ML20057F833
| ML20057F833 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 10/13/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F827 | List: |
| References | |
| GL-86-10, GL-88-12, NUDOCS 9310190219 | |
| Download: ML20057F833 (13) | |
Text
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- t UNITED STATES y
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j NUCLEAR REGULATORY COMMISSION
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t COMMONWEALTH EDISON COMPANY DOCKET N0. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AM_fNDMENT TO FACILITY OPERATING LICENSE Amendment No.148 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commisrion) has found that:
I A.
The application ror amendment by Commonwealth Edison Company (the licensee) dated December 22, 1992, 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; l
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 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 Specifications as indicated in the attachment to this license amendment, and paragraphs 2.C.(2) and 2.C.(5) of Facility Operating License No.
DPR-39 are hereby amended to read as follows:
- Page 6 is attached, for convenience, for the composite license to reflect this change.
9310190219 931013 PDR ADOCK 0500 5
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i (2)
Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
148, are hereby incorporated in the license. The licensee shall operate the facility in' accordance with the Technical Specifications.
(5)
The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as descrioed in the i
(Updated) Final Safety Analysis Report for the Zion Nuclear Power Station and as approved in the SERs dated Marcn 10, 1978, May 26, 1978, June 26, 1978, February 14, 1979, April 13, 1979, March 24, 1980, November 24, 1980, December 9, 1980,1-iarch 7, 1983, June 7, 1988, January 7, 1991, and August 27, 1993, subject to the following provision:
The licensee may make changes to the approved Fire Protection Program without prior approval of the i
commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
3.
This license amendment is effective as of the date of its issuanee and shall be implemented within 45 days from its date of issuance.
FOR THE ?!ULLEAR REGULATORY COMMISSION l
4W (.
W ames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation t
Attachment:
1.
License page 6 2.
Changes to the Technical Specifications Date of Issuance: Octo'oer 13, 1993 l
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(4) The licensee shall not operate the reactor in Mode 1 or 2 f as defined in Technical Specification Table 1.1) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted and approval for less than four loop operation in Mode 1 or 2 has been granted by the Commission by amendment to this license.
l l
(5) The licensee shall implement and maintain in effect all provisions of l
the approved Fire Protection Program as described in the (Updated) l Final Safety Analysis Report for the Zion Nuclear Power Station and as approved in the SERs dated March 10, 1978, May 26, 1978, June 26, 1978, February 14, 1979, April 13, 1979, March 24, 1980, November 24, 1980, December 9, 1980, March 7, 1983, June 7, 1988, January 7, 1991, and August 27, 1993, subject 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.
(6) The licensee shall fully implement and maintain in effect all provisions of the Cammission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.P ed 10 CFR 50.54(p).
The plans, which contain Safeguards Informauon protected under 10 CFR 73.21, are entitled:
" Zion Nuclear Power Station Security Plan," with revisions submitted through September 22, 1993; "7 ion Power Station Training and Qualification Plan," with revision submitted through March 2, 1993; and " Zion Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through i
December 4, 1992.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(revised 1-15-81; Am. 61; revised 10-11-88; kn.113)
(7)
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel 301 ;, described in the application dated January 15, 1992, as suppl 9ntrJ October 2 l
and 16, 1992.
l (a) Deleted i
(b) No loads heavier than the weight of a single spent fuel assembly plus the tool for moving that assembly shall be carried over fuel stored in the spent fuel pool. The spent fuel handling tool, the burnable poison tool, the rod cluster control changing fixture and the thimble plug shall not be carried at heights greater than two feet over fuel stored in the spent fuel pool.
(c)
(deleted 1-15-81; Am. 61)
(d)
(deleted 1-15-81; Am. 61)
Amendment No. 148 j
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[pucuglt UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20MiE-0001
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i COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-304 l
ZION NUCLEAR POWER' STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING' LICENSE Amendment No. 136 l
License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 22, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended-(the l
Act) and the Commission's rules and regulations set forth in l
10 CFR Chapter I r
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the i
Commission; j
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; l
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.-
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2.
Accordingly, the license
- is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, I
and paragraphs 2.C.(2) and 2.C.(5) of Facility Operating License No.
DPR-39 are hereby amended to read as follows:
,j l
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- Page 5 is attached, for convenience, for the composite license to reflect this change.
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g (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 136, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(5)
The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the (Updated) Final Safety Analysis Report for the Zion Nuclear Power Station and as approved in the SERs dated March 10, 1978, May 26, 1978, June 26, 1978, February 14, 1979, April 13, 1979, March 24, 1980, November 24, 1980, December 9, 1980, March 7, 1983, June 7, 1988, January 7, 1991, and August 27, 1993, subject to the following provision:
The licensee tay 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.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 45 days from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4*dc f.
GV James E. Dyer, Director Project Directorate III-2 Division of Reactor Prajects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
1.
License page 5 2.
Changes to the Technical Specifications 1
Date of Issuance:
October 13, 1993
)
9I
' i (3)
(deleted 3-11-83; Am. 72)
(4)
The licensee shall not operate the reactor in Mode 1 or 2 (as defined in Technical Specification Table 1.1) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted and approval for less than four loop operation in Mode 1 or 2 has been granted by the Commission by amendment to this license.
(5)
The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the (Updated) Final Safety Analysis Report for the Zion Nuclear Power Station and as approved in the SERs dated March 10, 1978, May-26, 1978, June 26, 1978, February 14, 1979, April 13, 1979, March 24, 1980, November 24, 1980, December 9, 1980, March 7, 1983, June 7, 1988, January 7, 1991, and August 27, 1993, subject 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.
(6)
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 i
CFR 73.55 (51 FR 27817 and 27822) and 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:
" Zion Nuclear Power Station Security Plan," with revisions submitted through September 22, 1993; " Zion Power Station Training and Qualification Plan," with revision submitted through March 2, 1993; and " Zion Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through December 4,1992. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(revised 10 '
88; Am. 102) i Amendment No.136
1 1
ATTACHMENT TO LICENSE AMENDMENTS i
AMENDMENT NO. 148 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 136 TO FACILITY OPERATING LICENSE NO. DPR-48 t
DOCKET NOS. 50-295 AND 50-304 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.
Remove Paaes Insert Paaes iv iv xi xi 2950 295D-V 295E 295F 295G 295H 2951 295J 295K 295L 295M 295N 2950 295P 295Q r
295R t
2955 295T 295U 295V 300 300 301 301 324 324 l
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SURVEILLANCE LltilTING CONDITION FOR OPERATION RE0VIREMENT EA_G.E 3.13 Refueling Operations 4.13 243 3.13.1 Core Reactivity 4.13.1 243 3.13.2 Protection from Damaged Spent Fuel 4.13.2 244a 3.13.3 Containment Status 4.13.3 246 3.13.4 Radiation Monitoring 4.13.4 246a 3.13.5 Refueling Equipment Checkout 4.13.5 246a 3.13.6 Refueling Equipment Operability 4.13.6 246a 3.13.7 Spent Fuel Pit Cooling Systems 4.13.7 246a 3.13.8 Fuel Inspection Program 4.13.8 247 3.13.9 Residual Heat Removal 4.13.9 247a System Operation 3.13.10 Water Level - Reactor Vessel 4.13.10 247c 3.13.11 Water Level - Storage Pool 4.13.11 247d 3.13.13 Spent Fuel Pool Storage 4.13.13 247c 3.13.14 Spent Fuel Storage Pool Boron Concentration 4.13.14 247e Bases 248 3.14 Plant Radiation Monitoring 4.14 250 Bases 254 3.15 Auxiliary Electrical Power System 4.15 255 Bases 271 3.16 (Section Deleted) 275 3.17.1 Ventilation 4.17.1 281 3.17.2 (Section Deleted) 283 Bases 287 3.18 Steam Generator Activity 4.18 289 Bases 290 3.19 Failed Fuel Monitoring 4.19 292 Bases 293 3.20 (Section Deleted) 4.20 295a 3.21 (Section Deleted) 4.21 2950-V l
3.22 Shock Suppressors (Snubbers) 4.22 295W Bases 295AA8 3.23 (Section Deleted) 295AB 3.24 Sealed Source Contamination 4.24 295AD Bases 295AF TABLE OF CONTENTS (Continued) iv Amendment Nos.148 and 136
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Table Paae 4.15-1 Deleted 270 4.15-2 Diesel Generator Test Schedule 270a 4.16-1 Deleted 280 4.17-1 Charcoal Filters 284 4.17-2 HEPA Filters 286 4.19-1 Deleted 295 4.21-1 Deleted 2950-V 4.21-2 Deleted 295D-V 4.21-3 Deleted 2950-V 1
4.21-4 Deleted 295D-V 4.21-5 Deleted 2950-V 6.6-1 Special Reports 323 6.8-1 Boundary Doors for Flood Conditions 328 LIST OF TABLES (Continued) xi Amendment Nos.148 and 136
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6.0 60!ilNISTRATIVE C0111ROLS 6.1 Organization, Review, Investigation, and Audit 1.
Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
safety of the nuclear power plant.The onsite and offsite organt7ations shall include the positions for activities aff Lines of authority, responsibility, and communication shall be established and defined for the highest a.
management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activity and Section 6 Inttr-Departmental Relationships, b.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
The Senior Vice President Nuclear Operations shall have corporate responsibility for overall plant c.
nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to an appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
2.
Deleted.
3.
The shift manning for the station shall be as shown in Figure 6.1-1.
The Assistant Superintendent Operating, Operating Engineer, Shift Engineers, and Shift Foreman shall have a Senior Reactor Operators License.
The Fuel Handling Foreman shall have a Senior Reactor Operator or Limited Senior Reactor Operators License.
The Vice President PHR Operations on the corporate level has responsibility for the Fire Protection Program.
An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program.
300 Amendment Nos. 148 and 136 A
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(Continued) 6.1.4 Qualifications of the Station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1 " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971 with the exception of the Health Physics Supervisor or lead Health Physicist, who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8 September, 1975.
The Shift Control Room Engineer shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients, and accidents.
individual filling the position of Technical Superintendent shall meet the minimum acceptable level for The
" Technical Manager" as described in 4.2.4 of AN3I N18.1, 1971.
5.
Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
6.
Retraining shall be conducted at intervals not exceeding two years.
7.
The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsib111tles and authorttles outilned below:
Offsite Review And Inygitigative Funit10D A.
The Superintendent of the Offsite Review and Investigative Function shall be appointed by the Hanager of Quality Assurance / Nuclear Safety (QA/NS).
the Manager of QA/NS and shall be independent of Operations.The Corporate Audit Function shall be the resp The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS.
The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
1.
The Superintendent of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative function and' appoint a senior participant to provide appropriate direction, (2) select each participant for this function, 301 Amendment Mos.148 and 136 j
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6.6.3.8 Special Reports (Continued)
TOPIC SUBMITTAL DATE 1.
Pressurizer PORV or Safety Valve Document the event in the Annual Report challences J.
(Future) k.
Steam generator tube inspection and/or Per surveillance requirements 4.3.1.B.5 plugging.
1.
Emergency Core Cooling System (ECCS)
Within 30 days as LER - include nozzle usage actuation and injection when RCS temp 2 factor per T.S. 3.3.2.F.3 350*F m.
Diesel generator failures Per surveillance requirement 4.15.1.B.5 n.
Post Accident Radiation monitor Within 14 days per T.S. Table 3.14-1 to the inoperable greater than 7 days Regional Administrater of the NRC Regional Office.
SPECIAL REPORTS Table 6.6-1 (Continued) 324 Amendment Nos.148 and 136
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