Text

Amend 216 to License NPF-3,revising TS 3/4.5.2,TS 3/4.5.3 & TS 3/4.7.Several Surveillance Intervals Changed from 18 Months to Once Each Refueling Interval
	ML20203C149
Person / Time
Site:	Davis Besse
Issue date:	12/02/1997
From:	Hansen A; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20203C155	List: ML20203C149; ML20203C270;
References
	NUDOCS 9712150244
	Download: ML20203C149 (9)
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i UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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-TOLEDO E01 SON COMPANY CENTERIOR SERVICE COMPANY MQ THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-316 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. NPF-3 1.

The Nuclear Regulatory Commission (the Comission) 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 January 20, 1997, 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; 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 license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

ENCLOSURE 1 9712150244 971202 PDR ADOCK 05000346 P

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Technical Specificaticali The fechnical Specifications contained in Appendix A, as revised through Amendment No. 216, 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 120 days after issuance.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: December 2, 1997 n

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ATTACHMENT TO LICENSE AMENDMENT NO.pis FACIllTY 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 5-4 3/4 5-4 3/4 5-5 3/4 5-5 3/4 7-5 3/4 7-5 3/4 7-12b 3/4 7-12b 3/4 7-14 3/4 7-14 3/4 7-15 3/4 7-15 4

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Revised by NRC Letter Dated June 6, 1995 SURVEILLANCE RE0VIREMENTS (Continued)

b. At least once each REFUELING INTERVAL, or prior to operation after ECCS piping has been drained by verifying that the ECCS pipirg is full of water by venting the ECCS pump casings and discharge piping high points.

c.

By a visual inspection which verifies that no loose det,iis (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment emergency sump and cause restriction of the pem,9 suction during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

For all areas of containment affected by an entry, at least once daily while work is ongoing and again during the final exit after completion of work (containment closeout) when CONTAINMENT INTEGRITY is established, d.

At least once each REFUELING INTERVAL by:

l 1.

Verifying that the interlocks:

a) Close DH-ll and DH-12 and deenergize the pressurizer heaters, if either DH-ll or DH-12 is open and a simulated reactor coolant system pressure which is greater than the trip setpoint (<438 psig) is applied. The interlock to close DH-11 and/or DH-12 is not required if the valve is closed and 480 V AC power is disconnected from its motor operators, b) Prevent the opening of DH-ll and DH-12 when a simulated or actual reactcr coolant system pressure which is greater than the trip setpoint (<438 psig) is applied.

2.

a) A visual inspection of the containment emergency sump which verifies that the subsN tem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

b) Verifying that on a Borated Water Storage Tank (BWST) Low-Low Level interlock trip with the motor operators for the BWST outlet isolation valves and the containment emergency sump recirculation valves energized, the BWST Outlet Valve HV-DH7A (HV-DH78) automatically close in $75 seconds after the operator manually pushes the control switch to open the Containment Emergency Sump Valve HV-D39A (HV-DH98) which should be verified to open it, s75 seconds.

3.

Deleted DAVIS-BESSE, UNIT 1 3/4 5-4 Amendment No. 3,25,28,40,77, 135,182,195,195,200,2 H, 216 i

l

s EMERGENCY CORE COOLING SYSTEMS SURVElllANCE REOUIREMENTS (Continued) 4.

Verifying that a minimum of 290 cubic feet of trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.

5.

Deleted 6.

Deleted c.

At least once each REFUELING INTERVAL, by l

1.

/erifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

2.

Verifying that each HPI and LPI pump starts automatically upon receipt of a SFAS test signal.

f.

By performing a vacuum leakage rate test of the watertight enclosure for valves DH-11 and DH-12 that assures the motor operators on valves DH-ll and DH-12 will not be flooded for at least 7 days following a LOCA:

1.

At least once per 18 months.

2.

After each opening of the watertight enclosure.

3.

After any maintenance on or modification to the wctertight enclosure which could affect its integrity.

The inspection port on the watertight enclosure may be opened without requiring performance of the vacuum leakage rate test, to perform inspections. After use, the inspection port must be verified as closed in its correct position.

Provisions of TS 3.0.3 are not applicable during these inspections.

g.

By verifying the correct position of each mechanical position stop for valves DH-14A and DH-148.

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of the opening of the valves to their mechanical position stop or following completion of maintenance on the valve when the LPI system is required to be OPERABLE.

2.

At least once each REFUELING INTERVAL.

l DAVIS-BESSE, UNIT 1 3/4 5-5 Amendment No. 20,25,40,101,207,215, 216 l

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b..

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

l.

Verifying that each valve (power operated or automatic) in the flow path is in its correct position.

2.

Verifying that t.11 manual valves in the auxiliary feedwater pump suction and discharge lines that affect the system's capacity to deliver water to the steam generator are locked in their proper position..

3.

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

c.

At least once each REFUELING INTERVAL. by:

l 1.

Vei fying 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 change or-Auxiliary Feedwater Safety Grade Flow Indication. -Verification of the Auxiliary feedwater System's flow capacity is not required.

d.

lne Auxili ry Feed Pump Turbine Steam Generator Level Control System shall be demonstrated OPERABLE by performance of'a CHANNEL Cli2CK 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 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. 43,53,00,122,216 131.103, n

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r PLANT SYSTEMS iJLY.E1LLANC.E EDMIRDOLU (continued) 3.-

When in MODE'l-at RA'/ED 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 Fwedwater-Pump flow p th 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.)

'At least once per 92 days and prior to entry into MODE 3 from MODE c.

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 Pump.**

d. -

At least once each REFUELING INTERVAL by:

l 1

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 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 I hour.

- When conducting tests of the Motor Driver Feedwater Pump System in MODE 1

^

greater than 40% RATED THERMAL POWER which require local manual realignment of,

.va ves t at ma e the system-inoperable. both auxiliary feedwater pumps and l

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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 communication with the control room) able to restore the valves to normal system OPERABLE status.

e DAVIS-BESSE; UNIT 1-3/4 7-12b Amendment No. 403,103, 200, 216 ~

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PLANT SYSTEMS, 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 Two independent component cooling water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one component cooling water loop inoperable, restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SH'JTDOWN within the following 30 hour:.

SVRVEILLANCE RIOVIREMENTS 4.7.3.1 Each component cooling water loop shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) s9rvicing safety related equipment that is not locked, sealed or etherwise secured in position, is in its correct position, b.

At least once each REFUELING INTERVAL, by:

l 1.

Verifying that each automatic valve in the flow path actuates to its correct position on an SFAS test signal.

2.

Verifying that each component cooling water emergency pump starts automatically on an SFAS test signal.

DAVIS-BESSE, UNIT 1 3/4 7-14 Amendment No. 216

s PLANT SYS1 EMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 Two indept.ident service water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one service water loop inoperable, restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3,RVElllANCFRE001REMENTS 4.7.4.1 Each service water loop shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

At least once each REFUELING INTERVAL, by:

l 1.

Verifying that each automatic valve in the flow path actuates to its correct position on an SFAS test signal.

2.

Verifying that each service water emergency pump starts automatically on an SFAS test signal.

DAVIS-BESSE, UNIT 1 3/4 7-15 Amendment No. 216

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ML20203C149

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