ML20247N902
| ML20247N902 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 07/26/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20247N908 | List: |
| References | |
| NPF-37-A-031, NPF-66-A-031, NPF-72-A-021, NPF-77-A-021 NUDOCS 8908030223 | |
| Download: ML20247N902 (12) | |
Text
{{#Wiki_filter:. _, O' digc
- [
'og UNITED STATES J g NUCLEAR REGULATORY COMMISSION 7,.
- p
~ WASHINGTON, D. C. 20EiS5 %,...../ k COMMONWEALTH EDISON COMPANY DOCKET NO. 50-454 LYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-37~ 1. The Nuclear Regulatory Commission (the Commission) has found that: 'A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 17, 1987, supplemented May 6, 1988 and June 23, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commissien; C. There is reasonable assurance (i) that the activities authorized by this amendment 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; D. The. issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows: 890803o223 ggoygg gDR ADOCK 0500o454 PDC
L. l;.. 2-(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 31 and the Environmental Protection Plan a containe' 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. l
- 3..
This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION L l Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects i l l
Attachment:
l-Changes to the Technical Specifications Date of Issuance: July 26, 1989 l
b + ~ k. Ld arc L, 'og. UNITED STATES ' f T)%,,().;/ . p NUCLEAR REGULATORY COMMISSION 5 E WASH 6NG f 0N,0. C. 20555 % M.... i COMMONWEALTH EDISON ~ COMPANY 00CKET N0. 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l Amendment No. 31 License No. NPF-66 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 17, 1987, supplemented May 6, 1988 and June 23, 1989, complies with the standards and requirements of the Atomic l Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1 L C. There is reasonable assurance (i) that the activities authorized by this amendment 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; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and i paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows: 1 I
t 1 l (2) Technical Specifications The-Technical Specifications contaised in Appendix A (NUREG-1113), as revised through Amendment No. 31. and' revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 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. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION 9 q c. cML Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Chancas to the Technical Spe;ifications Date of Issuance: July 26, 1989 i i i
i ATTACHMENT TO LICENSE AMENDMENT NOS. 31 AND 31 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. 50-454 AN') 50-455 Revise Appendix A as follows: Remove Pages Insert Pages 3/4 4-20 3/4 4-20 c__-
REACTOR COOLANT SYSTEM L3/4.4.6 RE CTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION'FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE: The Containment Atmosphere Particulate Radioactivity Monitoring System, a. b. The Containment Floor Drain and Reactor Cavity Flow Monitoring System, and c. The Containment Gaseous Radioactivity Monitoring System. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: . ith'a. or c. of the above required Leakage Detection Systems inoperable, W a. operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed for gaseous and particulate radioactivity at least once per 24 hours when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. b. With b. of the above required Leakage Detection Systems inoperable, restore to.0PERABLE status within 7 days; otherwise be in at least HOT STANDBY 'within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. With a. and c. of the above required Leakage Detection Systems inoperable: c. 1) Restore either Monitoring System (a. or c.) to OPERABLE status within 72 hours and 2) Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours, and 3) Perform a Reactor Coolant System water inventory balance at least once per 8 hours. Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by: a. Containment Atmosphere Gaseous and Particulate Monitoring System-perfctmance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, BYRON - UNITS 1 & 2 3/4 4-20 AMENDMENT NO.il _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ = _ _ _ _ _ - _ _ _ _ _ _ _ _ _ ~
l:- ( sw [7 'o,, UNITED STATES g NUCLEAR REGULATORY COMMISSION 5 -l WASHINGTON, D. C. 20555 l.. = f ....+ COMMONWEALTH EDISON COMPANY l DOCKET N0. 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l Amendment No.E.1 License No. NFF-72 1. The Nuclear Regulatory Commission (the Commission) has found that: A. 'The application for amendment by Commonwealth Edison Company (the licensee) dated June 17, 1987, supplemented May 6, 1988 and June 23, 1989, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Commission's rules and regulations set forth in 10 CFR Chapter.I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 'C. There is reascnable assurance (i) that the activities authorized by this amendment 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; D. The istuance of this amendment will not be inimical.to the common defense and security or to the health and safety of the public; and j t E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and paratraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amenced to read as follows: l )
x. 3 - F. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 21 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. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION. (- Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: July 26, 1989-l L_______..___..__.
'L dha V o 8' ~g UNITED STATES NUCLEAR REGULATORY COMMISSION n WASHINGTON, D. C. 20555 E ag...../ COMMONWEALTH EDISON COMPANY DOCKET NO. 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-77 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 17, 1987, supplemented May 6, 1988 and June 23, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comiaission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conduc.7d without endangering the health and safety of the public, and (ii) +'at such activities will be conducted in compliance with the Commissicn's regulations; I D. The issuance of this amendment will not be inimical to the common I defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. l l 2. Accordingly, the license is amended by changes to the Technical Specifica-l- tion as indicated in the attachment to this license amendmert, and para-l graph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows: l' lL__.--__--
l \\ l (2) Technical Specifications The Technical Specifications contained in Appenoix A as revised through Amendment No. 21 and the Et'<ironmental Protection Plan I contained in Appendix B, both of which were attached to License No. HPF-72, dated July 2,1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. iLis license ctnendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY C0t1 MISSION C - [W Paul C. Shemanski, Acting Director Project Directorate 111-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: July 26, 1989
.i i
- ATTACHMENT TO LICENSE AMENDMENT I405. 21 AND 21 FACILITY OPERATING LICENSE N05. NPF-72 AND NPF-77 DOCKET N05. 50-456 AND 50-457 Revise Appetidix A as follows:
Remove Pages Insert Pages 3/4'4-20 3/4 4-20 I
e REACTOR COOLANT SYSTEM-3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECT' ION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE: The Containment Atmosphere Particulate Radioactivity Monitoring System, a. b. The Containment Floor Drain and Reactor Cavity Flow Monitoring System, and c. The Containment Gaseous Radioactivity Monitoring System. APPLICABILITY: MODES 1, 2, 3,'and 4. ACTION: With a. or c. of the above required Leakage Detection Systems inoperable, a. operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed for gaseous and particulate radioactivity at least orce per 24 hours when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. b. With'b. of the above required Leakage Detection Systems inoperable, restore to OPERABLE status within 7 days; otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. c. With a. and c. of the above required Leakage Detection Systems inoperable: 1) Restore either Monitoring System (a. or c ) to OPERABLE status within 72 hours and 2) Obtain and analyze a grab sample of the containment atmosphere for j gaseous and particulate radioactivity at least once per 24 hours, and 3) Derform a Reactor Coolant System water inventory balance at least once per 8 hours. Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by: a. Containment Atmosphere Gaseous and Particulate Monitoring System-performance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, b. Containment Floor Drain and Reactor Cavity Flow Monitoring System-performance of CHANNEL CALIBRATION at least once per 18 months,# and c. Verify the oil separator portion of the containment floor drain l-collection sump has been filled to the level of the overflow to the containment floor drain unidentified leakage collection weir box once per 18 months, following refueling, and prior to initial startup.
- The specified 18 month interval may be extended to 32 months for cycle 1 only.
.BRAIDWOOD - UNITS 1 & ' 3/4 4-20 AMENDMENT NO. 21 =_a L _.}}