ML20090G651
| ML20090G651 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Brunswick |
| Issue date: | 10/05/1983 |
| From: | Mackay S NRC |
| To: | |
| Shared Package | |
| ML17139C189 | List:
|
| References | |
| FOIA-84-105 NUDOCS 8310210373 | |
| Download: ML20090G651 (4) | |
Text
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Att tiOTICIriG A~ TION i
N Units 1 and 2 50-325 and 50-324 73cj)j y Socxe-ri:.
. Cai6 Tina Poser & Light Co. ~..
Cate of application: June 3,1982 Licensee:
Reques: for:
i (See attached.)
Initial Dete-mination:
(
) Proocsed determination - amendment reque:: involves no significant hazards consiaerations (NSHC).
(XX) Final decemination_ - amendment request involves sicnificant ha ards
- ensiderations (SHC).
Basis fer Dete-mination
(
) Licensee's liSHC discussion has been reviewed and is acceoted.
See attached amen ment request.
- XX) Basis for this determina-ion is presented in the attached.
(
) Other (state):
( A::ach. additional sheets as needed.)
Initial Noticine A:: ion:
(Attach appropriate notice or input for monthly FRfi) 1.
(
) Monthlv FRN.
Notice of opportunity for hearing (30 days) and request 1
for comments on proposed NSHC determination - monthly FRN input is I
attached (Attachment 8).*
1 2.
(
) Individual FR:i (30 days).
Same notice matter as above.
Time does not
~ ailow waiting for next monthly FRN (A::achments 9a and 95).
i (THIS FORM SH"ULD 5E TYPEC EXCE?T.FOR UNUSUAL, URGENT CIRCUMSTANCES.)
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Request for:
' The amenament would change the Technical Specifications to incorporate revised safety and operating limits associated with the operation of Brunswick Steam Electric Plant, Units 1 and 2 with one recirculation loop out of service. The changes propo' sed' by ~ the licensee would provide for reduced Average Power Range Monitor ( APRM) flux scram trip and rod block settings, an increase in the safety limit Minimum Critical Power Ratio (MCPR) value and revisions to the allowable Faximum Average Planar Linear Heat Generation Rate (MAPLHGR) values suitable for use with an idle recirculation loop. Presently the Brunswick Technical Specifications would require plant shutdown if an idle recirculation loop cannot be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The amendment would authorize the plant to cperate up to 50% of rated power for extended periods of time.
Supporting the amendment request, is a report pre-pared by General Electric that presents tne analysis for core performance.
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f the standards for Basis.for:
i The Commission has provided guidance for the applicat on o significant hazards consideration exists by providin One such amendment involves a relief
~ detennining whether aexamples of amendments that are considered not from an operating restric-hazards consideration (48 FR 14870).
i granted upon demonstration of acceptable operat ontion was not yet ia to be applied tion that was imposed because acceptable operai This assumes that the operating restriction and the cr terrior review to a request for relief have been established in a p been met.
lant shutdown if i
The ~ Brunswick Technical Specifi ations presently requ re p ice within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
an idle recirculation loop cannot be returned to serv i
existed to This restriction was imposed because insufficient informat onith a enable the staff to establish criteria for operation wAlthou d analyses have indicated that it should be safe to operate Boi i
perience with an tion loop.
on 'a single loop in the range of 85% power, opera 1979 raised concerns about authorizing single loop operation for BWRs. A t 59% of rated power while operating on a single loop, unexcecte Ne.ither the causes flow, neutron flux, and related parameters were noted.been determin nor the potential effects of tnese variations have Thus, it has not l tion loop.
by the staff for operation with a single recircu abeen i
for operation with a The application for snendment involves chan single loop have been mat.
ificant hazards consideration.
which do not satisfy the criteria of the appi which would likely ce found not to involve s gn lication for Therefore, tne staff has made a determination that the app i
amendment may involve a significant hazards considerat on.
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nLOP 228, Rev. 1 3.
(
) Local media notice.
Valid exigent circumstances exist (evaluated below).
Local media notice requesting public comments on proposed '{SHC determination is attached (Attachment 10).
4.
(
) No notice.
A valid emergency situation exists (evaluated below) and i!
there is no time for public notice on proposed NSHC determination.
(No attachment.)
5.
(
) Individual FRN (30-days).
Licensee's cit im of exigent or emergency ii circumstance: is invalid (evaluated below).
Notice of opportunity for hearing (30 days) and request for comments on proposed NSHC determina-l tion is attached (Attachments 9a and 9b).
Letter of explanation to licensee is also attached.
6.
(X) Individual FRN (30-davs).
The amendment request involves SHC.
No tice
[,
of opportunity for prior hearing is attached (Attachment 5).
Letter to licensee also attached.
7.
(
) Individual Short FRN.
Valid emergency circumstances exist (evaluated below).
There is no time for the usual 30-day FRN.
( Attachment 16).
Evaluation of exigent or emergency circumstances (if applicable):
(attach additional sheets as needed)
(
Accrovals:
Date 1.
4 AM 27,/9 6 (Pro echMan' age 2.
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Additional accroval (.or noticing actions types 3, 4, 5, 5 and 7):
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\\c-\\r\\.;3 (Assistant Director)
Additional aceroval (for noticing action types 4 and 5):
i m.
(Director, Division of Licensing)
Attachment:
as indicated Original - Docket File (with note " Docket File only")
cc:
Project Manager Licensing Assistant i
Branch Files 4
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JIp uruq'e UNITED STATES s
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NUCLEAR REGULATORY COMMISSION E, g e [l WASHINGTON, D. C. 20555 h
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h MEMORANDUM FOR: TCMainisi[ Assistant Director "f6E0Teia~tingReactors,DL FROM:
L. S. Rubenstein, Assistant Director for Core and Plant Systems, DSI
SUBJECT:
SLO OPERATION SER'S As discussed in our meeting of January 26, we are withdrawing our SER approvals for all the plants currently requesting pennanent SLO.
This decision is based on new data which indicates the potential for local thennal hydraulic instabilities which would not be detected by only monitoring APRM fluv noise, which we previously recommended.
He are continuing to evaluate this problem and expect to establish c'riteria for acceptable SLO in the near future.
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L. S. Rubenstein, As#Etant Director s
for Core and Plant ; Systems, DSI cc:
R. Mattsen D. Eisenhut L. Phillips R. Label
Contact:
G. Schwenk, CPB:DSI X-29421 Mme -
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it, NUCLEAR REGULATORY COfAMISSION I h")%
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DEC 161332 Cocket N3. 50-373 e
Mr. Louis 0. De1 George Director of Nuclear Licensing Ccamenwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Cear Mr. DelGeorge:
Suoject:
Amendment No. 11 to Facility Operating License No. NPF-ll - La Salle County Station, Unit No. 1 The Nuclear Regulatory Comissica has issued tne enclosec Amancment No.
to Facility Operating License No. NPF-il for La Salle County Station, Unit 1.
This Amendnent is in response to ycur letter catec December 6,19E2, and authorizes cperaticn at la Salle County Station, Unit I with one recirculation icoc out of service.
This single recirculation loop coeratien is granted for only the first fuel cycle and only up to 50 percent of rated pcwer.
Single icop operation at 50 carcent of rated pcwer at Browns Ferry, Unit 1 and several cther plants, has shown acceptable ficw ard power characteristics.
Althougn analyses indicate tnat operation above 50 percent power witn ene recirculaticn loop may be safe, the experience at Browns Ferry Unit I has caused concern about flow and power oscillations at such pcwer levels.
The staff, therefore, may require additional iiformation in this area of stability for approval for single recirculation loop cperation beyond the first cycle.
It is important to note that the enclosed Amendment adds a license Condition requiring a pcwer level reduction and reduced safety system settings to orovide an ecuivalent level of safety for operation with one recirculation loop out of service.
A copy of the related safety evaluation su;, porting Amendment No.11 to Facility Operating License NPF-11 is enclosed. Also enclosed is a copy of a related notice wnich has been forwarded to the Office of the Federal Register for publi-cation.
Sincerely, Pt
-Q G= w ~ k-en:rY Darrell G. Eisenhut, irector y
Division of Licensing Office of Nucler.r Reactor Regulation Encloscres:
l.
Amendment No.-11 to NPF-ll 2.
Safety Evaluation Report 3.
Federal Register notice i
cc w/ enclosures:
See next page A
thlh 4 2nu s.y 4 e 7
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.la Salle Nr. Louis 0. DelGeor'ge Director of. Nuclear Licensing Commonsealth Edison Compar.y P. O. Box 767 Chicago, Illinois 60690 cc:
Philip P. Steptoe, Esquire Suite 4200 One First Naticnal Plaza Chicago, Illinois 60603 Dean Hansell, Esquire
,e Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601
'iilliam G. Guldemond, Risident Inspector la Salle, NPS, U.S.N.R.C.
P. O. Box 224 Marseilles, Illinois $1364 Chairman La Salle County Board of Supervisors La Salle County Ccurthouse Otteaa, Illinois 61350 Att:rney General 500 South 2nd Street Springfield, Illinois 62701
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Department of Public Health Attn:
Chief, Divisica of Nuclear Safety 535 West Jefferson
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Springfiel d,, Illinci s 62761 The Ho'norable Tom Corcoran United States Heuse of Representatives
'n'a shington, D. C.
20515 Chai r. nan Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 4
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COMMONWEALTH EDISON COMPANY DOCXET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-ll Amencment No. 11 1.
The Nuclear Regulatory Comission (the Commission or the NRC) having found that:
A.
The application for arendrent filed by the Commonwealth Ediscn Car;any, dated Dececer 6,1982, complies with the standards and rauire. ents of the Atcaic Energy Act of 1954, as amended (the Act), anc the Commissicr's regulations set forth in 10 CFR Chapter I; 3.
The facility will cperate in conformity with tr.e application, tre crc-visions of the Act, and the regulations of the Cc missien; C.
There is reasonable assurance:
(i) that the activities aut..cri:ed by this Amancment can be conducted without endangering the nealth and safety of the public, and (ii) that such activities will be concucted in compliance with the Commissien's regulations; set forth in 10 CFR Chapter I; D.
The issuance of this Amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this Amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by the addition of Paragraph 2.C.(34) to the Facility Operating License No. NPF-11 to read as follows:
(34)
Through the First Fuel Cycle of Plant Oceration, Technical Scecifica-tion 3.4.1.1 is Mocified for One Recirculation Loco out of Service with Provisions (a) The steady-state thermal power level will not exceed 50 percent of rated power.
(b)
The minimum critical _pcwer ratio (MCPR) safety limit will be increased by 0.01 to 1.07.
2.a1ASAs00 g g ww a = l 2 { Q
-2 (c) The minimum critical pcwer ratio limiting condition for operation (LCO) will be increased by 0.01.
(d) The maximum average planar linear heat generation (MAPLHGR) limit will be reduced by 0.85.
(e)
Technical Specifications Setpoints shall read as follows:
T. S. 2.2.1 5 _! 0.66W + 45.7 (Trip Setpoint)
S _$ 0.66W +~48.7 (Allowable)
T. S. 3.2.2 S < (0.66W + 45.7) T*
~~
S
_f (0.66W + 36.7) T*
R8 f-T* as defined in T. S. 3.2.2 T. S. 3.3.6 APRM Upscale < 0.66W + 36.7 (Trip Setpoint)
AFRM U; scale < 0.66W + 39.7 (Allowable)
REM Ucscale 5 0.66W + 34.7 (Trip Setpoint)
RSM Upscale < 0.66W + 37.7 (Aliowable)
(f)
The average pcwer range monitor (ATRM) fiux noise will be measured once per shift; and.the recirculation loop flow will be reduced if the flux noise averaged over 1/2 hour exceeds 5 percent peak to ceak, as measured by the APRM chart recorder.
(g)
The core plate delta P noise will be measured cnce per shift, and the recirculation loop flow will be reduced if the noise exceeds one (1) psi peak-to-peak.
3.
This Amencment is effective as of the date of isst ance.
FOR THE fiUCLEAR REGULATORY COMMISSION S&&c. t--
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuanca: 0EC 1 o Usi e
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SAFETY EVALUATION AMENDMENT !;0. il TO LICENSE !;PF-11 LA SALLE COUNTY STATION, UNIT NO. 1
'0CKET NO. 50-373 1.0, INTRODUCTION The current la Salle County Station, Unit 1 Technical Specifications do not allcw 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 pcwer with a single locp is highly desirable from an availability outage planning standpoint in the event that main-tenance or ccaponent unavailability rendered one 1 cop inoperable.
By letter dated December 6,1982, Commonwealth Edison Cocpany (CECO) { the licensee) requested changes to the Technical Specification for Single Lcop Operation cf La Salle, Unit 1.
The requested changes wculd permit Unit 1 to cpe-ate at up to 50 percent of rated power with cne recirculatten loop cut of service for unlimited time. While analyses indicate that it may be safe to operate boiling water reactors en a single loop in the range higher than 50 carcent of rated pcwer, the experience (reference letter from L. M. Mills, TVA daced March 17, 1550 to H. Denton, NRC) at Brcwns Ferry, Unit 1 has caused concern abcut ficw and pcwer oscillations.
Mcwever, because single 1 cop cceration a-50 percent of rated power at several plants, including 3rewns Ferry, Unit 1, has shewn acceptable ficw and pc er characteristice, we will pemit La Salle, Unit 1 to cperate at pcwer levels up to 50 percent of rated pcwer with cne icop out of service during its initial fuel cycle.
We will request fr0 the licensee any additional information required for permanent approval for single lecp opera-tien. -If requested, we will also consider operatien at a higher cceer level for la Ealle with one recirculation loop out of service after the staff concerns stemming from Brewns Ferry, Unit 1 single loop coeration, which shewed 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 Affeccea oy One Recirculation Loco out of Service 2.1.1 One Pumo Seizure Accidents The licensee states that the one-pump sei:ure accident is a relatively mild event during two recircu'ation pump operations. Analyses were perfer:ed to determine the impact this accident would have on one. recirculation pump opera-tion. These hnalyses were performed using NRC staff approved models. The analyses were conservatively conducted frec a steady-state operating condition
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ef 73 percent of rated thermal power and 63 percent core flow. Putp seicure las simulated by setting the single operating purp 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 en the course of abnormal operational transients.
Pressurization and cold water increase events, as well as rod withdrawal error, were addressed.
F1cw 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 73 percent of rated thermal pcwer and 63 percent core flow.
2.1.2.1 a)
Pressurization Events The limiting pressurization event is the cenerator lead rejection without bypass transient.
For single loop operatien, the licensee has calculated that the maximum vessel pressure is li23 psig and the u,CPR i s 1.29.
Each of the values satisfies its respective safety limit.
b)
Cold Water Increase The limiting cold water increase event is the feed ater centro 11er failure to maximum demand transient.
The reactor is assumed to be in single loop operatica at conservative initial operating conditiens of 78 percent of rated power and 63 percent core flow when failure of the feedwater control system instantaneously ir. creases the feedwater flow to the runout capacity of 160 percent of rated ficw.
The peak pressure is calculated to be 1126 psig and the MCPR is 1.26, each satisfying its respective safety limit.
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c)
Rod Withdrawal Error The rod withdrawal error at rated powar 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 fual cladding ir.tegrity safety limit.
Correc-tion of the rod block equation and lower initial pcwer for single-loop operation in the. Technical Specifications (see Section 5 of this safety
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evaluation) assures that the MCPR safety limit is not violated.
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t One-pump operation results in backflow through 10 of the 20 jet pumps while flow is being supplied to the icwer plenum from the active jet pumps.
Because of this backflow through the inactive jet pumps, present r.od-block equation and APRM settings must be modified.
The licensee ha,itor (APRM) settings that exist in the Technicals modified the t power range, mon Specifications for one-pump operation and the staf f has found them acceptable.
The staff finds that one loop transients and accidents other than LOCA, which is discussed below, are bounded by the two ioop operation analyses and are therefore acceptable.
2.1.3 Minimum Critical Power Ratio (MCPR) Uncertainties For single-loop operation, the rated condition steady-state MC?R 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 1cw initial MCPR at reduced flew conditions.
Therefcre, the required MCPR must be increased at reduced core flow by a flow factor X,.
The X, factors for two icop operation are derived assuming both recirculatic'n loop centro 11ers fail.
This ccndition of both recirculation loop controllers failing naximizes the pcwer increase and hence bounds the maximum delta MCPR for single loop opera-tion transients. When operating on one loop, the ficw and power increase will be less than that associated with two loops at full flow.
The K, factors derived frca the twc-loop assumptions are therefore conservative for single loop cperation.
2.2 Loss of Ccolant Accident (LOCA)
The licensee 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 Ccapany Analytical Model for loss-of-Cociant Analysis in Accordance with 10 CFR 50 Appendix X - 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 3 x SR fuel have been required to use a reduction factor of 0.55.
We require that La Salle, Unit 1 likewise reduce its MAPLHGR by 0.85.
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i 3.0 THERMAL HYDRAULICS 1
, The licensee has confirmed that analysis uncertainties are independ_ent of whether ficw is provided by two loops or a single icop. The only exceptions to this are core total flow and i1P 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 icw ficws. The steady state operating MCPR with single-loco 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 wa*er reactor stability characteristics and analysis methods continues. The previcus stability analysis results include natural circulatien conditions and thus beund the single loop operation.
In addition, the decay ratio (0.50) predicted for initial cycle for Unit 1 shows margin relative te Browns Ferry, Unit 1 (.53) which had the flew r.:ise escilla-tions during single recirculation leap cperation.
We conclude that with acpec-priate limitations to recogni:e and avoid operating instabilities, that the reactor can be operated safely in the single loop mode. Our evaluation of the flew / power oscillations evidenced in Browns Ferry will continue and any pertinent conclu'sicas resulting from this >Ludy will be applied to La Salle, Unit 1.
5.0 SUMM.ARY ON SINGLE LOOP OPERATION 5.1 Steady State Thermal Power Level will not exceed 50 percent of Rated Power.
Operating a't 50 percent of rated pcwer with appropriate Technical Specifi-cation (TS) changes has been approved on a cycle basis for several operating pl ants.
It is concluded for La Salle, Unit 1 that for operation at 50 percent of rated pcwer, consistent with the provisions of item h belcw, that transi-ent and accident bounds will not be exceeded.
5.2 Mininum Critical Power Ratic (MCPR) Safety Limit Will Be Increased by 0.01 to 1.0/
The MCPR Safety Limit will be increased by 0.01 to account for increased (TI?) readings. The licensee has determined that the change conservatively
'bcunds the uncertainties introduced by single loop cperation.
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-5 5.3 Minimum Critical Power Ratio (MCPR) Limiting Condition for Doeration tLCO) will De-increasea oy u.ul The staff requires that the operating limit MCPR be increased by 0.01 and multiplied by the appropriate two loop Kg factors that are in the La Salle, Unit 1 TS. This will preclude an inadvertent flow increase fron causing the MCPR to drop belcw the safety limit MCPR.
5.4 The Maximcm-Average-Planar Linear Heat Generation Rate-(MAPLHGR)
Limtis will De Recucea Dy Approorlate Multipliers The licensee prcposed reducing the TS MAPLHGR by 0.87 for Single Loop Operation. These recuctions were based on an analysis method proposed by General Electric in NEDE-20555-2. We require a reduction factor of 0.85 consistent with previous single recirculation locp operation approvals for plants with 8 x SR fuel. This change has been discussed with and agreed to by licensce.
5.5 The APRM Scram and Rod Block Setooints will be Reduced The licensee proposed to modify the two loop A?RM Scram, Rod Block and Rod Block Monitor (REM) setpoints to account fer back flow througi1 half the jet pumps. These setpoint equatiens will be changed in the La Salle, Unit 1 TS. The above changes are similar to c h?r clant TS changes and are acceptable to the staff.
5.5 The Recirculation Control will be-in Manual Control The staff requires that the licensee operate the recirculation system in the manual mode to elimir. ate the need for control system ar.alyses and to reduce the effects of potential flow ir. stabilities.
5.7 Surveillance Recuirements 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 peeps in that loop by more than 5 percent.
5.8 Provisions to A11cw Operation with One Recirculation Loco-Out of Service a.
The steady-state thermal power level will, not exceed 50 percent of.
rated power.
b.
The Minimum Critical Pcwer 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.
The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) d.
Limit will be reduced by 0.85.
e.
Technical Specification Setpoints shall read as follows:
T. S. 2.2.1 5<
0.66W + 45.7 (Trip Setpoint)
Si 0.66W + 48.7 (Allowable)
T. S. 3.2.2 S<
(0.66W + 45.7) T*
S~( (0.66W + 36.7) T*
RB T* as defined in T. S. 3.2 2 T. S. 3.3.6 APRM Upscale g 0.55W + 36.7 (Trip Se: point) g 0.66W + 39.7 (Allcwable)
REM Upscale s 0.66W + 34.7 (Trip Se: point) g 0.56W + 37.7 (Allcwable) f.
APRM flux noise will be measured once per shift; and the recircula-tion loop ficw will be reduced if the flux noise averace over 1/2 hour exceeds 5 percent peak to peak, as measured by tha A:RM 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 Sased 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 cperation up to pcwer level of 50 percent is authorized during cycle 1 until the staff concerns sterr.ing frcm Brcwns Ferry, Unit 1 single Icop operation are satisfied.
7.0 ENVIRONMENTALCONSIDERATI0?!
We have detemined 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 sicnificant environmental impact.
Having made this determination, we have further concluded that this Amendmant 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 envircr. mental impact appraisal need not be prepared in connection with the issuance of this statement.
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8.0 CONCLUSION
'Je have concluded, based on the considerations discussed abcVe, that; ' (1) because the Amendment does not involve a significant increase in the probability or consequences or accidents previously considered, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant dccrease 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 andangered by operation in the proposed manner; and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this Amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Data-DEC 1 s 1932 O
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[7$90-01]
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UNITED STATES NUCLEAR REGULATORY-C0". MISSION DOCKET-NO. SCs373 COMMONWEALTH-EDISON COMPANY NOTICE 0F* ISSUANCE 0F-AMENDMENT OF FACILITY OPERATING-LICENSE The U. S. Nuclear Regulatory Commission (the Comission) has issued Amendmant No.11 to Facility Operating License No. NPF-11, issued to Comon-wealth Edison Company, which adds License Condition E.C.(34) for operation of the La Salle County Station, Unit No.1 (the facility) located in Brookfield Tcwnship, La Salle County, Illinois.
The Amendment authorizes the operation of La Salle County Station, Unit 1 with one recirculation 1 cop out of service for the first fuel cyc'.e only.
- Also, the Amen!:.ent adds a license condition limiting a pcwer level to 50 percent of full pcwer or less during the operation with one recirculatier loop cut of service.
The applicaticn for amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ccamission's rules and regulations. The Comission has made appropriate findings as required by the Act and.the Cemission's rules and regulations in 10 CFR Chapter I, wnich are set forth in the license amendment.
Prict public notice of this Amendment was not required since the Amendment does not involve a significant hazards consideration.
The Commission has determined that the issuance of this Amendment will not result in any significant environmental impact and that pursuant to 10 CFR Section 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal r.eed not be prepared in ccanection with issuance of this, Amendment.
Aff.
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[7590-013
. For furtner details with respect to this action, see (1) the application for amendment dated December 6, 1982; (2) Amendment No.11 to L! cense No. NPF-ll dated December 16,1932; and (3) the Commission's related safety evaluation. All of these items are available for public inspection at the Comission's Public Document Room located at 1717 H Street, N'4, 'Jashington, DC 20555, and the Public Library of Illinois Valley Comunity College, Rural Route No.1, Ogelsby, Illinois 61348.
A copy of items (1), (2) and (3)
' may be obtained upcn request addressed to t'ae U. 5. Nuclear Regulatory Cc=.issien,
'4ashington, DC 20555, Attention: Director, Givision of Licensing.
Dated at :sthesda, Maryland, this 16th day of Decerber 1952.
FOR THE NU EAR REGULATORY COMMISSION r Q gutf*&($%
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A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing 9
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