Text

Amend 96 to License NPF-38,changing TS by Modifying Channel Tests to Quarterly for Radiation Monitors & Increasing Time to 7 Days for Remaining Cold Shutdown W/O Leak Testing for RCS Isolation Valves
	ML20069K150
Person / Time
Site:	Waterford
Issue date:	06/06/1994
From:	Beckner W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20069K152	List: ML20069K150; ML20069K161;
References
	NUDOCS 9406150281
	Download: ML20069K150 (16)
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UNITED STATES

(

{O NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 g.y ENTERGY OPERATIONS. INC.

DOCKET N0. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-38 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated December 23, 1993, 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 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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.

9406150281 940606 PDR ADOCK 05000382 p -

PDR

. 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 Specifications and Environ' mental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION b

WL$ ~ D. hk William D. Beckner, Director-Project Directorate IV-I i

Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation I

Attachment:

Changes to the Technical Specifications 4

Date of Issuance: June 6, 1994 i

i i

Mr. Ross P. Barkhurst Entergy Operations, Inc.

Waterford 3 CC:

Mr. William H. Spell, Administrator Regional Administrator, Region IV Radiation Protection Division U.S. Nuclear Regulatory Commission Office of Air Quality and Nuclear Energy 611 Ryan Plaza Drive, Suite 1000 Post Offir'

'x 82135 Arlington, Texas 76011 Baton Ro-uisiana 70884-2135 Resident Inspector /Waterford NPS Mr. Jerrold G. Dewease Post Office Box 822 Vice President, Operation:-

Killona, Louisiana 70066 Support Entergy Operations, Inc.

Parish President Council P. O. Box 31995 St. Charles Parish Jackson, Mississippi m

P. O. Box 302 Hahnville, Louisiana 70057 Mr. R. F. Burski, Director Nuclear Safety Mr. Harry W. Keiser, Executive Vice-Entergy Operations, Inc.

President and Chief Operating Officer P. O. Box B Entergy Operations, Inc.

Killona, Louisiana 70066 P. O. Box 31995 Jackson, Mississippi 39286-1995 Mr. Robert B. McGehee Wise, Carter, Child ~ ':iraway Chairman P.O. Box 651 Louisiana Public Service Commission Jackson, Mississippi

.59205 One American Place, Suite 1630 Baton Rouge, Louisiana 70825-1697 Mr. D. F. Packer General Manager Plant Operations Entergy Operations, Inc.

P. O. Box B Killona, Louisiana 70066 Mr. L. W. Laughlin, Licensing Manager i

Entergy Operations, Inc.

P. O. Box B Killona, Louisiana 70066 Winston & Strawn Attn:

N. S. Reynolds 1400 L Street, N.W.

Washington, DC 20005-3502

t ATTACHMENT TO LICENSE AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE NO. NPF-33 DOCKET NO. 50-382 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 areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAG 11 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 4-9 3/4 4-9 3/4 4-19 3/4 4-19 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5

1 I

l TABLE 3.3-6 (Continued)

ACTION STATEMENTS l

ACTION 23 -

With the number of channels OPERABLE less than required by the

)

Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.

ACTION 24 -

With the number of channels OPERABLE less than required by the Minimum Channe?s OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 25 -

With the number of channels OPERABLE less than required by the Minimum Channe'.s OPERABLE requirement, comply with the ACTION requirements cf Specification 3.9.9.

A TION 26 -

With the number of cha rls OPERABLE less than required by the Minimus Channels OPERA:.: requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operatic 9.

A:~ ION 27 -

With the number of OPERABLE Channels less than required by the Minimut Channels OPERABLE requirement, either restore the ine;e-aole Channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1.

Initiate the preplanned alternate method of monitoring the a;propriate parameter (s), and 2.

If the monitor is not restored to OPERABLE status within 7 days af ter the failure, prepare and submit a Special Re: ort to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans anc l

schecule for restoring the system to OPERAELE status.

A:~;;N 2E -

Witn the number of channels OPERABLE less than required by the Pe ricar Channels OPERABLE requirements, operation of the plant ray continue for up to 30 days provided grab samples are taken once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the monitor is not restored to OPERABLE status within 30 days after the failure, continue sampling and prepare and submit a Special Report to the Commission pursuant to.

Specification 6.9.2 within 34 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

1 WATER ~DRD - UNIT 3 3/4 3-31 Amendment No. 91

I Allt i 4.3-3 (Continucel)

RADIAll0N MONilORINI; IN51RUMINIAI10N SURVI lil ANCf REQl_LREMENTS

)

(.llANNI I MODES FOR WillCil CllANNII

( llANNI I i 'JNCi 10NAL SURV[11tANCE INSTRUMENT (111iK.

C AI lilRA110N TlS?

IS REQUIRED 3.

EFFLUENT ACCIDENT MONITORS a.

Containment High Range S

R Q

1, 2, 3, & 4 l

b.

Plant Stack liigh Range S

R Q

1, 2, 3, & 4 i

c.

Condenser Vacuum Pump High Range S

R Q

1, 2, 3, & 4 l

d.

Fuel llandling Building Exhaust liigh Range S

R Q

1*,2*,3*,&4*

l e.

Main Steam Line liigh Range 5

R Q

1, 2, 3, & 4 l

l l

With irradiated fuel in the storage pool.

WATERFORD - UNIT 3 3/4 3-33 Amendment No. 96

l REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION l

l i

3.4.3.1 The pressurizer shall be OPERABLE with:

I a.

A steady-state water volume greater than or equal to 26% indicated level (350 cubic feet) but less than or equal to 62.5% indicated level (900 cubic feet), and, j

b.

At least two groups of pressurizer heaters powered from Class IE buses each having a nominal capacity of 150 kW.

APPLICABillTY: MODES 1, 2, and 3.

i ACTION:

l a.

With only one group of the above required pressurizer heaters OPERABLE, restore at least two groups 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the pressurizer otherwise inoperable, be in at least-H0T STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in i

HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEltLANCE REOUTREMENTS 4.4.3.1.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 4.4.3.1.2 The capatity of each of the above required groups of pressur12er j

heaters shall be verified to be at least 150 kW at least once each refueling interval.

4.4.3.1.3 The emergency power supply for the pressurizer heaters shall be

. demonstrated OPERABLE at each refueling interval by:

a.

Verifying the above pressurizer heaters are automatically shed from-the emergency power sources upon the injection of an SIAS test signal.

b.

Verifying that the above heaters can be manually placed and.

energized on the emergency power source from the control room.

WATERFORD - UNIT 3 3/4 4-9 Amendment No.~ Nhr 96 1

y

TABLE 3.3-6 (Continued)

ACTION STATEMENTS A: TION 23 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.

ACTION 24 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 25 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

A; TION 26 -

With the number of cha c1s OPERABLE less than required by the Minieur Channels OPERA:.: requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

A:' ION 27 -

With the number of OPERABLE Channels less than required by the Minimar Channels OPERABLE requirement, either restore the ino;e-t!

"hanne1(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1.

Initiate the preplanned alternate method of monitoring the a:prcpriate parameter (s), and 2.

If the monitor is not restored to OPERABLE status within 7 days a*ter the failure, prepare and submit a Special Re: ort to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans anc schecule for restoring the system to OPERABLE status.

A '::s 2E -

Witn the numoer of channels OPERABLE less than required by the V nica-Channels OPERABLE requirements, operation of the plant ray continue for up to 30 days provided grab samples are taken once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the monitor is not restored to OPERABLE status within 30 days after the failure, continue sampling and prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 14 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

WATER ~DRD - UNIT 3 3/4 3-31 Amenement he. 91

I Allt I 4.3-3 RADIAI.10N MONiiORING_INSIRUMENIAll0N SURViILLANCE REQUIREMENTS CilANNEL MODES FOR WillCil (llANNII CilANNIL FUNCT10NAL SURVEILLANCE INSTRUMENT

_ tlll CK_

CAllBRA110N TEST IS REQUIRED 1.

AREA MONITORS I

a.

Fuel Storage Pool Area l

Fuel llandling Building Ventilation System l

Isolation S

R Q

l b.

Containment - Purge &

Exhaust isolation S

R Q

1, 2, 3, 4 & *

I 2.

PROCESS MONITORS a.

Containment Atmosphere 1)

Gaseous Activity -

RCS Leakage Detection S

R Q

1, 2, 3, & 4 i

2)

Particulate Activity -

RCS Leakage Detection S

R Q

1, 2, 3, & 4 l

b.

Control Room Intake Monitors S

R Q

ALL MODES I

c.

Steam Generator Blowdown S

R Q

1, 2, 3, & 4 1

d.

Component Cooling Water Monitors A&B S

R Q

ALL MODES I

e.

Component Cooling Water Monitor A/B S

R Q

1, 2, 3, & 4 l

With irradiated fuel in the storage pool.

- During CORE ALTERATIONS or movement of irradiated fuel within the containment.

WATERFORD - UNIT 3 3/4 3-32 Amendment No. W 96 i

I Allt i 4.3 3 (Continueil) 1 Rf DI AI.10N MONil0 RING INSIRUMI NTAT ION SURVf Ill ANCE_R_EQUIREMENTS 3

CilANNfl MODES FOR WillCil CilANNI I

( llANNI I IUNCT10NAL SURVEILLANCE INSTRUMENT

( lli (K CAlIBRAI10N TI Si 15 REQUIRED 3.

EFFLUENT ACCIDENT MONITORS a.

Containment High Range S

R Q

1, 2, 3, & 4 l

b.

Plant Stack High Range S

R Q

1, 2, 3, & 4 i

c.

Condenser Vacuum Pump High Range S

R Q

1, 2, 3, & 4 l

d.

Fuel Handling Building Exhaust High Range S

R Q

1*,2*,3*,&4*

l e.

Main Steam Line High Range S

R Q

1, 2, 3, & 4 1

With irradiated fuel in the storage pool.

WATERFORD - UNIT 3 3/4 3-33 Amendment No. 96

i INSTRUMENTATION IN:0RE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

At least 75%* of all incore detector locations, and l

a.

b.

A minimum of two quadrant symmetric incore detector locations per core quadrant.

An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERABLE rhodium detectors.

APPLICABILITY: When the incore detection system is used for monitoring:

a.

AZIMUTHAL POWER TILT, b.

Radial Peaking Factors, c.

Local Power Density, d.

DNB Margin.

A: TION:

With the incore detection system inoperable, do not use the system a.

for the above applicable monitoring or calibration functions.

t.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SU VEI'.l ANCE RE0VIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use a.

and at least once per 7 days thereafter when required for monitoring

~

the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin:

b.

At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to. installation in the reactor core.

For the remainder of fuel cycle 6 the incore detection system may be considered OPERABLE with < 75% and 150% of all incore locations provided that penalties are applied to the COLSS and CPCs to account for a 1% increase (from i

6.92% to 7.92%) in overall uncertainty of CECOR measured planar radial peaking factors (F,,) and power distributions calculated by COLSS.

l l

WATERFORD - UNIT 3 3/4 3-34 Amendment No. Mr 90 l

l

REACTOR COOLANT SYSTEM

't 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3.1 The pressurizer shall be OPERABLE with:

i a.

A steady-state water volume greater than or equal to 26% indicated

'(

level (350 cubic feet) but less than or equal to 62.5% indicated

+

level (900 cubic feet), and, b '.

At least two groups of pressurizer heaters powered from Class lE buses each having a nominal capacity of 150 kW.

APPLICABitITY: MODES 1, 2, and 3.

ACTION:

a.

With only one group of the above required pressurizer heaters OPERABLE, restore at least two groups 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j t

b.

With the pressurizer otherwise inoperable, be in at least HOT

[

STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in j

HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0V!REMENTS 4.4.3.1.1 The pressurizer water volume shall be determined to be within its-limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3 l.2 The capacity of each of the above required groups of pressurizer heaters shall be verified to be at least 150 kW at least once each refueling interval.

j i

4.4.3.1.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at each refueling interval by:

j Verifying the above pressurizer heaters are automatically shed

{

a.

from the emergency power sources upon the injection of an SIAS test signal.

b.

Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.

b WATERFORD - UNIT 3 3/4 4-9 Amendment No. 247 96-

=

l REA:~C: COOLANT SYSTEM AUv!LIADY SPRAY LIM:7]N3 CON:ITION FOR OPERATICN 3.4.3.2 Both auxiliary spray valves shall be OPERABLE.

APPLICABIL]TY:

MODES 1, 2 and 3.

ACTION:

With only one of the above required auxiliary spray valves OPERABLE, a.

restore both valves to OPERABLE status within 30 days 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With none of the above required auxiliary spray valves OPERABLE, restore at least one valve to OPERABLE status within the next E hours or be in at least HOT STANDBY within the next 6 houes and in HDT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SU;.iE ! L L AN:E REQUIREMENTS 4.4.3.2.1 The auxiliary spray valve shall be verified to have power available to ea:n valse every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.3.2.2 T e aws lia*y s; ray valves shall be cycled at least once see IE r: t s.

4 WATERFCRC - UNIT 3 3/4 4-9a Amendment No. 22

REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Monitoring the reactor head flange leakoff system at least once e.

per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months, b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, Prior to returning the valve to service following maintenance, c.

repair. or replacement work on the valve, d.

Following valve actuation for valves in Section B due to automatic or manual action or flow through the valve:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying valve closure, and 2.

Within 31 days by verifying leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

4.4.5.2.3 Each Reactor Coolant System pressure isolation valve power-operated valve specified in Table 3.4-1, Section C, shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance, repair, or replacement work on the valve.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

WATERFORD - UNIT 3 3/4 4-19 Amendment No. 96

i TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES SECTION A SI-329A SIT Check 51-329B 51-330A 51-3308 51-336A Cold Leg Injection Check SI-336B SI-335A 51-335B 51-510A Hot Leg Injection Check 51-512A 51-510B 51-512B 51-241 HPSI Check 51-242 51-243 51-244 SECTION B I

SI-142A LPSI Check SI-142E 51-143A SI-143B SECTION C POWER-OPERATED VALVES SI-4C14 SDC Suction Isolation SI-4CIE 51-4: 5A 51-4CES (a) Masima Allowable Leakage (each valve):

1.

Except as noted below, leakage rates greater than 1.0 gpm are unacceptable.

2 For po er-operated valves (POVs) only, leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between previous measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3.

For power-operated valves (POVs) only, leakage rates _ greater than 1.0 gpm but less than or equal to 5.0 gpm are unacceptable if the latest measured rate exceeded the rate dete. mined by the previous test by an amount that reduces the margin between measured leakage rate and the maxi.num permissible rate of 5.0 gpm by 50% or greater.

4 Leakage rates greater than 5.0 gpm are unacceptable.

(b) To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by' computations showing that the method i

is capable of demonstrating valve compliance with the leakage criteria.

(c) Minimum test differential pressure shall not be less than 200 psid.

WATERFORD - UNIT 3 3/4 4-20

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1 WATERFORD - UNIT 3 3/4 7-3

PLANT SYSTEMS EMERGENCY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3

3.7.1.2 At least three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two feedwater pumps, each capable of being powered from separate OPERABLE e.nergency busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam f

supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With one emergency feedwater pump inoperable, restore the required emergency feedwater pumps 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With two emergency feedwater pumps inoperable be.in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three emergency feedwater pumps inoperable, immediately initiate corrective action to restore at least one emergency feedwater pump to l

OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS f

4.7.1.2 The emergency feedwater system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

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

1.

Verifying that each motor-driven pump develops a discharge pressure of greater than or equal. to 1298 psig on recirculation flow.

2.

Verifying that the turbine-driven pump develops 'a discharge pressure of greater than or equal to 1342 psig on recirculation flow when the steam generator pressure is greater than 750 psig.

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

WATERFORD - UNIT 3 3/4 7-4 Amendment No. 8th 96

i I

PLANT SYSTEMS f

SURVEILLANCE REOUIREMENTS (Continued) c.

At least once per 18 months during shutdown by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an emergency feedwater i

actuation test signal.

2.

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

d.

Following any cold shutdown of 30 days or longer or whenever feed-I water line cleaning through the emergency feedwater line has been 4

performed, by verifying, by means of a flow test, the normal flow path from the condensate storage pool through each emergency feedwater ump to each of the steam generators.

The provisions of l

Specification 4.0.4 are not applicable for entry into MODE 3 for the j

turbine-driven pump, t

i I

1

)

-WATERFORD - UNIT 3 3/4 7-5 Amendment No. 96

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1 f

P L' N' SYSTEMS CONDENSATE STORAGE POOL l

LIMIi!NG CONDITION FOR OPERATION-l s

3.7.1.3 The condensate storage pool (CSP) shall be OPERABLE with a contained volume of at least 82% indicated level (170,000 gallons).

ADPLICABILITY:

MODES 1, 2, and 3.

ACTION:

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

P a.

Restore the CSP to OPERABLE status 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or i

De castrate the OPERABILITY of the wet cooling tower basins as a Oackuc supply to the emergency feedwater pumps and restore the conce, sate stcrage pool to_0PERABLE status within 7 days or be in at j

least HOT STANDEY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within tre fc11owing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

5.:.E:.

','E RECUI RE*ENTS

' 7.1.3.'.

the condensate storage pool shall be demonstrated OPERABLE at least

:+

e-II ecurs by serifying the contained water volume is within its limits e-t e scs; is tne supply source for the emergency feedwater pumps.

4.7.1.3.2 The et cooling tower basins shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the wet cooling tower basins are the supply source for the emergency feedwater pumps by verifying:

l a.

That each automatic and/or non-automatic valve in the flow path from the wet cooling tower basics to the emergency feedwater pumps is-open or OPERABLE.

b.

That the wet cooling tower basins contain'a minimum contained l

water volume of 170,000 gallons.

l c.

That both auxiliary component cooling trains required by l

Specification 3.7.3 are OPERABLE and in operation.

I r

i i

WATERFORD - UNI -a j? -

3/4 7-6 s

ML20069K150

Text

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