ML20029C187

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Proposed Tech Specs 3/4.9.13 Re Spent Fuel Assembly Storage & 3/4.9.14 Re New Fuel Assembly Storage
ML20029C187
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 03/18/1991
From:
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20029C186 List:
References
NUDOCS 9103260397
Download: ML20029C187 (9)
v • d • e


Text

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INDEX Q

s. y LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT Buit0 LNG PENETRAT10NE.................. ..... 3/4 9-4 3/4.9.5 COMMUN: CATIONS........................................... 3/4 9-5 3/4.9.6 R E F U E U 4G MA C H I N E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9 6 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE AREAS.................. 3/4 9-7 3/4.9.8 RES10 VAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Levei........................................ 3/4 9-8 Low Water Level.......................................... 3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..... ..... 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................. 3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE POOL ........ .................. .. 3/4 9-12 3/4.9.12 FUEL STORAGE BULL 0 LNG EMERGENCY AIR CLEAN!NG SYSTEM...... 3/4 9 13 3__/ .10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUT 00WN MARGIN.......................................... 3/4 10 1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS... 3/4 10 2 3/4.10.3 PHYSICS TESTS............................................ 3/4 10 3 3/4.10.4 REACTOR COOLANT L00PS.................................... 3/4 10 4-3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN.................... 3/4 10 5 C 3/4.10.6 REACTOR COOLANT L0"S.................................... 3/4 10-6 D ,-'

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration........................... ................ 3/4 11 1 00se..................................................... 3/4 11-2 L i q u i d R a dwa s t e T r e a tme n t Sy s t e rr.. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-3 Liquid Holdup Tanks...................................... 3/4 11-4 3/4.11.2 GASEOUS EFFLUENTS Dose Rate................................................ 3/4 11-5 Dose - Noble Gases............................... ....... 3/4 11-6 Dose - lodine-131, Iodine-133, Tritium, and Radioactive Materi al i n Particulate Form. . . . . . . . . . . . . . . . . . . . . . . . . . . . . '; /4 11-7 Gaseous Radwaste Treatment System............. ......... 3/4 11-8 o Expl os i ve Gas Mixture - Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-9 coM E8' 3/4.11.3 SOLIO RADIOACTIVE WASTES............................ .... 3/4 11-10 og 3/4.11.4 TOTAL 00SE............................................... 3/4 11-12 VO m.e 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 40 mo oca 3/4.12.1 MONITORING PROGRAM.......... .......................... 3/4 12-1 oI N ~ S/4 9.13 SffNf fuCL-d 5SEMBL Y $ R.VGC AlY 9 */l C* fIGun 3.9-l furu M5K4LY BuANuP V1-TNET.[M ENRlufMNr Q j)g $fTNr fun. A S5CP6LY 3 rb 8 tt Gl" 3g 9,j7 SEABROOK - UNIT 1 ix '

sjy.9, ty- n:w FaEu A5S O'SL Y $ TM A&[ S/4 4 -Y

e INDEX a BASES t.;g i v Y.'

SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............. B 3/4 9-2 i 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...... ..... B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and .

STORAGE P00L............................................ B 3/4 9-2

-+ 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM....... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN........................................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.... B 3/4 10-1 3/4.10.3 PHYSICS TESTS............................................. B 3/4 10 1 3/4.10.4 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN..................... B 3/4 10-1 3/4.10.6 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS................... .................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................ B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTES................................. B 3/4 11-5 3/4.11.4 TOTAL 00SE............................................... B 3/4 11 5 g

gg 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING _

3/4.12.1 MONITORING PR0 GRAM....................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS.......................................... B 3/4 12-1 .

3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM....................... B 3/4 12-2 5.0 DESICN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.............................................. 5-1 5.1. 2 LOW POPULATION Z0NE.....'.................................... 5-1 5.1. 3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.................... 5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA 00VNDARY..................... 5-3 FIGURE 5.1-2 LOW POPULATION 20NE.................................. 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION................... 5-7

5. 2 CONTAINMENT 5.2.1 CONFIGURATION............................................... 5-1 5.2.2 0ESIGN PRESSURE AND TEMPERATURE............................. 5-9 1

6-' 3/4.9.15 S PW f ue t. A $sw 64.Y S TM n G C 0 SN $~3 3/>l,9. tf New Fun A ss nMBLY SrbaAa2 y spf 9-s SEABROOK - UNIT 1 xii L - ._. _

. 1 Add the Following Technical Specification to Section 3/4.9 t

PEFUELING OPERATIONS  !

3/4.9.13 SPENT FUEL ASSEMBLY STORAGE f LIMITING CONDITION FOR OPERATION >

3.9.13 Fuel a_ssemblies stored in the spent fuel pool shall be placed in the spent fuel ,

storage racks according to the criteria shown in Figure 3.01.

6PPLICABILITY: Whenever fuel is in the spent fuel pocl.

f ACTION:

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a. With the requirements of the above specification not satisfied, suspend all other fuel I movement within the spent fuel pool and move the non-complying fuel assemblies to allowable locations in the spent fuel pool in accordance with Figure 3.91.
b. The provisions of Specification 3.0.3 are not applicable.  !

gl)RyglLLANCE F.POUIREMENTS 4.9.13.1 The burnup of each fuel assembly to be stored in the spent fuel pool shall be; '

determined from it's measured burnup history prior to storage in the spent fuel pool. A complete record of each assembly shall be maintained as long as that fuel assembly i is retained on site.  ;

i.

4.9.13.2 After fuel assembly (les) movement into or within the spent fuel pool, the

_ posii t on of the fuel assembly (les) that was (were) moved shall be checked andi independently verified to be in accordance with the criteria in Figure 3.91.  !

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t 1 can be stored anywhere - '

' 2inust not be stored next to 3 i 3 rnust be stored next to 1 or empty locatbns a

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Type 3 0 - .

2.5 - 2.75 3,0 3.25 3.5 3.75 4.0 4.25 4.5 4.75 - 5.0 initialEnrichtnent(w/o U235)

Figure 3.9-1 Fuel-Assembly Burnup vs. Initial I,nrichment--

For Spent Fuel' Assembly Storage-

_,,_--, . . . . _ _ . , _ . _ _ ._ , _ ..- . _. _ .- _ .. .__ ,. --...._... _ ... _ ... _ . _ ........~. _ _ _ . . . . _ . . - . ~ _ . _ _ _ . . . . - _ . _ . . ~ _ .

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'- . j Add the Following Technical Sp4:lfication to Section 3/4.9 REFUELING OPERATIONS

  • 3/4.9.14 NEW FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The new fuel storage vault may be maintained with a fullloading of 90 i assemblies with fuel enrichment up to 3.675 w/o "U. The loading must be reduced i to 81 assemblies for enrichments from 3.675 to 5.0 w/o '"U by limiting the fuel assembly placement in the central column of the New Fuel Storage Vault to every '

other location.

APPLICABILITY: Whenever fuel is in the New Fuel Storage Vault.

l ACTION: ,

a. With the requirements of the above specification not satisfied, suspend all other fuel movement _within the New Fuel Storage Vault and move the non complying fuel assemblies to allowable locations in the New Fuel Storage Vault in accordance with the requirements of the above Specification. .

b.'The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS-

. 4.9.14.11 After fuel assembly (les) movement into or within the New Fuel Storage Vault, the' position of the new fuel assembly (les) that was (were) _ moved shall be checked  ;

and independently verified to be In'accordance with the requirements of the above specification.

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1 Add Bases on Page B 3/4 9 3  !

3/4.9.13 Soent Fuel Assembiv Storace i Restrictions on placement of fuel assembiles of certain enrichments within the l spent fuel poo1is dictated by Figure 3.91. These restrictions ensure that the k,, of <

the spent fuel pool will always remain less than 0.95 assuming the pool to be flooded #

with unborated water. The restrictions delineated in Figure 3.91 and the action statement are consistent with the critical!ty safety analysis performed for the spent fuel ,

pool as documented in the FSAR. '

3/4.9.14 New Fuel Assembly Storace  !

Restrictions on placement of fuel assemblies of certain enrichments within the ,

New Fuel Storage Area is dictated Specification 3/4.9.14. These restrictions ensure that the is, of the New Fuel Storage Area will always remain less than 0.95 assuming the area to be flooded with unborated water. In addition, these restrictions ensure that _'

the k,n of the New Fuel Storage Area will always remain less than 0.98 when aqueous foam moderation is assumed. The restrictions delineated in Specification 3/4.9.14 and the action statement are' consistent with the criticality safety analysis performed for the- ,

spent fuel pool as documented in the FSAR.

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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE fu, b

5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 52.0 psig and a teiuperature of 296'F.

5.3 REACTOR CORE FUEL ASSEH9 TIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235. Reload fuel shall be similar in phy-sical design to the initial core loading and shall have a maximum enrichment of

-4,4 weight percent U-235.

S.O CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 57 full length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver, 15% in-dium, and 5% cadmium. All control rods shall be. clad with stainless steel tubing.

5. 4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE h 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a. In accordance with the Code requirements specified in Section 5.2 '

of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and
c. For a temperature of 650*F, except for the pressurizer which is 680'F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,265 cubic feet at a nominal T,yg of 5$8.5'F. -

5.5 METEOR 01.0GICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

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SEABROOK - UNIT 1 5-9 g 9/

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DESIGN FEATURES

5. 6 FUEL STORAGE o%> CRITICAll]

i . 6.1.1 The spent fuel storage racks are designed and shall be maintained with, i

pg a. A k,ff quivale- to le than or equal to .95 when coded wi .

A --- :* unbo ted wat r, whic includes a consery tive allo nce of 1 .% ak/k for uncertajdties as describe in Sectiyn 4.3 of tpe FSAR, a d

b. A nominal 10.35 inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6. 2 The for JMar 6~

,f f ewfue[1forthe rst core ioacing s fred dry i the sp nt fuel terage eks sh 1 not e eed 0.98 .en aquea s foam me ration i sumed.

DRAINAGE ~

5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 14 feet 6 inches.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a

' g) storage capacity limited to no more than 1236 fuel assemblies.

57 2 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1. ,

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SEABROOK - UNIT 1 5-10 g

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' insert A

a. A k,, equivalent to less than or equal to 0.95 when flooded with unborated water,  ;

which includes margin for uncertainty in calculational methods and mechanical i tolerances with a 95% orobability at a 95% confidence level. l insert B  !

5.6.1.2 The new fuel storage racks are designed and shall be maintained with:

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a. A k,, equivalent to less than or equal to 0.95 when flooded with'unborated water, I which includes margin for uncertainty _In calculational methods and mechanical -'

tolerances with a 95% probability at a 95% confidence level.

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b. A k,, equivalent to less than or equal to 0.98 when aqueous foam moderation is -

Lassumed, which includes margin for uncertainty in calculational methods and '

mechanical tolerances w!th a 95% probability at a 95% confidence level.

c. A nominai 21 Inch center to center distance between fuel assemblies placed in the  !

storage racks.

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