ML20210L832
| ML20210L832 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/25/1986 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Bernero R, Rossi C, Speis T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8610030223 | |
| Download: ML20210L832 (14) | |
Text
%
.o 2 5 SEP 1986 MEMORANDUM FOR:
Themis P. Speis, Director, DSR0 Charles E. Rossi, AD/PWR-A Robert M. Bernero, Director, Division of BWR I.icensing Frank J. Miraglia, Director, Division of PWR licensing-B Edward S. Christenbury, Director & Chief Counsel, OGC Edward I.. Jordan, Director DEPER, IE William T. Fussell, Director, DFFS Robert F. Burnett, Director, DS, NMSS C. Norelius, Director Division of Reactor Projects, Region III G. Wayne Kerr, Director, SP Richard E. Cunningham, Director Division of Fuel Cycle & Material Safety, NMSS-1
\\
- FROM
Thomas M. Novak, Acting Director Division of PWR I,1 censing-A i
SUBJECT:
FINAL. DRA DWOOD STATION, UNIT 1 FACILITY OPERATING LICENSE
~
l A copy of the Final Draft of the Facility Operating 1.icense for Braidwood Station, Unit 1 is provided as,an enclosure. This license authorizes the applicant to load fuel and conduct certain precritical testing pursuant to 10 CFR 50.57(c). This draft license has been modified to reflect all comments received from your staff to date. A draft of Attachment I to the license is requested from Region III.
Please provide your comments and concurrence to the Braidwood Project Manager, J. A. Stevens, (x27702, MS110) by October 1, 1986, in order to support the projected fuel load date of October 15, 1986.
Thomas M. Novak, Acting Director Division of PWR I.icensing-A l
l Distribution
,; Docket-File *'
I. Dinitz, SP J. Partlow*
PWR PD#5 OEI.D B. Grimes
- J. Stevens*
OPA E. Jordan
- V. Noonan*
P. Denton/R. Vollmer I.. Parmon*
M. Rushbrook*(5)
S. Treby, OEl.D*
E. Jordan
- l J. Saltzman, SP B. Vogler, OELD*
F0B BC* & reviewer for local PDR W. I.amb, P&RAB appropriate Division NRC POR R. Diggs,l.FMB E. Putcher Tech. Specialist Name*
T. Barnhart (4)*
Inez Bailey
- ACRS (10) b J
q tr fN o
PD#5 B
PWR-A DIR:PD#5 Aj JSte ns:ss TNovak VNoonan
/U 9/p// 6 9/1f/86 9
86 l
8610030223 860925 PDR ADOCK 05000406 A
FDR
e snuqk UNITED STATES
[g g
NUCL. EAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 O
1
\\*****/
gp $b.o 7g MEMORANDUM FOR:
Themis P. Speis, Director, DSR0 Charles E. Rossi, AD/PWR-A Robert M. Bernero, Director, Division of BWR licensino Frank J. Miraglia, Director, Division of PWR I.icensing-B Edward S. Christenbury, Director & Chief Counsel, 0GC Edward I.. Jordan, Director DEPER, IE William T. Russell, Director, DPFS Robert F. Burhett, Director, DS, NMSS C. Norelius, Director Division of Reactor Projects, Region III G. Wayne Kerr, Director, SP Richard E. Cunningham, Director Division of Fuel Cycle & Material Safetv, NMSS FROM:
Thomas M. Novak, Acting Director Division of PWR licensing-A SUP1ECT:
FINAI. DRAFT BRAIDWODD STATION, UNIT 1 FACII.ITY OPERATING l.ICENSE A copy of the Final Draft of the Facility Operating 1.icense for Braidwood Station, Unit 1 is provided as an enclosure. This license authorizes the applicant to load fuel and conduct certain precritical testing pursuant to 10 CFR 50.57(c). This draft license has been modified to reflect all comments receivad from your staff to date. A draft of Attachment I to the license is requested from Region III.
Please provide your comments and concurrence to the Braidwood Project Panager, J. A. Stevens, (x27702, MS110) by October 1, 1986, in order to support the projected fuel load date of October 15, 1986.
I
'l
(
.. h \\ d t.u s 0 v 4 Thomas M.
ovak, Acting Director Division of PWR I.icensing-A
Enclosure:
As stated
[
UNITED STATES p '$ [n p q, kb / ' i..
e g
NUCLEAR REGULATORY COMMISSION N
^l WASHINGTON, D. C. 20555
'j }&Ll h a
2 - SEF SV Docket No.:
STN 50-456 Mr. Dennis I.. Farrar Director of Nuclear I.icensing Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
Subject:
Issuance of Facility Operating I.icense NPF Braidwond Station, Unit'l The U. S. Nuclear Regulatory Commission (NRC) has issued the enclosed Facility Operating 1.icense NPF-59, together with Technical Specifications and Environmental Protection Plan for Braidwood Station, Unit 1.
I.icense No.
NPF-59 authorizes fuel loading and precriticality testing for Braidwood Station, Unit 1, and is issued without prejudice to future consideration by the Commission.
Enclosed is a copy of a related notice, the original of which has been forwarded to the Office of the Federal Register for publication.
Five signed copies of Amendment No.
to Indemnity Agreement No. B-which covers the activities authorized under I.icense No. NPF-59 are also enclosed.
Please sign both copies and return one copy to this office.
Safety Evaluation Report Supplement No. 2 (SSER 2) was prepared in support of issuing the enclosed license. Enclosed is a pre-printed copy of SSER 2.
Twenty (20) bound copies of SSER 2 will be sent to you in the near future.
Sincerely, Thomas M. Novak, Acting Director Division of PWR I.icensing-A Office of Nuclear Reactor Regulation
Enclosures:
1.
Facility Operating 1.icense NPF-59 2.
Federal Register Notice 3.
Amendment No.
to Indemnity Agreement No. 8-4.
Supplement No. 2 to the Safety Evaluation Report I
cc: w/ enclosures:
nqgry See next pace
.,3,...'y
[
.t I
,( p m c h UNITED STATES n p p sn. v oq
~d R%5 y
p3 NUCLEAR REGULATORY COMMISSION
.)>klsa 5
'f W ASHINGTON, D. C. 20555
\\...../
2 5 SEF 1W COMMONWEALTP EDIS0N COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 FACILITY OPERATING LICENSE license No. NPF-59 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that for purposes of loading' fuel and conducting precritical testing:
A, The application for a license filed by Comironwealth Edison Company (the licenseel 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; 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 Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0, 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 Commission's regulations set forth in 10 CFP Chapter I (except as exempted from compliar,ce in Section 2.0. below);
E.
Commonwetith Edison Company is technically Qualified to engage in the activ ties authorized by this license in accordance with the Commissi s's regulations set fnrth in 10 CFR Chapter I; F.
Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements " of the Commission's regulations:
J in
DRAFT
~
~
-p-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; P.
After weighing the environmental, economic, technical, and cther benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating I.icense No NPF-59, sub.iect 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, possession,'and use of source, byproduct 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 1.icense 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 mi southwest of the Kankakee River, 20 mi south-soutwest of the town of Joliet, and 60 mi 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.
Sub. ject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Commonwealth Edison Company (CECO), pursuant to Cection 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 AnaTysis Report, as supplemented and amended; (3) 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:
BRAFT
DRAFT
. ~
a.
Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area, b.
New fuel asserblies may be stored in the Spent Fuel Storage Pool subject to the following additional conditions:
1.
The maximum U-235 enrichment shall be 3.22 w/o.
2.
The fuel assemblies shall be stored in a checherboard pattern, c.
No more than one fuel assembly shall be out of its shipping container, storage location, 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.
(4) 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; (5) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as reouired 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 (6) 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 Corrmission'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 additionel conditions specified or incorporated below:
DRAFT
(1) Maximum Power f.evel The licensee is authorized to load fuel and conduct preoperational tests and startup tests in accordance with the conditions specified herein.
Pending Commission approval, this license is restricted to fuel loading and precritical operations.
(2) Technical Specifications and Enviorrrental 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, the Fire Protection Program report, and the Fire Protection of Safe Shutdown Capability report for the facility through Amendment No. 47 and as described in submittals dated
,and as approved in the SER dated November 1983 (and Supplement 21 sub. ject 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.
(4) Emergency Planning (Section 13.3, SSER 2)
In the event that 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 ma.jor substantive problem exists in achieving or maintainino an adeouate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s')(2) will apply.
- 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.
MAFT
DRAFT
~ (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 18.0, SSER 2)
The licensee shall submit the final summary report for the DCRDR by Deqember 1, 1986.
(7) Regulatory Guide 1 97, Revision ? 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 DCCDR by March 1, 1987).
(8) TVI Item II.F.1, Iodine / Particulate Samplino (Section 11.5, SSER 2)
Prior to startup following the first refueling outage, the licensee shall demorstrate that the operating iodine / particulate sampling system will perform its intended function.
(9) Emergency Diesel Enoine Auxiliary Support Systems (Section 9.5.4.1, SSER 11
'~
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 necessaryl 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 core and makeup water during fuel loading and l
DRAFT
. precriticality testing. The licensee shall take the following special measures to verify that sources of unborated water will be isolated from the reactor coolant system (RCSI 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 system to verify that the bcyron concentration is at least 2000 ppm.
- c. The appropriate valves listed in Attachment A and B will be trechanically locked closed with chains and padlocks to prevent unborated water or borated water at concentration levels less than 2000 ppm frcm 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.
D.
The facility requires exemptions from certain recuirments 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, (b) an exemption from GDC-13 and GDC-17 of Appendix A, the requirement 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. These exemptions are authorized by law, will not present an undue risk to the public l
health and safety, and are consistent with the common defense and MMT r
a
DRAFT 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 Commission.
In addition, an exemption was previously granted pursuant to 10 CFR 50.12. A partial exemption from those portions of General Design Criteria 4 of Appendix A to 10 CFR 50 (which require protection of structures, systems and" components important to safety acainst dynamic effects associated with postulated reactor coolant system pipe breaks) was granted on October 28, 1985, for a period ending with the completion of the second refueling outage for Braidwood Station, Unit 1 or the adoption of the proposed rulemaking for modification of GDC-4 whichever occurs first. Effective May 12, 1986, GDC-4 has been modified to exclude from the design basis the protection of structures, systems and components against dynamic effects associated with postulated pipe ruptures of primary coolant loop piping in PWRs when analyses demonstrate the design basis conditions (51 FR 12502 April 11, 1986)y low under probability of rupture of such piping to be extremel 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 Commission 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.
Uhe Security Personnel Training and Qualification Plan and the Safeguards Contingency Plan are Appendices to the Security Plan. As reouested by CECO letter dated April 22, 1983, Revision 6 is to be considered "the initial formal submittal."
DRAFT
DRAFT 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(bl, (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, as amended, to cover public liability claims.
P.
This license is effective as of the date of issuance and shall expire at midnight on
, 2026.
FOR THE NUCl. EAR REGUI.ATORY COMMISSION Parold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Appendix A - Technical Specifications (NUREG-1223)
- 2. Appendix 8 - Environmental Protection Plan Date of Issuance:
- u. -
DRAFT
ATTACHMENT A VALVES ISOLATING DTRECT UNBORATED WATER SOURCES TO RCS Valve EPN P&ID/ Location Type Status 1CV111B M64-4 B4 Air Operated Always Locked closed ICV 8439 M64-4 C4 Manual Always Locked Closed ICV 8453 M64-4 D2 Manual Always Locked Closed ICV 8441 M64-4 B1 Manual Always Locked Closed OA3010 M65-5A D3 Manua,1 Always Locked Closed ICV 8523A 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 ge e a
e 1
+
ATTACHMENT B VALVES ISOLATING OTHER UNBORATED WATER SOURCES I.
INDIRECT SOURCES OF UNBORATED WATER TO REACTOR COOLANT SYSTEM Valve EPN P&TD/ 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 2AB8629B M65-1B A3 Manual Always Locked Closed OAB009B.
M65-2A E6 Manual Always Locked Closed 0AB8557B M65-2A E4 Manual Always Locked Closed OAB023B M65-2A E3 Manual Always Locked Closed OAB8563A 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 u-2AB022 M65-2C C7 Manual Always Locked Closed 2PS142 M140-5 E8 Manual Always Locked Closed 1AB8629A M65-1B A3 Manual Locked Closed Exceot During OB HUT Makeup to RCS 1CV8553 M65-2C D7 Manual Locked Closed During OB HUT Makeup to RCS 1AB8551 M65-2C D7 Manual Locked Closed During OB HUT Makeup to RCS
~
=
8 ATTACHMENT B (Cont.)
II.
OTHER CONSERVATIVE ACTIONS Valve EPN P&ID/ Location Type Status i
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 Clesed Except When Shell Side Vent is Locked Closed ICV 032A M64-5 B2 Manual Locked Closed Except When Shell Side Vent is Locked Closed ICV 032B M64-5 D2 Manual Locked Closed Except When Shell Side Vent is Locked Closed v-ICV 9527A M64-6 B6 Manual Locked Closed Except When Sluicing Domineralizer Resin l
1CV8521 M64-6 AS Manual Locked Closed Except When Sluicing Demineralizer Resin 1CV8527B M64-6 B4 Manual Locked Closed Except When sluicing Demineralizer Resin OAB8618A M65-3 E3 Manual Always Locked Closed 0AB8618B M65-6 E3 Manual Always Locked Closed
.. _. -. - _.. - - - - - -. -