ML13156A248
| ML13156A248 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  (NPF-087, NPF-089) |
| Issue date: | 07/11/2013 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Flores R Luminant Generation Co |
| Singal B | |
| References | |
| TAC ME9065, TAC ME9066 | |
| Download: ML13156A248 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 2013 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 5.7, "HIGH RADIATION AREA," AND TECHNICAL SPECIFICATION TABLE 3.3.3-1, "POST ACCIDENT MONITORING INSTRUMENTATION" (TAC NOS. ME9065 AND ME9066)
Dear Mr. Flores:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 159 to Facility Operating License No. NPF-87 and Amendment No. 159 to Facility Operating License No. NPF-89 for Comanche Peak Nuclear Power Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 12, 2012, as supplemented by "CP-201201253, Supplement to License Amendment Request (LAR)12-001, Revision to Technical Specification 5.7, [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. and Technical Specifications Table 3.3.3-1, Post Accident Monitoring Instrumentation|letter dated October 23, 2012]].
The amendments revise TS 5.7.1, "High Radiation Areas with Dose Rates not Exceeding 1.0 rem [roentgen equivalent manJ/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation," and TS 5.7.2, "High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation," to allow entry into high radiation areas by personnel continuously escorted by individuals qualified in radiation protection procedures and to require a pre-job briefing prior to entry into such areas. The amendments also incorporate an editorial change to TS Table 3.3.3-1, "Post Accident Monitoring Instrumentation," to correct a typographical error.
R. Flores
- 2 A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
-lT~a~a~i~~ Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 159 to NPF-87
- 2. Amendment No. 159 to NPF-89
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT. UNIT NO.1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. NPF-87
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Luminant Generation Company LLC dated July 12, 2012, as supplemented by "CP-201201253, Supplement to License Amendment Request (LAR)12-001, Revision to Technical Specification 5.7, [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. and Technical Specifications Table 3.3.3-1, Post Accident Monitoring Instrumentation|letter dated October 23, 2012]], 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, as amended, 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 license 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
- 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. NPF-87 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 159 and the Environmental Protection Plan contained in Appendix Bf are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan as indicated in the attachment to this license amendment.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~~~
Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-87 and Technical Specifications Date of Issuance: July 11, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT. UNIT NO.2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. NPF-89
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Luminant Generation Company LLC dated July 12, 2012, as supplemented by "CP-201201253, Supplement to License Amendment Request (LAR)12-001, Revision to Technical Specification 5.7, [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. and Technical Specifications Table 3.3.3-1, Post Accident Monitoring Instrumentation|letter dated October 23,2012]], 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, as amended, 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 license 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
- 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. NPF-89 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 159 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC 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 and shall be implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-89 and Technical Specifications Date of Issuance: July 11, 2013
ATTACHMENT TO LICENSE AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Facility Operating License Nos. NPF-87 and NPF-89, and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License No. NPF-87 REMOVE INSERT 3
3 Facility Operating License No. NPF-89 REMOVE INSERT 3
3 Technical Specifications REMOVE INSERT 3.3-38 3.3-38 5.7-2 5.7-2 5.7-3 5.7-3 5.7-4
- 3 (3)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 13 and 3612 megawatts thermal starting with Cycle 14 in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 159 and the Environmental Protection Plan contained in Appendix S, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Unit 1 Amendment No. 159
- 3 (3)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission'S regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 159 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions DELETED Unit 2 Amendment No. 159
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1
- 1. Refueling Water Storage Tank Level
- 2. Subcooling Monitors
- 3. Reactor Coolant System (RCS) Hot Leg Temperature (Wid~ Range) (T hot)
- 4. RCS Cold Leg Temperature (Wide Range)
(TCOld)
- 5. RCS Pressure (Wide Range)
- 7. Containment Sump Water Level (Wide Range)
- 8. Containment Pressure (Intermediate Range)
- 9. Steam Line Pressure
- 10. Containment Area Radiation (High Range)
- 11. Deleted
- 12. Pressurizer Water Level
- 13. Steam Generator Water Level (Narrow Range)
- 14. Condensate Storage Tank Level
- 15. Core Exit Temperature - Quadrant 1
- 16. Core Exit Temperature - Quadrant 2
- 17. Core Exit Temperature - Quadrant 3
- 18. Core Exit Temperature - Quadrant 4
- 19. Auxiliary Feedwater Flow
- a. AFW Flow
- b. AFW Flow and Steam Generator Water Level (Wide Range) 2 E
2 E
1 per loop E
1 per loop E
2 E
2(a)
F 2
E 2
E 2 per steam line E
2 F
2 E
2 per steam generator E
2 E
2(c)
E 2(c)
E 2(c)
E 2(C)
E 2 per steam generator E
1 each per steam E
generator (a) A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the upper section and three or more in the lower section, are OPERABLE.
(b) Deleted (c) A channel consists of two core exit thermocouples (CETs).
COMANCHE PEAK - UNITS 1 AND 2 3.3-38 Amendment No. 160, 166, 159
5.7 High Radiation Area 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued) ii.
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- e.
Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation:
- a.
Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
- 1.
All such door and gate keys shall be maintained under the administrative control of the [shift manager], or his or her designee.
- 2.
Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
- b.
Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c.
Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d.
Each individual or group entering such an area shall possess:
COMANCHE PEAK - UNITS 1 AND 2 5.7-2 Amendment No. 4eQ.; 159
5.7.2 High Radiation Area 5.7 5.7 High Radiation Area High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
- 1.
A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 2.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or
- 3.
A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and,
- i.
Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or ii.
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.
- 4.
In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the Low As is Reasonably Achievable principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
- e.
Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
- f.
Such individual areas that are within a larger area, such as PWR containment, where no enclosure exists for the purpose of locking and where COMANCHE PEAK - UNITS 1 AND 2 5.7-3 Amendment No. 4eG; 159
5.7.2 High Radiation Area 5.7 5.7 High Radiation Area High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued) no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.
Amendment No. 159 COMANCHE PEAK - UNITS 1 AND 2 5.7-4
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-89 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By application dated July 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12202A085), as supplemented by "CP-201201253, Supplement to License Amendment Request (LAR)12-001, Revision to Technical Specification 5.7, [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. and Technical Specifications Table 3.3.3-1, Post Accident Monitoring Instrumentation|letter dated October 23,2012]] (ADAMS Accession No. ML12310A197), Luminant Generation Company LLC (the licensee) requested changes to the Technical Specifications (TSs) for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The proposed changes would revise TS 5.7.1, "High Radiation Areas with Dose Rates not Exceeding 1.0 rem [roentgen equivalent man]/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation,"
and TS 5.7.2, "High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation," to allow entry into high radiation areas by personnel continuously escorted by individuals qualified in radiation protection procedures and to require a pre-job briefing prior to entry into such areas. The amendments also incorporate an editorial change to TS Table 3.3.3 1, "Post Accident Monitoring Instrumentation," to correct a typographical error.
2.0 REGULATORY EVALUATION
Section 50.36, "Technical specifications," of Title 10 of the Code of Federal Regulations (10 CFR) contains the requirements for the content of TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
- 2 Section 20.1101, "Radiation protection programs," of 10 CFR requires licensees to develop and implement a radiation protection program appropriate to the potential radiation hazards in the given facility.
The regulations in 10 CFR 20.1601, "Control of access to high radiation areas," paragraphs (a) and (b) establish requirements for entry into high radiation areas and paragraph (c) authorizes licensees to apply to the U.S. Nuclear Regulatory Commission (NRC) for approval of alternative methods for controlling access to high radiation areas.
NRC Regulatory Guide (RG) 8.38, Revision 1, "Control of Access to High and Very High Radiation Areas in Nuclear Power Plants," May 2006 (ADAMS Accession No. ML061350096),
describes methods that the NRC staff finds acceptable for implementing the requirements of 10 CFR 20.1101, 10 CFR 20.1601, 10 CFR 20.1602, "Control of access to very high radiation areas," and 10 CFR 20.2102, "Records of radiation protection programs."
NUREG-1431, Revision 4, "Standard Technical Specifications, Westinghouse Plants,"
April 2012 (ADAMS Accession No. ML12100A222), provides Standard Technical Specifications (STSs) that are acceptable to the NRC staff.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes
3.1.1 TS 5.7, "High Radiation Areas" Current TS 5.7.1.e states:
Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
Revised TS 5.7.1.e would state:
Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. Those continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
Current TS 5.7.2.e states:
Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
- 3 Revised TS 5.7.2.e would state:
Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. Those continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
3.1.2 TS Table 3.3.3-1, "Post Accident Monitoring Instrumentation" The current title of the last column heading in TS Table 3.3.3-1, Post Accident Monitoring Instrumentation" would be changed from "CONDITION REFERENCED FROM REQUIRED ACTION E.1" to "CONDITION REFERENCED FROM REQUIRED ACTION D.1" to correct a typographical error.
TS 5.7.1.e is applicable for entry into high radiation areas (HRAs) with dose rates not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation. The current TS 5.7.1.e is unclear regarding provisions that would allow individuals to be escorted into HRAs by individuals qualified in radiation protection procedures. The revised TS 5.7.1.e would allow individuals to be escorted into HRAs by individuals qualified in radiation protection procedures, as long as the continuously escorted personnel receive a pre-job briefing prior to entry into such areas.
TS 5.7.2.e is applicable to HRAs with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any source penetrated by the radiation. The current TS 5.7.2.e is unclear regarding provisions that would allow individuals to be escorted into HRAs by individuals qualified in radiation protection procedures. The revised TS 5.7.2.e would require continuously escorted personnel to receive a pre-job briefing prior to entry into such areas.
The change to TS Table 3.3.3-1 is editorial in nature and is intended to correct a typographical error. Limiting Condition for Operation (LCO) 3.3.3, Condition D, Required Action D.1 requires entry into the Condition listed/noted in Table 3.3.3-1, if the Required Action and associated Completion Time of Condition C is not met. However, TS Table 3.3.3-1 incorrectly states it as Required Action E.1.
3.2
NRC Staff Evaluation
The NRC staff developed RG 8.38, Revision 1, to describe methods that the NRC staff finds acceptable for implementing the requirements of 10 CFR 20.1101, 10 CFR 20.1601, 10 CFR 20.1602, and 10 CFR 20.2102. Also, NUREG-1431, Revision 4, Section 5.7, "High Radiation Area," provides Standard Technical Specifications (STSs) for administrative controls acceptable to the NRC staff for entry into the HRAs.
- 4 The NRC staff compared the proposed changes for HRA controls as described in the license amendment request (LAR) to the controls specified in RG 8.38. Revision 1. RG 8.38 notes that in some instances. the requirements of 10 CFR 20.1601 (a) for access to HRAs may unnecessarily restrict plant operations. Paragraph 10 CFR 20.1601 (c) provides that a licensee may apply for Commission approval of alternate methods of controlling access to HRAs. RG 8.38 provides guidance on the alternate methods that are acceptable to the NRC for controlling access. One such method is that any individual or group of individuals are permitted to enter such areas if they are provided with or accompanied by an individual qualified in radiation protection procedures. This individual qualified in radiation protection procedures is responsible for providing positive radiation protection control over the activities within the area and should perform periodic radiation surveillance at the frequency specified in the radiation protection procedures or the applicable radiation work permit (RWP). The NRC staff concludes that the proposed TS changes are acceptable because the proposed HRA controls are consistent with controls described in RG 8.38.
The NRC staff also compared the changes for HRA controls as described in the LAR to the controls as described in the STS provided in NUREG-1431. Revision 4. Section 5.7. STS 5.7.1 establishes requirements for entry into HRAs not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation (Le.. HRAs S 1 rem/hr).
Additionally. STS 5.7.2 establishes requirements for entry into HRAs with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation. but less than 500 rads/hours at 1 meter from the radiation source or from any surface penetrated by the radiation (Le.* HRAs greater than 1 rem/hour and less than 500 rads per hour). The proposed changes to the CPNPP. Units 1 and 2 TSs 5.7.1e and 5.7.2e for controlling access to HRA are consistent with the guidance of STSs (NUREG-1431. Revision 4).
Also. the requirement for pre-job briefing in TSs 5.7.1.e and 5.7.2.e for personnel continuously escorted by individuals qualified in radiation protection procedures is consistent with the provisions of STSs 5.7.1.e and 5.7.2.e (NUREG-1431. Revision 4).
The change to TS Table 3.3.3-1 is editorial in nature. corrects reference to Required Action 0.1 in Table 3.3.3-1. consistent with the STSs, and does not change the intent or technical content of the original TSs.
Based on the above, the NRC staff concludes that the requested changes meet the requirements of regulations 10 CFR 20.1101, 10 CFR 20.1601 (a), and 10 CFR 20.1601 (c), are consistent with the guidance provided by RG 8.38. Revision 1. and NUREG-1431, Revision 4.
and are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations. the Texas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts. and no
- 5 significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 13, 2012 (77 FR 67683). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Steven Garry, NRRIDRAlAHPB Date: July 11, 2013
R. Flores
-2 A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 159 to NPF-87
- 2. Amendment No. 159 to NPF-89
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrDraAhpb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMComanchePeak Resource RidsRgn4MailCenter Resource SGarry, NRRlDRNAHPB ADAMS Accession No. ML13156A248 Sincerely, IRA!
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- via email AHPB safety evaluation transmitted by memo dated May 13,2013 OFFICE NRRlDORULPL4/PM NRRlDORULPL4/LA NRRlDSS/STSB/BC NRRlDRAlAHPB/BC NAME BSingal JBurkhardt*
RElliott UShoop DATE 6/10/13 6/10/13 6/19/13 6/11/13 OFFICE OGC - NLO NRRlDORULPL4/BC NRR/DORULPL4/PM NAME MYoung MMarkley BSingal DATE 7/3/13 7/10/13 7/11/13 OFFICIAL AGENCY RECORD