ML20197B707

From kanterella
Jump to navigation Jump to search
License NPF-59 for Facility
ML20197B707
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 10/17/1986
From: Vollmer R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19303E337 List:
References
NUDOCS 8610300382
Download: ML20197B707 (11)
v • d • e


Text

.[

UNITED STATES NUCLEAR REGULATORY COMMISSION 2

o n

j WASHINGTON, D. C. 20$55

\\...../

COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-59 1.

The Nuclear Regulatory Commission (the Comission or the NRC) has found that for purposes of loading fuel and conducting precritical testing:

A.

The application for a license filed by Comonwealth 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 required notifications to other agencies or bodies have been duly made; B.

Construction of Braidwood Station, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No.

CPPR-132 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 Commission (except es 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.D. below);

E.

Commonwealth 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; h

861017 P

05000456 PDR

. ~

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; 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-59, 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 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.

2.

Based on the foregoing findings regard 0ng this facility, Facility Operating License No. NPF-59 is hereby issued to Commonwealth Edison Company (the licensee) to read as follows:

A.

This license applies to Braidwood Station, Unit 1, a pressurized water reactor, and associated equipment (the facility) owned by Commonwealth Edison Company. The facility is located in north eastern Illinois, 3 miles southwest of the Kankakee River, 20 miles south-southwest of the town of Joliet, and 60 miles southwest of Chicago, Illinois. The facility is within Reed Township, Will County, Illinois and is described in the Byron /Braidwood Stations' Final Safety Analysis Report, as supplemented and amended, and in the Environmental Report, as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

l (1) Commonwealth Edison Company (Ceco), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in Will County, Illinois, in accordance with the procedures and limitations set forth in this license; (2) CECO, 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) 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 special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

(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 facil.ity.

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 Level The licensee is authorized to load fuel and conduct preoperational tests and startup tests in accordance with the conditions specified herein and other items identified 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 this license. Pending Commission approval, this license is restricted to fuel loading and precritical operations.

(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 with the Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection (Section 9.5.1, SSER 2)*

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the SER dated November 1983 and its supplements, subject to the following provision:

  • 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.

^

a The licensee may make changes to the approved fire protection program w'ithout 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.

(4) Emergency Planning In the event tilat the NRC finds that the lack of progress in completion 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.

(5)

Initial Startup Test Program Any changes to the Initial Test Program described in Section 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.

(6) Detailed Control Room Design Review (DCRDR) (Section 18.2, SSER 2)

The licensee shall submit the final summary report for the DCRDR by December 1, 1986.

(7) Reoulatory 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).

(8) TMI Item II.F.1: Iodine / Particulate s'ampling (Section 11.5.2, SSER 2)

Prior to startup following the first refueling outage, the licensee shall demonstrate that the operating iodine / particulate sampling system will perform its intended function.

(9) Emergency Diesel Engine Aaxiliary Support Systems (Section 9.5.L.1, SSER 1)

Prior to startup following the first refueling outage, the controls and monitoring instrumentation on the local control panels shall be dynamically qualified for their location or shall be installed on a free standing floor mounted panel in such a manner (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.

(10) Inadvertent Boron Dilution The licensee shall maintain a boron concentration of at least 2000 ppm in the reactor coolant and makeup water during fuel loading and precriticality testing. The licensee shall take the following special measures to verify that the sources of unborated water will be isolated from the reactor coolant system (RCS) and that the boron concentration level in the RCS will be maintained at a level of at least 2000 ppm:

a. Grab samples will be manually taken from the reactor coolant and makeup water systems and analyzed at least once per shift to verify that the boron concentration is at least 2000 ppm.
b. The makeup water system will be sampled and analyzed each time any water is added to the RCS to verify that the boron concentration is at least 2000 ppm.
c. The appropriate valves listed in Attachment 2 will be mechanically locked closed with chains and padlocks to prevent unborated water or borated water at concentration levels less than 2000 ppm from flowing into the RCS.
d. Certain valves (e.g. the demineralizer sluice water inlet and outlet isolation valves) will be locked closed except for the infrequent occasions when an activity required by plant chemistry requires these valves to be opened for a short time interval (e.g.

replacement of demineralizer resin).

In order to preclude inadvertent dilution at these times, an independent confirmation of valve positions will be made by a separate person knowledgeable of the systems being used each time the valves are manipulated.

e. Each time valves are manipulated and water is added to the RCS, the licensee shall sample the RCS both before and after the addition of the water to determine the level of boron concentration of the water in the RCS and to ensure that the level is at or above 2000 ppm.

(11) Fresh Fuel Storage Until the core is loaded or the spent fuel pool is filled with water, the following conditions shall be imposed on fresh fuel storage in spent fuel racks:

Fuel assemblies shall be stored in such a manner that a.

water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.

l b.

New fuel assemblies may be stored in the Spent 4

3 Fuel Storage Pool subject to the following s

' additional conditions:

1.

The maximum U-235 enrichment shall be 3.22 w/o.

2.

The fuel assemblies shall be stored in a checkerboard pattern.

c.

No more than two fuel assemblies shall be out of their shipping containers, storage locations, or reactor vessel at any given time.

d.

The minimum edge-to-edge distance between the fuel assembly outside its shipping container, storage rack, or reactor vessel, and all other fuel assemblies shall be 12 inches.

(12) Inservice Inspection Program (Section 5.2.4, 6.6.3, SSER 2)

The licensee shall submit the inservice inspection program which conforms to the ASME code in effect 12 months prior to the date of this license, in accordance with 10 CFR Section 50.55a(g)(4),

for NRC staff review and approval within twelve months from the date of this license.

D.

The facility requires exemptions from certain requirements of Appendices A and J to 10 CFR Part 50. These include (a) an exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J, the testing of containment air locks at times when containment integrity is not required (SER Section 6.2.6); and (b) an exemption from GDC-13 and GDC-17 of Appendix A, the requiremer.t 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 (SSER 1, Section 9.5.4.1).

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto'. These exemptions are granted pursuant to 10 CFR 50.12. With 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 Comission.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1938, issued October 8, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is exempted from 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.

. ~

E.

The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Coninission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Braidwood Station Physical Security Plan,-Security Personnel Training and Qualification Plan,* and Safeguards Contingency Plan *" with revisions submitted through May 27, 1986.

F.

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).

G.

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, c_s amended, to cover public liability claims.

H.

This license is effective as of the date of issuance and shall expire at midnight on Oct.

17, 2026.

FOR THE NUCLEAR REGULATORY COMMISSION ichard H. Vollmer, Acting Director Office of Nuclear Reactor Regulation Attachments:

1.

Work Items to be completed 2.

Isolation Valves 3.

Appendix A - Technical Specifications (NUREG-1223) 4.

Appendix B - Environmental Protection Plan Date of Issuance: OCT 171986

l

w ATTACHMENT I This attachment identifies specific items which must be completed to the Commission's satisfaction in accordance with the operational modes as identified below.

The preoperational testing exceptions identified in the September 19, 1986, letter from Dennis Farrar to Harold R. Denton shall be completed in accordance with the scheduled commitments contained in that letter.

ATTACHMENT 2 VALVES ISOLATING DTRECT UNBORATED WATER SOURCES TO RCS Valve EPN PATD/ Location Type Status 1CV111B M64-4 B4 Air Operated Always Locked Closed 1CV8439 M64-4 C4 Manual Always Locked Closed 1CV8453 M64-4 D2 Manual Always Locked Closed 1CV8441 M64-4 B1 Manual Always Locked Closed OAB010 M65-5A D3 Manual Always Locked Closed 1CV8523A M64-6 C6 Manual Locked Closed Except When Sluicing Demineralizer Resin 1CV8515 M64-6 B5 Manual Locked Closed Except When Sluicing Demineralizer Resin 1CV8523B M64-6 C3 Manual Locked Closed Except When Sluicing Demineralizer Resin 1CV8428 M64-4 D5 Manual Always Locked Closed O

e l

-,.,_~,_ _ __,._ _ ______ _ _ -

ATTACHMENT 2 (Cont.)

VALVES ISOLATING OTHER UNBORATED WATER SOURCES T.

INDIRECT SOURCES OF UNBORATED WATER TO REACTOR COOLANT SYSTEM Valve EPN P&ID/ Location Type Status 1SI8936 M61-1B E7 Manual Always Locked Closed 1S18931 M61-1B D7 Manual Locked Closed When RWST is Making Up to RCS 1CV8434 M64-4 D4 Manual Locked Closed When RWST is Making Up to RCS OAB8494 M65-5A F3 Manual Locked Closed When Boric Acid Bat'ch Tank is Discharging 2AB8629R M65-1B A3 Manual Always Locked Closed OAB009B M65-2A E6 Manual Always Locked Closed OAB8557B M65-2A E4 Manual Always Locked Closed OAB023B M65-2A E3 Manual Always Locked Closed 0AB8563A M65-2B D4 Manual Always Locked Closed 2AB023 M65-2C C8 Manual Always Locked Closed 2AB8551 M65-2C D8 Manual Always Locked Closed 2CV8553 M65-2C D7 Manual Always Locked Closed 2AB022 M65-2C C7 Manual Always Locked Closed 2PS142 M140-5 E8 Manual Always Locked Closed 1AB8629A M65-1B A3 Manual Locked Closed Except During OB HUT Makeup to RCS 1CV8553 M65-2C D7 Manual Locked Closed During OB HUT Makeup to RCS 1ABB551 M65-2C D7 Manual Locked Closed During OB HUT Makeup to RCS

~

ATTACHMENT 2 (Cont.)

II.

OTHER CONSERVATIVE ACTIONS Valve EPN P&ID/ Location Type Status 1BR7053 M64-6 B8 Manual Always Locked Closed 1BR7054 M64-6 B7 Air Operated Always Locked Closed 2AB8468 M65-5A B6 Manual Always Locked Closed 2AB8465 M65-5A B4 Manual Always Locked Closed 1RH004C M62 F5 Manual Locked Closed Except When Shell Side Vent is Locked Closed 1RH004D M62 C6 Manual Locked Closed Except When Shell Side Vent is Locked closed ICV 008A M64-4 B8 Manual Locked Closed Except When Shell side Vent is Locked Closed ICVO32A M64-5 B2 Manual Locked Closed Except When Shell Side Vent is Locked closed 1CVO32B M64-5 D2 Manual Locked Closed Except When Shell Side Vent is Locked Closed ICV 8527A M64-6 D6 Manual Locked Closed Except When Sluicing Demineralizer Rosin 1CV8521 M64-6 A5 Manual Locked Closed Except When Sluicing Demineralizer Resin 1CV8527B M64-6 B4 Manual Locked Closed Except When sluicing Demineralizer Rosin OAB8618A M65-3 E3 Manual Always, Locked Closed 0AB8618B M65-6 E3 Manual Always Locked Closed

_...,

Retrieved from "https://kanterella.com/w/index.php?title=ML20197B707&oldid=4108150"