ML20198B346

Amend 137 to License NPF-38,changing App a TS 3.7.1.3 by Increasing Minimum Required Contained Water Volume in Condensate Storage Pool from 82% to 91% Indicated Level

ML20198B346
Person / Time
Site:	Waterford
Issue date:	12/18/1997
From:	Chandu Patel NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198B351	List: ML20198B346 ML20198B360
References
NUDOCS 9801060279
Download: ML20198B346 (7)

Text

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UNITED STATES f.'

y NUCLEAR REGULATORY COMMIS880N wasmwotow, o.c. sesmumet ENTERGY OPERATIONS. INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Nn.137 License No. NPF-38 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the_

licensee) dated July 17, 1996, as supplemented by letters dated June 3, and July 7,1997, and your application dated April 11, 1997, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I:

B.

The facility will operate in conformity with the applications, 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 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.

MYoE. bMe2 PDR p

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-38 is hereby amended to read as follows:

(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.137, and the Environmental Protection Plan conta'ned in A>pendix B, are hereby incorporated in the license.

The licensee sia11 operate the facility in accordance with the i

Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMISSION

$ fa, Chandu P. Patel, Project Nanager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: December 18, 1997 l

4 ATTACMENT T0 t!(INSE AMENDMENT NO.137 TO FACIL]ILOPEPP G LICENS EN0. NPF-38 DOC KL I NO. 50-382 Replace the following pages of the Appendix A T&cimical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAq[1 3/4 7-6 3/4 7-6 8 3/4 7-2 8 3/4 7-2 P

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PLANT SYSTEMS i

10RVffttANCE REQUIREMENTS (Continued) l c.

At least once per 18 months during shutdown by:

1.

Verifying that each automatic valve in the flow path actdates to its correct position upon receipt of an emergency feedwater actuation test signal.

2.

Verifying that each pump starts automatically upon receipt of an emergency feedwater actuation test signal i

d.

Following any cold shutdown of 30 days or longer or whenever feed.

water line cleaning through the emergency feedwater line has been the normal flow

)

performed, by verifying, by means of a flow test,h emergency path from the condensate storage pool through eac i

feedwater ump to each of the steam generators. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine driven pump.

I i

.WATERIDAD - UNIT 3 3/4 74 Amendmerit No. 96 N.1 6 itif

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PLANT SYSTEMS CONDENSATE STORAGE POOL LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage pool (CSP) shall be OPERABLE with a minimum contained volume of at least 91% indicated level.*

APPLICABIllTY: MODES 1, 2, 3 and 4.

l ACTION:

e In MODES 1. 2._gnd_1:

With the condensate storage pool inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> restore the CSP to OPERABLE status or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.

jn MODE 4:

With the condensate storage pool inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> "9stora ?.he CSP to OPERABLE stttus or be in at least COLD SHUTDOWN within the next 24

. hours.

$MRVEILLAN(E REQUIREMENTS 4.7.1.3.1 The condensate storage pool 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 is within its limits.

• In MODE 4, the CSP shall be OPERABLE with a minimum contained volume of at

-least 11% indicated level.

WATERFORD - UNIT 3 3/4 7-6 Amendment No.137

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4 3/4.7 _ PLANT SYSTEMS i

BASE $

t 3/4.7.1 TURBIF CYCLE 3/4.7.1.1 SAF;'TY VALVES, The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be Ilmited to within 1105 (1210 psta) of its Align pressure of 1100 psia during the most severe anticipated system opersilonal transient. The maximum relieving capacity is associated with a turbine trip from 2005 RATED THERNAL POWER coincident with an assumed loss of s

condenser heat sink (i.e., ne steam bypass to the condenser).

The specified valve lift set. tings and relieving capacities are in accordance with the requirements of Section 111 of the ASME Boiler and Pressum Vessc1 Code. 1974 Edition. The total relieving capacity for all valves on all of the steam lines is 16.267 x 10' lb/hr (at 1210 psia desiga pressure less 50 psi pressure drop to the inlet of the valves) which is 104.5 of the total socortdary

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4 steam flow plus N uncertainties of 15.61 x 10' lb/hr at 1005 RATED THERMAL POWER.

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A minimum of 2 OPERA 8LE safety valves per stsam generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OiERATION is allowable with safety valves inoperable within ti.6. limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels.

The reactor trip setpoint reductions are derived on the following bases:

For two-loop 4 pump operation

$P = Y x 104.5 where:

reduced reactor trip setpoint in percent of RATED THERMAL SP

=

POWER maximum number of inoperable safety valves per staan line N

=

the ratio of the total relieving capacity of all 12 main 104.2

=

steam safety valves divided by the secondary steam flow at 200K Rated Thermal Load, plus N uncertainty.

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WATERFORD - UNIT 3 3 3/4 7-1

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PLANT.SYSIEMS 1

RASES 3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM

-The OPERAB!t.ITY of the emerpency feedwater syr' s ensures that the i

Reactor Coolant System can be coo ed dovn to less than 350*F from normal operating conditions in the event of a total less-of-offsite power.

Each electric-driven emergency feedwater pump is capable of delivering a total feedwater flow of 350 gpa at a pressure of 1163 psig to the entrance of the steam generators. The steam-driven emergency feedwater pump is capable i

of delivering a total feedwater flow of 700 gpa at a pressure of 1163 psig to the entrance of the steam generators. 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 350*F when the shutdown cooling system may be placed into operation.

The surveillance requirement to verify the minimum pump discharge i

pressure on recirculation flow ensures that the pump performance curve has not degraded below that used to show that the pumps meet the above flow i

requirements and is consistent with the requirements of ASME Section XI.

l 3/4.7.1.3 CONDENSATE STORAGE POOL The OPERABILITY of the condensate storage pool (CSP) with the minimum water volume ensures that sufficient water is available (173,500 gallons) to cool the Reactor Coolant System to shutdown cooling entry conditions following any design basis accident. Additional makeup water is stored in the wet cooling tower (WCT) basins providing the capability to maintain HOT STANDBY conditions for at least an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to initiating shutdown cooling. The total makeup capacity also provides sufficient cooling for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until shutdown cooling is initieted in the event the ultimate heat sink sustains tornado damage concurrent with the tornado event. The CSP contained water volume limit (91% indicated in MODES 1, 2, and 3) includes an allowance r

for water not usable because of vortexing and instrumentation uncertainties.

This provides an assurance that a minimum of 170,000 gallons of water is available in the CSP for the emergency faedwater system and that 3,500 gallons of water is available in the CSP for use by the component cooling water makeup a

system. The CSP contained water volume limit (11% indicated in MODE 4) includes an allowance for water not usabla because of vortexing and

- instrumentation uncertatuties. This provides an assurance that a minimum of 3,500 gallons of water is available in the CSP for the component cooling water makeup system.

If natural circulation is required, the combined capacity (WCT 4

and CSP) is sufficient to maintain the plant at H0T STANDBY for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to shutdown cooling entry conditions-assuming the availability of only onsite power or only offsite power, and the worst single failure (loss of a diesel generator or atmospheric dump valve).

This requires

- approximately 276,000 gallons and complies with BTP RSB 5-1.

- WATERFORD - UNIT 3 8 3/4 7-2 AMENDMENT WO.137 l

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