ML20058D803
| ML20058D803 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 10/31/1990 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058D781 | List: |
| References | |
| NUDOCS 9011060276 | |
| Download: ML20058D803 (12) | |
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,E ys, i g NUCLEAR REGULATORY COMMISSION s 'l WASHINGTON, D. C. 20555 ...../ COMMONWEALTH EDISON COMPANY i DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT l' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 t License No. DPR-39 1. The Nuclear Regulatory Comission (the Comission) has'found that: A. The application for amendment by Commonwealth Edison Company (thelicensee)datedOctober 17, 1986, as supplemented October 22, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1987, complies with the standards and re and the Comission'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. Comission;- 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 Comission's regulations; D. The issuance of this amendment will not be inimical' to the comon 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 P'rt 51 of the Comission's regulations and all' applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical' Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is'hereby amended to read as follows: 9011060276 901031 PDR ADOCK 05000295 p PDC
_. = - -. i l . ( (2) Technical Specifications l The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 120, are l hereby incorporated in the license. The licensee shall l operate the facility in accordance with the' Technical Specifications. 3. This license amendment is effective as'of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION [ l fu,r l Richard rrett, Director Project Directorate III-2 i Division of Reactor Projects - III, IV, Y and Special Projects Office of. Nuclear Reactor Reguation
Attachment:
Changes to the Technical Specifications l Date of Issuance: October 31, 1990 l l 1 s t ,,6
pnha ,,f. g'*,, + UNITED STATES -{ g NUCLE AR REGULATORY COMMISSION s ej wAssiNoTON, D. C. 20555 (..../ COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. DPR-48 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Commonwealth Edison Company (the licensee) dated October 17, 1986, as supplemented October 22, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1987, complies with the standards and re and the Comission'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 Comission; 1 C. There is reasonable' assurance (1) 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable ' requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical l Specifications as indicated in the attachment--to this license amendment, and paragraph 2.C.(2) of Facility Operating License i No. DPR-48 is hereby amended to read as follows: ~. - -..,
3 4 2 (2) Technical Specifications The Technical Specifications contained in Appendices-A and B, as revised. through Amendment No.109, are hereby incorporated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULAT RY COMMISSION lI w' jgqv Richar J. Barrett, Director Projec Directorate III-2~ Division of Re e. tor Projects - III, IV,' V and Special Projects -Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 31, 1990 Y
6 s t 4 ATTACHMENT TO LICENSE AMENDP.ENTS AMENDMENT NO.120 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.109 TO FACILITY,_0PERATING LICENSE NO. DPR-48 l DOCKET NOS. 50-295 AND 50-304 l Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. 1 - Remove Pages Insert Pages-80 80 99 99 100 100 101 101 102 102 103 103 i i 6* -,w -e ,----v
i LIM 111NG CONDITION FOR OPERA 110N SURVElttANCE REQUIRENENT t 3.3.2 (Continued) 4.3.2 B. The limit lines shown in Figures 3.3.2-1 and B. Not Applicable 3.3.2-2 shall be recalculated periodically as required, based on results from the material surveillance program. C. The secondary side of the steam generator .i must not be pressurized above 200 psig.lf C..Not Applicable i the temperature of the primary and secondary l coolant is below 70*F. D. 'The pressurizer heatup rate shall not exceed D. Not Applicable 100*F/hr and-the pressurizer cooldown rate l not exceed 200*F/hr. ' Tine spray ~ shall not be l used if the temperature difference between I the pressurizer:and-the spray fluid is l greater than 320*F. l l E. Hydrostatic Testing E. Not Applicable 1. System inservice leak and hydrotests shall be performed in accordance with i p the requirements of ASME Boiler and j Pressure Vessel-Code, Section XI and applicable-addenda; except as stated in Specification'4.3.4.C.1. t i l l l 3 I i Amendments 120 and 109 80
e LIM 111NG CONDIT10N FDF. OPERA 110N SURVEILLANCE REQUIREMENT i 3.3 4.3 4. Structural Integrity 4. Structural Integrity The structural integrity of the primary system A. General boundary shall be maintained at a level comparable to the original acceptance standards The baseline inspection and all subsequent throughout the life of a unit. Weld repairs In-Service Inspections shall be done by shall be made to the original acceptance levels. Individual contracts. As each contract period nears expiration, a review of the j 4 previous inspections shall be made in order to correlate past and future inspections. During this negotiation period, reviews will be conducted to take advantage of improvements in technology and to utilize-the latest developed equipment _for the inspection procedures. As always, decisions in regard to new inspection techniques sha11 he nede 'to comply with Section XI of the ASME Code regarding In-Service Inspections. B. Not applicable. l ) i l Amendments 120 and 109-99 i n. n. e r. 9.--
i LIMITING CONDITION FOR OPERA 110N SURVEILLANCE REQUIREMENT l I -i This page intentionally left blank 1 4 4 i 4 - a Amendments 120 and -If'9 100 .~...
LIMITING CONDITION FOR OPERAIlON SURVEILLANCE REQUIREMENT t i l 1 This page intentionally left blank 4 4 4 -e 1 Amendments 120 and 109 101 w .~ ~ - a v-
i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i 4.3.4 C. In-Service Inspection and Testing 1. Inservice Inspection and Testing of the ASME Code Class 1. Class 2. and-4 Class 3 components shall be performed in accordance with'Section XI of the l ASME Boller and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, Section 50.5$a(g)(6)(1). Inservice Inspection and Testing activities shall be. incorporated into other specified surveillance l requirements. The program shall be written in accordance with requirements of the ASME Section XI Inservice Inspection Code and will. ) include the utilization of the procedures developed for the 3-1/3, 6-2/3, and 10 year Inservice Insepctions...These procedures shall be used to perform baseline examination of the planned Inservice Inspection areas and shall also be used as a basis for comparing the baseline examination of the welds in 3 the system to future Inservice Inspection Results, as required by the ASME Section XI Inservice Inspection Code. i Amendments 120 and_109 102 2
LIMITING CDNDITION FOR OPERAll'ON SURVEILLANCE REQUIREMENT 4.3.4.C 2. Inspection following a Refueling Af ter a Reactor Coolant system is closed following opening for refueling all accessible pressure-retaining components, piping and/or valves of i the reactor coolant pressure boundary shall be visually examined in accordance with the requirements of ASME Section XI except as stated in Specification 4.3.4.C.1 for evidence of reactor coolant leakage while the system is under a test. I L i I l^ l l I 1 l t Amendments 120 and 109 103 '}}