ML20054E024
| ML20054E024 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/17/1982 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054E025 | List: |
| References | |
| NUDOCS 8204260017 | |
| Download: ML20054E024 (20) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
CASHINGTE N, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for a license filed by the Commonwealth Edison Company complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other.
agencies or bodies have been duly made; 8.
Construction of the La Salle County Station, Unit 1 (the facility),
has been substantially completed in conformity with Construction Permit No. CPPR-99 and the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; D.
There is reasonable assurance: l i)' that the activities authorized by this operating license can be conducted without endangering the healtn and safety of the public, and (14) that such activities will be con-ducted in compliance with the Corimission's regulations set forth in 10 CFR Chapter I; E.
The Commonwealth Edison Company is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I;
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F.
The Commonwealth Edison Company has satisfied the applicable provision's of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's. regulations; G.
The issuance of this license will not be inimical to the common defense and security or to' the, health and safety of the public; 82 04 2 6 00 n aw~
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After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-11, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, by-product and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings regarding this facility, Facility Operating License NPF-11 is hereby issued to the Commonwealth Edison Company (the licensee) to read as follows:
A.
This license applies, to the La Salle County Station, Unit 1, a bailivg water nuclear reactor and associated equipment, owned by the Common-wealth Edison Company. The facility is located in Brookfield Township, La Salle County, Illinois, and is described in the licensee's " Final Safety Analysis Report," as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses:
(1) Commonwealth Edison Company, pursuant to Section 103 of the Act and 10 CFR Part 50, "Licensin Facilities," to possess, use,g of. Production and Utilizati,onarid operate the designated location in Brookfield Township, La Salle County, Illinois, in accordance with the procedures and limitations set forth in this license, (2) Commonwealth Edison Company, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Commonwealth Edison Company, pursuant to iihe Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation b
and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
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(4) Commonwealth Edison Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Commonwealth Edison Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Livel The licensee is authorized to operate the facility at reactor core power levels not in excess of 5 percent of full power (166 megawatts themal) in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup tests and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is an integral part of this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B attached hereto are hereby incorporated in this license. The licensee shall orerate the facility in accordance with the Technical Specifications a.1d the Environmental Protection Plan.
(3) Conduct of Work Activities During Fuel Load and Initial Startup The licensee shall review by committee all Unit 1 Preoperational Testing and System Demonstration activities perfomed concurrently
- with Unit 1 initial fuel loading or with the Unit 1 Startup Test Program to assure that the activ.ity will not affect the safe performance of the Unit 1 fuel loading or the portion of the Unit i
1 Startup Program being perfomed. The review shall address, as a minimum, system, interaction,, span of control, staffing, i
security and health physics, with respect to perfomance of the l
I activity concurrently with the Unit 1 fuel loading or the portion of the Unit 1 Startup Program-*being performed. The committee for the review shall be composed of a least three members, knowledgeable in the above areas, and who. meet the qualiff-cations for professional-techn.ical personnel specified by
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4-4 section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Assistant Superintendent of.
Operation's staf f.
(4) Resolution of Rebar Damage and Adequacy of Off-gas Building Roof The licensee shall complete its assessment of the' rebar damaged due to drilling and coring in concrete and the structural adequacy of the off-gas building roof. The results shall be reported to the NRC staff for review and approval, prior to power operation following initial criticality and zero power physics testing.
(5) Snubbers (a) Prior to criticality, the licensee shall submit for NRC approval, a revised list of safety-related snubbers to be contained in Table 3.7.9-1 of the Technical Specifications to include such. snubbers on lines 3 inches in diameter or less.
(b) Prior to sta,rtup after the first refueling outage, the li.cen}ee shall provide, as necessary, a revision to the Technical Specifications to remove snubbers that are detennined to be unnecessary and replace them with rigid strut and rod assemblies.
(6) Deferred Preoperational Deficiencies The licensee shall satisfactorily resolve those deficiencies which were deferred from the preoperational testing program on a schedule that shall assure that the capability of a system required to be operable by Technical Specification is not degraded.
(7) Surveillance of Tendons (Sectio ~n 3."8.1*, SSER #3)
Prior to full power, the licensee shall supply the predicted lift-off forces required to complete
- Tables 4.6.1.5-1 and 4.6.1.5-2 of the Tecnnical Speci.fications.
(8) Masonry Wall (Section 3.8.3, SER,SSER #2)
Based on the findings of our preliminary review of. the licensee's submittals and its commitments related to masonry wall evaluation, the following actions are required by the li.censee:
(a) The present fixes for modifications implemented shall not preclude the option of implementing additional modifications if directed by our future review of the licensee's design 5
criteria.
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- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
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(b) Prior to startup after the first refueling outage, the licensee shall resolve the differences between our interim criteria and the criteria used by the licensee to the satisfaction of the staff and shall implement the required wall fixes or modifica-tions that might result from such a resolution.
(9)
Inservice Testing of Pumps and Valves (Section 3.9.6, SER)
Pursuant to 10 CFR Part 50.55a, the relief that the licensee has requested from the pump and valve testing requirements of 10 CFR Part 50, Section 55.55 (g)(2) and (g)(4)(i) is granted for that portion of the initial 120-month period during which we complete our review.
(10) Dynamic Qualification (3.10, SER, SSER #1, SSER #2)
(a) Prior to startup after the firs efueling outage, the licensee shall complete any modifications r replacement of equipment as a result of the fatigue evaluation.
In the interim, the licensee shall document the occurrence of every safety relief valve actuatiorr into the suppression pool, the associated cumulative damage factors calculated for typical representative equipment and kept up-to-date, and report to NRC any malfunction of equipment that occurs due to any safety relief discharge.
(b) Prior to startup after the first refueling outage, the licensee shall replace or modify the NSSS equipment (intennediate range monitor, C51-K-601 A/H and two-inch air-operated globe valve, C11-F011) if the results of the requalification tests indicate either change is required.
(11) Environmental Qualifications- (Section 3.11, SER, SSER #1, SSER #2)
(a) No later than June 30,,1982, the licensee shall be in compliance with the provisions of NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", for safety-related electrical equipment exposed to a harsh environment.
(b) Complete and auditable records must be available and maintained at a central location which describe the envirorinental qualification methods used for all safety-related electrical equipment in sufficient detail to document l
the degree of complianc,e with NUREG-0588.
Such records shall be updated and maintained' current as equipment is replaced, further tested, or otherwise further qualified to document
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complete compliance no late,r than June 30, 1982.
(c) The licensee shall complete the corrective actions stipulated in Appendix { to Supplement No. 2 of the Safety l
Evaluation Report by Ju.ne 30, 1982.
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6-(12) Seismic and Loss-of-Coolant Accident Loads (Section 4.2.3.4, SER,-
SSER #1, 55ER #2)
(a) By July 30, 1982, the licensee shall submit to NRC a complete t
description of the analytical methods along with all analytical results necessary to show that La Salle fully meets the criteria of Appendix A to the Standard Review Plan, Section 4.2 (NUREG-0800) with regard to fuel assembly liftoff.
(b) Prior to startup after the first refueling outage, the review of the fuel assembly liftoff issue must be satisfactorily resolved to the satisfaction of the staff.
(13) Surveillance of Control Blade (Section 4.2.3.14, SER)
I IE Bulletin No. 79-26, Revision 1, " Boron loss from BWR Control Blades," describes certain actions to be taken by licensees to '
detennine boron loss from BWR control blades. The licensee shall 5
comply with items 1, 2 and 3 of this bulletin and submit a written response on item 3 within 30 days after plant startup followi.ng the fi st refueling outage.
(14) Scram Discharge h,1ume (Sections 4.6.2, SER and 6.3.2.3, SSER #2)
(a) Prior to startup after the first refueling outage, the licensee shall incorporate the following additional modifications into the scram discharge volume system:
(i)
Redundant vent and drain valves, and (ii) Diverse and redundant scram instrumentation for each instrumented volume, including both delta pressure sensors and float sensors.
d (b) Prior to startup after the first refueling outage, the licensee shall complete system or procedural modifications, if required, as a result of the staff's completion of its review of the licensee's response to NUREG-0803.
(15) Low Pressure in Pump Discharge of the Control. Rod Drive (Section 4.6.2, SSER F2)
Prior to startup after the first refuelinc outage, the licensee shall install instrumentation for an automatic scram that would shut down the reactor in the event of low control rod drive pump discharge pressure to be activated during startup and refueling s
modes only.
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(16) Containment Long Term Program Load Specifications (6.2.1.1, SSER #2)
'l Prior to October 1,1982, the licensee shall submit its confinnatory assessment of the containment design adequacy for pool dynamic loads (chugging, vent lateral and diaphragm reverse pressure) developed in conjuction with the Long Tenn Program and reported in NUREG-0808.
(17) Pressure Interlocks on Yalves Interfacing at Low and High Pressure (Section 6.3.4, 55ER #2)
Prior to startup after the first refueling outage, th[ license.e shall implement isolation protection in confonnance to the~
requirements of Section 6.3 of the Standard Review Plan against overpressurization of the low pressure emergency core coolfr.g systems (RHR/LPCI and LPCS) at the high and low pressure intar-face containing a check valve and a closed motor-operated valve.
(18) Compliance with Regulatory Guide 1.97 (Sections 7.5.2, SER)
By July l',19'82, the licensee shall provide a pla' for imp 1enienting
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n modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"
dated December 1980.
(19) Additional Instrumentation and Control Concerns (Section 7.7.3.4, SSER #1)
The licensee shall resolve the following concerns to the NRC staff's satisiaction prior to startup,after the first refueling outage:
(a) whether common electrical power sources or sensor malfunctions may cause multiple control systems failures, and (b) whether high energy line breaks will result in unacceptable consequential control system failures.
(20) Low and/or Degraded Grid Voltage (Section 8.2.2.2, SER)
The licensee shall install a second level of undervoltage protection prior to startup after the first refueling outage.
l (21)
Reliability of Diesel-Generators (Sections 8.3.1.1, SER and 9.6.3.4, SER)
Prior to startup after the first refueling outage, the licensee shall implement the following design modifications with respect to diesel-generator reliabi.li,ty:
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i (a) A heavy duty turbocharger gear drive assembly be installed on the diesel-generators.
(b) A prelube pump, powered from a reliable direct current power supply, be installed in the s; stem,to operate in parallel with the engine-driven lube oil pump, or an alternative acceptable to the NRC shall be installed to preclude dry-starting of the diesel-engine.
(c) Cantrols and monitoring instrumentation be removed from the engine and engine skid, except instruments qualified for this location. The non-qualified control and monitoring,
instruments shall be instElled on a free standing floor mounted panel and located on a vibration free floor area.
If the floor is not vibration fr ee, the panel shall be equipped with vibration mounts.
(22) Direct Current Power Systems (Section 8.3.1.2, SER)
Prior to startup after the first refueling outage.for, the 125.
and 250-volt direct current systems for Divisions 1 and 2 and the 125-volt Division 3 direct current system, the following additional instrumentation shall be provided in the control room:
(1) Battery current (ammeter-charge / discharge), (2) Battery charger output voltage (voltmeter), (3) Battery charger output current (ammeter),
(4) Battery high discharge rate alann, and (5) Battery charger trouble alarm.
In the interim, the licensee shall implement approved procedures to monitor battery current, battery charger output voltage, ar4 battery charger output current at the local panels at 1 cast once per eight hour shift.
(23) J eactor Containmhnt ElectricalNenetrations (Section 8.4.1,
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, rior to st'artup after i.he f'irst refueling outage, a redundant p
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fault. current device (circuit breakers or fuses) shall be provided on each penetrating circuit that would limit a fault current surge to be less than the surge for which the penetration is qualified except for low energy (milliamps) instrument systems.
t (24) Separation of Class 1E and Non-Class IE Cable Trays (Section 8.4.6.1, SER, SSER el, SSER 72)
Prior to startup after the first refueling outage, the licensee shall,rovide adequate separation or barriers between Class lE and adjacent non-Class lE cable trays.
(25) Fire Protection Program (Section 9.5, SER, SSER #2, SSER #3)
(a) The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan.
In addition, the licensee shall maintain the fire protection program set forth in Appendix R to 10 CFR Part 50, except for the following deviations:
(i) Hydrostatic hose tests in accordance with NEPA 1962-1979, and (ii) No automatic fire detection systems in areas 2X/3K and 5B4.
(b) Prior to initial criticality, the licensee shall install a 1-hour rated barrier on all. four sides of a partially protected power cable pan and a general sprinkler system, both located in the diesel-generator corridor..
(c) Prior to startup after the first refueling outage, the licensee shall provide fire protection systems in fire areas 2C/3C, 4C3 and 6E.
(d) Prior to startup after the first refueling outage, the licensee with respect to fire doors shall implement one of the following:
(i) Perform an engineering review of the manufacturer's certified doors and. door frames by a nationally recognized laboratory to certify that the door and door frames provide the required fire resistance rating, or d
(ii) Test a replicate as installed" door assembly by a nationally recognized laboratory to determine the door rating, or (iii) Replace manufacturer's labeled doors and door' frames with UL rated items.
(e) Prior to startup after the first refueling outage, the licensee shall demonstrate the adequacy of its fire protection for record st age.
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4 (26) Radiation / Chemistry Technicians on the Backshift (Section 13.1, SSER#2T (a) All Radiation / Chemistry Technicians on the backshift shall be trained per the la Salle's Tranining Qualification Guide. All such Technicians shall also have satisfactorily completed the following emergency response training:
(i) Tasks to be performed during the first 60 minutes of a sert'ous emergency on the backshift; (ii) Post-accident sampling and analysis for the first three hours of an emergency; (iii)
In-plant radiation surveys during an accident; (iv) Use and interpretation of both portable and fixed area radiation monitoring equipment, such as the Eberline PING-3 and SAM-2; (v)
Interpretation of critical effluent monitoring data for assisting the Chief-Engineer during the first hour of an accident (i.e.,
station vent monitor and standby gas treatment monitor);
(vi) First aid and bioassay techniques; and (vii) Use of respiratory. equipment during emergency situations.
(b) By June 1,1983, the licensee shall have Radiation / Chemistry Technicians onshift for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day who meet ANSI N18.1-1971 or who are qualified in accordance with a NRC approved alternative program.
(27)
Industrial Security (Section 13.6, SE'R, SSER#3)
The licensee shall maintain in ef,fect and fully implement all provisions of the Commission'-s approved physical security plan, guard training and qualification plan, and contingency plan, including amendments made pursuant to the authority of 10 CFR 50.54(p). The approved plans which contain safeguard information are collectively entitled:
"La Salle County Station Security Plan Units 1 and 2," Revision 11, dated December 24, 1981; "La Salle County Station Guard Training and Qualification Plan," submitted by their letter dated August 16, 1979, as revised in August, 1980; and "La Salle Nuclear Power Station Contingency Plan, dated March,1980, as revised by,pages dated June,1980.
The licensee is exempt from the commitment to fully implement those portions of the Security Plan as described in Items 1 and 2 in the d
licensee's letter dated April 1,1982, provided that the compensatory measures delineated in the above referenced letter are in place.
Compensatory measures as described in Item 3 in the April 1,1982 letter are approved with full imp.lementation of the security plan commitments to be accomplished no later than July 1,1982.
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The licensee is exempted from the provisions of 10 CFR 73.55(d)(9),
but shall meet all other commitments of the physical security plan and the following additional items.
(a) Change all keys, locks, and combinations and related equipment used to control access to protected areas and vital areas at least every 12 months.
(b). Issue keys, locks, combinations, and other access control devices to protected and vital areas only to those individuals who possess access authorization to those areas.
(c) Change keys, locks, combinations, and related equipment to which an individual had access within 5 days and immediately for card keys after access authorization is withdrawn due.
to lack of' trustworthiness, reliability, or inadequate work performance.
(28)
Initial Test Program (Section 14, SER)
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The licensee 'shall conduct the post-fuel-loading initial t'est program (set forth in Section 14 of the licensee's Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
(a) Elimination of any test identified in Section 14 of the licensee's Final Safety Analysis Report, as amended as being essential; (b) Modification of test objectives, methods or acceptance criteria I
for any test identified in Section 14 of the licensee's Final Safety Analysis Report, as amended as being essential;"
(c) Performance of any test at a power level different from that described in the program; and (d) Failure to complete any tests included in the described program (planned or scheduled for power leven up to the authorized t
power level).
r (29) Assurance of Proper Design and Construction (Section 17.4, SSER #2)
Prior to exceeding 5 percent of full power, the licensee shall have conducted an independent review of the mechanical and structural design of the. loop C residual heat removal system, excluding all branch piping.less than 3 inches, in the functioning mode of the low pressure injection system using loads resulting from i
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- i the actuation of the automatic depressurization system in conjunction with the operating basis earthquake to verify that this system has been designed and constructed in accordance with all pertinent NRC requirements. This verification review shall consider design, e
installation, inspection, testing, and any othe~r aspects necessary to ensure conformance with the design. This review shall be performed independently of the licensee and its contractors who performed.
design and construction activities for the La Salle County Station, j
and it shall be completed to the satisfaction of NRC.
(30) NUREG-0737 Conditions (Section 22.2)
The licensee shall complete the following conditions to the satisfaction of the NRC. These conditions reference the appro-priate items in Section 22.2, "TMI Action Plan Requirements for Applicants for Operating Licenses," in the Safety Evaluation Report and Supplements 1, 2 and 3, NUREG-0519.
(a) Shift Technical Advisor (I.A.l.1, SER, SSER #2)~
The Shift Technical Advisor (STA) function shall be fulfilled by the Station Cont ~ ol Room Engineer (SCRE) who will be a r
designated SRO. However, if a SCRE is not ava%able, the licensee shall provide a fully-trained on-shift technical advisor to the shift engineer (shift supervisor).
(b) Nuclear Steam Supply System Vendor Review of Procedures (l.C.7, SER)
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Prior to beginning low-power testing, the licensee must assure that the General Electric review of the power-a.scension test procedures has been completed and the General Electric recommendations have been incorporated.
(c)
Independent Safety Engineering Group (I.B.1.2, SER)
The licensee shall have an on-site independent engineering group.
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(d) Control Room Design Review (I.D.1, SER, SSER #2)
The licensee shall correct the design deficiencies identified in Appendix C of Supplement No. I to the S #ety Evaluation Report, NUREG-0519 on the schedule prescribed therein.
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(e) Training During low-Power Testing (I.G.I, SER, SSER #2)
At least 4 weeks prior to performing the Special Test, Simulated Loss of Onsite and Offsite Alternating-Current Power Test, the licensee shall provide a safety analysis for the test and its procedures to NRC for review and approval.
(f) Post Accident Sampling (II.B.3, SSER #2)
Prior to criticality, the licensee shall install and test a high radistion sampling system for obtaining reactor coolant and containment atmosphere sampling under degraded core accident conditions without excessive-exposure.
(g) Direct Indication of Safety / Relief Valve Position (II.D.3, SER, SSER 72)
Prior to startup after the first refueling outage, the licensee shall replace the safety / relief valve position indicator to a model that meets the IEEE Standards 323-19 74 and 344-1975.
(h) Additional hccident-Monitoring Instrumentation (II.F.1, SER, SSER #2), Noble Gas Effluent Monitor Prior to criticality, the licensee shall install and have procedures approved by the NRC for noble gas effluent monitoring system at plant effluent. pathways., Sampling and Analysis of Plant Effluents Prior to criticality,#-the licensee shall install and have procedures approved by the NRC for radiofodine and particulate sampling and analysis system at plant effluent pathways.
(i)
Instrumentation for Detection of Inadeauate Core Coolng (II.F.2, SER SSER #1, SSER #2) i By July 31, 1982, the licensee shall submit a report addressing I
the analysis performed by the BWR Owners Group regarding additional instrument,ation relative to inadequate core cooling and that the licensee shall implement the staff's requirements after the completion of the staff's review L
of this: report.
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(j) Proper functioning of Heat Removal Systems (II.K.1.22, SER,'
SSER #2, and II.K.3.13, SER, 55ER #2)
The licensee shall implement the logic to restart automatically the core isolation cooling system prior. to startup after the first refueling outage.
(k) Modify Break Detection Logic to Prevent Spurious Isolation of high Pressure Coolant Injection and Reactor Core Isolation l
Cooling System (II.K.3.15, SER, SSER #2) j Prior to startup after the first refueling outage, the I
licensee shall implement a circuit modification to assure l
that transients monitored by pressure instruments to sense flow in these two systems actually sense continuous high steam fl ow.
(1) Modific'ation of Automatic Depressurization System Logic -
Feasibility for Increased Diversity for Some Event Sequences
-(II.K.3.18, SER, SER #1, SSER #3)
(a' By October 1,1982, the licensee shall evaluate the alternative. design modifications of the BWR Owners l
Group relative to the logic for the automatic depressurization system, submit such evaluation, and propose modification to NRC for review and approval.
(b) Prior to startup after the first refueling outage, the licensee shall implement the approved alternative logic modification of the. automatic depressurization system.
(m) Restart of Core Spray and Low Pressure Core Injection System Tll.K.3.21, SER, SSER.e2)
Prior to startup after the first refueling outage, the licensee shall provide an auto start for the high pressure core spray.
(n) Automatic Switchover of Reactor Core Isolation Cooling System Suction--Verify Procedures and Modify Design (II.K.3.22, SER)
Prior to startup after the first refueling outage, the licensee shall implement the automatic switchover of the reactor core isolation cooling sys' tem suction from the condensate storage tank to the suppression pool when the. condensate storage tank b
level is low.
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(o) Upgrade Emergency Support Facilities (III.A.l.2, SER, SSER #1)
The licensee shall complete its Emergency Response Facilities' as follows:
(i) Safety Parameter Display System October 1,1-982 (ii) Emergency Operations Facility October 1,1982 (iii) Technical Support Center October 1,1982 (p)
Improving Licensee's Emergency Preparedness - Long Term (III.A.2, SER, SSER #1, SSER #2)
(1) Prior to exceeding five percent power, the licensee shall complete a successful emergency exercise with the La Salle facility ~ and La Salle County.
(2) Prior to exceeding five percent power, a test shat 1 bt perfonned to demonstrate an adequate alerting / notification system.
(3) Prior to exceeding five percent power, the licensee shall demonstrate that the state of offsite preparedness provides assurance that adequate protective measures can and will be taken in the event of a radiological emergency. The use of 10 CFR 50.54(s)(2) to specify a period within which corrective actions must be taken to assure an adequate state of emergency prepared. ness will include instances where NRO firids that the lack of progress in completion of the procedures in the Federal Emergency Management Agency'g proposed rule set forth in 44 CFR Part 350 is an indication that major substantive problems exist in achieving or maintaining an adequate state of preparedness.
Any corrective period specified will relate to substantive problems identified by the Federal Emergency Management Agency.
(4) The licensee shall provide the interim neteorological improvement and shall provide the mechanism for long-term improvements as follows:
(i)
Prior to exce'eding five percent power, the lic'ensee shall install a process computer with the capability
= to, retrieve meteorological information that provides S
a redundant means for data access.
(ii)
Prior to exceeding five p6rcent power, the licensee shall propose a plan for meeting the meteorological and dose assessment capability guidance of Appendix 2, NUREG-0654, Revision 1 as follows:
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installation of hardware and sof tware capability e
described above by July 1,1982; and e
full operational capability de' scribed above by January 1, 1983.
(iii) Prior to exceeding five percent power, the licensee t
shall include a description of the dose calculational methodology with a Class A transport and diffusion module, and a description of an acceptable meteorological measurement preventative and corrective maintenance program in the. radiological emergency plan.
D.
Exemptions from certain requirements of Appendices G, H, J, R and $50.55(a) to 10 CFR Part 50 and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement No.1, No. 2 and No. 3 to the Safety Evaluation Report 6 In addition, an exemption.was' requested until the completion of the first refueling from the requirements of 10 CFR $70.24 and an exemption from 10 CFR Part 50, Appendix E from performing a full scale exercise within one year before issuance of an operating license, both exemptions are -
described in Supplement No. 2 of the Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common -
defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
This license is subject to the following additional condition for the protection of the environment:
.Before engaging in additional construction 'cir operational activities 'which
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may result in a significant adverse environmental impact that was not evaluated or that is significantly greatpr than that evaluated in the Final Environmental Statement and its Addendumi the licensee shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive w'ritten approval from that office before proceeding with such activities.
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F.
The licensee shall notify the Commission, as soon as possible but not later than one hour, of any accident at this facility which could' result in an unplanned release of quantities of fission products in excess of allowable
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limits for normal operation established by the Commission.
G.
The licensee shall have and maintain financ'ial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
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~ 11. This license is effective as of the date of issuance and shall expire at midnight on April 17, 2022; provided however that should the Cormiission, in conjunction with its consideration of the petition for Rulemaking in Docket No. PRM-50-30 detemine that the temination date for operating licenses should appropriately run from the date of the issuance of a licensee's construction pemit, the expiration date of this license will be September 10, 2013, effective upon notice to the Licensee of the Commission's action in this regard.
FOR TiiE HUCLEAR REGULATORY COMMISSION Harold R. Denton, Director Office of Huclear Reactor Regulation
Attachment:
1.
Attachnent 1 2.
Appendix A - Technical Specifications (hUREG-0861) 3.
Appendix B - Environtmntal Protection Plan Date of Issuance:
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7 F.
The licensee shall have and naintain financial protection of such type and in such amounts as the Comission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
G.
This license is effective as of the date of issuance and shall expire at midnight on April 16, 2022; provided however that should the Comission, in conjunction with its consideration of the petition for Rulemaking in Docket No. PRM-50-30 determige that the temination date for operating licenses should appropriatelf, run from the date of the issuance of a licensee's construction pemit, the erpiration date of this license will be September 10, 2013, effective upon notice to the Licensee of the Catmission's action in this regard.
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\\ FOR THE NUCLEAR REo ATORY C0f! MISSION
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')iarold R. Denton, Director
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Office of Nuc1' ear Reactor Regulation
Attachment:
- 1.
2.
Appendix A - Technical Specifications (NUREG-0861) 3.
Appendix B - Environmental Protection Plan Date of Issuance:
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ATTACHMENT 1 TO LICENSE NPF-11 This attachment identifies certain preoperational tests, system demonstrations and other items which must be completed to the Commission's satisfaction prior to proceeding to Operational Mode 2 (initial criticality or 212'F as appli-cable).
The licensee shall not proceed beyond this Operational Mode without written confirmation from NRC that the following items have been completed in accordance with the conditions set forth below.
1.
The following Preoperational Tests shall be completed, including all reviews:
a.
Containment Monitoring System (PT-CM-101) b.
Drywell Pneumatic System (PT-IN-101) c.
Traversing Incore Probe (PT-NR-102) (Prior to Entering Test Conditi.on 1) d.
Off-Gas System (PT-0G-101) e.
Primary Containment ILRT (PT-PC-101) f.
Pipe Vibration Monitoring (PT-SI-102) 2.
The following System Demonstrations shall be completed, including all reviews:
a.
High Radiation Sampling System (SD-PS-102) b.
Dynamic Effects (5D-S1-101) 3.
Commonwealth Edison Company must install and test the microwave voice channel communications system.
(373/81-14-25) 4.
Commonwealth Edison Company must install radiation measurement equipment in the E0F.
(373/81-14-31) 5.
Commonwealth Edison. Company must assure the following couaitments per TMI Action Plan Requirement III.D.3.3 are met:
a.
Availability of 5 PING-3 (2A special) particulate, iodine, and noble gas air monitoring systems mounted on carts.
b.
Availability of Eberline ins ~trument Corporation SAM-2 iodine monitors wius silver zeolite cartridges.
Availability of'a low background, low contamination area c.
for analyzing iodine cartridges.
(373/81-00-102) l 1
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6.
Commonwealth Edison Company muct assure that results from Preopera-j tional Test PT-RP-101 for response time of the scram signals for the turbine stop valve and turbine control valve fast closure are added to the results obtained in Preoperational Test PT-RR-101 to obtain correct scram response times for these items.
(373/80-15-12) 7.
Commonwealth Edison Company must conduct a site assembly drill' (373/80-53-03) 8.
Commonwealth Edison Company must include in Startup Test Pro-cedure STP-17 requirements for measuring GAP. clearances between the process pipe and the surrounding pipe whip restraint struc-tural assemblies.
(373/81-29-01) 9.
Commonwealth Edison Company must develop procedures for esti-mating Noble Gas Radioiodine Release Rates required by Table II.F.1-2 per TMI Action Plan Requirement II.F.1.
(373/81-00-104) 10.
Commonwealth Edison Company must satisfactorily resolve those deficiencies affecting systems for which Preoperational. Tests or System Demonstrations are required to be completed prior to initial criticality.
(Category 4 deficiencies as per the licensee's procedure).
11.
Commonwealth Edison Company must review the Cable Pan Loading Report to verify there are no outstanding discrepancies.
(373/79-34-01) 12.
Commonwealth Edison Company must calibrate high range station vent and standby gas treatment system monitors.
(373/81-14-20) 13.
Commonwealth Edison Company must complete modifications to the laboratory HVAC system to meet.de'ign criteria requirements of s
positive pressure betveen the counting room and surrounding areas.
(373/81-43-03) t 14.
Commonwealth Edison Company must review the stop and control valves closure time acceptance criteria basis to determine it meets design specifications.
(373/81-43-06) 15.
Commonwealth Edison Company must conduct a 100% reinspection of high strength steel bolting.
(373/81-48-06) 16.
Commonwealth Edison Company must develop a written technical basis for the practice of installing high strength bolts without torquing requirements.
(373/81-48-07) 6 17.
Commonwealth Edison Company must complete a testing program for vibration monitoring of the Low Pressure Core Spray 1A and Residual Heat Removal System 1B pumps.
(373/82-10-15 and 373/82-18-01) 2 m
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