ML20044H017
| ML20044H017 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/27/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044H018 | List: |
| References | |
| NUDOCS 9306070217 | |
| Download: ML20044H017 (13) | |
Text
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NUCLEAR REGULATORY COMMISSION c
WASHINGTON, D. C. 20555
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ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE. INC.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated February 11, 1993, 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 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9306070217 930527 PDR ADDCK 05000461 P
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(2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 76, are hereby. incorporated into this license.
Illinois Power Company shall operate the' facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m g u eM y James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the ic;hnical Specifications Date of Issuance:
May 27, 1993 W
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i ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 j
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages, as indicated by an asterisk, are provided to maintain document completeness.
i Remove Paaes insert Paaes j
xxv xxv
- xxvi
- xxvi 1-5 1-5
- 1 6
- l-6 i
- 3/4 7-17
- 3/4 7-17 3/4 7-18 3/4 7-18 6-19 6-19
- 6-20
- 6-20 I
6-25 6-25 l
- 6-26
- 6-26 r
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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE REVIEW AND AUDIT (Continued)
Meeting Frequency......................
6 Quorum............................
6-11 Review............................
6-11 Audits............................
6-11 Authority 6-13 Records 6-13 6.5.3 TECHNICAL REVIEW AND CONTROL.................
6-13 Activities..........................
6-13 6.6 REPORTABLE EVENT ACTION 6-14 6.7 SAFETY LIMIT VIOLATION......................-6-14 6.8 PROCEDURES AND PROGRAMS 6-15 6.8.1 PROCEDURES..........................
6-15 6.8.2 REVIEW AND APPROVAL 6-15 6.8.3 TEMPORARY CHANGES......................
6-15 6.8.4 PROGRAMS'...........................
6-16 6.9 REPORTING RE0VIREMENTS.....................
6-f/
6.9.1 RCUTINE REPORTS.......................
6-17 Startup Report........................
6-17 Annual Reports.......
6-17 Annual Radiological Environmental Operating Report......
6-18 Radioactive Effluent Release Report 6-19 Monthly Operating Reports..................
6-21.
Core Operating Limits Report.................. 6-21 CLINTON - UNIT 1 xxv AMENDMENT NO. 76-E-
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INDEX h
ADMINISTRATIVE CONTROLS i
r SECTION PAGE t
REPORTING REQUIREMENTS (Continued) 6.9.2 SPECIAL REP 0RTS..............................................
6-21 6.10 RECORD RETENTION........................................
6-21 6.11 RADIATION PROTECTION PR0 GRAM..................................
6-23 r
t 6.12 HIGH RADIATION AREA....................
6-23 6.13 PROCESS CONTROL PROGRAM (PCP).................................
6-24 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)........................
6-25 CLINTON - UNIT 1 xxvi Amendment No. 40 JUL 13 h6G-
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' DEFINITIONS t
MINIMUM CRITICAL POWER RATIO
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1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the crre.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.26 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodol'ogy and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and-liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the
- 1 Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by-Specifications 6.9.1.6 and 6.9.1.7.
OPERABLE - OPERABILITY 1.27 A system, subsystem, train, component or device shall be OPERABLE or i
have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.
PHYSICS TESTS 1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation as 1) described in Chapter 14 of the FSAR, 2) as authorized under the provisions of o
10 CFR 50.59, or 3) as otherwise approved by the Comission.
PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a nonisolable fault in -
a reactor coolant system component body, pipe wall or vessel wall.
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CLINTON - UNIT 1 1-5 AMENDMENT NO. 76.
DEFINITIONS PRIMARY CONTAINMENT INTEGRITY l.31 PRIMARY CONTAINMENT INTEGRITY shall exist when:
All primary containment penetrations required to be closed during accident I
a.
conditions are either:
1.
Capable of being closed by an OPERABLE containment automatic isolation system or 2.
Closed by at least c,ne manual valve, blind flange, or deactivated automatic valve secured in its closed pcsition, except as provided in Specification 3.6.4.
I b.
All primary containment equipment hatches are closed and sealed.
l Each primary containment air lock is in compliance with the requirements of l
c.
Specification 3.6.1.3.
d.
The primary containment leakage rates are within the limits of Specification l 3.6.1.2.
The suppression pool is in compliance with the requirements of e.
Specification 3.6.3.1.
f.
The sealing mechanism associated with each primary containment penetration e.g., welds, bellows or 0-rings, is OPERABLE.
l PROCESS CONTROL PROGRAM (PCP) 1 1.32 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71 and Federal and State regulations, burial ground requirements and other requirements governing the disposal of the radioactive waste.
PURGf - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition in such a manner that replacement air'or gas is required to purify the confinement.
RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2B94 MWt.
CLINTON - UNIT 1 1-6 Amendment No. /D. 68 i
DEC 0 41,'T
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i PLANT SYSTEMS 3
3/4.7.6 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION l
3.7.6 The main turbine bypass system shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITION 1 with THERMAL POWER greater than or equal to 25% of RATED THEMAL POWER.
ACTION:
f I
With the main turbine bypass system inoperable, restore the system to OPERABLE l
status within I hour or reduce THERMAL POWER to less than 25% of RATED THERMAL I
POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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SURVEILLANCE REQUIREMENTS I
4.7.6 The main turbine bypass system shall be demonstrated OPERABLE I
At least once per 31 days by cycling each turbine bypass valve through'at a.
least one complete cycle of full travel, and b.
At least once per 18 months by:
1.
Performing a system functional test which includes simulated auto.
matic actuation and verifying that each automatic valve'actuat?s to its correct position.
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2.
Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME meets the following re:;uirements when measured from the initial movemer,t cf the main' turbine stop or control valve:
a) 80% of turbine bypass system capacity shall be established in
< 0.3 seconds.
b)
Bypass valve opening shall start in 1 0.1. seconds.
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CLINTON - UNIT 1-3/4 7-17
r PLANT SYSTEMS 3/4.7.7 L10VID STORAGE TANKS
- 1 LIMITING CONDITION FOR OPERATION 3.7.7 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, t
excluding tritium and dissolved or entrained noble gases.
a.
Cycled Condensate Storage Tank b.
RCIC Storage Tank c.
Outside temporary tank APPLICABILITY: At all times.
1 ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radioactive Effluent Release Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.7 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
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- Tanks included in this specification are those outdoor tanks that are not j
surrounded by liners, dikes, or walls capable of holding-the tank contents and that do not have tank overflows and surr;anding area drains connected:
to the liquid radwaste treatment system.
j CLINTON - UNIT 1 3/4 7-18 AMENDMENT NO. 76 i
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c ADMINISTRATIVE CONTROLS RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 The Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of
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radioactive liquid and gaseous effluents and solid waste released from the i
unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP.and (2) in conformance with 10 CFR 50.36a and e
Section IV.B.1 of Appendix I to 10 CFR Part 50.
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r CLINTON - UNIT 1 6-19 AMENDMENT NO. 76
THIS PAGE INTENTIONALLY DELETED.
1 CLINTON - UNIT 1 6-20 Amendment No. 40 JUL 181930
i ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) l Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.n.
This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),
and 2.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and.
not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the FRG and the approval of the Manager - Clinton Power Station.
c.
Shall be submitted to the Commission in the form of a complete, legible e of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change.shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
Cl.INTON - UNIT 1 6-25 AMENDMENT NO. 76
ADMINISTRATIVE CONTROLS THIS PAGE INTENTIONALLY DELETED.
CLINTON - UNIT 1 6-26 Amendment No. 40 JUL 18 [990 I