W3F1-2004-0092, Supplement to Amendment Request NPF-38-249 Extended Power Uprate

Supplement to Amendment Request NPF-38-249 Extended Power Uprate

ML042880418
Person / Time
Site:	Waterford
Issue date:	10/08/2004
From:	Peters K Entergy Nuclear South, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NPF-38-249, W3F1-2004-0092
Download: ML042880418 (7)

Text

' Entergy Entergy Nuclear South Entergy Operations. Inc.

17265 River Road Killona, LA 70057 Tel 504 739 6440 Fax 504 739 6698 kpetersaentergy.com Ken Peters Director. Nuclear Safety Assurance W:aterford 3 W3F1 -2004-0092 October 8, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Supplement to Amendment Request NPF-38-249, Extended Power Uprate Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

1. Entergy Letter dated November 13, 2003, "License Amendment Request NPF-38-249 Extended Power Uprate"

2. Entergy Letter dated August 25, 2004, "License Amendment Request NPF-38-249 Extended Power Uprate"

3. Entergy Letter dated July 14, 2004, "Supplement to Amendment Request NPF-38-249 Extended Power Uprate"

Dear Sir or Madam:

By letter (Reference 1), Entergy Operations, Inc. (Entergy) proposed a change to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Operating License and Technical Specifications to increase the unit's rated thermal power level from 3441 megawatts thermal (MWt) to 3716 MWt.

By letter (Reference 2), Entergy informed the NRC staff that the allowable value for the steam generator pressure - low setpoint proposed in Reference 1 required revision, based on the latest calculation, and committed to provide revised marked-up Technical Specification pages to reflect the change in a future supplement. Revised marked-up Technical Specification pages 2-3, 3/4 3-19, and 3/4 3-20 are attached and supersede those previously submitted.

The allowable value previously proposed was 647.9 psia and the revised allowable value is 648.4 psia. The proposed steam generator pressure - low trip setpoint of 662 psia remains unchanged as does the analytical limit of 576 psia.

The no significant hazards consideration included in Reference 3 is not affected by any information contained in this supplemental letter. There are no new commitments in this letter.

10
1

W3F1 -2004-0092 Page 2 of 3 If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.

I declare under penalty of perjury that the foregoing is true and correct. Executed on October 8, 2004.

Sincerely,

,'i si ttachment:

Revised Markup of Technical Specification Pages

W3Fl-2004-0092 Page 3 of 3 cc:

Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Nageswaran Kalyanam MS 0-7D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445

Attachment To W3Fl -2004-0092 Revised Markup of Technical Specification Pages

TABLE-2.2-1 REACTOR PROTECTIVf INSTRumENTATioN TRiUSETPOIILMIIS TIP SFTPDIT AL1OWABLE VAt I IF Not Applicable Not Applicable FUNCTION Al UNIT

1. Manual Reactor Trip

2. Linear Power Level - High Four Reactor Coolant Pumn Operating

3.

Logarithmic Power Level -

(D mx 0 RocD 00 6 0 (0

'ps High (1)

< 108% of RATED THERMAL POWER

< 108.76% of RATED THERMAL POWER

< 0.257% of RATED THERMAL POWER (6) S 0.280% of RATED THERMAL POWER (6) 4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

Pressurizer Pressure - High Pressurizer Pressure - Low Containment Pressure - High Steam Generator Pressure - Low Steam Generator Level - Low Local Power Density - High DNBR - Low Steam Generator Level - High Reactor Protection System Logic Reactor Trip Breakers Core Protection Calculators CEA Calculators Reactor Coolant Flow - Low

< 2350 psia

> 1684 psla (2)

< 17.1 p(3)

> 27.4% (4)

S 21.0 kW/ft (5)

> 1.26 (5

< 87.7% (4)

Not Applicable Not Applicable Not Applicable Not Applicable

> 19.00 psid (7)

S 2359 psia

> 1649.7 psia (2)

> 17.4 p(3)

> 26.48% (4)

S 21.0 kWlft (5)

> 1.26 (5)

S 88.62% (4)

Not Applicable Not Applicable Not Applicable Not Applicable

> 18.47 psid (7)

RD -

2-3 Amendment N

AIAAWAI CD -

0 0 60-(0 iUCiONAL UNIT

1.

SAFETY INJECTION (SIAS)

a.

Manual (Trip Buttons)

b.

Containment Pressure. High

c.

Pressurizer Pressure - Low

d.

Automatic Actuation Logic

2.

CONTAINMENT SPRAY (CSAS)

a.

Manual (Trip Buttons)

b.

Containment Pressure - High-High

c.

Automatic Actuation Logic

3.

CONTAINMENT ISOLATION (CIAS)

a.

Manual CIAS (Trip Buttons)

b.

Containment Pressure - High C.

Pressurizer Pressure - Low

d.

Automatic Actuation Logic

4.

MAIN STEAM LINE ISOLATION

a.

Manual (Trip Buttons)

b.

Steam rGeneator Pressure - Low

c.

Containment Pressure - High

d.

Automatic Actuation Logic IBE~EIM QN

-VALUES.

Not Applicable s 17.1 psla 21684 psla'"

Not Applicable Not AppcaeW s 17.7 psla Not Applicable NotAppcbkl s 17.1 psia 21684 paint'"

Not Applicable Not A~cble s 17.1i psla Not Applicable Not Applicable s 17.4 psla 2 164i9.7 psla" Not Apicable Not Appiicable s 18.0psla Not Applicab NO Applicable s 17.4 psla 2 1649.7 psia"'

Not Applicable Not Appkabl 28psld't s 17.4 pslb Not Applicabe A -NI3/4319 AMENDMENT NO. 4_3, 4

TAEL J-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE (a

Er CD -.

o or 0D C)

FUNCTIOHAL Wil S. SAFETY INJECTION SYSTEM SUMP RECIRCULATION (

a. Manual MS (Trip Buttons)

b. Refueling Water Storage Pool - Low

c. Automatic Actuation Logic

6. LOSS OF POWER

a. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

b. 480 V Emergency Bus Undervol tage

c. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

7.

EMERGENCY FEEDWATER (EFAS)

a.

Manual (Trip Buttons)

b.

Steam Generator (1I2) Level - Low

c.

Steam Generator tP - High (SG-1 > SG-2)

d.

Steam Generator bP - High (SG-2 > SG-I)

e. Steam Generator (12) Pressure - Low

f. Automatic Actuation Logic

g. Control Valve Logic (Wide Range SG Level - Low)

TRIPVALUE VALUES MAS)

Not Applicable 10.0% (57,967 gallons)

Not Applicable 2 3245 volts Not Applicable 9.08% (52,634 gallons)

Not Applicable 2 3245 volts 2 372 volts 2 354 volts 2 3875 volts 2 3860 volts Not Applicable 2 27.4%)

(4)

S 123 psid S 123 psid G

2 psi&, )

Not Applicable Not Applicable 2-0 26.48x"' 4)

S 134 psid S 134 psid e

2 p Sai 2 Not Applicable

'A

Ž,

36.3%(3) (5

> 35.30()

(S)

- UNIT 3 3/4 3-20 Amendment No.