Text

Amend 164 to License NPF-3,revising TS 3/4.7.1.3 & Bases Section Which Deletes Ref to Deaerator Storage Tanks as Condensate Storage Facilities for Auxiliary Feedwater Sys
	ML20079M112
Person / Time
Site:	Davis Besse
Issue date:	10/21/1991
From:	Hopkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20079M117	List: ML20079M112; ML20079M124;
References
	NUDOCS 9111080034
	Download: ML20079M112 (6)
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u UNITED STATES i

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NUCLEAR REGULATORY COMMISSION 7,.

p W A$mNG TON. D. C. 20656 f

T01EDO EDISON COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 giENDMENTTOFACILITYOPERATINGLICENSE Amendment No.164 License No. NPF-3 1.

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

A.

The application for ataendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated February 15, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act).-

cad 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 Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cumpliance with the Comission's regulations;

-D.

The isseence of this amendment will not be inimical-to the sommon defense and security or-to the' health and safety of the public; and E.

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

2.

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

' amended to read as follows:

91t1000034 911021' PDR. ADOCK 0b000346 P:

PDR

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2 (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amer.dment No.164, 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 45 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

? ? h)i l 1

f[ don B. Hopkins, Sr. Project Manager Project Directorate 111 3 Division of Reactor Projects !!!/IV/V.

Office of Nuclear Reactor Regulation

Attachment:

Chenges to the Technical Specifications Date of issuance: October 21, 1991

ATTACHMENT TO LICENSE AMENDMENT NO.164 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Repl&ce the following pages of the Appendix " A" Technical Specifications with the attached pages. The revised pages are f satified by anendment nunber and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove insert INDEX VII INDEX VII 3/4 7-6 3/9 7-6 B 3/4 7-2 B 3/4 7-2

.INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE_QUIREMEN15 S.ECl!0R PAfGE.

3f4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE S a f e ty V a l v e s..............................................

3/ 4 7 - 1 Au x i l i a ry f eedwa t e r Sys t em.................................

3/ 4 7-4 Condens a te S tora ge Ta nks...................................

3/4 7 6 l

Ac t i v i ty...................................................

3 / 4 7 - 7 Main Steam Line Isolation Va1ves...........................

3/4 7-9 Motor Dri ven f eedwater Pump Sys tem.........................

3/4 7-12a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMIT ATION............

3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM.............................

3/4 7-14 3/4. 7. 4 - SERV I CE WATE R SY ST EM.......................................

3/ 4 7-15 3/4.7.5 ULTIMATE HEAT SINK..............

4.........................

3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..................

3/4 7-17 3/4.7.7 SNUBBERS...................................................

3/4 7-20 3/4.7.8 SE AL ED SOURCE CONTAMI NAT ION................................, 3/ 4 7-3 6 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fi re Suppression Wa ter Sys tem..............................

3/4 7-38 Spray a nd/or Spri nkl er Sys tems.............................

3/4 a2

-l F i r e Ho s e S ta t i o ns.........................................

3/ 4 7-4 4 3/4. 7.10 F I RE B ARRI E RS..............................................

3/4 7-4 7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 p e ra t i ng..................................................

3/ 4 8 - 1 l

l Shutdown...................................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating..............................

3/4 8-6 A. C. Di s tri bu ti on - Shu tdown...............................

3/4 8-7 D. C. Di s tri bu ti on - Opera ti ng..............................

3/4 8-8 D. C. Distri bu tion - Shu tdown..............................

3/4 8-11 DAVIS-BESSE. UNIT 1 VII Amendment No./S.J03.J05.J35.164 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RERVIREMENTS_ _ _

l SECTION PAGE l

3/4.9__ REFUELING OPERATIONS t

3/4.9.1 BORON CONCENTRATION......................................

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

3/4 9-2 3/4.9.3-D E C A Y T I M E................................................

3 / 4 9 - 3

'3/4.9.4-CONTAINMENT PENETRAT IONS.................................

3/4 9-4 3/4.9.5 CO MMUN I C AT I O N S...........................................

3 / 4 9 - 5 3/4.9.6 FUEL HANDL ING BRIDGE OPERABIL ITY.........................

3/ 4 9-6 e

[

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 Levels.........................................

3/4 9-8 L ow Wa t er L ev e 1..........................................

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

i 3/4.9.10 WATER LEVEL - REACTOR VESSEL.............................

3/4 9 t 3/4. 9.11 ' STORAGE POOL WATER L EVEL.................,................ 3/4 9-11 l-L 3/4.9.12 STORAGE P00L.VENTILAT10N.................................

3/4 9-12 l

3/4.9.13-SPENT FUEL POOL FUEL ASSEMBLY ST0 RAGE............

3/4 9-13 l

l _

3/_4,.,1_0 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT. INSERTION AND POWER i

DISTRIBUTION LIMITS....................................

3/4 10-1

.i i

3/4.10.2 PH YS I CS 1 EST S............................................

3 / 4 10- 2

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3/4.10.3 REACTOR COOLANT L00PS....................................

3/4 10-3

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-3/ 4.- 10. 4 _ S HUT DOWN MARG I N..........................................

3/ 4 10- 4 DAVIS-BESSE. UNIT 1 VIII Amendment No. 38 130 m

PLANT SYSTEMS C0f(DERSATE ST_0RAftE TAfgS.

LJji!TIR(CONDJ110N f0R. 0 DERM JOR.

3. 7.1. 3 The condensate stonge tants snall be OPERABLE with a minimum contained

{

volume of 250,000 gallons of water, o

APP _L IC ABill_T Y : MODES 1, 2, and 3.

A.ET.1014.:

With the condensate storage tcnks inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

l a.

Restore the condensate storage tanks to OPERALLE status l

or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or b.

Demonstrate the OPERABILITY of the service water system as a backup supply to t'te auxilia y feedwater system and restore the condensate s+orage tanks to OPERABLE status within 7 days l

or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILL ANCE REQUIREMENTS

4. 7.1. 3.1 The condensate storage tanks shall be demonstrated OPERABLE at least l

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water volume to be within its limits when the tanks are the supply source for the au::iliary feedwater pumps.

l 4.7.1.3.2 The service water system shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that at least one service water loop is operating and that the service water loop-auxiliary feedwater systen) isolation valves are either open or OPERABLE whenever the service water system is the supply source for the auxiliary feedwater pumps, DAVIS-BESSE, VillT 1 3/4 7-6 Amendment No.164 I

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PLANT SYSTEMS BASES i 3/4.7.1.2 AUXILIARY FEEDWATED SYSTEMS (Continued)

Following any.nodifications or repairs to the Auxiliary Feeawater System piping from the Condensate Storage Tank through auxiliary feed pumps to the steam generators that could affect the system's capability to deliver water to the steam generators, following extended cold shutdown, a flow path verification test shall be performed, fhis test may be conducted in MODES 4, 5 or 6 using auxiliary steam to drive the auxiliary feed pumps turbine to demonstrate that the flow path exists from the Condensate Storage Tank to the-steam generators via auxiliary feed pumps, Verification of the turbine plant cooling water valves (CW 196 and CW 197),

the startup feedwater pump suction vahes (FW 32 and FW 91), and the startup feedwater pump discharge valve (FW 10b) in the closed position is required to address the ccncerns associated with potential pire failures in the auxiliary feedwater pump rooms, that could occur during operation of the startup feeJwatei pump.

3/4.7.l.3 CONDENSATE STORAGE TANKS l

i The OPERABILITY of the Condensate Storage Tanks with the minimum water volume i

s available to maintain the RCS at HOT STANDBY ensures that sufficient water i conditions for 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months with.iMar harge to atmosphere and to cooldown the Reactor Coolant System to less than 280 under normal conditions (i.e., no loss of offsite power).

The contained water volume limit includes an allowance for

, water not usable because of tank discharge line location or other. physical characteristics.

3/4.7.1.4 ACTIVITY The limitatier,i on secondary system specific activit" ensure that the resultant oc cite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.

These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than o.ie steam generator will blowdown in the event of a steam line rupture.

This restriction is required to 1) minimize the DAVIS-BESSE, UNIT 1 B 3/4 7-2 Amendment hu. ES,96,JJ7/Y77,

,W/. 5/1/9Y,164 t

ML20079M112

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