ML20092A168

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Amend 200 to License NPF-3,revising TS 3/4.7.1.2, Auxiliary Feedwater Sys, to Provide Addl Clarity for Action a & Remove References to Pressure Indicators & Specific Pressure Readings
ML20092A168
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 09/05/1995
From: Gundrum L
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20092A169 List:
References
NUDOCS 9509080234
Download: ML20092A168 (3)


Text

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UNITED STATES 7

E NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20555 0001 TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY ANQ THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT N0. 1 i

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.200 License No. NPF-3 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 (the licensees) dated April 10, 1995, 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 provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) 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 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 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 licer.m amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 4 Sereby amended to read as follows:

9509000234 950905 PDR ADOCK 05000346 p

PDR

(a)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 200, 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 Linda L. Gundrum, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV e

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

September 5, 1995

ATTACHMENT TO LICENSE AMENDMENT N0. 200 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. 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 7-6 3/4 7-6 3/4 7-12a 3/4 7-12a 3/4 7-12b 3/4 7-12b B 3/4 7-lb B 3/4 7-lb B 3/4 7-3 8 3/4 7-3 i

PLANT SYSTEMS AUXILIARY 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.

ACTION:

a.

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

b.

With any Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks inoperable, restore the inoperable interlocks to OPERABLE status within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l SURVEILLANCE REQUIREMENTS l

4.7.1.2.1 Each Auxiliary Feedwater train shall be demonstrated OPERABLE:

a.

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

1.

Verifying the differential pressure of each steam turbine driven pump is greater than or equal to the required differential pressure at the specified recirculation flow rate.

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

  • 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.

l DAVIS-BESSE, UNIT 1 3/4 7-4 Amendment No. 95,122 431,494,200 1

_ - - = - - - _.

t PLANT SYSTEMS CONDENSATE STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tanks shall be OPERABLE with a minimum contained volume of 250,000 gallons of water.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

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

a.

Restore the condensate storage tanks to OPERABLE status or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or b.

Verify by administrative means the OPERABILITY of the service water system as a backup supply to the auxiliary feedwater system, verify once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, and restore the condensate storage tanks to OPERABLE status within 7 days or be in H0T SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l l

SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The condensate storage tanks shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume to be within its limits when the tanks are the supply source for the auxiliary feedwater pumps.

DAVIS-BESSE, UNIT 1 3/4'7-6 Amendment No. 164-200

PLANT SYSTEMS MOTOR DRIVEN FEEDWATER PUMP SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.7 The Motor Driven Feedwater Pump and associated flow paths to the Auxiliary Feedwater System shall be OPERABLE.

l APPLICABIt111: MODES 1, 2 and 3.

ACTION:

With the Motor Drive Feedwater Pump or its associated flow paths to the Auxiliary feedwater System inoperable, restore to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.7.1.7 The required Motor Driven Feedwater Pump and flow paths to the l

Auxiliary feedvater System shall be demonstrated OPERABLE:

a.

Deleted l

b.

At least once per 31 days by:

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.

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.

]

l DAVIS-BESSE, UNIT 1 3/4 7-12a Amendment No. 103r1 % 200

PLANT SYSTEMS SURVEILLANCE RE0VIREf ENTS (Continued) 3.

When in MODE I at RATED THERMAL POWER equal to or less than 40% or when in MODES E 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 SysP..

(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 the Motor Driven Feedwater Pump starts from the Control Room. **

3.

Verifying proper operation of the Motor Driven Feedwater l

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 Indication.

Verification of Motor Driven feedwater Pump System flor 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the Motor Driven Feedwater Pump has been aligned to the Auxiliary Feedwater System for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

    • When conducting tests of the Motor Driven Feedwater Pump System in MODE 1 greater than 40% RATED THERMAL POWER which require local manual realignment i

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 controi room) able to restore the valves to normal system OPERABLE status.

DAVIS-BESSE, UNIT 1 3/4 7-12b Amendment No. M3r19h 200

c PLANT SYSTEM g3}ES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled dowa 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 OPERABILITY.

The Condensate Storage Tanks are the non-safety-related primary source of the water for the Auxiliary Feedwater System. When the auxiliary feedwater pumps are needed and either the Condensate Storage Tanks are not available or have been emptied by the Auxiliary Feedwater System, a safety-related transfer system transfers the suction from the Condensate Storage Tanks to the Service Water System. The Service Water System is the safety-related secondary source of the water and must be available for the associated Auxiliary Feedwater System train to be OPERABLE. The transfer is initiated upon detection of a low suction pressure at the suction of the auxiliary feedwater pumps by suction pressure interlock switches. These pressure switches, upon sensing low suction pressure, will automatically transfer the suction of the auxiliary feedwater pumps to the Service Water System. On a sustained low-low suction pressure, additional Auxiliary Feedwater Pump Suction Pressure Interlocks will operate to close the steam supply valves to protect the turbine driven auxiliary feedwater pumps from cavitation. The steam supply valves will re-open automatically upon restoration of suction pressure to the pumps.

Both the low and the low-low suction Auxiliary Feed Pump Suction Pressure Interlocks are required to be OPERABLE for OPERABILITY of the associated auxiliary feedwater train.

Each steam driven auxiliary feedwater pump is 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. Each train of auxiliary feedwater must be capable of providing feedwater flow to each steam generator in order to be OPERABLE.

However, the design of the system does not provide for feeding both steam generators simultaneously from one train.

When conducting tests of an auxiliary feedwater train in MODES 1, 2, or 3 which require local manual realignment of valves that make the train inoperable, a dedicated individual shall be stationed at the valves, in communication with the control room, able to restore the valves to normal system OPERABLE status.

However, it is not required to have this dedicated individual stationed if the other train of the Auxiliary Feedwater System is OPERABLE and the Motor Driven Feedwater Pump System is OPERABLE pursuant to Technical Specification 3/4.7.1.7 because two sources of auxiliary feedwater to the steam generators are OPERABLE.

In either situation, the Auxiliary Feedwater System train with the local manual realigned valves is inoperable and the Limiting Condition for Operation ACTION must be followed.

Closure of valve AF 599 or AF 608 will render both trains of the Auxiliary Feedwater System and the Motor Driven Feedwater Pump Systea 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. 117,122,131, 153d93,200 Next page is B 3/4 7-2

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 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 conducting tests of the Motor Driven Feedwater Pump System in MODE 1 at greater than 40% RATED THERMAL POWER which requires local manual realignment of valves which make the system inoperable, a dedicated individual shall be stationed at the realigned train's valves, in communication with the control room, able to restore the valves to normal system OPERABLE status.

However, it is not required to have this dedicated individual stationed if both trains of the Auxiliary Feedwater System are OPERABLE pursuant to Technical Specification 3/4.7.1.2 because two sources of auxiliary feedwater to the steam generators are OPERABLE.

In either situation, the Motor Driven Feedwater Pump System with the local manual realigned valves is inoperable and the Limiting Condition for Operation ACTION must be followed.

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 maintained with the ability for manual positioning of valves such that DAVIS-BESSE, UNIT 1 B 3/4 7-3 Amendment No. 103,135,193,200