ML20244D396

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Amend 130 to License NPF-3,changing Tech Specs to Allow Fuel W/Max Enrichment of 3.80 Weight Percent U-235 to Be Stored in New Fuel Storage & Spent Fuel Storage Locations in Existing Fuel Storage Facilities at Plant
ML20244D396
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/13/1989
From: Hannon J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20244D399 List:
References
NUDOCS 8904210324
Download: ML20244D396 (13)
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TOLEDO EDISON COMPANY.

AND 1l THE CLEVELAND ELECTRIC ILLUMINATING COMPANY-DOCKET NO. 50 346' DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 JENDMENT TO FACIljTY OPERATING LICENSE Amendment No.130 License No. NPF-3 1.

The Nuclear Regulatory Commission (the Commission) has found that:

. A. -

The application' for' amendment by the Toledo Edison Company and The Cleveland Electric-Illuminating Company (the licensees) dated

. April-11, 1988 complies with the standards and requirements.cf the g-Atomic Energy Act of-1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

. B.

The' facility will operate in conformity with the application, the

. provisions of the' Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) I! hat the activities authori::ed by.

this~4mendment can be conducted without endangering the health and safety of the public,'and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.-

The issuance of this' amendment will not be inimical to the common

[ defense and security or to the health ano safety of the public; ar.d E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2; Accordingly, the. license is ' amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby l

amended to read as follows:

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OCK 05000346 1

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.. j (a) Technical Specifications, The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than May 30,.1989.

FOR THE NUCLEAR REGULATORY COMMISSION f/

A John N. llannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 13, 1989 I

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ATTACHMENT TO LICENSE AMENDMENT NO.130 J

FACILITY OPERATING' LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with l

- the attached pages. The revised pages are identified by amendment number and-contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert VIII VIII XIII XIII 3/4 9-13 3/4 9-14 B3/4 9-3 B3/4 9-3 5-4 5-4 5-5 5-5 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION............-..........................

3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 3/4.9.3 DECAY TIME...............................................

3/4 9-3 3/4.9.4 CONTAINMENT PEhETRATI0NS.................................

3/4 9-4 3/4.9.5 COMMUNICATIONS...........................................

3/4 9-5 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY.........................

3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING....................

3/4 9-7 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION All Water Leve1s.........................................

3/4 9-8 Low Water Leve1..........................................

3/4 9-8a 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...........

3/4 9-9 3/4.9.10 WATER L EVEL - REACTOR VESSEL.............................

3/4 9-10,,

3/4.9.11 STORAGE POOL WATER LEVEL.................................

3/4 9-11 3/4.9.12 STORAGE P0OL VENTILATION.................................

3/4 9-12 3/4.9.13 SPENT FUEL P0OL FUEL ASSEMBLY ST0 RAGE....................

3/4 9-13 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS....................................

3/4 10-1 3/4.10.2 PHYSICS TESTS...........................

3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS....................................

3/4 10-3 3/4.10.4 SHUTDOWN MARGIN..........................................

3/4 10-4 f

DAVIS-BESSE, UNIT 1 VIII Amendment No. 3E, 130 a

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INDEX BASES

$ECTION:

PAGE 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY.......................... B 3/4 9-2 3/4.9.71 CRANE TRAVEL - FUEL HANDLING BUILDING..................... B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION....................................... B 3/4 9-2 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 POOL WATER LEVEL........................................ B 3/4 9-2 3/4.9.12. STORAGE P0OL VENTILATION.................................. B 3/4 9-3 3/4.9.13 SPENT FUEL POOL FUEL ASSEMBLY ST0 RAGE..................... B 3/4 9-3 3/4.10 SPECIAL' TEST EXCEPTIONS

's/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.~.................................... B 3/4 10-1 3/4.10.2 PHYSICS TESTS............................................. B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.10.4 SH UT DOWN MARG I N........................................... 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 GASE0US EFFLUENTS......................................... B 3/4 11-3 3/4.11.3 SOLID RADI0 ACTIVE WASTE................................... B 3/4 11-6 3/4.11.4 TOTAL D0SE................................................ B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MON I TOR I N G P R0G RAM........................................ B 3/ 4 12 3/4.12.2 LAND USE CENSUS........................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM........................ B 3/4 12-1 DAVIS-BESSE, UNIT 1 XIII Amendment No. 86,130 l

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _. _ = _ _

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1 INDEX DESIGN FEATURES

.; r SECTION' PAGET 5.1 SITE:

Exc l u s i En Area.................................................

5-11

' L ow Popul a ti on Zone............................................. 5-1 5.2 CONTAINMENT K

-. C o n f i g u ra t i o n. '...'..........................................'....

5 s

-Desig'n P ressu re and Tempera ture................................

5-4 '

L 5.3 REACTOR CORE

.-r Fuel Assemblies.................................................- 5-4L C o n t ro l R o d s...................................................

5 '

5. 4 ? REACTOR COOLANT-SYSTEM ry Design Pressure and Temperature................................

5-4 3

Vo1ume.........................................................

5-5 5.54 METEOROLOGICAL TOWER L0 CATION...................................

5 t;

5. 6 FUEL STORAGE L C r i t i c a l i ty..................................................... 5-5

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Drainage.......................................

5-5 C a p a c i ty.......................................................

5-6 E

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT............................

5-6

[n DAVIS-BESSE, UNIT 1 XIV Amendment No. 38 i

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REFUELING OPERATIONS SPENT FUEL POOL FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION i

3.9.13 Fuel assemblies stored in the spent fuel pool shall be placed in the j

spent fuel storage racks according to the criteria shown in Figure 3.9-1.

j APPLICABILITY:

Whenever fuel assemblies are in the spent fuel pool.

i

_ 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.

r SURVEILLANCE REQUIREMENTS I

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 assemoly that was. moved shall be checked and independently verified to be in accordance with the criteria in Figure 3.9-1.

DAVIS-BESSE, UNIT 1 3/4 9-13 Amendment No. 130 l

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Figure 3.9-1 Burnup vs. Enrichment Curve for Davis <-Besse Spent Fuel Storage Racks Fuel Assembly Burnup (B). NWD/MTU 40.000 (3.8. 35930.8)

(3.3. 30354.3) 30.000 (22584 x El-(161o x E')g

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20.000 Not Permitted g

10.000 (i. 3. 0,. 0)

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1.5 2

2.5 3

3.5 4

4.5 Initial Fuel Enrichment (E), wtX U-235 Category 'A' Fuel - May be located anywhere within the storage racks-Category 'B' Fuel - Shall only be located adjacent 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. 130

l REFUELING OPERATIONS BASES I

3/4.9.12 STORAGE P0OL VENTILATION 1

The requirements on the emergency ventilation system servicing the storage pool area to be operating or OPERABLE ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber. prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety. analyses.

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, ensure 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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DAV0S-BESSE, UNIT 1 B 3/4 9-3 Amendment No. 130

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s ac 1A DAVIS-BESSE NUCLEAR POWER STATION LOW POPULATON ZONE FIGURE 5.1-2 DAVIS-BESSE, UNIT 1 5-3

e 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.

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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 fue? rod shall have a nonninal active fuel length of 144 inches and contain : naximum total weight of 2500 grams uranium.

The initial core leading 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 hcVe a maximum enrichment of 3.8 weight percent U-235.

CONTROL RODS 5.3.2 The reactor core shall contain 53 safety and regulating and 8 axial power shaping (APSR) control rods.

The safety and regulating control rods shall contain r nominal 134 inches of absorber material. The nominal values of ahorber material shall be 80 per. cent Silver,15 percent Indium and 5 percent Cadmium. All control rods shall be clad with stainless steel tubing.

The APSRs shall contain a nominal 63 inches of absorber material at their lower ends. The absorber material for the APSRs shall be 100 per-cent Inconel-600.

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 degrountion pursuant i

to applicable Surveillance Requirements.

b.

For a pressure of 2500 psig, and c.

For a temperature of 650 F, except for the. pressurizer and

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pressurizer surge line which is 670*F.

DAVIS-BESSE, UNIT 1 5-4 Amendment No. JJ,79.J23, 130

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DESIGN FEATURES

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VOLUME:

5.4.2 -The; total-water.and steam volume of the reactor coolant system is 12.110 1 200 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 on 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 wit $ff:equivalenttolessthanorequalto0.95when. flooded unborated water, which includes a conservative allowance of 1% delta k/k for calculation uncertainty,

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b.

A rectangular array of stainless steel cellt spaced-12 31/32 inches on centers in one direction and 13 3/e 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 with:-

a.

A-Keff' equivalent to less than.or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of'1% delta k/k:for uncertainties as~ described in Section 9.1 of the USAR.

l-b.

'A Keff 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.

c.

A nominal 21 inch center-to-center distance between fuel assemblies 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 Amendment No. J9, 130 l

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' DESIGN FEATURES 1

CAPACITY

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5.6.3 The spent fuel storage pool is designed and shall be maintained I

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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DAVIS-BESSE, UNIT 1 5-6 Amendment No.13

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