ML20095K146
| ML20095K146 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/19/1995 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095K150 | List: |
| References | |
| NUDOCS 9512280124 | |
| Download: ML20095K146 (12) | |
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UNITED STATES y
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NUCLEAR REGULATORY COMMIE 610N p
WASHINGTON, D.C. enmaa mi S
DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 161 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated January 12, 1995, as supplemented by letter dated June 29, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and the Commission's rules and regulations as set forth in 10 CTR 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 set forth in 10 CFR Chapter I; 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 Comission's regulations and all applicable requirements have been satisfied.
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9512280124 951219 PDP ADOCK 05000369 P
2.
Accordingly, the license is hereby amended by page 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-9 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.161
, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Pl an.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION 0LeonardA.Wiens,(ActingDirector Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
December 19, 1995 1
1
1 pn arwy oo t
UNITED STATES f
j NUCLEAR REGULATORY COMMISSION e
WASHINGTON D.C. 20066-0001 b.....*
DUKE POWER COMPANY QQCKET NO. 50-370 ticSUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
143 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated January 12, 1995, as supplemented by letter dated June 29, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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.
I J
. 2.
Accordigly, the license is hereby amended by page 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-17 is hereby amended to read as follows:
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 143, are hereby incorporated into this license. The licensee 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 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION LeonardA. Wins,[ActingDirector Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification
?
Changes I
Date of Issuance:
December 19, 1995 i
H Y
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ATTACHMENT TO LICENSE AMENDMENT NO. 161 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 l
83Q TO LICENSE AMENDMENT NO. 143 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET N0. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-14 6-14 6-16 6-16 6-23 6-23 e
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ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTRQL ACTIVITIES Programs shall be established for the preparation, review, approval, and retention of documents required by the activities described in Specifications 6.5.1.1 through 6.5.1.11.
Approvals shall be by the head of the appropriate site organization, the head of the appropriate station organization, the head of the appropriate site engineering organization, the head of the environmental organization, or an alternate as specified in other applicable regulatory documents or administrative controls.
6.5.1.1 Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, shall be prepared by a knowledgeable individual / organization.
Each such procedure, and changes thereto, shall be reviewed by an individual / organization other than the individual / organization which prepared the procedure, or changes thereto.
Procedures, or changes thereto, shall be approved in accordance with Specifications 6.8.2 and 6.8.3.
6.5.1.2 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a knowledgeable individual / organization.
Each such modification shall be reviewed by an individual / organization other than the individual / organization which designed l
the modification.
6.5.1.3 Individuals responsible for reviews performed in accordance with Specifications 6.5.1.1 and 6.5.1.2 shall be members of the supervisory staff assigned to the site, previously designated by the Site Vice President to perform such reviews.
Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the appropriate designated site review personnel.
6.5.1.4 Proposed changes to the Appendix A Technical Specifications shall be prepared by a knowledgeable individual / organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual /
organization other than the individual / organization which prepared the proposed change.
6.5.1.5 Proposed tests and experiments which affect station nuclear safety
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and are not addressed in the FSAR or Technical Specifications shall be prepared and approved in a manner identical to that of Specification 6.5.1.1.
These proposed tests and experiments shall be reviewed by a knowledgeable individual / organization other than the individual / organization which prepared
-the proposed tests and experiments.
McGUIRE - UNITS 1 and 2 6-8 Amendment No.161 (Unit 1)
Amendment No.143 (Unit 2)
ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.1.6 ALL REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports shall be reviewed by a knowledgeable individual / organization other than the individual / organization which prepared the report.
6.5.1.7 Special reviews and investigations, and the preparation of reports thereon, shall be performed by a knowledgeable individual / organization.
6.5.1.8 A knowledgeable individual / organization shall rewiew every unplanned onsite release of radioactive material to the environs and prepare reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence.
6.5.1.9 A knowledgeable individual / organization shall review changes to the l
PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.
6.5.1.10 A knowledgeable individual / organization shall review the Fire l
Protection Program and implementing procedures.
6.5.1.11 Reports documenting each of the activities performed under Specifi-l cations 6.5.1.1 through 6.5.1.10 shall be maintained.
f,5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, McGUIRE - UNITS I and 2 6-9 Amendment No.161 (Unit 1)
Amendment No.143 (Unit 2)
ADMINISTRATIVE CONTROLS FUNCTION (Continued) d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, and h.
Administrative control and quality assurance practices.
ORGANIZATION 6.5.2.2 The Director, members and alternate members of the NSRB shall be appointed in writing by the Senior Vice President, Nuclear Generation and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a i
minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1.
In special cases, candidates for appointment without an academic degree in engineering or physical science may be qualified with a minimum of ten years experience in one of the areas in Specification 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
I j
6.5.2.3 The NSRB shall be composed of at least five members, including the Director. Members of the NSRB may be from the Nuclear Generation Department,
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from other departments within the Company, or from external to the Company. A maximum of one member of the NSRB may be from the McGuire Nuclear Site staff.
6.5.2.4 Consultants shall be utilized as determined by the NSRB Director to provide expert advice to the NSRB.
6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the i
proper, timely, and expeditious performance of its functions.
6.5.2.6 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least twice per i
year thereafter.
6.5.2.7 The quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these Technical Specifications shall consist of the Director, or designated alternate, and at least four other NSRB members l
Ancluding alternates. No more than a minority of the quorum shall havo lino responsibility for operation of McGuire Nuclear Station.
McGUIRE - UNITS 1 and 2 6-10 Amendment No. 161 (Unit 1)
Amendment No. 143 (Unit 2)
P i
ADMINISTRATIVE CONTROLS REVIEW 6.5.2.8 The NSRB shall review:
a.
The safety evaluations for: (1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question; b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; d.
Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; e.
Significant operating abnormalities or deviations from normal and l
expected performance of unit equipment that affect nuclear safety; f.
All REPORTABLE EVENTS; l
g.
All recognized indications of an unanticipated deficiency in some l
aspect of design or operation of structures, systems or components that could affect nuclear safety; h.
Quality Assurance Program audits relating to station operations l
and actions taken in response to these audits; and i.
Reports of activities performed under the provisions of Specifications 6.5.1.1 through 6.5.1.10.
AUDITS 6.5.2.9 Audits of site activities shall be performed under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable licenso conditions; b.
The performance, training, and qualifications of the entire station staff; i
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McGUIRE - UNITS 1 and 2 6-11 Amendment No. 161 (Unit 1)
Amendment No. 143 (Unit 2)
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ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Site Vice President, within 14 days of the violation; and d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.
The applicable procedures required to implement the requirements of NUREG-0737; c.
Deleted d.
Deleted e.
PROCESS CONTROL PROGRAM implementation; f.
OFFSITE DOSE CALCULATION MANUAL implementation; and g.
Quality Assurance Program for effluent and environmental monitoring.
h.
Technical Review and Control Program implementation.
l 1.
Fire Protection Program implementation.
l j.
Plant Operations Review Committee implementation.
l k.
Commitments contained in FSAR Chapter 16.0 l
6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed and approved by an appropriate division manager, superintendent /
manager, or one of their designated direct reports prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
For procedures which implement offsite environmental, technical, and laboratory activitics, the above review and approval may be performed Sy the General Manager, Environmental Services or designee.
6.8.3 Temporary changes to procedures of Specification 6.0.1 above may be
,made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management j
staff, at least one of whom holds a Senior Operator license on the unit affected; and J
1 McGUIRE - UNITS 1 and 2 6-14 Amendment No.161 (Unit 1)
Amendment No.143 (Unit 2)
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e.
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective actions for all off-control point chemistry conditions, and 6)
A procedure identifying:
(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Backuo Method for Determinina Subcoolina Marain A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:
1)
Training of personnel, and 2)
Procedures for monitoring.
e.
Post-accident Samplina 4
A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines, and particulates in plant i
gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
i 1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
f.
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in FSAR Chapter 16, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The prograu shall include the following elements:
l 1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the Offsite Dose Calculation Manual (0DCM),
l 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2, McGUIRE - UNITS 1 and 2 6-16 Amendment No. 161 (Unit 1)
Amendment No. 143 (Unit 2)
ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) g.
Records of training and qualification for current members of the unit staff; i
h.
Records of inservice inspections performed pursuant to these Technical Specifications; i.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; j.
Records of meetings of the NSRB and reports required by Specification 6.5.1.11; l
k.
Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records; 1.
Records of secondary water sampling and water quality; and m.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
n.
Records of reviews performed for changes made to the 00CM and the PCP.
6.10.3 Records of quality assurance activities required by the QA Manual shall be retained for a period of time required by ANSI N45.2.9-1974.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by para-graph 20.203(c)(2) of 10 CFR 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than
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1000 arem/hr at 45 CM (18 in.) from the radiation source or from any surfaco which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Radiation Protection Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem /hr provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
t McGUIRE - UNITS 1 and 2 6-23 Amendment No.161 (Unit 1)
Amendment No.143 (Unit 2)
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