ML20151L760

Proposed Tech Specs,Adding Tech Spec & Bases 3/4.9.1.13 Re Refueling Operations,Spent Fuel Pool Assembly Storage & Revising Tech Spec 5.3.1 Re Fuel Assemblies & Tech Spec 5.6.1.2 Re Criticality

ML20151L760
Person / Time
Site:	Davis Besse
Issue date:	04/11/1988
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20151L756	List: ML20151L751 ML20151L755 ML20151L760
References
NUDOCS 8804220136
Download: ML20151L760 (10)

Text

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Docket No. 50-346 INDEX L'icense No. NPF-3 Serial No. 1479 Page1 LIMITING CON 0!TICL'15 FOR OPERATION AND SURvf1LLAxCE REQU SECTION g

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................................. 3/491 3/4.9.2 INSTRUMENTATION..................................... 3/4 9 2 3/4.9.3 O ECA Y T I ME . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/49-3.........

3/4.9.4 C ONTA INMEN T P EN ETRAT IONS. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/494 3/4.9.5 COMMUNICATIONS...................................... 3/4 9-5 3/4.9.6 FUEL MAN 0L ING BR IDGE OPERABIL ITY . . . . . . . . . .3/49-4 ..........

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.. . . . . . . . .3/4 . . .9-7 3/4.9.8 OECAY HEAT RI.TVAL AND C00LANT .CIRCLATION Al l Wa t e r L e ve 1 s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4

. . . 9-a low W a t e r L e ve 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 . . .9-a4 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION ST5 3/49-) TEN......

3/4.9.10 WAT ER 1.EV El. - R EAC TOR VE5 5 EL . . . . . . . . .3/4 . . 9-10 3/4.9.11 STCRAGE POOL WATER LEVEL............................ 3/4911 3/4.3.12 STO RAG E PCOL 'I EN1 I LA T : 0N . . . . . . . . . . . . . . 3/4 . . . 3-12 3/4.1.13 SPCNT FOEL POOL CUE (. AS S E M 61.Y STofM (,F........

3/d 9-13 {

3/4.10 SPEC!AL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT. INSERTION AMO POWER DISTRIBUTION L IMIT5. . . . . . . . . . . . . . . . . . . . .2/4 . . .10-1 3/4.10.2 PHYSICS TEST 5....................................... 3/4 10-2 3/4.10.3 R EACTO R CO O LAN T L 00 P S . . . . . . . . . . . . . . . . . . 3/4 . . . 10-3 3/4.10.4 SHUTOOWN MARGIN..................................... 3/4 10-4 04vis BESSE, UNIT 1 v!!! Ar,endment No. 33 8804220136 880411 PDR ADOCK 05000346 p DCD

Docket No.-50-346 L'icense No NPF-3

. Serial No. 1479

! Attachment 3 Page 2

!Not1 SASE!

SICTICN PAG [

3/4.9.5 7UEL MANCLING 3RICGE OPE.U3 f L *Tr . . . . . . . . . . . . . . . . .' . . 8 3/4 9-2 3/4.3.7 CAME TRAVEL FUEL MANDL ING BUILD ING. . . . . . . . . . . . . . 8 3/4 9-2 .I 3/4.9.8 CCOLANT CIRCULAT"!0N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 9-2 3/4.9.9 CONTAINMENT PURGE MD EIMAUST ISCLATION SYSTEM..... I 3/4 9-2 3/4.9.10 and 3/4.3.11 WATER LEVEL - REACTOR VE33EL AND l STO RAGE PCCL WATER LIV EL . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 9 2 3/4.9.12 3TORAGE 7001. V ENTILATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 9-3 3/4.'n .13 S PENT F UEL poot F UEL A SS E t4 GLY S TonAcc . . .. . B 3/4 *l-3 l 3/4.10 SP!CIAL T!!T !IC!*TIONS )

3/4.10.1 GRCUP.NEIGHT INSIITION AMO i POWER O!!TR! 3UTI ON L IMIT3. . . . . . . . . . . . . . . . . . . . . . . . I 3/4 10-1 l 3/4.10.2 PHYSIC 3 TEIi3...................................... 8 3/4 10-1 l 3 / 4 .10. 3 A EAC C A CCC LANT L 0 0 P 5. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 3/4 10-1 3/4.10.4 3HUTDOWN MAA3!N.................................... 8 3/4 10-1 3/4.11 UOf 0AC*IVE im.UENTS 3/4.11.1 LIQUID E M UENT3..................... ............. 83/411-1 3/4.11.2 3Ast005 I m utNT3.................................. B 3/411-3 3/4.11.3 SOLID RA DI CACTh i. W A5 fl . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/411-6 3/4.11.4 TOTAL 0031. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-7 3/4.12 RA010 LOGICAL ENVIRONMENTAL mMITORING 3/4.12.1 MOMITORING PR04AAM................................. I 3/4 12-1 3/ 4 .12. 2 1.AND US E CEM5US . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/412-1 3/4.12.3 !NTERLA80RATORY COMPARISON PR04AAM. . . . . . . . . . . . . . . . . 8 3/4 12-1 CAV!3 i!33i UN!T 1 1111 Mendment No. 86

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Docket No. 50-346 License No. NPF-3'

+ ' Serial No. 1479 Attachment 3 1 Page 3 REFUELING 0PERATIONS e

SPENT FUEL POOL FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.13 Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel storage racks according to the criteria shown in Figure 3.9-1.

APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.

ACTION:

With the requirements of the above specification not satisfied, suspend all other fuel 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 3.9-1. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4

4.9.13.1 The burnup of each fuel assembly to be stored in the spent fuel pool shall be ascertained through analysis of its burnup history prior to ,

storage in the spent fuel pool. A complete record of each analysis shall be maintained as long as that fuel assembly is retained onsite.

4.9.13.2 After each fuel assembly move in the spent fuel pool, the position of the fuel assembly that was moved shall be checked and independently verified to be in accordance with the criteria in Figure 3.9-1.

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l DAVIS-BESSE, UNIT 1 3/4 9-13 , Aneadocat No. i

Docket No. 50-346 License No. NPF-3 Serial No. 1479 Attachment 3 Page 4 Figure 3.9-1 Burnup vs. Enrichment Curve for Davis-Besse Spent Fuel Storage Racks Fuel Assembly Burnup (8) . NWD/MTU

40. 000 -

-(3.8. 35930.8)

(3.3. 30354.3) 30.000 -

.8 - -26640 + (22584 x E)-(1610 x E )g 20.000 -

Not

"*"**'**d A C B 10.000 -

' ' ' ' ' ' ' ' ' ^*

0 0 0.5 i 1.5 2 2.5 3 3.5 4 4.5 Initial Fuel Enrichment (E). wt% U-235 Category 'A' Fuel - May be located anywhere i within the storage racks 1 Category 'B' Fuel - Shall only be located adjecent to  !

Category "A" Fuel or water holes within the storage racks Category 'C' Fuel - Shall not be located adjacent to Category "B" Fuel l

Davis-Besse, Unit 1 3/4 9-14 Amendment No. ,

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Docket No. 50-346

• License No. NPF-3 Serial No. 1479 .

Attachment 3

• l Page 5 l j

REFUELING OPERATIONS _

BASES l

3/4.9.12 STORAGE POOL VENTILATION l The requirements on the emergency ventilation system servicing I the storage pool area to be operating or OPERABLE ensure that all radio- l active material released from an irradiated fuel assembly will be filtered i through the HEPA filters and charcoal adsorber prior to discharge to the l a tmosphere. The OPERABILITY of this system and the resulting iodine i removal capacity are consistent with the assumptions of the safety l analyses. f I N S ,,

E RT n ' A*I I

N DAVIS-BESSE, UNIT 1 B 3/4 9-3 Amendment No.

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Pocket No. 50-346 License No. NPF-3 Serial No. 1479 Page 6 tf A' '

3/4.9.13 SPENT FUEL POOL FUEL ASSEMBLY STORAGE The restrictions on the placement of fuel assemblies within the spent fuel pool, as dictated by Figure 3.9-1, ensures that the k-effective of the spent fuel pool will always remain less than 0.95 assuming the pool to be flooded with non-borated water. The restrictions delineated in Figure 3.9-1 and the action statement are consistent with the criticality safety analysis performed for the spent fuel pool.

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Docket No. 50-346 License No. NPF-3 Serial No. 1479 Page 7 DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 40 psig and a temperature of 264*F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 177 fuel assemblies with each fuel assembly containing 208 fuel rods clad with Zircaloy -4. Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 2500 grams uranium. The initial core loading shall have a maximum enrichment of 3.0 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of-3d weight percent U-235.

3.8 CONTROL RODS 5.3.2 The reactor core shall contain 53 safety and regulating and l 8 axial power shaping (APSR) control rods. The safety and regulating control rods shall contain a nominal 134 inches of absorber material.

The APSR's shall contain a nominal 36 inches of absorber material at their lower ends. The nominal values of absorber material shall be 80 l percent silver,15 percent indium and 5 percent cadmium. All control l rods shall be clad with stainless steel tubing. l l

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE .

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 applicable Surveillance Requirements,

b. For a pressure of 2500 psig, and c, .For a temperature of 650*F, except for the pressurizer and pressurizer surge line which is 670*F.

DAVIS-BESSE, UNIT 1 5-4 Amendment No. JJ,4+

a i nse h . NPF-3 A00lil0NAL CHANGES PREVIOUSLY serial No. 1479 PROPOSED BY LETTER Serial No. /W7._ Date_B/gB2 Page 8 DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12.110 + 200 cubic feet at a nominal T,yg of 525'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown nn Figure 5.1 -1.

5.6 FUEL STORAGE CRITICALITY

5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. AK equivalent to less than or equal to 0.95 when flooded with ubof$(ed water, which includes a conservative allowance of 15 delta k/k for calculation uncertainty.

b. A rectangular array of stainless steel cells spaced 12 31/32 inches on centers iri one direction and 13 3/16 inches on centers in the other direction. Fuel assemblies stored in the spent fuel pool shall be placed in a stainless steel cell of 0.125 inches nominal thickness or in a failed fuel container.

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

a. AX equivalent to less than or equal to 0.95 when flooded with unb8fIted water, which includes a conservative allowance of 15 delta k/k for uncertainties as described in Section 9.1 of the MAk.

Insert 6' = 7 U3AR l

-b A nominal 21 inch center-to-center distance between fuel assemblies

c. placed in the storage racks.' ,

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 9 feet above the top of the fuel storage racks.

DAVIS-BESSE, UNIT 1 5-5 Mendment No.it

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Docket No. 50-346 )

Licsnse No. NPF-3 l Serial No. 1479 Attachment 3 Page 9 "B"

b. Ak ff equivalent to less than or equal to 0.98 when immersed in a hydrogenous "mist" of such a density that provides optimum moderation (i.e., highest value of keff), which includes a conservative allowance of 1% delta k/k for uncertainties as described in Section 9.1 of the USAR.

7 p$$ketNe. 50-346 .,

Seri 1 N 1 j l ,

Attachcient 3

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FORIHORM!Il0N ONLY DESIGN FEATURES CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 735 fuel assemblies.

5.7 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 limit of Table 5.7-1.

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, s 0WIS-BESSE, UNIT 1 5-6 Atendment No.19 d