ML20107L521

License NPF-37,authorizing Operation at 100% Power

ML20107L521
Person / Time
Site:	Byron
Issue date:	02/14/1985
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML20107L524	List: ML20107L521 ML20107L532 ML20107L546
References
NUDOCS 8502280691
Download: ML20107L521 (11)

Text

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/prucgg UNITED STATES e*

NUCLEAR REGULATORY COMMISSION o

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COMMONWEALTH EDISON COMPANY

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DOCKET NO. STN 50-454 l

BYRON STATION, UNIT NO. l' FACILITY OPERATING LICENSE License No. NPF-37 1.

The Nuclear Regulatory-Comission (the Comission) has found that:

A.

The application for license filed by Comonwealth Edison Company.

(licensee), complies with the standards and requirements of the

- Atomic Energy Act of 1954, as amended (the Act), and the Commis-

'sion's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Byron Station, Unit No. 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-130 and the application, as amended, the provisions of the l

Act, and the regulations of the Commission; l

C.~ The facility will' operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Com-missfon (except as exempted from compliandLr in Section 2.D below);

D.

There is reasonable assurance:

(i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activitiec will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D beTo>);

E.

Connonwealth Edison Company is technically qualified to engage 'in the activities authorized by this -license in accordance with the Comis-sion's regulations set forth in 10 CFR Chapter I; F.

Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140 " Financial Protection Requirements and Indemnity Agree-

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ments," 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; S

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After weighing the environmental, economic, technical and other benefits

_pf.the. facility against environmental and other costs and considering available alternatives, the issuante of this-Facility Operating License No. NPE-37, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached'as Appendix B.

is in accordance with 10 CFR Part 51 of the Commission's regulations-and all applicable requirements have been. satisfied; and I.

The receipt, possess 1on, and u~se of source, byproduct and special nuclear material as authorized by this license will be in accordanc'e with the Commission's regulations in 10 CFR Parts 30, 40 and 70.

T 2.

Pursuant to approval by the Nuclear Regulatory Commission at a meeting on '

February 12, 1985, the License for Fuel Loading and Low Power Testing, 4

' License No. NPF-23, issued on October 31, 1984, is superseded by Facility Operating License No. NPF-37 hereby issued to Commonwealth Edison Company (the licensee) to read as follows:

A.

The license applies to the Byron Station, Unit No.1, a pressurized water nuclear reactor and associated equipment (the_ facility), owned by Commonwealth Edison Company. The facility is located in north cen-tral Illinois within Rockvale Township, Ogle County, Illinois and is described in the licensee's " Final Safety Analysis Report", as supple-mented and amended, and in the licensee's Environmental Report, as supplemented and amended.

B.

Subjec't to the conditions and requirements incorporate'd herein, the Commission hereby licenses Canmonwealth Edison Company:

(1)

Pursuant to 'Section 103 of the Act and 10 CFR Part 50 to possess, use and operate the facility at the designated location in accordance with the procedures and limitations set forth in this license;

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(2)

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;

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(3)

Pursuant to the 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 source's for reactor startup, i

sealed sources for reactor instrume'ntation and radiation moni-toring equipment calibration, and as fission detectors in amounts as required; O

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(4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, pos_sess, and,use in amounts as: required any bypr.oduct, source

" 'or special.nuclea,r material without restriction to chemical or physical form, for sample analysis or instrumenf calibration tr associated with radioactive apparatus or com'ponents; and (5)

Pursuant to th'e Act and 10 CFR Parts 30, 40 an'd 70, to possess, but not separate, such byproduct and special nuclear materials as may be produc'ed by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions

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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 additions conditions specified or incorporated below:.

l (1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100%

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power) in accordance with the conditions specified herein and

..in Attachment' I 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 hereby incorporated into thfi; lidnse; (2) -Technical Specifications and Environmental Protection Plan

'The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.~ The licensee shall operate the facility in accordance

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with the Technical Specifications and the Environmental Protec-tion Plan; (3) Post-Fuel-Loading I-itial Test Program (Section 14, SER)

An~y changes.to the Initial Test Program described in Section~14

~ of the FSAR made in accordance with the provisions of 10 CFR

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50.59 shall be reported in accordance.with 50.59(b) within one month of such change.

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(4) Seismic and Dynamic Oualification (Section 3.10, SSER #5)*

Prior to startup following the first refueling outage, the N11censee shall completely) qualify the Westinghouse 7300 Process Protection System (ESE-13

.for both Nuclear Steam Supply System 4

and Balance of Plant applications, including any hardware changes, if fo'und necessary.

(5). Equipment OuaTification~(Section 3.11, SSER #5, SSER #6)

All electrical equipment within the scope of 10 CFR 50.49 must be environmentally qualified by November 30, 1985.

~(6) Fire Protection Program (Section 9.5.1, SER, SSER #3, SSER #5, 55ER f6)

(a) The licensee shall maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility through Amendment 4 and

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the licensee's letters dated August 20, 1984, October 11, 1984 and October 15, 1984, and as approved in the SER through Supplement 6, subject to provisions b & c below.

(b) The licensee may make no' change to the approved. fire pro-tection program which would deqpease the level of fire protection in the plant without prior approval of the Commission. To make such a change thi licensee must subnit an application for license amendment pursuant x

to 10 CFR 50.90.

(c) The licensee may make changes to features of the approved-fire protection program which do not decrease the level of

, fire protection without prior Commission approval provided:

(1) Such changes do not otherwise involve a change in a

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license condition or Technical Specification or result in an unreviewed safety question (see 10 CFR 50.59),

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(ii) such ' changes do not result in failure to complete the

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fire protection program approved by the, Commission prior to license issuance.

• Requires exemption; see Paragraph 2 D 4

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The lice.nsee shall maintain, in an auditable form, a current

..,...... record of al.1 such changes, including.an analysis of the effects of the changes on the fire protection program, and shall make such r'ecords available to NRC inspectors upon

' request. "Al1 changes to the approved program made without prior Commission approval shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses.

(d) Prior to July 1, 1985, the licensee shall complete instal-lation ' nd test ng of the continuous thermistors in the a

Auxiliary-Building ventilation system charcoal filter plenums.

Pending completion of this work, the licensee shall conduct an hourly fire watch patrol to inspect the

' charcoal filters in the Auxiliary Building.

(7) Control Room Human Factors (Section 18.2, SSER #4)

Unless the staff determines that the test results do not support the change, the licensee shall, prior to startup following the first refueling outage, move the range and volume controls for the SOURCE RANGE nucle.ar instrument on Unit I from the nuclear instrumentation cabinet IPM07J to the main control board IPM05J.-

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(3). TMI Item II.F.1, Iodine / Particulate lampling (Section 11.5,

'.SSER #5)

Prior to startup following the first refueling outage, the li-censee shall demonstrate that the operating iodine / particulate s

sampling system will perform its intended function.

(9)

Emergency Response Capability (NUREG-0737, Supplement #1) l The licensee shall complete the emergency response capabilities l

as required by Attachment 2 to this license, which is incorpo-rated into this license.

i (10) Reliability of Diesel-Generators (Section 9.5.4.1, SER, SSER #5)*

j Prior to startup following the first refueling outage, the con-

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trols and monitoring instrumentation on the local control panels shall be dynamically qualified for their location or shall be

• Requires exemption; see Paragraph 2.D

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installed on a free standing floor mounted panel.in such a man-

...ner--(including the use of vibration isolation mounts as necessary) that there is reasonable assurance that any induced vibrations "will not result in cyclic fatigue failure for the expected life of the instrument.

(11) Gener'ic Letter 83-28 (Required Actions Based on Generic

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Implications of Salem ATWS Events)

The l'icensee shall submit responses to and implement the requ' ire-ments of Generic Letter 83-28 on a schedule which is consistent with that given in its letters dated November 5,1983, February 29 1984, June 1, 1984 and October 10, 1984.

(12) Formal Federal ~ Emergen'cy Management Agency Finding In the event that the NRC finds that the lack of progress in com-pletion of the procedures.in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving _or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54 (s)(2) will apply.

(13).ControlRoomVentilationSystem(Section6.5.1,SSER#5,SSER#6)*

' Prior to July 1, 1985, the licensee shall i.ncorporate modifica-tions, as necessary, to ensure _that the control room ventilation system may be used during an accident to protect operators within sthe criteria specified in 10 CFR 50, Appendix A. General Design l

Criteria 19.

(14).TurbineMissiles(Section3.5.1.3,SSER#5)

The-licensee shall volumetrically inspect all three low pressure.

turbine rotors by every third refueling outage, until a turbine system maintenance program based on the manufacturer's calcula-

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tions of missile generation probabilities is approved.by the staff.

• Requires exemption; see Paragraph 2 D m

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(15) Operating Staff Experience Requirements (Saction 13.1.2.1, SSER #5)

The licensee shall'have a' licensed senior operat'or on each shift

. h'o has had at least s'ix months of hot operating experience on a w

similar type plant, including at least six weeks at power levels greater than 20%,of full power, and who has had' start-up and shut-down experiened. except as follows. For those shifts where such an individual is not available on the plant' staff, an advisor shall be provf'ded who has had at least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility. Use of adiisors who were licensed only at the R0 level will be evaluated on a case-by-case basis. Advisors shall be trained on plant procedures, tech-nical specifications and plant systems, and shall be examined on these topics at a level sufficient to assure familiarity with the plant.

For each shift, the remainder of the shift crew shall be trained as to the role of the advisors. These advisors shall be retained until the experience levels identified in the first sentence above have been hchieved. The NRC shall be notified at l

least 30 days prior to the date that the licensee proposes to l

release the advisors from further service.-

D.

The facility requires hxemptions from certain requirements of Appendices A, E and-J-to.10 CFR Part 50. These include.(a) Jm exemption from the require-I ment of Paragraph III.D.2(b)(ii) of Appendix J, the testing of containment air locks at times when containment integrity is not required (Section 6.2.6 of the SER), (b) an exemption from GDC-2 of Appendix A, the requirement that structures, systems and components important to safety be designed to with-stand the effects of. nat val phenomena such as earthquakes (Section 3.10 of

'SSER #5), (c) an exemption from GDC-13 and GDC-17 of Appendix A, the require-ment that instrumentation be provided to monitor variables and systems over their anticipated ranges, and the requirement that provisions be included to minimize the probability of losing electric power-(Section 9.5.4.1 of SSER #5), (d) an exemption from GDC-19 of Appendix A, the requirement' that the control room have adequate radiation protection to permit access and occupancy under accident conditions (Section 6.5.1 of SSER #6), and (e) an exemption.from the requirement of Section IV.F of Appendix E that a full participation emergency planning exercise be conducted within one year be-fore issuance of the first operating license for full power and prior to

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operation above 5% of rated power (Section 13.3 of SSER #6). These exemp-tions are authorized by' law and will not endanger life or. property or the.

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comon defense and security and are otherwise in the public interest.

Therefore,Jh_e.se exemptigns are_hereby' granted pursuant to'10 CFR 50.12.

4 With th's granting of these exemptions 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.

The licensee shall maintain in effect and fully implement all provisions of.the Commission approved Physical S'ecurity Plan, Guard Training and Quali.

fication Pf an, and Contingency Phm, including amendments made pursuant to the authotity of 10 CFR 50.54(p). The approved plans which contain Safe-guards I.nformation and are required to be protected against unauthorized disclosure in accordance with 10 CFR 73.21 are collectively entitled:

Connonwealth Edison Company, By 3n Nuclear Power Station Physical Security -

Plan,' Security Personnel Trainiq and Qualification _ Plan *, and Safeguards Contingency Plan *, Revision 2 (May 1980), transmitted by letter dated May 2, 1980, as revised by Revision 3 (June 1980) transmitted by_ letter i

dated June 27, 1980, as revised by Revision 4 (August 1980) transmitted by letter of August 11, 1980, as revised by Revision 5 (January 1982) transmitted _by letter of January 25, 1982, as revised by Revision 6 (April 1982) transmitted by letter dated April 19, 1982, as revised by Revis~ ion 7 (September 1982) transmitted by(August 1983) transmitted by letteis d letters dated October 8'and December 22, 1982 as revised by Revision 8 Septaimber 16, 1983 and October 28, 1983, as revised by Revision 9 (October 1983) transmitted by letter dated November 17, 1983, as revised by Revision 10 (January 1984) transmitted by letter dated December 30, 1983, as revised l

by Revisions 11 and 12 (July and August 1984) Transmitted by letter dated l

August 29,' 1984.

l-l F. -Except~as otherwise provided in the Technical Specifications or Environmental s

Protection Plan, the licensee shall report any violations of the requirements -

contained in Section 2.C of this license in the following manner: initial-

-notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c) and(e).

G.

The licensee shall have ar.d maintain financial 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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• The Security Personnel Training and Qualification Plan and the Safeguards -

Coittingency Plan are Appendices to the Security Plan.

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H. ^ This license is effdctive as of 'the date of issuance and shall expire at Midnight October 31, 2024.

FOR THE NUCLEAR REGULATORY COMMISSION

/5 Harold R. Dento'n, Director Office of Nuclear Reactor Regulation Attachments / Appendices:

1.

2.

3. -Appendix A - Technical Specifications (NUREG-1113)

4. -Appendix B - Environmental Protection Plan Date of. Issuance:

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ATTAChKENT 1

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l This attachment identifies certain preoperational tests and other itenis which must be completed to the Consnission's satisfaction and identifies the required timing for their completion.

A..Preoperational' test VA 84.11 (auxiliary building ventilation) shall be

' completed, including the resolution of any retest deficiencies, prior to July 1, 1985, i

B.

For' initial startup test program tests in the 50%, 75%, 90% and 100% power sequences, procedures wMch haveimen approved by both the Station and PED shall be provided to Region III at least 30 calendar days before the start

d. ate of the applicable sequence.

C.

Prior to July 1, 1985, the licensee shall complete integrated testing of the Control Room (VC), Auxiliary Building (VA), Miscellaneous Electric Equipment Rooa (VE, anf ESF Switchgear PJom (VX) ventilation systems in all modes of operation to demonstrate that the Control Room _ envelope can be maintained at a positive 1/8 inch water gauge differential pressure-with respect to adjacent areas.

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ATTACHMENT 2 EMERGENCY RESPONSE CAFABILITIES The licensee shall complete. the_ following requirements of NUREG-0737 Supple-ment #1,on.the.sch.edule.noted below:

1.

Detailed Control Room Design' Review (DCRDR)

The licensee shall s'ubmit the final summary report f5r the DCRDR by December 1, 1986.

2.

Reculatory Guide 1.97, RevisiU~n 2 Compliance

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The licensee sha11' submit by March 1, 1987, a preliminary report describing how the requirements of Regulatory Guide 1.97, Revision 2 have been or will be met. The licensee shall submit by September 1, 1987, the final report and a schedule for im the NRC approves the DCRDR by March 1, 1987)plementation (assuming

3. -Upgrade Emergency Op4 rating Procedures (EOPs)

The licensee shall submit a Procedures Generation Package within 3 months of NRC approval of Westinghouse Owners Group (WOG) Emergency Procedure Guidelines (EPG) Revision 1.

The licensee shall implement the upgraded E0Ps based on WOG E0Ps Revision 1 within 12 months of NRC

, approval of WOG EPG Revision 1.

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4.

Buergency Response Facilities The 11'censee shall implement the Emergency Response Facility meteoro-

. logical A-model by January 1,1986.

5.

Safety' Parameter Display System (SPDS)

The licensee shall have SPDS operational by March 30, 1985.

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