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

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Supplement to Amendment Request NPF-38-249 Extended Power Uprate
ML042880418
Person / Time
Site: Waterford Entergy icon.png
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)
v • d • e


Text

Entergy Nuclear South Entergy Operations. Inc.

17265 River Road

' Entergy 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.

101

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 2 9 th 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 (D mx 0 FUNCTION Al UNIT TIP SFTPDIT AL1OWABLEVAtIIF RocD

1. Manual Reactor Trip Not Applicable Not Applicable 00 60 (0
2. Linear Power Level - High Four Reactor Coolant Pumn'ps < 108% of RATED THERMAL POWER < 108.76% of RATED THERMAL POWER Operating
3. Logarithmic Power Level - High (1) < 0.257% of RATED THERMAL POWER (6) S 0.280% of RATED THERMAL POWER (6)
4. Pressurizer Pressure - High < 2350 psia S 2359 psia
5. Pressurizer Pressure - Low > 1684 psla (2) > 1649.7 psia (2)
6. Containment Pressure - High

< 17.1 p(3) > 17.4 p(3)

7. Steam Generator Pressure - Low
8. Steam Generator Level - Low > 27.4% (4) > 26.48% (4)
9. Local Power Density - High S 21.0 kW/ft (5) S 21.0 kWlft (5)
10. DNBR - Low > 1.26 (5 > 1.26 (5)
11. Steam Generator Level - High < 87.7% (4) S 88.62% (4)
12. Reactor Protection System Logic Not Applicable Not Applicable
13. Reactor Trip Breakers Not Applicable Not Applicable
14. Core Protection Calculators Not Applicable Not Applicable
15. CEA Calculators Not Applicable Not Applicable
16. Reactor Coolant Flow - Low > 19.00 psid (7) > 18.47 psid (7)

RD - 2-3 Amendment N

CD -

AIAAWAI 0 0 iUCiONAL UNIT IBE~EIM QN -VALUES. 60-(0

1. SAFETY INJECTION (SIAS)
a. Manual (Trip Buttons) Not Applicable Not Applicable
b. Containment Pressure. High s 17.1 psla s 17.4 psla
c. Pressurizer Pressure - Low 21684 psla'" 2 164i9.7 psla"
d. Automatic Actuation Logic Not Applicable Not Apicable
2. CONTAINMENT SPRAY (CSAS)
a. Manual (Trip Buttons) Not AppcaeW Not Appiicable
b. Containment Pressure - High-High s 17.7 psla s 18.0psla
c. Automatic Actuation Logic Not Applicable Not Applicab
3. CONTAINMENT ISOLATION (CIAS)
a. Manual CIAS (Trip Buttons) NotAppcbkl NO Applicable
b. Containment Pressure - High s 17.1 psia s 17.4 psla C. Pressurizer Pressure - Low 21684 paint'" 2 1649.7 psia"'
d. Automatic Actuation Logic Not Applicable Not Applicable
4. MAIN STEAM LINE ISOLATION
a. Manual (Trip Buttons) Not A~cble Not Appkabl
b. rGeneator Pressure - Low Steam 28psld't
c. Containment Pressure - High s 17.1i psla s 17.4 pslb
d. Automatic Actuation Logic Not Applicable Not Applicabe A-NI3/4319 AMENDMENT NO. 4_3, 4

TAEL J-4 (Continued)

(a Er ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES CD -.

o or ALLOWABLE FUNCTIOHAL Wil TRIPVALUE VALUES 0D C)

S. SAFETY INJECTION SYSTEM SUMP RECIRCULATION ( MAS)

a. Manual MS (Trip Buttons) Not Applicable Not Applicable
b. Refueling Water Storage Pool - Low 10.0% (57,967 gallons) 9.08% (52,634 gallons)
c. Automatic Actuation Logic Not Applicable Not Applicable
6. LOSS OF POWER
a. 4.16 kV Emergency Bus Undervoltage 2 3245 volts 2 3245 volts (Loss of Voltage)
b. 480 V Emergency Bus Undervol tage 2 372 volts 2 354 volts
c. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage) 2 3875 volts 2 3860 volts
7. EMERGENCY FEEDWATER (EFAS)
a. Manual (Trip Buttons) Not Applicable Not Applicable
b. Steam Generator (1I2) Level - Low 2 27.4%) (4) 2-0 26.48x"' 4)
c. Steam Generator tP - High (SG-1 > SG-2) S 123 psid S 134 psid
d. Steam Generator bP - High (SG-2 > SG-I) S 123 psid G S 134 psid e
e. Steam Generator (12) Pressure - Low 2 psi&, ) 2 . pSai&2
f. Automatic Actuation Logic Not Applicable Not Applicable

'A g. Control Valve Logic (Wide Range SG Level - Low) Ž,36.3%(3) (5 > 35.30() (S)

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

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