ML20210P455
| ML20210P455 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/30/1987 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20210P460 | List: |
| References | |
| NUDOCS 8702130390 | |
| Download: ML20210P455 (9) | |
Text
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.ma are UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
- E WASHINGTON, D. C. 20555
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COMMONWFALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-66 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for a license filed by Commonwealth Edison Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all reqrired notifications to other agencies or bodies have been duly made; B.
Construction of Byron Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No.
CPPR-131 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance 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 activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.0. below);
E.
Comonwealth Edison Company is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F.
Comonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations;
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G.
The issuance of this license will not be inimical to the comon defense and security or to the health and safety of the public;.
H.
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-66, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached 4
4 as Appendix B to License No. NPF-37, issued February 14, 1985, is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40 and 70.
l 2.
Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-66 is hereby issued to Comonwealth Edison j
Company (the licensee) to read as follows:
A.
- This license applies to Byron Station, Unit 2, a pressurized 4
water reactor, and associated equipment (the facility) owned by Comonwealth Edison Company. The facility is located in north i
central Illinois within Rockvale Township, Ogle County, Illinois i
and is described in the Byron /Braidwood Station's Final Safety j
Analysis Report, as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.-
l B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses:
j (1) Commonwealth Edison Company (Ceco), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and i
operate the facility at the designated location in i
Ogle County, Illinois, in accordance with the procedures and limitations set forth in this license; i
j (2) Ceco, pursuant to the Act and 10 CFR Part 70, to receive, i
possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for i
storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; j
f (3) Ceco, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and i
special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation
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monitoring equipment calibration, and as fission detectors in j
amounts as required; t
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4 3 (4) CECO, 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) CECO, 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 Comission's regulations set forth in 10 CFR Chaoter I and is subject to all applicable provis' ions 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 Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 5 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) initial Test Program Any changes to the Initial Startup Test Program described in Chapter 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(4) Regulatory Guide 1.97, Revision 2 Compliance The licensee shall 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 implementation (assuming the NRC approves the DCRDR by March 1, 1987).
,e g The facility requires an exemption from the requirements of Appendix J D.
to 10 CFR Part 50, Paragraph III.D.2(b)(fi) of the testing of contain-ment air locks at times when containment integrity is not required (SERSection6.2.6).
This exemption is authorized by law, will not present an undue risk to the p;blic health and safety, and is consistent with the common This exemption is hereby granted. The special defense and security.
circumstances regarding the exemption are identified in the referenced section of the safety evaluation report and the supplements thereto.
This exemption is granted pursuant to 10 CFR 50.12 (51 FR 37096 dated October 17,1986). With this exemption, 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 Comission.
The An exemption was previously granted pursuant to 10 CFR 70.?4.
exemption was granted with NRC materials license No. SNM-1916, issued March 4, 1985, and relieved the licensee from the requirement of havina Therefore, the licensee is exempted from a criticality alarm system.
the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
The licensee shall implement and maintain in effect all provisions E.
of the approved fire protection program as described in the licensee's Fire Protection Report through Amendment 8 and the licensee's letters dated September 23, 1986, October 23, 1986, November 3, 1986, December 12 and 15, 1986, and January 21, 1987, and as approved in the SER dated February 1982 through Supplement No. 8, sub.iect to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
The licensee shall fully implement and maintain in effect all F.
provisions of the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the The plans, which authority of 10 CFR 50.90 and 10 CFR 50.54(p).
contain Safeguards Information protected under 10 CFR 73.21, are Comonwealth Edison Company Byron Nuclear Power Station entitled:
Physical Security Plan, Security Personnel Training and Qualification Plan, and Safeguards Contingency Plan"* with revisions submitted through December 9, 1986, i
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. G.
Except as otherwise.provided in the Technical Specifications or
~ Environmental Protection Plan, the licensee shall report any violations of the requirments 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).
H.
The licensee shall have and 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.
I.
This license is effective as of the date of issuance and shall expire at midnight on November 6, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION lf Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Work Items to be completed
- 2. Revision to Appendix A -
Technical Specifications (NUREG-1113)
Date of Issuance: January 30, 1987 PD#3 RAB P
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ATTACHMENT 1 TO BYRON STATION UNIT 2 OPERATING LICENSE NPF-66 This attachment identifies specific items which must be completed to the Consnission's satisfaction in accordance with the operational modes as identified below:
A.
The preoperational tests and testing deficiencies in Attachments A and B, respectively, of the November 3,1986 letter from K. A. Ainger to H. R. Denton, as modified by the January 14, 1987 letter from K. A. Ainger to H. R. Denton, shall be completed in accordance with the schedule comitments contained in those attachments.
B.
Until testing of the Unit 2 Auxiliary Building ventilation system is complete, including post test review and approval by PED, the licensee shall not operate Byron Unit 2 at power levels exceeding 30%, unless the Auxiliary Building ECCS leakage can be shown to be below the corresponding limit presented in Figure 1 of the October 24, 1986 letter S. C. Hunsader to H. R. Denton.
Leak rate determination shall be in accordance with the October 30, 1986, letter, S. C. Hunsader to H. R. Denton, and performed three times:
1.
Prior to exceeding 30% power, 2.
During the first two weeks of April 1987, and 3.
During the first two weeks of July 1987.
4.
Should Unit 2 be in an outage condition during the periods specified in paragraphs B.2, B.3 above, the leakage rate determinations shall be performed within the first two weeks after returning to power.
In the event that total leakage during any of these tests is GREATER than the value for the corres-ting power level, the licensee shall, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate ACTION s o reduce the leakage to an acceptable value or reduce power in accordance with Figure 1 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C.
Prior to exceeding 5% power, the licensee shall seal all construction design penetration openings in designated fire barriers. Completion of nine (9) seals may be accomplished as requested in the S. C. Hunsader to J. G. Keppler letter dated January 13, 1987, and in addition, penetrations may be left unsealed to facilitate a requirement of a plant modification or plant maintenance requirement; however, the licensee shall provide compensatory measures.
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ATTACHMENT 2 TO NPF-66 REVISION TO NUREG-1113 Revise Appendix A Technical Specifications (NUREG-1113) by removing the page identified below and inserting the enclosed page. The overleaf page(*)
has been provided to maintain document completeness.
REMOVE INSERT 3/4 7-19*
3/4 7-20 3/4 7-20 4,+
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PLANT SYSTEMS 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7*
Three independent non-accessible area exhaust filter plenues (50%
capacity each) shall be OPERABLE.
APPLICA8ILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one non-accessible area exhaust filter plenum inoperable, restore the inoperable plenum to OPERABLE status within 7 days or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.7 Each non-accessible area exhatst filter plenum shall b's demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.
from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that operation occurs for at least 15 minutes; b.
At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or. charcoal adsorber housings, or.(2) following painting, fire, or chemical release in any ventilation zone communi-cating with the exhaust filter plenum by' u
1)
Verifying that the exhaust filter plenum satisfies'the in place penetration and bypass leakage testing acceptance criteria of less than 1% when using the test procedure guidande in Regulatory Positions C.5.a. C.5.c and C 5.d of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the flow rate is 66,900 cfm i 10% for the train and 22,300 cfm 110% per bank; 2)
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample from each bank of adsorbers of the train obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52. Revision 2. March A978, for methyl idodido penetration of less than 1% when telted at the temperature of 30*C and a relative humidity of 70%;
- Not applicable prior to July 1, 1985.
BYRON - UNITS 1 & 2 3/4 7-19 I
e PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)
Verifying a system flow rate of 66,900 cfm i 10% through the train and 22,300 cfm *10% per bank through the exhliust filter plenum during operation when tested in accordance with ANSI M510-1980; and 4)
Verifying that with the system operating at a flow rate of 66,900 cfm 110% through the train and 22,300 cfm 110% per bank and exhausting through the HEPA filter and charcoal adsorbers, the total bypass flow of the system and the damper leakage is less than or equal to 1% when the system is tested by admitting cold DOP at the system intake and the damper leakage rate is determined by either direct measurements or pressure decay measurements at a test pressure of 2 inches of water and the auxiliary building exhaust fans are operating at their rated flow.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, c.
within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained from each bank of adsorbers of the' train in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing cri-teria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, when the average for a methyl iodide penetration o,f less than 1% when tested at a temperature of 30'C and a relative humidity of 70%.
d.
At least once per 18 months by:
1)
Verifying for each filter bank of the train that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 6.0 inches Water Gauge while operating the exhaust filter plenum at a flow rate of 66,900 cfm + 10% through the
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train and 22,300 cfm 1105 per bank; 2)
Verifying that the exhaust filter plenum starts on manual initiation or Safety Injection test signal; and 3)* Verifying that the system maintains the ECCS equipment rooms at a negative pressure of greater than or equal to 1/4 in. Water Gauge relative to the outside atmosphere during system operation while operating at a flow rate of 66,900 cfm 110% through the train and 22,300 cfm 110% per bank.
After each complete or partial replacement of a HEPA filter bank, by e.
verifying that the exhaust filter plenum satisfies the in-place penetration testing acceptance criteria of less than 1% in accord-ance with ANSI N510-1980 for a D0P test aerosol while operating at a flow rate of 66,900 cfm t,10% through the train and 22,380 cfm 210%
per bank; and "Not applicable to Unit 2 until October 1, 1987.
BYRON - UNITS 1 & 2 3/4 7-20