ML20134A702

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Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy
ML20134A702
Person / Time
Site: River Bend Entergy icon.png
Issue date: 01/20/1997
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML19355E516 List:
References
NUDOCS 9701290052
Download: ML20134A702 (14)
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s ATTACIIMENT 3

TECHNICAL SPECIFICATIONS CIIANGES 4

PROPOSED CHANGES 1

To implement this request changes will be required to the Recirculation Loop and APRM flow

biased scram and rod block limits. The changes are listed below and markups of the

, specifications are included.

1 1 Tech Snc Sections Proposed Changes  !

1 j LCO 3.4.1; item B.1, page 3.4-1 T11ERMAL POWER $ 83% RTP i LCO 3.4.1; CONDITION B, page 3.4-2 TIIERMAL POWER > 83% RTP during single loop operation ,. i

? I LCO 3.4.1 REQUIRED' ACTION B.1, page 3.4-2 Reduce THERMAL POWER to 5 83% RTP TABLE 3.3.1.1-1 FUNCTION 2.b, page 3.3-7 5 0.66 W + 67% RTP and 5113% RTP i

TABLE 3.3.1.1-1 FUNCTION 2.b footnote (b), Allowable value is 5 0.66 W + 61% RTP when reset

page 3.3-7 for single loop operation per LCO 3.4.!," Recirculation 1 Loops Operating." I i I Markups of the Technical Requirements Manual and BASES changes are also included in . I i

support of this request. l l

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9701290052 970120 PDR ADOCK 05000458 P PDR

RPS Instrumentation

} 3.3.1.1 4

l Table 3.3.1.1 1 (page 1 of 3)

Reactor Protection Systevn Instrumentation CON 0lfl0NS APPLICABLE REQUIRED REFERENCED l l' '

MODES OR OTHER CHANNELS FROM

$ SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE

FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
1. Intermediate Range Monitors
a. Neutron Fla - High 2 3 H SR 3.3.1.1.1 s 122/125 l l SR 3.3.1.1.4 divisions I i SR 3.3.1.1.6 of full i sa 3.3.1.1.7 scale SR 3.3.1.1.13 SR 3.3.1.1.15 5(*) 3 I SR 3.3.1.1.1 s 122/125 )

$R 3.3.1.1.5 divisions '

SR 3.3.1.1.13 of full I sR 3.3.1.1.15 scale  !

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b. Inop 2 3 H SR 3.3.1.1.4 NA I l SR 3.3.1.1.15 )

. 5(a) 3 I SR 3.3.1.1.5 NA j SR 3.3.1.1.15 l

2. Average Power Range Monitors l
a. Neutron Flux - High, 2 3 H SR 3.3.1.1.1 s 20% RTP Setdown SR 3.3.1.1.4 '

SR 3.3.1.1.7 sR 3.3.1.1.8 sR 3.3.1.1.11 sR 3.3.1.1.15 v7 2

b. Flow Biased Simulated 1 3 G SR 3.3.1.1.1 sf W+

j Thermal Power - High su 3.3.1.1.2 W JTP and  ;

. SR 3.3.1.1.3 1 13%

1 SR 3.3.1.1.8 RTP(b)

I SR 3.3.1.1.9 st 3.3.1.1.11 SR 3.3.1.1.14 l SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 (continued) l l

(a) With any control rod withdrawn from a core cell containing one or more fuel assenblies.

(b) Allowable Value is s 0.66 W + . TP when reset for single loop operation per LC0 3.4.1,

" Recirculation Loops Operett ."

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l RIVER BEND 3.3-7 Amendment No. 81 i

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-_ =- . . - _ . - - . . ~ . . - . - - . . _ - - -- , . . - _ , -

1 RFS Int.trumsntation TR 3.3.1.1 4

i Tacle 3.3.1.1-1 f rage 1 of 3)

Pgactor Protection System Instrumentation FUNCTION APPLICABLE REQUIPID CONDITIONS SURVE!!.i.ANCE NOMINAL 1 MODES OR OTHER CHANNELS PIFEPINCED PIQU1PIMENTS SETPOINT/

q SPECIFIED PER TRIP FROM PIQUIPID PISPONSE 7 CONDITIONS SYSTEM ACTION D.1 TIME J l 1

1. Intermediate Range Monttors l 4 Neutron Flux. 2 3 H SR 3.3.1.1.1 120/125 High SR 3.3.1.1.4 divisions of SR 3.3.1.1.6 full scale SR 3.3.1.1.7 i

SR 3.3.1.1.13 SR 3.3.1.1.15 {

' 5'al 3 1 SR 3.3.1,1,1 120/12$

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SR 3.3.1.1.5 atvtstons of SR 3.3.1.1.13 full scale SR 3.3.1.1.15 l l)

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c. Incp 2 3 H fR 3.3.1.1.4 NA I

.i R 3.3.1.1.15

]

$(4) 3  ! SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power PJnge Monitors

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a. Neutron Flux. 2 3 H SR 3.3.1.1.1 15% RTP

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High. Setsown SR 3.3.1.1.4 SR 3.3.1.1.7

! SR 3.3.1.1.8

{ SR SR 3.3.1.1.11 3.3.1.1.15 g I

o. Flow Stased 1 3 G SR 3.3.1.1.1 0.66 W +
SLmulated SR 3.3.1.1.2 RTP and

, Thermal Power. SR 3.3.1.1.3 4 Magn SR 3.3.1.1.8 p7p(b)

SR 3.3.1.1.9 g SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17

i. SR 3.3.1.1.18 5 0.],\ )

l sec 1

.j (continued)

.at With any ton'.101 rod withdrawn f rom a core : ell contatning one or more fuel assemelles.

on N:m.nal Jetpoint is 0.66 W t P P wnen reset for single loop operation per LCO 3.4.1, "Pecirculation Loops

.?;e r a t ; r g . "

.:) '.: t in:1231ng simulated thermal -

56ame constant specified in the COLR.

si s.up:nse time shall be measured frcm the detector output or from the inpot to the first electronic component in the raannel l et, :ff, 3) :tl not ased this page l

I l RIVER BEND TR 3.3-2 Revision 16 (91)

Control Rod Block Instrumsntation TR 3.3.2.1 Table 3.3.2.1-1(Page 1 of 2)

, Control Rod Block Instrumentation FUNCTION APPLICABLE REQUIRED CONDITIONS SURVEILLANCE NCNINAL ALLOWABLE MODES OR OTHER CHANNELS REFERENCED FROM PEQUIREMENTS SETPOINT VALUE l SPECIFIED PER TRIP TLCO REQUIRED CONDITIONS N !ON ACTION A.1

1. Rod Pattern Control System

]

l a. Rod withdrawal (a) 2 ENTER SR 3.3.2.1.1 limiter SR 3.3.2.1.6 Ic0 3.3.2.1 SR 3. 3. 2.1. 9 TSR 3.3.2.1.7

. TSR 3.3.2.1.10 (b) 2 SR 3. 3. 2.1. 2

, SR 3.3.2.1.5 3

SR 3. 3. 2.1. 7 SR 3.3.2.1.9 TSR 3.3.2.1.10 l b. Rod pattern g(c)'2 2 EMER SR 3.3.2.1.3 controller SR 3.3.2.1.4 If0 3 3'2*I SR 3.3.2.1.5 SR 3.3.2.1.7 SR 3. 3.2.1. 9

2. Reactor >bde Switch Shutdown (d) 2 ENTER SR 3.3.2.1.8 Position Ic0 3.3.2.1 1
3. Low Power Setpoint (b),(c),2 2 ENTER TSR 3.3.2.1.11 27.5 4 34 27.5 1 7.54 Iro 3.3.2.1 RTP RTP 4.Hign Power Setpoint > HPSP 2 ENTER TSR 3.3.2.1.11 67.94 RTP 5 66.2% RTP ICO 3.3.2.1
5. Average Power Range Monitors
4. Flow Biased Simulated l Thermal Power - High l 58 bl
1) Two Recirculation 6 8 TSR d

Loop Operation 1

TSR 3.3.2.1.13 3.3.2.1.14 \.IW+

  1. 94RTP '"

\ 5. 6W +

MtRTP 'N

TSR 3.3.2.1.16
TSR 3.3.2.1.18 and $100% and 5110n
2) Single Recirculation 1 6 8 TSR 3.3.2.1.1 .66W +

, Loop Operation TSR 3.3.2.1.14 - RTP O M.6W+4RTp O' TSR 3.3.2.1.16 TSR 3.3.2.1.18 and $100% and 5110%

RTP RTP i

b. Inoperative 1,2 6 8 TSR 3.3.2.1 13 NA NA 4

TSR 3.3.2.1.14

c. Downscale 1 6 8 TSR 3.3.2.1.13 54 RTP 2 34 RTP TSR 3.3.2.1.14 TSR 3.3.2.1.16
d. Neutron Flux = High, 2 6 8 TSR 3.3.2.1.13 124 RTP 5 144 RTP Setdown TSR 3.3.2.1.14 TSR 3.3.2.1.16 (continued)

.f RIVER BEND TR 3.3-10 Revision 18 l a (181)

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LC0 3.4.1 A. Two recirculation loops shall be in operation with:

. 1. Matched flows; and

2. Total core flow and THERMAL POWER within limits.

08 i B. One recirculation loop shall be in operation with:

j
1. THERMAL POWER RTP; sgr Q3
2. Total core flow and THERMAL POWER within limits;
3. Required limits modified for single recirculation loop operation as specified in the COLR; and
4. LCO 3.3.1.1, " Reactor Protection System (RPS) 4 Instrumentation," Function 2.b (Average Power Range l

Monitors Flow Biased Simulated Thermal Power--High),

Allowable Value of Table 3.3.1.1-1 reset for single loop operation.

.........................---N0TE----------------------------

. Required limit and setpoint modifications for single j recirculation loop operation may be delayed for up to i 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation.

i APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

A. Recirculation loop jet A.1 Shutdown one 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pump flow mismatch not recirculation loop.

within limits.

i (continued)

RIVER BEND 3.4 1 Amendment No. 81

Recirculation Loops Operating 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. THERMAL POWER > B.1 Reduce HERMAL POWER 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RTP during sing e loop to s operation. g ~3 C. Total core flow as a C.1 Determine APRM and Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> function of THERMAL LPRM neutron flux POWER within Region II noise levels. AND of Figure 3.4.1-1.

30 minutes after an increase of a: 5% RTP l

D. Total core flow as a D.1 Rectore APRM and LPRM 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l function of THERMAL neutron flux noise l POWER within Region 11 level to s 3 times j of Figure 3.4.1-1. established baseline '

levels.

AND APRM or LPRM neutron flux noise level > 3 times established baseline noise level.

E. Total core flow as a E.1 Restore total core 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> function of THERMAL flow as a function of POWER within THERMAL POWER to Region III of Figure within Region I or II 3.4.1-1. of Figure 3.4.1-1.

(continued) 1 RIVER BEND 3.4-2 Amendment No. 81

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.. q .

Racirculetion Loops Oparating (Single Loop)

TR 3.4.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.1.1.1 Verify volumetric loop flow rate of the loop in Initially, within operation is 5 33000 gpm. I hour and once i

per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l thereafcer 1

1 TSR 3.4.1.1.2 Verify THERMAL POWER is 5 - RTP. Initially, within i o 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once l g_D ,

per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter J TSR 3.4.1.1.3 Verify flow control is in Loop Manual. Initially, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter l

RIVER BEND TR 3.4-3 REVISION 5 (511)

Recirculation loops Operating B 3.4.1 BASES APPLICABLE The recirculation system is also assumed to have sufficient SAFETY ANALYSES flow coastdown characteristics to maintain fuel thermal (continued) margins during abnormal operation 21 transients (Ref. 2),

which are analyzed in Chapter 15 of the USAR.

A plant specific LOCA analysis has been performed assuming 4

only one operating recirculation loop. This analysis has demonstrated that, in the eve 9t of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency

Core Cooling System response will provide adequate core cooling, provided the APLHGR requirements are modified accordingly (Ref. 3).

l The transient analyses of Chapter 15 of the USAR have also been performed for single recirculation loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed provided the MCPR requirements are modified. During single recirculation loop operation, modification to the Reactor Protection System average power range monitor (APRM) instrument setpoints is also required to account for the different relationships between recirculation drive flow and reactor core flow. The APLHGR and MCPR limits for single loop operation are specified in the COLR. The APRM flow biased simulated thermal power setpoint is in LC0 3.3.1.1, " Reactor Protection System (RPS) Instrumentation."

Recirculation loops operating satisfies Criterion 2 of the NRC Policy Statement.

LC0 Two recirculation loops are normally required to be in operation with their flows matched within the limits specified in SR 3.4.1.1 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. In addition, the total core flow must be a: 45% of rated core flow or total core flow expressed as a function of THERMAL POWER must be in Region I as identified,in Figure 3.4.1-1, '

" THERMAL POWER / Core Flow Stability Regions." Alternatively, with on1 ecirculation loop in operation, THERMAL POWER RTP, the total core flow limitations 6 3-1nust be-d ove must be met, modifications to the required identifi APLHGR limits (LC0 3.2.1, " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APlHGR)"), MCPR limits (LCO 3.2.2, " MINIMUM (continued)

RIVER BEND B 3.4 3 Revision No. O 2

Recirculation loops Operating B 3.4.1 BASES ACTIONS A.1 (continued)

Alternatively, if the single loop requirements of the LC0 are applied to operating limits and RPS setpoints, operation with only one recirculation loop would satisfy the requirements of the LC0 and the initial conditions of the accident sequence. I The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Completion Time is based on the low probability of an accident occurring during this time period, on a reasonable time to complete the Required Action, and on l frequent core monitoring by operators allowing abrupt changes in t. ore flow conditions to be quickly detected.

- l B.1 m re4N/s

~ )

Should a LOCAj, occur with THERMAL POWER > W%'RTP, during l single by th , loo operation analyses.theTherefore, core response may not be bounded l only 4l imited time is j SMGy WTTowed'to reduce THERMAL POWER to s M% RTP.

  1. y g3 The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on ht ow probability of an accident occuring during this time period, on a reasonable time to complete the Required Action, and on frequent core monitoring by operators allowing changes in THERMAL POWER to be quickly detected. I C.I. D.l. and E.1 Due to thermal hydraulic stability concerns, operation of i the plant is divided into three regions based on THERMAL l POWER and core flows. Region III is a power / flow ratio with core flow < 39% of the rated core flow. Region II is a power / flow ratio with core flow 2: 39% and < 45% of the rated core flow. Deliberate entry into Region III is not permitted, and if it occurs, immediate action is required to exit the region within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by reducing THERMAL POWER through control rod insertion or by increasing recirculation loop flow by opening the flow control valve. Operation in Region II is also more susceptible to instability than normal operating parameters. However, operation in this

, region is allowed with the exception that if evidence of (continuedl RIVER BEND B 3.4-5 Revision No. 1 J

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s ATTACHMENT 4 l NEDC-32611P -

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Note: this document provides the proprietary portions of the aforementioned request, General l Electric Report NEDC-32611P. EOI requests that this attachment be held proprietary in

accordance with 10 CFR 2.790(b) for the reasons stated in the attached General Electric affidavit.

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, General Electric Company 4

AFFIDAVIT I, David J. Roban, being duly swom, depor,e and state as follows:

(1) I am Licensing Services Manager, General Electric Company ("GE") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its

withholding.

(2) The information sought to be withheld is contained in the GE proprietary report NEDC-32611P, MAXIMUM Extended Load Line Limit Analyses for River Bend Station. (GE Company Proprietary Information), dated November 1996. The proprietary information is delineated by bars marked in the margin adjacent to the specific material.

(3) In making this application for withholding of proprietary information of which it is the owner, GE relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"),5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and 2.790(d)(1) for " trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all " confidential commercial information", and some portions also qualify under the narrower definition of" trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Fnerav Project v. Nuclear Regulatory Commission 975F2d871 (DC Cir.1992), and Public Citi7en Health Research Group

v. FDA,704F2dl280 (DC Cir.1983).

(4) Some examples of categories of information which fit ir.to the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention ofits use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies;
b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; IUl3/93RTH Affidavit Page i

i j c. Information which reveals cost or price information, production capacities, j budget levels, or commercial strategies of General Electric, its customers, or its suppliers; i d. Information which reveals aspects of past, present, or future General Electric

customer-funded development plans and programs, of potential commercial J

value to General Electric;

} e. Information which discloses patentable subject matter for which it may be

{ desirable to obtain patent protection. 2 4  !

! The information sought to be withheld is considered to be proprietary for the reasons I set forth in both paragraphs (4)a. and (4)b., above. ,

i i (5) The information sought to be withheld is being submitted to NRC in confidence.

l The information is of a sort customarily held in confidence by GE, and is in fact so  ;

held. The information sought to be withheld has, to the best of my knowledge and  !
belief, consistently been held in confidence by GE, no public disclosure has been l made, and it is not available in public sources. All disclosures to third parties I i including any required transmittals to NRC, have been made, or must be made,  ;

pursuant to regulatory provisions or proprietary agreements which provide for

, maintenance of the information in confidence. Its initial designation as proprietary

information, and the subsequent steps taken to prevent its unauthorized disclosure, j are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value l and sensitivity of the information in relation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis.

J (7) The procedure for approval of extemal release of such a document typically requires i review by the staff manager, project manager, principal scientist or otber equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

12/13HRTH Affidavit Page 2

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(8) The infonnation identified in paragraph (2), above, is classified as proprietary l because it contains detailed results of analytical models, methods and processes,  !

including computer codes, which GE has developed, obtained NRC approval of, and 1 applied to perform evaluations ofinstrument setpoints for BWR's.

The development and approval of the BWR setpoint methodology was achieved at a significant cost, on the order of a million dollars, to GE.

The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GE asset.

(9) Public disclosure of the information sought to be withheld is likely to cause ,

substantial harm to GE's competitive position and foreclose or reduce the availability .

of profit-making opportunities. The infonnation is part of GE's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development i of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses - I done with NRC-approved methods. j The research, development, engineering, analytical and NRC review costs comprise 1 a substantial investment of time and money by GE.

The precise value of the expertise to devise an evaluation process and apply the i correct analytical methodology is difficult to quantify, but it clearly is substantial.

GE's competitive advantage will be lost if its competitors are able to use the results of the GE experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate retum on its large investment in developing these very valuable analytical tools.

Ibl3/93RTH Affidavit Page 3

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STATE OF CALIFORNIA )

) ss: 1 COUNTY OF SANTA CLARA )

David J. Robare, being duly sworn, deposes and says:

1 That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.

Executed at San Jose, California, this Ny of Mo\lEMBER 1996. ,

David J. Robare

. General Electric Company J

Subscribed and sworn before me this 93Nay of M uruk 1996.

l ,

PAutA r. sussey ccm eiomim I

3 g NWW Mc - Co8fono ,. qf SANTA CLARA COUNTY

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wcomm. Ee osc i.io9eNotary f Public, State of Califordia 4

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ivi3/93Rm Affidavit Page 4

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