6 SIZE 26-252 TYPE CEU CONNECTED IN ,

I 7 SURFACE PER UNIT'2057 E FF . SHELLS PER UNIT 1 SURFACE PER SHELL 2087 EFF. 6 3 .

PERFORMANCE OF ONE UNIT (STANDBY) -

9 e 0 SHELL SIDE t TUBE SIDE I 10 FLUTD CIRCULATED Pool Water . .

Cooling Wtr-Studby Ser. Wtr.

11' TOTAL FLUID ENTERING 550000.000 (1100 GPM) 532500.000 (1065 CPM) *

, 12 VAPOR 13 LIQUID i

, 14 STEAM l 15 NON-CONDENSABLES 16 FLUID VAPORIZED OR CONDENSED 17 STEAM CONDENSED .

18 LIQUID DENSITY I 61.801 62.068

!, 19 VISCOSITY-LIQUID 0.562 0.700 20 MOLECULAR WEIGHT-VAPORS

!! SPECIFIC HEAT-LIOUIDS 1.000 STU/f 1.000 BTU /t 12 LATENT BEAT-VAPORS BTU /f BTU /r I 23 TEMPERATURE IN 125.000 'F i 90.000 'F 24 TEMPERATURE OUT 111.252 'F 104.200 . "F i

25 OPERATING PRESSURE 150.000 f/Sq. In. 150.000 f/SQ. IN.

16 NUMBER OF PASSES 1 2

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27 VELOCITY I 2.738 Pt./Sec. 4.062 FT./SEC.

• ( PRESSURE DROP a 9.991 f/Sc. In. 3.041 f/SO. IN.

. .00050 0.00230 (d*POULINGRESISTANCE F1 THERMAL CONDUCTIVITY REAT EXCHANGER - BTU /HR.

l' O.371 7561500.000 1 0.362 M.T.D (CORRECTED) 19.380 1

32 TRANSFER RATE - SERVICE 186.953 CLEAN 392.321 i 33 CONSTRUCTION 34 _ DESIGN PRESSURE i 250.000 f/so. In. 150.000 f/SO. IN.

35 TEST PRESSURE 375.000 d/Sc. In. 225.000 f/SQ. IN.

150.000 l

, 36 DESIGN TEMPERATURE i

'F 150.00 'F 37 TUBES SS316L SA249 No. 233 0.D. .750 BWG 18 M.W. LENGTH 21.00 PITCH .9375 TRI.

38 __SRELL CS SA-106S Seam 1.D. O.D. 26 THICKNECS 0.375 39 SRELL COVER CS SA516 (CRADE 70) FLOATING READ COVER 40 CRANNEL CS SA-1068 SEAM AND SA-105 CRANNEL COVER CS SA516-70 il _TURE SREETS - STATIONARY SS316L SA-240 FI4ATING 42 SAPFLES-CROSS CS SA-36 TYPE SPLIT SEC # 10.00 TRICKNESS 3/16 43 BAFFLE-LONG TTPE THICKNESS i i4 TUBE SUPPORTS THICKNESS

' i5 GASKETS DOUSLE JACEETED ASBESTOS

. 46 CDNNECTIONS-SRELL-IN S OUT S SERIES 150 f ASA *

! .7 c?*_=rEL-IN 4 OUT S SERIES 150 f ASA *

+8 _ CORRDSION ALLOWANCE-SHELL SIDE 0.08 TUBE SIDE 0.08 & .005 on Tube i9 _CDIE REQUIREMENTS SEC. III SUB SEC. ND, C1.3 TEMA GLASS C 0 WEIGHTS-EACM SHELL 9198 SUNDLE 4995 FULL OF WATER 14.092

<'l __ NOTE : Indicate after each part whether stress relieved (S.R.) and whether Radiographed (E.R.J.

,f RESULTS This is the heat exchanger performance at the point of switch-over from i  %. primary to standby service water coolinS. Tubes will foul up to .002 l l_ af ter 1 year of service. Bowever, the best exchanger duty required j -

declines esponentially and at a faster rate than fouling evild up.

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