Text

Amend 193 to License NPF-3,revising TSs 3/4.7.1.2 & 3/4.7.1.7 for AFW Sys & Motor Driven Feedwater Pump Sys
	ML20076J293
Person / Time
Site:	Davis Besse
Issue date:	10/18/1994
From:	Gundrum L; Office of Nuclear Reactor Regulation
To:	;
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ML20076J295	List: ML20076J293; ML20076J303;
References
	NUDOCS 9410250257
	Download: ML20076J293 (12)
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k UNITED STATES f

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NUCLEAR REGULATORY COMMISSION.

WASHINGTON, D.C. 20555-0001 TOLEDO EDISON COMPANY CENTERIOR SERVICE COMPANY A!iQ THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NVCLEAR POWER STATION. UNIT N0. 1 l

AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No.193 License No. NPF-3 l

1.

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company l

(the licensees) dated April 5, 1994, complies with the standards and requirements of the 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 l

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

There is reasonable assurance (i) that the activities authorized by l

this amendment 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; j

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and I

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of 1

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 amended to read as follows:

9410250257 941018 PDR ADOCK 05000346 P

PDR

. (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.193, 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 90 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION VJ u

Linda L. Gundrum, Project Manarr.-

Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: October 18, 1994

ATTACHMENT TO LICENSE AMENDMENT NO. 193 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the followin the attached pages. g pages of the Appendix "A" Technical Specifications with The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 3/4 7-Sa 3/4 7-Sa l

3/4 7-12a 3/4 7-12a l

3/4 7-12b 3/4 7-12b l

3/4 7-12c 3/4 7-12c 8 3/4 7-lb B 3/4 7-lb B 3/4 7-2 8 3/4 7-2 8 3/4 7-3 8 3/4 7-3

PLANT SYSTEMS AUXILLARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1 2 Two trains of auxiliary feedwater, each consisting of an auxiliary feedwater pump and associated flow path to both steam generators, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

I ACTION l

a.

With one train of auxiliary feedwater inoperable to either steam generator, restore the inoperable train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With any Auxiliary Feed Pump Turbine inlet Steam Pressure Interlocks inoperable, restore the inoperable interlocks to OPERABLE status l

within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With steam generator inlet valve AF 599 or AF 608 closed, re-open the closed valve AF 599 or AF 608 within one hour or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVElllANCE REQUIREMENTS 4.7.1.2.1 Each Auxiliary Feedwater train shall be demonstrated OPERABLE:

l a.

At least once per 92 days on a STAGGERED TEST BASIS by:*

l 1.

Verifying that each steam turbine driven pump develops a differential pressure of > 1070 psid on recirculation flow when the secondary steam supply pressure is greater than 800 psia, as measured on PI SP 12B for pump 1-1 and PI SP 12A for pump 1-2.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

l

When conducting tests of an auxiliary feedwater train in MODES 1, 2, and 3 which require local manual realignment of valves that make the train inoperable, the Motor Driven Feedwater Pump and its associated flow paths shall be OPERABLE per Specification 3.7.1.7 during the performance of this surveillance.

If the Motor Driven Feedwater Pump or an associated flow path is inoperable, a dedicated individual shall be stationed at the realigned auxiliary feedwater-train's valves (in communication with the control room) able to restore the valves to normal system OPERABLE status.

DAVIS-BESSE, UNIT 1 3/4 7-4 Amendment No. 96,122,131,193

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) b.

At least once per 31 days on a STAGGERED TEST BASIS by:

l 1.

Verifying that each valve (power operated or automatic) in-the l

flow path is in its correct position.

2.

Verifying that all manual valves in the auxiliary feedwater pump l

suction and discharge lines that affect the system's capacity to deliver water to the steam generator are locked in their proper position.

1 3.

Verifying that valves CW 196, CW 197, FW 32, FW 91 and FW 106 are.l closed.

c.

At least once per 18 months by:

l 1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Steam and Feedwater Rupture Control System actuation test signal.

2.

Verifying that each pump starts automatically upon receipt of a Steam and Feedwater Rupture Control System actuation test signal.

The provisions of Specification 4.0.4 are not applicable for entry in MODE 3.

3.

Verifying that there is a flow path from each auxiliary feedwater pump to both steam generators by pumping water from the Condensate Storage Tank with each pump to both steam generators.

The flow paths shall be verified by either steam generator level l

change or Auxiliary Feedwater Safety Grade Flow Indication.

Verification of the Auxiliary Feedwater System's flow capacity is not required.

d.

The Auxiliary Feed Pump Turbine Steam Generator Level Control System l

shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

e.

The Auxiliary Feed Pump Suction Pressure Interlocks shall be l

demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

DAVIS-BESSE, UNIT 1 3/4 7-5 Amendment No. A),Q,#,J//, JA),193 1

7 ev,.

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-s

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PLANT SYSTEMS i

i SURVEILLANCE RE0VIREMENTS (Continued) i l

f.

After any modification or repair to the Auxiliary Feedwater System l

that could affect the system's capability to deliver water to the steam generator, the affected flow path shall be demonstrated available as follows:

1.

If the modification or repair is downstream of the test flow line, each auxiliary feed pump (s) associated with the affected flow path shall pump water from the Condensate Storage Tank to the steam generator (s) associated with the affected flow path; and the flow path availability will be verified by steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication.

2.

If the modification or repair is upstream of the test flow line, the auxiliary feed pump shall pump water through the Auxiliary Feedwater System to the test flow line; and the flow path availability will be verified by flow indication in the test flow line.*

l This Surveillance Testing shall be performed prior to entering MODE 3 if the modification is made in MODES 4, 5 or 6.

Verification of the Auxiliary Feedwater System's flow capacity is not required.

g.

Following each extended cold shutdown (> 30 days in MODE 5), by:

l l.

Verifying that there is a flow path from each auxiliary feedwater pump to both steam generators by pumping Condensate Storage Tank water with each pump to both steam generators.

The flow paths shall be verified by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

Verification of the Auxiliary Feedwater System's flow capacity is not required.

T 4.7.1.2.2 The Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks shall be demonstrated OPERABLE when the steam line pressure is greater than 275 psig, by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

The CHANNEL FUNCTIONAL TEST shall be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding 275 psig during each plant startup, if the test has not been performed within the last 31 days.

When conducting tests of an auxiliary feedwater train in MODES 1, 2, and 3 which require local manual realignment of valves that make the train inoperable, the Motor Driven Feedwater Pump and its associated flow paths shall be OPERABLE per Specification 3.7.1.7 during the performance of this surveillance.

If the Motor Driven Feedwater Pump or an associated flow path is inoperable, a dedicated individual shall be stationed at the realigned auxiliary feedwater train's valves (in communication with the control room) able to restore the valves to normal system OPERABLE status.

DAVIS-BESSE, UNIT 1 3/4 7-Sa Amendment No. 46, /lM,193

PLANT SYSTEMS MOTOR DRIVEN FEEDWATER PUMP SYSTEM LIMITING CONDITION FOR OPERATION l

3.7.1.7 The Motor Driven Feedwater Pump and associated flow paths to the l

l Auxiliary Feedwat.r System shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

l With the Motor Drive Feedwater Pump or its associated flow paths to the l

Auxiliary Feedwater System inoperable, restore to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

j SURVEILLANCE RE0VIREMENTS l

4.7.1.7 The required Motor Driven Feedwater Pump and flow paths to the l

Auxiliary Feedwater System shall be demonstrated OPERABLE:

l a.

At least once per 92 days by:*

l 1.

Verifying the Motor Driven feedwater Pump OPERABLE by starting l

the Motor Driven Feedwater Pump (if the pump is not already running) from the control room, and by indication of flow.

b.

At least once per 31 days by:

l 1.

When in MODE 1 with RATED THERMAL POWER greater than 40%,

verifying that each manual valve in the Motor Driven feedwater Pump suction and discharge lines that affect the system's capability to deliver water to the steam generators is locked in its proper position.

l 2.

When in MODE 1 with RATED THERMAL POWER greater than 40%,

verifying that each power operated valve in the flow path is in its correct position.

When conducting tests of the Motor Driven Feedwater Pump System in MODE 1 greater than 40% RATED THERMAL POWER which require local manual realignment of valves that make the system inoperable, both auxiliary feedwater pumps and their associated flow paths shall be OPERABLE per Specification 3.7.1.2 during the performance of this surveillance.

If one auxiliary feedwater pump or flow path is inoperable, a dedicated individual shall be stationed at the realigned Motor Driven feedwater Pump System's valves (in communica-tion with the control room) able to restore the valves to normal system OPERABLE status.

DAVIS-BESSE, UNIT 1 3/4 7-12a Amendment No. 103/, 193

I PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 3.

When in MODE I at RATED THERMAL POWER equal to or less than 40%

or when in MODES 2 or 3, verifying that each valve (manual or power operated) in the Motor Driven Feedwater Pump flow path is able to be positioned locally for delivering flow to the Auxiliary Feedwater System.

(Ability is demonstrated by verifying the presence of handwheels for all manual valves and the presence of either handwheels or available power supply for motor operated valves.)

c.

At least once per 92 days and prior to entry into MODE 3 from MODE 4 (if not performed in the past 92 days) by:*

1.

Verifying proper operation of each power operated and automatic valve in the Motor Driven feedwater Pump flow path to the Auxiliary Feedwater System.

2.

Verifying proper operation of the Motor Driven Feedwater Pump.**

d.

At least once per 18 months by:

1.

Verifying that there is a flow path between the Motor Driven Feedwater Pump System and the Auxiliary Feedwater System by pumping water from the Condensate Storage Tanks to the steam generators.

The flow path to the steam generators shall be verified prior to entering MODE 3 from MODE 4 by either steam generator level change or Auxiliary Feedwater Safety Grade Flow l

Indication.

Verification of Motor Driven FeeJwate Pump System flow capacity is not required.

If the Motor Driven Feedwater Pump cannot be tested within the time period

[

specified, due to being aligned to the Main Feedwater System, the Surveillance Requirement shall be met within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the Motor Driven feedwater Pump has been aligned to the Auxiliary Feedwater System for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

- When conducting tests of the Motor Driven Feedwater Pump System in MODE 1 greater than 40% RATED THERMAL POWER which require local manual realignment of valves that make the system inoperable, both auxiliary feedwater pumps and their associated flow paths shall be OPERABLE per Specification 3.7.1.2 during the performance of this surveillance.

If one auxiliary feedwater pump or flow path is inoperable, a dedicated individual shall be stationed at the realigned Motor Driven Feedwater Pump System's valves (in communica-tion with the control room) able to restore the valves to normal system OPERABLE status.

DAVIS-BESSE, UNIT 1 3/4 7-12b Amendment No. 103,193

1 PLANT SYSTEMS J

SURVEILLANCE RE0VIREMENTS (Continued) 2.

Verifying proper operation of the Motor Driven Feedwater Pump i

lube oil interlocks.

3.

Verifying proper operation of manual valves by shifting the Motor i

Driven Feedwater Pump between the Main Feedwater System and the Auxiliary Feedwater System.

i e.

After any modification or repair to the Motor Driven feedwater Pump l

j System that could affect the system's capability to deliver water from 1

the Condensate Storage Tanks to the Auxiliary Feedwater System, the affected flow path shall be demonstrated available as follows:*

l 1.

If the modification or repair is in the Auxiliary Feedwater flow path downstream of the Motor Driven Feedwater Pump test flow line 1

tie-in, the Motor Driven Feedwater Pump shall pump water from the Condensate Storage Tanks to the Auxiliary Feedwater System and the flow path availability will be verified by either steam l

generator level change or Auxiliary Feedwater Safety Grade Flow Indication.

2.

If the modification or repair is upstream of the Motor Driven Feedwater Pump test flow line tie-in, the Motor Driven Feedwater Pump shall pump water from the Condensate Storage Tanks to the test flow line and the flow path availability will be verified by Motor Driven Feedwater Pump Safety Grade Flow Indication.

l 8

f.

Following each extended COLD SHUTDOWN (greater than 30 days in j

i MODE 5), by:

l.

Verifying that there is a flow path between the Motor Driven Feedwater System and the Auxiliary Feedwater System by pumping i

water from the Condensate Storage Tanks to the steam generators.

The flow path to the steam generators shall be verified prior to entering MODE 3 from MODE 4 by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication.

l Verification of Motor Driven Feedwater Pump flow capacity is not required.

1 i

I

This surveillance testing shall be performed prior to entering MODE 3 from MODE 4 if the modification is made in MODES 4, 5, or 6.

Verification of the Motor Driven Feedwater Pump flow capacity is not required.

l DAVIS-BESSE, UNIT 1 3/4 7-12c Amendment No. 177,193 i

l l

PLANT SYSTEMS BASES 3/4,7.1.2 AUXILIARY FEEDWATER SYSTEM l

The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor l

Coolant System can be cooled down to less than 280*F from normal operating conditions in the event of a total loss of offsite power.

The OPERABILITY of the Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks is required only for high energy line break concerns and does not affect Auxiliary Feedwater System 0PERABILITY.

Each steam driven auxiliary feedwater pump ;s capable of delivering the required feedwater flow at the full open pressure of the Main Steam Safety Valves as assumed in the Updated Safety Analysis Report. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 280*F where the Decay Heat Removal System may be placed in operation.

Closure of valve AF 599 or AF 608 will render both trains of the Auxiliary Feedwater System and the Motor Driven Feedwater Pump System inoperable.

This is because closure of these valves would result in a complete loss of auxiliary feedwater to the steam generators for certain postulated feedwater line and steam line breaks.

(3/4.7.1.2 is continued on page B 3/4 7-2.)

DAVIS-BESSE, UNIT 1 B 3/4 7-lb Amendment No. ff7,222,43A,A43,193 Next page is B 3/4 7-2

PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (Continued) l Following any modifications or repairs to the Auxiliary Feedwater 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. This 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),

j the startup feedwater pump suction valves (FW 32 and FW 91), and the startup feedwater pump discharge valve (FW 106) in the closed position is required to address the concerns associated with potential pipe failures in the auxiliary feedwater pump rooms, that could occur during operation of the startup feedwater pump.

3/4.7.1.3 CONDENSATE STORAGE TANKS 1

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

ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months with steam discharge to atmosphere and to cooldown the Reactor Coolant System to less than 280* under normal conditions (i.e., no j

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 limitations on secondary system specific activity ensure that the resultant offsite 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.

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

This restriction is required to 1) minimize the positive reactivity effects of l

the Reactor Coolant System cooldown associated with the blowdown, and 2) limit

[

the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves l

DAVIS-BESSE, UNIT 1 B 3/4 7-2 Amendment No. AS,96,JJ7,122, Ltr. 5/1/91,JE4,193

!l-

PLANT SYSTEMS BASES within the closure times of the surveillance requirements are consistent with the assumptions used in the safety analyses.

3/4.7.1.6 SECONDARY WATER CHEMISTRY - Deleted j

3/4.7.1.7 MOTOR DRIVEN FEEDWATER PUMP SYSTEM The OPERABILITY of the Motor Driven Feedwater Pump System ensures that the Reactor Coolant System can be cooled down from normal operating conditions in the event of the total loss of Main Feedwater and Auxiliary feedwater Pumps.

The Motor Driven Feedwater Pump System must be capable of providing feedwater flow to each steam generator in order to be OPERABLE.

The Motor Driven Feedwater Pump flow capability ensures that adequate feedwater flow is available to remove Decay Heat and reduce the Reactor Coolant System temperature to where the Decay Heat System may be placed into operation.

When at 40% RATED THERMAL POWER or less and in MODES 1, 2, or 3, the Motor Driven Feedwater Pump System may be aligned to provide a flow path from the Deaerator Storage Tank through the Motor Driven Feedwater Pump to the Main Feedwater System.

During this Motor Driven Feedwater Pump mode of operation, a flow path from the Condensate Storage Tanks through the Motor Driven Feedwater Pump to the Auxiliary Feedwater System shall be i

maintained with the ability for inanual positioning of valves such that 4

DAVIS-BESSE, UNIT I B 3/4 7-3 Amendment No. ApA, JAA,193

ML20076J293

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