ML20076G404

Forwards marked-up Tech Specs Re Ac/Dc Sources,Single Loop Recirculation & Max Critical Power Ratio Operating Limit W/O EOC-RPT,per Telcon Requests

ML20076G404
Person / Time
Site:	LaSalle
Issue date:	08/23/1983
From:	Schroeder C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
7187N, NUDOCS 8308310249
Download: ML20076G404 (7)

Text

"

/^'N Commonwealth Edison i

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) One First Nationil Piva, Chicago, Illinoj_s i(O 7 Address Reply to: Post Offica Box 767 j Chicago, Illinois 60690 August 23, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 2 C.",5 5

Subject:

LaSalle County Station Unit 2 Specific Requests for Unit 2 Technical Specifications NRC Docket No. 50-374

Dear Mr. Denton:

During recent telecons with Mr. D. Hoffman and others of your staff regarding Unit 2 Technical Specifications, it was stated that the licensee should docket certain technical information related to our discussions.

Enclosed please find the following technical packages:

1.

AC/DC Sources Required in Unit 1 for Unit 2 Operation.

2.

Single Loop Recirculation Unit 2 Technical Specifications.

3.

MCPR Operating Limit Without EOC-RPT Unit 2 Technical Specification.

To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.

In some respects these statements are not based on my personal knowledge but upon infor-mation furnished by other Commonwealth Edison and contractor employees.

Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

Enclosed please find one signed original and forty (40) copies of this letter and the enclosures.

If there are any further questions in this matter, please contact this office.

Very truly yours, C. W. Schroeder Nuclear Licensing Administrator 1m D@l cc:

Don Hoffman/l Fed. Express NRC Resident Inspector - LSCS

/P 8308310249 830823 7187N PDR ADOCK 05000374 P

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SUBJECT:

AC/DC sources required in Unit I for Unit 2 operation.

REFERENCE Unit 2 Technical Specification pages 3/4 8-10, 3/4 8-14, 3/4 8-15, 3/4 8-17 BACKGROUND The Draft Technical Specification pages for LaSalle County Station Unit 2 listed in the references contain AC and DC power supplies for Division 1 of Unit 1 which do not supply any power requirements to Unit 2 required equipment.

DISCUSSION On the referenced pages the following Unit 1 electrical distribution buses are not required to supply power to any Unit 2 required equipment:

480 volt bus 135X.

480 volt McC's 135X-2 and 135X-3 120 volt A.C. distribution panels in 480 volt MCC's 135X-2 and 135X-3.

125 volt battery 1A 125 volt battery charger IA 125 volt distribution panel 111Y The only required Unit 1 division 1 power source is 4160 volt bus 141Y which can supply a second source of off site AC power through the unit cross tie breakers if manually aligned.

The above required equipment need not be operable per Technical Specification requirements to perform this function.

We therefore request that these changes be incorporated in the LaSalle County Station Unit 2 Technical Specifications prior to the issuance of the operating license, r

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q-ELECTRICAL POWER SYSTEMS dji 3/4,8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. distribution system electrical divisions shall be OPERABLE and energized:

a.

Division 1, consisting of; 1.

4160 volt bus 241Y.

2.

480 volt buses 235X and 235Y.

3.

480 volt MCC's 235X-1, 235X-2, 235X-3, 235Y-1 and 235Y-2.

4.

120 volt A.C. distribution panels in 480 volt MCCs 235X-1, 235X-2, 235X-3 and 235Y-1.

b.

Division 2, consisting of; 1.

4160 volt bus 242Y.

2.

480 volt buses 236X and 236Y.

3.

480 volt MCC's 236X-1, 236X-2, 236X-3, 236Y-1 and 236Y-2.

4.

120 volt A.C. distribution panels in 480 volt MCCs 236X-1,

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236X-2, 236X-3 and 236Y-2.

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c.

Division 3,. consisting of;

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1.

4160 volt bus 243.

2.

480 volt MCC 243-1.

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3.

120 voit A.C.' distribution panels'in 480 volt MCC 243-1.

d.

Unit 1 Division 1, consisting of;

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1.

4160 volt bus 141Y.

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45;.w; L Los liin.

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4.

'20,wl;-A.C. a;c.i a tivu peneia in 400 wit "~C'; 13?v-9 = rid 135 3.

e.

Unit 1 Division 2, consisting of;

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1.

4160 volt bus /42Y.

2.

480 volt buses 136X and 136Y.

3.

480 volt MCC's 136X-1, 136X-2, 136X-3, 136Y-1, and 136Y-2.

4.

120 volt A.C. distribution panels in 480 volt MCC's 136X-1, 136X-2, 136X-3, and 136Y-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

4 LASALLE-dNIT2 3/4 8-10 I

3 i

ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR ODERATION 3.8.2.3 The following D.C. distribution system' electrical divisions shall be OPERABLE and energized:

a.

Division 1, consisting of;

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125 volt battery 2A.

2.

125 volt full capacity charger.

. 3.

125 volt distribution panel 211Y.

l b.

Division 2, consisting of; I

1.

125 volt battery 28.

2.

125 volt full capacity charger.

i 3.

125 volt distribution pans 1,212Y.

I c.

Division 3, consisting of; l

1.

125 volt battery 2C.

2.

125 volt full capacity charger.- 5 l

3.

125 volt distribution panel 213.H 2

1-CiVTsion 1, consisting of; ; Z ',

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ACTION:

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c With either Division 1 or Division I in' operable or not energized,'

a.

restore the inoperable division-to OPERABLE and energized status '

a within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within the next 5

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With Division 3 inoperable or not energized, declare the HPCS' l

system inoperable and take the ACTION required by Specification 3.5.1.

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ELECTRICAL POWER SYSTEMS U

LIMITING CONDITION FOR OPERATION (Continued)

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ACTION:

(Continued)-

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With either "ai.

'. Oie !s:v.. ee Unit 1 Division 2 inoperable or e

not energized, restore the inoperable _ division to OPERABLE and energized status within 7 days or be' in at least HOT' SHUTDOWN.

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..

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SURVEILLANCE REOUIRP1ENTS

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ELECTRICAL

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SURVEILLANCE REQUIREMENTS (Continued)'

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Division 2, greater than~or equal.to:

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T488.5) amperes for the first (603 seconds,7 ;;.

2)

(237.63amperesforthenextT14) minutes,-

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(177.6) amperes for the next (15) minutes,... '

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(141.6), amperes for the next (30) minutes,'andl 5) 4 54.4) amperes for the last 1180) minutes. -

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58.4T amperes for the first 1605 seconds, 1)

-(M1.13 amperes for. the next 4239-T minutes.'-

2) d)'

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battery capacity is atileast '80% of the manufacturers rating'when d :.MT4

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LA SALLE - UNIT 2 3/4~8-17 4"

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SUBJECT:

Single Loop Recirculation Unit 2 Technical Specifications

REFERENCES:

(A)

LaSalle County Station Unit 2 Potential License Conditions, letter C. W. Schroeder to A. Schwencer dated March 18, 1983 (B)

LaSalle County Station License NPF-11 Amendment Number 11, dated 12/16/82.

BACKGROUND Reference (b) granted permission for Single loop Recirculation for LaSalle County Station Unit 1.

Per reference (A)

Commonwealth Edison Company Officially requested the same for LaSalle County Station Unit 2.

DISCUSSION Single Loop Recirculation is acceptable as provided by the safety evaluation for reference (b) and should be incorporated into the Technical Specifications 3.4.1.1 for LaSalle Unit 2.

We therefore request that these changes be incorporated in the LaSalle County Station Unit 2 Technical Specifications prior to issuance of the operating license.

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i fo UNITED STATES I9 UF]

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g NUCLEAR REGULATORY COMMISSION i

y WASHINGTON. D. C. 205b5 e

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DEC 161982 Docket No. 50-373 Mr. Louis 0. DelGeorge Director of Nuclear i.icensing Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690

)

Subject:

Amendment No.11 to Facility Operating License No. NPF-il - La Salle County Station, Unit No. 1 The Nuclear Regulatory Commission has issued the enclosed Amendment No.

to Facility Operating License No. NPF-ll for La Salle County Station, Unit 1.

This Amendment is in response to your letter dated December 6, 1982, and authorizes operation at La Salle County Station, Unit I with one recirculation loop out of service. This single recirculation loop operation is granted for only the first fuel cycle and only up to 50 percent of rated power. Single loop operation at 50 percent of rated power at Browns Ferry, Unit 1 and several other plants, has shown acceptable flow and power characteristics. Although analyses indicate that operation above 50 percent power with one recirculation loop may be safe, the experience at Browns Ferry Unit I has caused concern about flow and power oscillations at such power levels.

The staff, therefore, may require additional information in this area of stability for approval for single recirculation loop operation beyond the first cycle.

It is important to note that the enclosed Amendment adds a license condition requiring a power level reduction and reduced safety system settings to provide an equivalent level of safety for operation with one recirculation loop out of service.

A copy of the related safety evaluation supporting Amendment No.11 to Facility Oper'ating License NPF-11 is enclosed. Also enclosed is a copy of a related notice which has been forwarded to the Office of the Federal Register for publi-cation.

Sincerely, 0*

On u

Darrell G. Eisenhut ector Division of Licensing Office of Nuclear Reactor Regulation l

Enclasures:

1.

Amendment No. 11 to NPF-11 r

2.

Safety Evaluation Report 3.

Federal Register notice cc w/ enclosures:

l See next page b OdOdd

- c' e

f La Salle Mr. Louis 0. DelGeor'ge Director of Nuclear Licensing Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 cc:

Philip P. Steptoe, Esquire Suite 4200 One First National Plaza Chicago, Illinois 60603 Dean Hansell, Esquire ge Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 William G. Guldemond, Resident Inspector La Salle, NPS, U.S.N.R.C.

P. O. Box 224 Marseilles, Illinois 61364 Chairman La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Department of Public Health Attn: Chief Division of Nuclear Safety 535 West Jefferson Springfield,. Illinois 62761 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.

20515 Chairman Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 D

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AMENDMENT NO. 11 TO LICENSE NPF-11 LA SALLE COUNTY STATION, UNIT NO. 1 DOCKET NO. 50-373

1.0 INTRODUCTION

The current La Salle County Station, Unit 1 Technical Specifications do not allow plant operation beyond 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if an idle recirculation loop cannot be returned to service. The ability to operate at reduced power with a single loop is highly desirable from an availability outage planning standpoint in the event that main-tenance or component unavailability rendered one loop inoperable.

By letter dated December 6,1982, Commonwealth Edison Company (CEC 3) (the licensee) requested changes to the Technical Specification for Single Loop Operation of La Salle, Unit 1.

The requested changes would permit Unit 1 to operate at up to 50 percent of rated power with one recirculation loop out of service for unlimited time. While analyses indicate that it may be safe to operate boiling water reactors on a single loop in the range higner than 50 percent of rated power, the experience (reference letter from L. M. Mills, TVA dated March 17, 1980 to H. Denton, NRC) at Browns Ferry, Unit 1 has caused concern about flow and power oscillations. However, because single loop operation at 50 percent of rated power at several plants, including Browns Ferry, Unit 1, has shown acceptable ficw and power characteristics, we will permit la Salle, Unit 1 to operate at power levels up to 50 percent of rated power with one loop out.of service during its initial fuel cycle. We will request from the licensee any additional information required for permanent approval for single loop opera-tion. If requested, we will also consider operation at a higher power level for La Salle with one recirculation loop out of service after the staff concerns steming from Browns Ferry, Unit 1 single loop operation, which showed unex-pected variation in jet pump flow and neutron flux at power level of 59 percent but these variations stopped when the power level was reduced, are satisfied.

2.0 EVALUATION 2.1 ' Accidents (Other than Loss of Coolant Accident (LOCA)) and Transients Affected by One Recirculation Loop out of Service i

2.1.1 One Pumo Seizure Accidents The licensee states that the one-pump seizure accident is a relatively mild event during two recirculation pump operations. Analyses were performed to determine the impact this accident would have on one recirculation pump opera-tion. These analyses were performed using NRC staff approved models. The analyses were conservatively conducted from a steady-tate operating condition of 78 percent of rated thermal power and 63 percent core flow. Pump seizure was simulated by setting the single operating pump speed to zero instantaneously.

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^ Results of the analyses indicate that neither pressure nor cladding thermal limits are exceeded during the event. Peak vessel pressure is calculated to be 1031 psig ( ASME code limit is 1375 psig) and minimum critical power ratio (MCPR) is 1.17 (safety limit is 1.06).

2.1.2 Abnormal Operational Transients The licensee discussed the effects of single loop operation on the course of abnormal operational transients. Pressurization and cold water increase events, as well as rod withdrawal error, were addressed. Flow decrease is covered by the pump seizure accident already described. The results of calculations for the limiting event for each category were also presented. Initial operating conditions were conservatively assumed to be 78 percent of rated thermal power and 63 percent core flow.

2.1.2.1 a) Pressurization Events The limiting pressurization event is the generator load rejection without bypass transient. For single loop operation, the licensee i

has calculated that the maximum vessel pressure is 1128 psig and the MCPR is 1.29.

Each of the values satisfies its respective safety limit.

b) Cold Water Increase The limiting cold water increase event is the feedwater controller failure to maximum demand transient. The reactor is assumed to be in single loop operation at conservative initial operating conditions of 78 percent of rated power and 63 percent core flow when failure of the feedwater control system instantaneously increases the feedwater flow to the runout capacity of 160 percent of rated flow. The peak pressure is calculated to be 1126 psig and the MCPR is 1.26, each satisfying its respective safety limit.

c) Rod Withdrawal Error The rod withdrawal error at rated power is given in the Final Safety Analysis Report for the initial core and in cycle dependent reload supplemental submittals. These analyses are performed to demonstrate that, even if the operator ignores all instrument indications and the alarms which could occur during the course of the transient, the rod block system will stop rod withdrawal at a minimum critical power ratio which is higher than the fuel cladding integrity safety limit. Correc-tion of the. rod block equation and lower initial power for single-loop operation in the Technical Specifications (see Section 5 of this safety l

evaluation) assures that the MCPR safety limit is not violated.

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One-pump operation results in backflow through 10 of the 20 jet pumps while flow is being supplied to the lower plenum from the active jet pumps. Because of this backflow through the inactive jet pumps, present rod-block equation and APRM settings must be modified.

2 The licensee has modified the two-pump rod block equation and average i

power range monitor (APRM) settings that exist in the Technical Specifications for one-pump operation and the staff has found them acceptable.

1 The staff finds that one loop transients and accidents other than LOCA, which is discussed below, are bounded by the two l'oop operation analyses and are therefore acceptable.

2.1.3 Minimum Critical Power Ratio (MCPR) Uncertainties _

For single-loop operation, the rated condition steady-state MCPR limit is increased by 0.01 to account for increased uncertainties in the core total flow and traversing in-core probe (TIP) readings. The MCPR will vary depending on flow conditions. This leads to the possibility of a large inadvertent flow increase which would cause the MCPR to decrease below the safety limit for a low initial MCPR at reduced flow conditions. Therefore, the required MCPR must factors for two be increased at reduced core flow by a flow factor K. The Kf f

loop operation are derived assuming both recirculation loop controllers fail.

This condition of both recirculation loop controllers failing maximizes the power increase and hence bounds the maximum delta MCPR for single loop opera-tion transients. When operating on one loop, the flow and power increase will' be less than that associated with two loops at full flow. The Kf factors derived from the two-loop assumptions are therefore conservative for single loop operation.

2.2 Loss of Coolant Accident (LOCA) i The licensce has performed analyses of a spectrum of recirculation suction line breaks under single loop operation conditions. The licensee states that evaluation of these calculations which are performed according to the procedure outlined in NE00-20556-2, Rev.1, " General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50 Appendix K - Amendment No. 2 One Recirculation Loop out of Service," indicates that a multiplier of 0.87 should be applied to the maximum average planar linear heat generation rate (MAPLHGR) limits for single loop operation of La Salle, Unit 1.

Other plants using 8 x 8R fuel have been required to use a reduction factor of 0.85.

We require that La Salle, Unit i likewise reduce its MAPLHGR by 0.85.

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i a 3.0 THERMAL HYDRAULICS The licensee has confirmed that analysis uncertainties are independent of whether flow is provided by two loops or a single loop. The only exceptions to this are core total flow and TIP reading. The effect of these uncertainties is an increase in the MCPR by.01, which is more than offset by the Kf factor required at low flows. The steady state operating MCPR with single-loop operation will be con-servatively established by multiplying the rated flow MCPR limit by the Kf factor.

4.0 STABILITY ANALYSIS As indicated in the applicant's submittal, operating along the minimum forced recirculation line with one pump running at minimum speed is more stable than operating with both pumps operating at minimum speed.

The licensee will be required to operate in master manual to reduce the effects of instabilities due to controller feedback. The staff has accepted previous stability analyses results as evidence that the core can be operated safely while our generic evaluation of boiling water reactor stability characteristics and analysis methods continues. The previous stability analysis results include natural circulation conditions and thus bound the single loop operation. In addition, the decay ratio (0.50) predicted for initial cycle for Unit i shows margin relative to Browns Ferry, Unit 1 (.83) which had the flow noise oscilla-tions during single recirculation loop operation. We conclude that with appro-priate limitations to recognize and avoid operating instabilities, that the reactor can be operated safely in the single loop mode. Our evaluation of the flow / power oscillations evidenced in Browns Ferry will continue and any pertinent conclusions resulting from this study will be aoplied to La Salle, Unit 1.

5.0

SUMMARY

ON SINGLE LOOP OPERATION 5.1 Steady State Thermal Power Level will not exceed 50 percent of Rated Pcwer Operating at 50 percent of rated power with appropriate Technical Specifi-cation (TS) changes has been approved on a cycle basis for several operating plants. It is concluded for La Salle, Unit 1 that for operation at 50 percent of rated power, consistent with the provisions of item h below, that transi-ent and accident bounds will not be exceeded.

5.2 Minimum Critical Power Ratio (MCPR) Safety Limit Will Be Increased by 0.01 to 1.07 The MCPR Safety Limit will be increased by 0.01 to account for increased (TIP) readings. The licensee has determined that the change conservatively bounds the uncertainties introduced by single loop operation.

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5.3 Minimum Critical Power Ratio (MCPR) Limiting Condition for Operation (Lcol will be increased by 0.01 The staff requires that the operating limit MCPR be increased by 0.01 factors that are in the and multiplied by the appropriate two loop Kf La Salle, Unit 1 TS. This will preclude an inadvertent flow increase from causing the MCPR to drop below the safety limit MCPR.

5.4 The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Limtis will be Reduced by Appropriate _MultiDliers The licensee proposed reducing the TS MAPLHGR by 0.87 for Single Loop Operation. These reductions were based on an analysis method proposed by General Electric in NEDE-20566-2. We require a reduction factor of 0.85 consistent with previous single recirculation loop operation approvals for plants with 8 x 8R fuel. This change has been discussed with and agreed to by licensee.

5.5 The APRM Scram and Rod Block Setooirts will be Reduced The licensee proposed to modify the two loop APRM Scram, Rod Block and Rod Block Monitor (RBM) setpoints to account for back flow through half the jet pumps. These setpoint equations will be changed in the La Salle, Unit 1 TS. The above changes are similar to other plant TS changes and are acceptable to the staff.

5.6 The Recirculation Control will be in Manual Control The staff requires that the licensee operate the recirculation system in the manual mode to eliminate the need for control system analyses and to reduce the effects of potential flow instabilities.

5.7-Surveillance Reouirements The staff requires that the licenee perform daily surveillance on the jet pumps to ensure that the pressure drop for one jet pump in a loop does not vary from the mean of all jet pumps in that loop by more than 5 percent.

5.8 Provisions to Allow Operation with One Recirculation Loop Out of l

Service l

a.

The steady-state thermal power level will not exceed 50 percent of rated power.

b.

The Minimum Critical Power Ratio (MCPR) Safety Limit will be increased by.01 to 1.07.

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c.

The MCPR Limiting Condition for Operation (LCO) will be increased by 0.01.

d.

The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Limit will be reduced by 0.85.

e.

Technical Specification Setpoints shall read as follows:

T. S. 2.2.1 S<

0.66W + 45.7 (Trip Setooint)

Si 0.66W + 48.7 (Allowable)

T. S. 3.2.2 S4 (0.66W + 45.7) T*

Sg (0.66W + 36.7) T*

RB T* as defined in T. S. 3.2.2 T. S. 3.3.6 APRM Upscale 4 0.66W + 36.7 (Trip Setpoint) 7 0.66W + 39.7 (Allowable)

RBM Upscale 2 0.66W + 34.7 (Trip Setpoi7t) 2_ 0.66W + 37.7 (Allowable) f.

APRM flux noise will be measured once per shift; and the recircula-tica loop flow will be reduced if the flux noise average over 1/2 hour exceeds 5 percent peak to peak, as measured by the APRM chart recorder.

g.

The core plate delta P noise be measured once per shift, and the recirculation loop flow will be reduced if the noise exceeds 1 psi peak-to-peak.

6.0 AUTHORIZATION FOR SINGLE LOOP OPERATION FOR FUEL CYCLE 1 Based upon the above evaluation and a history of successful operation of other boiling water reactors, we conclude that single loop operation of La Salle, Unit 1 up to a power level of 50 percent and in accordance with the proposed Technical Specification changes, will not exceed the accident and transient bounds previously found acceptable by the NRC staff and is therefore acceptable.

The approval for single loop operation up to power level of 50 percent is authorized during cycle 1 until the staff concerns stemming from Browns Ferry, Unit I single loop operation are satisfied.

7.0 ENVIRONMENTAL CONSIDERATION

We have determined that this Amendment does not authorize a change in effluent types of total amount nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that this Amendment involves action which is insignificant from the standpoint of environmental impact, and, pursuant to 10 CFR Section 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this statement.

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8.0 CONCLUSION

We have concluded, based on the considerations discussed above, that; (1) because the Amendment does not involve a significant increase in the probability or consequences or accidents previbusly considered, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant decrease in a safety margin, the Amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and (3) such activities wil1 be conducted in compliance with the Commission's regulations and the issuance of this Amendment will not be inimical to the common defense and security or to the health and safety of the public.

DEC 161962 Date:

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[7590-01]

UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET-NO. 50-373 COMMONWEALTH-EDISON COMPANY NOTICE-OF-ISSUANCE OF AMENDMENT OF FACILITY 0PERATING-LICENSE The U. S. Nuclear Regulatory Comissior. (the Comission) has issued knendment No.11 to Facility Operating License No. NPF-11, issued to Comon-wealth Edison Company, which adds License Condition 2.C.(34) for operation of the La Salle County Station, Unit No.1 (the facility) located in Brookfield Township, La Salle County, Illinois.

The Amendment authorizes the operation of La Salle County Station, Unit 1 with one recirculation loop out of service for the first fuel cycle only. Al so, the Amendment adds a license condition limiting a power level to 50 percent of full power or less during the operation with one recirculation loop out of service.

The application for amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.. Prior public notice of this Amendment was not required since the Amendment does not involve a significant hazards consideration.

The Comission has determined that the issuance of this Amendment will not result in any significant environmental impact ed that pursuant to 10 CFR

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Section 51.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with I

issuance of this Amendment.

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For further details with respect to thls action, see (1) the application for amendment dated December 6, 1982; (2) Amendment No.11 to License No. NPF-11 dated December 16,1982; and (3) the Commission's related safety evaluation. All of these items are available for public inspection at the Commission's Public Document Room located at 1717 H Street, NW, Washington, DC '20555, and the Public Library of Illinois Valley Community College, Rural Route No.1, Ogelsby, Illinois 61348. A copy of items (1), (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Director, Division of Licensing.

Dated at Bethesda, Maryland, this 16th day of December 1982.

FOR THE NU EAR REGULATORY COMMISSION f(gt vel %

i A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing 9

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SUBJECT:

MCPR Operating Limit without E0C-RPT Unit 2 Technical Specification

REFERENCES:

(A)

Letter from General Electric - MCPR Operating limit without E0C-RPT dated December 14, 1981.

(B)

NUREG - 0123 Standard Technical Specifications for General Electric (BWR/5).

BACKGROUND Reference (b) provides for a minimum Critical Power Ratio (MCPR) Technical Specification Limiting Condition for Operation that allows a revised MCPR operating limit if E0C-RPT is inoperable.

DISCUSSION Reference (A) provides the required data to allow the Technical Specifications to be revised to allow operation with EOC-RPT inoperable if the MCPR operating limit is changed. Attached pages 3/4 2-4, 3/4 2-5, and 3/4 3-39 include the revised Unit 2 Technical Specification changes which are necessary to accomplish this. These changes are similar to corresponding pages in reference (b).

We therefore request that these changes be incorporated in the LaSalle County Station Unit 2 Technical Specifications prior to the issuance of the operating license.

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i Decesoer 14, 1981 Mr. G. R. Crara Cc=onwealth Edison Corgany P.O. Box 767 Chicago, IL CG90

Dear Hr. Crane:

SU3 JECT:

LASAlif COUhTY STATION UNITS 1 & 2 MC?R OPERATING LIMIT WITHOUT EOC-RPT Per your reouest, the HCPR operating limit without EOC-RPT has been calculated for La hlle Unit 1.

The results of this evaluation are 7

sumarized below and on the attached gr@h.

Please note that the load rejection without bypass transient sets the limit at Optier. A and the feed <ater controller failure sets the limit at Option B.

The limit at scram times between the two options must be determined from the graph.

MCPR-Operatino Limit Transient Event ODtion A ODtion B Load Rejection without Bypass without EOC-RPT 1.37 1.25 Feednter Controlier Fai1ure vithout EDC-RPT 1.33 1.25 If you should any questions regarding the above or the attached, please feel free to call us.

Very truly youry, ff f.# /

bec: H. E. Urata, w/att

.R.Peffg,ProjectManager J. R. Pallette, v/att LaSalle C66nty Station Units 1 & 2

w. L. Ho, w/att HRP: ggt /794 Attachment cc:

K. J. Brown, w/att T. E. Watts, w/o att D. C. Haan, w/o att.

P. B. Kavanagh, w/o att B. R. Shelt %.w/o att R. E. Spencer, w/o att DBL /PT/CTK

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ff POWER DISTRIBUTION LIMITS ia

.t.

' ([

~V P'CWEkDI'5TRIBUTIONLIMITS

.1 =

-I.'.. f. ". c,._", @s.,c. w...

o MINIMUM CRITICAL POWER RATIO..._9-Si_c.:.. : ; f..- -

-.. u-w?.

~

.c 3/A.2.3

.=: :

.' E : : -

LIMITING CONDITION F03 OPERATION s

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater.-.

3.2.3 than the MCPR limit deter =ined from Figure 3.2.3-1 times the K ' determined '. s f

Figure 3.2.3-2/ pro 6 4., A 4 d 4.k s-6c.- E PT sys4es is opav Abl9 [--Ec -

a fro:

\\.

Spec; Civ 4;oa 5. S, %.K 8

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 5~

2E% of RATED THERMAL POWER.

ACTION r;,er4 e With MCPR less than th icable MCPR limit determined from Figures 3.2.3-1 p,gy.kd and 3.2.3-2, initiate correc. e action within 15 minutes and restore MCPR to N within the recuirec li=it within hours or reduce THERMAL POWER to less than

~

2.E% of RATED THERMAL POWER within thesext 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

r-I SURVEILLANCE REOUIREMENTS

~~~

- ' ~'-

4.2.3 MCPR, with:

0.85 prior to performance of th'e initial scram time. measurements -

for the cycle in accordance with Specification 4.'1.3.2, or

33. -f.

T

=

a ave

. :.c.c.

.. u. ~

of each scram time....

determined within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusic.

.m....

.x....

b.

I surveillance test required by Specification 4.1.3.2,

.QS -;.?.

?. :~ " -

ave M-+ : zi

?...:.

~'

shall be determined to be equal to or greate'r'.'.than the applicable. MCPR limitfG' 1.~

y

.?.

r.3 " '..

deter =ined fro: Figures 3.2.3-1 and 3.2.3-2:

-%-6.=_

..,... =.. g..,

n.

At 1 east once per 24. hours, Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of.

b.

at least 1E% of RATED 'QiERMAL POWER, and Initially and at least once per 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> when the reactor is ~ operating. -'

t.i.~

c.

with a LIMITING CONTROL RCD PAii:RN for MCPR.

e P.

[ ( ;..

'.,7

~ - -

y 3/4 2-4 LA SALLE

. UNIT 2 g

.A-m

l l

l A.

With the end-of-cycie recirculation pump trip system inoperable per Specification 3.3.4.2, operation may continue and the provisions of Specification 3.0.4 are not applicable provided that, within one hour, MCPR is determined to be equal to or greater than the MCPR limit shown in Figure 3 2.3-1 E0C-RPT inoperabie curve, times the K shown in Figure 3.2.3-2.

g B.

With MCPR less than the applicable MCPR limit shown in Figures 3.2.3-1 and 3.2.3-2, initiate corrective action within 15 minutes and restore MCPR to within the required limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4

hours, t

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.= _

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3 INSTRUMENTATJON

,....:q r w:...c...

73. _ :.

.py;

\\

..'."...-e-END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.

.g.:; :.

-% ;.gh:M

+.

r.

w..--. ~-

. ~. 2;--f~: ~

-M. L 3 9:.-h:.h ;h -

TC N S

LIMITING CONDITI N FOR OPERATION

... "3 -

-. v

-y 7-3.3.4.2 The end-o.-cycle recirculation puma trip (EOC-RPT)' system instrumenta"^ ~ N tionchannelsshownhinTable3.3.4.2-1shallbeOPERABLEwiththeirtrip

~

setpoints. set consistent with the values shcwn in the Trip 5etpoin colu=n of._

Table 3.3.4.2-2 and 4th the RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4. -3.

APPLICABILITY:

OPERATI NAL CONDITION 1, when THE??AL POWER is greater than er equal to 30% of PATED THE PAL POWER.

s ACTION:

Vith an end-of-cycje recirculation pt:p trip system instrumentation a.

channel trip setacipt less conservative than the value shown in the Allowable Values col"-.n of Table 3.3.4.2-2, declare the channel

~

inocerable until the -hannel is restored to OPERA 3LE status with the cha'nnel setpoint adjusted consistant with the Trip 5et' point value.

b.

With the number of OPEPqELE channel,s one less than required by the Mini== OPERABLE Channel (per Trip System requirement for one or

..~

both trip syste:s, place 5e inoperable _ channel (s) in the tripped ;p

- _ ~ ~ ~ ~

t condition within one hour.

- 4_.

z..

~

c.. With the nu=ber-of OPERABLE channels two or more less than required M F.

by the Mini =um OPERABLE'Chan els per Trip Syste.m requirement (s) forme.

2

.Q.

.,.,.. ; ]..

Gi one trip. system and.

~

. m.

~Q..

P'-

1.

If the inoperable channel consist of one tu'rbine control val.ve. -.

~

channel and one turbine st valve channel, place both inoperable

~

~"

1. .^

channels in the tripped con ition within one hour.. af_.

TN

-~=

l+C.c.;y f-[K J _.

e.~

2..

If the inoperable channels inglude two turbine control valve.>> -

~

~

channels or tvc turbine stop v ive. channels, declare the

• rip '

~

system inoperable.

. U.'

• p.

d.

With one trip systeminoperable, res* re the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or educe THERMAL POWER to less -

than 3C% of RATED THEPyAL POVER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. "

~,

e at 'least one trip system

~

y.

e.

With both trip syste=s inoperable, res to OPERABLE status within one hour or te uce THERMAL POWER to less i than 3C% of RATED THEP?AL POWER within th next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />..

l t

(

LA SALL5 - UNIT 2.

3/4 3-39 l

-.T

^

r INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION 10R OPERATION s.s.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown.in the Trip 5etpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 90)% of RATED THERMAL POWER.

ACTION:

With.an end-of-cycle recirculation pump trip system instrumentation a.

channel trip setpoint. less conservative than the value shown in the Allowable Values column of Table 3.3.4.2-2, declare the' channel inoperable until the chann'el is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of 0?ERABLE channils one less than required by the

~

6 Minimum OPERAELE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.

c.

With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

l.

If.the inoperable channels consist of one turbine centrol valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within one hour.

2.

If the inoperable channels include two turbine control valve channels or two. turbine stop valve channels, declare the trip system inoperable.

d.

With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or ftake the ACTION required by Speci fication 3.2. 39 -(-^' '- ":Pm W:D '- '~ "- ' " '

c c~ D 'MEP'".'. T.l:: sit P th: rt c "-" e) -

With both trip systems inoperable, restore at least one trip system e.

to OPERABLE status within one hour or (take the ACTION required by

'a 'm

n (30)% ofi Specification 3.2.3f --( e""ce WEN 1 00'2 D 2* ED THEP?"'. ?:"J:2 within the ncy'_ c '-rs).

b 4 E-ST: (:W:/~,;

3/4 3-39 amu.a -vu vr a.

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