ML20133G300
| ML20133G300 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/08/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20133G303 | List: |
| References | |
| NUDOCS 9701150292 | |
| Download: ML20133G300 (13) | |
Text
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k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
%*****/g WASHINGTON, D.C. 20066 0001 o
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.170 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and reigulations 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 1
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.
9701150292 970108 PDR ADOCK 05000266 F
k l l 2.
Accordingly, the license is hereby amended to approve the relocation of i
certain Technical Specification requirements to licensee-controlled i
documents, as described in the licensee's application dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, and reviewed in the staff's safety evaluation dated January 8, 1997. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 3.B., and 3.H. of Facility Operating License No. DPR-24 are hereby amended to read as follows:
B.
Technical Soecifications
}
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 170, are hereby incorporated in the license. The l
licensee shall operate the facility in accordance with the Technical Specifications.
H.
Wisconsin Electric shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety i
Analysis Report for the facility and as approved in the SER dated i
August 2,1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27,1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No.170, subject to the folbwing l
provision:
l 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 i
in the event of a fire.
3.
Paragraph 3.I. is revised by deleting the quotation marks at the beginning
]
and end of the license condition.
4.
This license amendment is effective as of its date of issuance and shall be 4
implemented within 90 days from the date of issue.
Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensee's application dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, and reviewed in the staff's safety evaluation dated January 8, 1997.
I FOR THE NUCLEAR REGULATORY COMISSION h
Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV i
Office of Nuclear Reactor Regulation Attachments:
Page 4a* to License DPR-24 and changes i
to the Technical Specifications 1
i Date of issuance: January 8, 1997
- Page 4a is attached, for convenience, for the composite license to reflect these changes.
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20086 4001 o
$9.....,o WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NVCLEAR PLANT. UNIT NO. 2 r
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 L.icense No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, 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 hereby amended to approve the relocation of certain Technical Specification requirements to licensee-controlled
.l' documents, as described in the licensee's application dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, and reviewed in the staff's safety evaluation dated January 8, 1997. This license is also hereby amended by changes to the Technical Specifications as indicated 1
in the attachment to this license amendment, and paragraphs 3.B., and 3.H. of Facility Operating License No. DPR-27 are hereby amended to read as follows:
1 B.
Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 174, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
H.
Wisconsin Electric shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated August 2, 1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27,1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No. 174, 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.
3.
Paragraph 3.G. is revised to correct the spelling of " actuation" and " unit,"
and paragraph 3.1. is revised by deleting the quotation marks at the
)
beginning and end of the license condition.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issue.
Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensee's 4
application dated April 29, 1996, as supplemented October 21, December 2, and December 16, 1996, and reviewed in the staff's safety evaluation dated January 8, 1997.
FOR THE NUCLEAR REGULATORY COPMISSION sds uk.umu Linda L. Gundrum, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachments:
Page 4* to License DPR-27 and changes i
to the Technical Specifications Date of issuance: January 8, 1997
- Page 4 is attached, for convenience, for the composite license to reflect these changes.
4 h
ATTACHMENT TO LICENSE AMENDMENT NOS.170 AND 174 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise the license and Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are 4
identified by amendment number and contain vertical lines indicating the area of change.
~
REMOVE INSERT License DPR-24 page 4a License DPR-24 page 4a License DPR-27 page 4 License DPR-27 page 4 Table of Contents page 15-1 Table of Contents page 15-1 15.3.14-1 15.3.14-1 15.3.14-2 15.3.14-3 15.3.14-4 15.3.14-5 Table 15.3.14-1 15.4.15-1 15.4.15-1 15.4.15-2 15.6.2-3 15.6.2-3 15.6.4/5-1 15.6.4/5-1 15.6.9-5 15.6.9-5
Wisconsin Electric Power Company
-4a-H.
Wisconsin Electric shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated August 2, 1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27,1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No.170, 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.
I.
Secondary Water Chemistry Monitorina Proaram l
The licensee shall implement a secondary water chemistry 1
monitoring program to inhibit steam generator tube degradation.
This program shall include:
1.
Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to quantify parameters that are critical to control points; 3.
Identification of process sampling points 4.
Procedure for the recording and management of data, 5.
Procedures defining corrective actions for off control point chemistry condition; and 6.
A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
l r
J.
The licensee is authorized to repair Unit 1 steam generators by replacement of major components.
Repairs shall be conducted in accordance with the licensee's commitments identified in the Commission approved Point Beach Nuclear Plant Unit No. 1 Steam Generator Repair Report dated August 9, 1982 and revised March 1, 1983 and additional commitments identified in the staff's related Safety Evaluation.
Amendment No.170
Wisconsin Electric Power Company G.
Safety Iniection Loaic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation l
1 channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures l
and placed in a block-permissive condition for safety injection actuation.
H.
Wisconsin Electric shall implement and maintain in effect all provisions of the approved fire protectit.n program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated August 2, 1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8,
1997, for Technical Specification Amendment No.174, 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 j
shutdown in the event of a fire.
I.
Secondary Water Chemistry Monitorina Proaram l
The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include:
1.
Identification of a sampling schedu?
For the critical parameters and control points for th6.w parameters; 2.
Identification of the procedures used quantify parameters that are critical to controi ; sints; 3.
Identification of process sampling point 4.
Procedure for the recording and management of data; 5.
Procedures defining corrective actions for off control point chemistry condition; and 6.
A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
l 4.
The issuance of this amended license is without prejudice to subsequent licensing action which may be taken by the Commission with regard to the on-going rulemaking hearing on the Interim Acceptance Criteria for Emergency Core Cooling Systems (Docket No. RM 50-1).
Amendment No.
174
TABLE OF CONTENTS Section Ijile Eags 15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Definitions 15.1 1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1 1 j
15.2.1 Safety Limit, Reactor Core 15.2.1 1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3-1 15.3 Limiting Conditions for Operation 15.3.0-1 15.3.0 General Considerations 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2 1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power Conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 15.3.6 Containment System 15.3.6-1 15.3.7 Auxiliary Electrical Systems 15.3.7-1 15.3.8 Refueling 15.3.8-1 15.3.9 Effluent Releases 15.3.9-1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In-Core Instrumentation 15.3.11-1 15.3.12 Control Room Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressors (Snubbers) 15.3.13-1 15.3.14 Fire Protection System (This section was deleted as of 1/8/97
)
15.3.14-1 l
15.3.15 Overpressure Mitigating System 15.3.15-1 i
15.3.16 Reactor Coolant System Pressure Isolation Valves 15.3.16-1 15.4 Sun'eillance Requirements 15.4 1 15.4.1 Operational Safety Review 15.4.1-1 15.4.2 In-Service inspection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15.4.4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment Cooling System Tests 15.4.5-1 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 15.4.9 Reactivity Anomalies 15.4.9-1 15.4.10 Operational Environmental Monitoring 15.4.10-1 15.4.11 Control Room Emergency Filtration 15.4.11-1 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane Lifting Devices 15.4.14-1 15.4.15 Fire Protection System (This section was deleted as of 1/8/97
)
15.4.15-1 l
15.4.16 Reactor Coolant System Pressure Isolation Valves Leakage Tests 15.4.16-1 Unit 1 - Amendment No. 96, 170 15-i Unit 2 - Amendment No. 199, 174
15.3.14 FIRE PROTECTION SYSTEM (This section was deleted as of 1/8/97
.)
i i
Unit 1 - Amendment No.32, 448,170 15.3.14-1 Unit 2 - Amendment No. 36, 424,174
15.4.15 FIRE PROTECTION SYSTEM (This section was deleted as of 1/8/97.)
4 a
Unit 1 - Amendment No. 32, 448.170 15.4.15-1 Unit 2 - Amendment No.36, !2+,174
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15.6 ADMINISTRATIVE CONTROLS (Continued) 15.6.2 ORGANIZATION (Continued)
FACILITY STAFF (Continued) i 15.6.2.2 (Continued)
At least two licensed Operators shall be present in the control c.
room during reactor start-up, scheduled reactor shutdown j
and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in either reactor."
All core alterations shall be directly supervised by either a l
e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
l
- SRO = NRC Senior Reactor Operator License RO = NRC Reactor Operator License
" This shift may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of personnel, provided immediate action is taken to restore the shift makeup to within the minimum requirements.
1 l
l Unit 1 - Amendment No. 446,164,170 15.6.2-3 i
Unit 2 - Amendment No, t50,168,174
15.6.4 TRAINING 15.6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
15.6.5 REVIEW AND AUDIT 15.6.5.1 Manager's Supervisory Staff 15.6.5.1.1 The Manager's Supervisory Staff (MSS) shall function to advise the Manager on all matters related to nuclear safety.
15.6.5.1.2 The Manager's Supervisory Staff shall be selected and designated by the Manager from a list of qualified individuals in the following disciplines:
Operations Maintenance Health Physics Engineering Licensing Training Chemistry 15.6.5.1.3 Each individual representing a MSS discipline shall meet or exceed the qualification requirements specified in Section 4.2 of ANSI N18.1-1971, except as described in Specification 15.6.3.2 for the Health Physics Manager.
Unit 1 - Amendme.t No.
128, 146, 170 15.6.4/5-1 Unit 2 - Amendment No.
132, 450, 174
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D.
Failure of Containment High-Range Radiation Monitor A minimum of two in-containment radiation-level monitors with a maximum j
range of 10' rad /hr (10'/hr for photons only) should be operable at all times except for cold shutdown and refueling outages. This is specified in Table 15.3.5-5, item
- 7. If the minimum number of operable channels are not restored to operable condition within seven days after failure, a special report shall be submitted to the NRC within thirty days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
E.
Failure of Main Steam Line Radiation Monitors if a main steam line radiation monitor (SA-11) fails and cannot be restored to operability in seven days, prepare a special report within thirty days of the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the channel to operable status.
t Unit 1 - Amendment No. 402, 448, 170 15.6.9-5 Unit 2 Amendment No. 195, 421, 174