W3F1-2004-0111, Supplement to Amendment Request NPF-38-249, Extended Power Uprate

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

ML043140283
Person / Time
Site:	Waterford
Issue date:	11/04/2004
From:	Mitchell T Entergy Nuclear South
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2004-0111
Download: ML043140283 (15)

Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road 5" Entergy Killona. LA 70057 Tel 504-739-6310 Fax 504-739-698 tmitchlentergy.com Timothy G. Mitchell Director, Engineering Waterford 3 W3F1-2004-0111 November 4, 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 October 8, 2004, "Supplement to Amendment Request NPF-38-249 Extended Power Uprate"

3. NRC Letter dated October 29, 2004, "Waterford Steam Electric Station, Unit 3 (Waterford 3) - Request for Additional Information Related to Revision to Facility Operating License and Technical Specifications -

Extended Power Uprate Request (TAC No. MC1355)"

4. 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. Reference 1 included a proposed change to the Technical Specifications regarding the steam generator pressure - low setpoint based on Instrument Society of America (ISA) 67.04 Part 2 Method 3 methodology. The proposed change was supplemented (Reference 2) to update the allowable value.

By letter (Reference 3), the NRC staff issued a Request for Additional Information (RAI) which informed Entergy that the staff can no longer accept any requested Technical Specification (TS) changes that are based upon the use of Method 3 unless the method is modified to alleviate the staff concerns.. In response to the RAI, to alleviate the staffs concern, Entergy has added 4 psi to the trip setpoint and allowable value that were previously submitted in Reference 3. Thus the revised trip setpoint is 666 psia and the revised allowable value is 652.4 psia. The steam generator pressure - low trip analytical limit of 576 psia used in the Extended Power Uprate safety analysis remains the same. Thus, the methodology used to develop the revised steam generator pressure - low setpoint and allowable value is based on CcOt

W3FI-2004-0111 Page 2 of 3 a modification of Instrument Society of America (ISA) 67.04 Part 2 Method 3. The method utilized adds margin such that the difference between the allowable value and analytical limit exceeds the non-measurable loop uncertainty. Revised marked-up TS pages 2-3, 3/4 3-19, and 3/4 3-20 are provided in Attachment 1 and supersede those pages previously submitted.

Revised marked-up TS Bases pages are provided for information only in Attachment 2 and supersede the equivalent Bases pages previously submitted. The bases for the acceptability of this revised setpoint methodology is provided in Attachment 3.

Entergy has followed the Method 3 issue closely and continues to maintain that Method 3 does not pose a significant safety issue. Entergy understands that the NRC staff will be addressing the Method 3 issue on a generic basis and looks forward to participating in the ultimate resolution to this industry issue.

The no significant hazards consideration included in Reference 4 is not affected by any information contained in this supplemental letter. There are no new commitments in this letter.

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 November 4, 2004.

SincerIv, TGM/DBM/cbh Attachments:

1. Revised Markup of Technical Specification Pages

2. Revised Markup of Technical Specification Bases (For Information Only)

3. Bases for Acceptability of Revised Setpoint Methodology

W3Fl-2004-0111 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 O-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. O. 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 1 To W3FI-2004-0111 Revised Markup of Technical Specification Pages

TABLF 2-2.1 REACT, OR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS c~o CD -m X a)

FUNCTIONAL UNIT -05 TRIP SETOI A -- VALIUES

1. Manual Reactor Trip Not Applicable Not Applicable 0 0

2. Unear Power Level - High Four Reactor Coolant Pumps < 108% of RATED THERMAL POWER S 108.76% of RATED THERMAL POWER Operating

3. Logarithmic Power Level - High (1) c 0.257% of RATED THERMAL POWER (6) c 0.280% of RATED THERMAL POWER (6)

4. Pressurizer Pressure - High S 2350 psla c 2359 psla

5. Pressurizer Pressure - Low 2 1684 psla (2) 2 1649.7 psla (2)

6. Containment Pressure - High 17 .1 p5la ;c 17.4 psia

7. Steam Generator Pressure - Low 2 pia (3) >Atsia (3)

8. Steam Generator Level - Low 2 27.4% (4) 2 26.48% (4)

9. Local Power Density - High < 21.0 kW/fl (5)

• 21.0 kWlRt (5)

10. DNBR - Low 2 1.26 (5) > 1.26 (5)

11. Steam Generator Level - High c 87.7% (4) c 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 psd (7) 2 18.47 psid (7)

WAEFORD - UNIT 3 2-3 Amendment No. 41e

,ABLE 134 ENr2lNEERED SAEETY FEATURES AMMON SYSMM INSTRUMEMMON TRIE VALUE ALLOWABLE 0 FUNCTIONAL UI TRIPETPOINT -0 1 SAFETY INJECTION (SIAS)

a. Manual (Trip Buttons) Not Applicable Not Applicabe

b. Containment Pressure - High s 17.1 psda s 17.4 psba

c. Pressurizer Pressure - Low 2 1684 psla"' 2 1649.7 pslat'

d. Automatic Actuation Logc Not Applicable Not Applicable

2. CONTAINMENT SPRAY (CSAS)

a. Manual (Trip Buttons) Not Applicable Not Appable

b. Containment Pressure - HghVI-h s 17.7 psia . s18.0psla

c. Automatic Actuation Logic Not Appicabc Not Applicable

3. CONTAINMENT ISOLATION (CIAS)

a. Manual CIAS (Trip Buttons) Not Applicable Not Applicable

b. Containment Pressue - High s 17.1 psa s 17.4 psia C. Pressurizer Pressure - Low 2 1684 PSWa, 2 1649.7 psiW"

d. Automatic Actuation Logic Not ApPcbe Not Applice

4. MAIN STEAM LINE ISOLATION

a. Manual (Trip Buttons) Nol Ap~pkaae

b. Steam Generator Pressure - Low

c. Containment Prssure. High s 17.1 pdia 5 17.4 psia k d. Automatic Actuation Logi U. AM hW

... %rwp-.--

WMnAnrA4,.Wm U314 19 AMENDMENT NO. 4O-X

ABLL J-4 (Continued CD -k0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE FUHCtlONAL UNIT Ro TRIP ALUE VIAEL 6 -o

5. SAFETY INJECTION SYSTEM SUHP RECIRCULATION (PLAS) -. 3 0

a. Manual RAS (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 Undervoltage 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 (112) Level - Low 2: 27.4%'" ("' 2. 26.48X"") '4

c. Steam Generator AP - High (SG-1 > SG-2) t 123 psid S 134 psid

d. Steam Generator AP - High (SG-2 > S6-I) g 123 3_ 5 134 psid

e. Steam Generator (112) Pressure - Low k Sia, N ppl iabl

f. Automatic Actuation Logic Not Applicable Not Atpplicable

g. Control Valve Logic (Wide Range SG Level - Low) 2 36.3X"") (S 2 35.3X"") '1 3/4 3-20 Ame nt No.

Attachment 2 To W3F1 -2004-0111 Revised Markup of Technical Specification Bases (For Information Only) to W3FI-2004-01 11 Page 1 of 2 yANALYTICAL-TISDICATE, ALE Table #2 UnaBPwred% Analytical Indicated 1 I TS Parameter Value Plant Value Comments \

1.24 RATED THERMAL 3735 MWt 3716 MWtl POWER Table #2 Linear Power 115% s5108%

2.2-1 Level High l Table #3 Logarithmic 4.4% s0.257%

2.2-1 Power Level High \

Table #4 Pressurizer 2422 psia s2350 psia 2.2-1 Pressure High Table #5 Pressurizer 1560 psia Ž1684 psia 2.2-1 Pressure Low Table #6 Containment 19.7 psia 5 17.1 psia 2.2-1 Pressure High Table #7 Steam Generator 576 psia Ž666 psia 2.2-1 Pressure Low Table #8 Steam Generator 5%NR Ž27.4%NR 2.2-1 Level Low Table #9 Local Power 21kW/ft 521kWfft 2.2-1 Density High _

Table #10 DNBR Low 1.26 k1.26 2.2-1 Table #11 Steam Generator 90% (NR) 587.7% (NR) 2.2-1 Level High Table #16 Reactor Coolant 60% flow Ž19.00 psid Analysis utilizes 2.2-Lowunits Flo In%flow while

.2 FIndications are In

\_ psid 3.1.2.7 BAMT Boron >4551 ppm 24900 ppm Concentration s6187 ppm s6125 ppm 3.1.2.7 RWSP Volume NA Ž12% level Modes 5 &6 3.1.2.7 RWSP Boron 2029 ppm 22050 ppm Concentration 4.1.2.7 RAB Air Temperature 50'F 55-F 4.1.2.7 BAMT Solution 497F 260Fl Temperature l 4.1.2.8 RAB Air Temperature Ž50'F Ž55-F 4.1.2.8 BAMT Solution 49F Ž 60'F Temperature 3 *

\ WATRFOR

- UIT 3B 0314 0-##

to W3Fl-2004-01 11 Page 2 of 2 TABLE B 3/4.0-1 - V1-S Zx-NALYTICAL-INDICATED Analytical Indicated I TS Parameter Value Plant Value Comments 3.2.6 RCS Cold Leg 2533'F 2536-F Temperature s552-F s549-F 3.2.8 Pressurizer Pressure 22090 psia Ž2125 psia s2310 psia s2275 psia Table #1.b, 3.b & 4.c 19.7 psia s17.1 psia 3.3-4 Containment Pressure High Table #1.c & 3.c 1560 psia 21684 psia @NOP 3.3-4 Pressurizer Pressure

_________L ow__ _ _ _ _ _ _

Table #2.b Containment 19.7 psia s17.7 psia 3.3-4 Pressure High High _

Table #4.b & 7.e 576 psia Ž666 psia @NOP 3.3-4 Steam Generator Pressure Low Table #5.b RWSP Level for 28,843 gal. 210% level Analysis utilizes 3.3-4 RAS units In gallons while Indications are In %.

Table #6.a 4.16 kV 1E Bus 3245 volts 23245 volts 3.3-4 Undervoltage (Loss of Voltage)

Table #6.b 480 V I E Bus 354 volts 2372 volts 3.3-4 Undervoltage Table #6.c 4.16kV 1E Bus 3860 volts Ž3875 volts 3.3-4 Undervoltage (Degraded Voltage)

Table #7.b Steam 5% (NR) Ž27.4% (NR) 3.3-4 Generator Level Low Table #7.c & 7.d 230 psid s123 psid 3.3-4 Steam Generator Delta Pressure High Table #7.g Control Valve 21.3% level 236.3% level 3.3-4 Logic (WR SG Level Low) 3.4.5.2c Primary - Secondary 75 gpd s75 gpd per SG Leakage I AE R 3/4 U3B-

Attachment 3 To W3Fl-2004-0111 Bases for Acceptability of Revised Setpoint Methodology to W3Fl-2004-01 11 Page 1 of 4 Bases for Acceptability of Revised Setpoint Methodology The NRC staff requested, in a letter dated October 29, 2004, "Waterford Steam Electric Station, Unit 3 (Waterford 3) - Request for Additional Information Related to Revision to Facility Operating License and Technical Specifications - Extended Power Uprate Request (TAC No. MC1 355)," that Entergy Operations, Inc. (Entergy) consider the following examples of acceptable actions regarding the Waterford Steam Electric Station, Unit 3 (Waterford 3) Extended Power Uprate (EPU) license amendment request:

1. Demonstrate that the approach used to develop the proposed limits provides adequate assurance that the plant will operate in accordance with the safety analyses. Show that Operability is ensured in the Technical Specifications (TS).

2. Suspend consideration of setpoint-related aspects of your request pending generic resolution of the staff concern.

3. Revise your request to incorporate Method 1, Method 2, or Performance-Based TS.

4. Revise your request to incorporate some other approach that you demonstrate to provide adequate confidence that the plant will operate in accordance with the safety analyses and show that Operability is ensured in the TSs.

The proposed "steam generator pressure- low" trip setpoint and allowable value have been derived using a method consistent with action 4 above. Waterford 3 historically has added margin to the total loop uncertainty (TLU) to establish a conservative trip setpoint to provide assurance with more than adequate confidence the plant would operate in accordance with the safety analyses. Additionally, the calculated allowable value (AV) was the acceptance criterion used to confirm the measurable portions of the channel functioned within statistical predictions, thus assuring the analytical limit would be protected by the trip setpoint.

However, to address the NRC Staff concerns with Instrument Society of America (ISA) 67.04 Method 3 (Method 3), Waterford 3 has revised the trip setpoint and allowable value to add 4 psi more margin. With this change, the AV derived by deducting the periodic test error (PTE) from the trip setpoint will be greater than the analytical limit plus non-measurable error effects. The non-measurable error effects include both the 95/95 error effects plus the applicable non-random biases. The proposed values will continue to assure that the plant will operate in accordance with the safety analyses and that operability is ensured in the TSs.

The addition of 4 psi margin to the steam generator pressure - low trip setpoint total loop uncertainty preserves the methodology for the derivation of setpoints and allowable values as described in the Waterford 3 current licensing basis. This assures consistency between this trip setpoint and other trip setpoints within the current licensing basis. Additionally, the additional 4 psi of margin ensures that the difference between the steam generator pressure

- low allowable value and analytical limit exceeds the non-measurable loop uncertainty.

A simple check calculation is provided below.

to W3FI-2004-01 11 Page 2 of 4 Simple Check Calculation Proposed Trip setpoint: 666 psia Periodic test error (PTE): -13.6 psi Proposed allowable value: 652.4 psia (Trip setpoint - PTE)

Analytical limit (AL): 576 psia Non-measurable uncertainties + bias: +76.1 psi AL + Non-measurable uncertainty: 652.1 psia Thus, the proposed trip setpoint less the PTE is greater than AL plus the non-measurable uncertainties. Entergy believes this addresses the staffs interpretation that the AV protect the analytical limit with greater than 95% probability and with 95% confidence.

An illustration, provided below, reflects the previously proposed trip setpoint, revised setpoint, and AV as derived using three different methods:

• by ISA 67.04 Method 3,

• the Waterford 3 current licensing basis (similar to Method 3), and

• Waterford 3 current licensing basis plus 4 psi.

The staff has indicated that setpoint AVs established by means of Method 3 do not provide adequate assurance that a plant will operate in accordance with the assumptions upon which the plant safety analyses have been based.

Waterford 3 respectfully maintains its position that the trip setpoint and allowable value using Method 3 does provide adequate assurance the plant will operate in accordance with the plant safety analyses. This is demonstrated in the illustration below which includes the probability that the trip will occur at a value greater than the analytical limit for this parameter for each method. Maintaining the proposed trip setpoint as the limiting safety system setting (LSSS) derived and maintained in accordance with Waterford 3 TS assures with greater than 95/95 confidence the analytical limit will be protected. The allowable value as currently listed in Waterford 3 TS is used to determine that plant protection system trip modules perform as statistically predicted to assure the trip setpoint (i.e., LSSS) protects the AL.

Attachment 3 to W3Fl-2004-0111 Page 3 of 4 The figure below illustrates the relationship between the proposed trip setpoint, new proposed setpoint, AV and AL, based on three calculation methods. NLU is the combination of the random portion of the non-measurable loop uncertainty effects. MLU is the combination of the random portion of the measurable effects, combined as they would be combined for the derivation of the TLU used to determine the trip setpoint.

Case 3:

Method per Waterford 3 Case 2: Current Licensing Basis, Case 1: with 4 psi additional margin ISA 67.04 Method 3 Method per Waterford 3 Current Licensing Basis P(Actuation > AL)

Combination > 97.9%

P(Actuation > AL) P(Actuation > AL)

> 97.2% TSP+4 DSi = 666 Dsia

> 97.1 % WI ,, 7SP = 662 psia 11 A

AI I I I MLU PTE Proposed AV PTE = 666 - PTE

= 15.2 psi = 13.6 psi = 13.6 psi E --

= 652.4 psia I AL + NLU + bias AV L AV

= 662 - PTE

= 648.4 psia

= 652.1 psia

= 662 - MLU

= 646.8 psi MB TLUI = 662 - 576

= (NLU2 + MLU2 2' +bias = 86 psia

= (68.322 + 15.22)"2 +7.77

= 77.8 psi MB+ 4 psi TLU2 = 666- 576

= (NLU2 + PTE2)1B +bias (NLU2 + PTE2 ) 2n+bias = 90 psia

= (68.322 + 13.62)11

= (68.322 + 13.62)1 +7.77

+7.77

= 77.4 psi = 77.4 psi NLU + bias

= +/-68.32 + 7.77

= 76.1 psi

-- T-Margin Margin Margin

= MB - TLU, = MB - TLU2 = MB+ 4 psi - TLU3

= 8.2 psi = 8.6 psi = 12.6 psi I&

I Analytical Limit (AL) = 576 psia to W3Fl-2004-01 11 Page 4 of 4 The terms used in the figure above are defined below:

AL Analytical Limit AV Allowable Value MB Measurement Band; difference between the trip setpoint and AL MLU Measurable Loop Uncertainty, the combination of the random portion of the measurable effects, combined as they would be combined for the derivation of the TLU used to determine the trip setpoint.

NLU Non-measurable Loop Uncertainty (also known as nCOT), the combination of the random portion of the non-measurable loop uncertainty effects PTE Periodic Test Error, the combination of the random portion of the measurable effects, combined as they would be combined in accordance Waterford 3 Technical Specifications for the derivation of the AV.

TLU Total Loop Uncertainty, the combination the non-measurable random effects, measurable random effects, and biases TSP Trip Setpoint (i.e., LSSS at Waterford 3)