ML20073G266
| ML20073G266 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/22/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073G267 | List: |
| References | |
| NUDOCS 9410040076 | |
| Download: ML20073G266 (14) | |
Text
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.4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20565 0001
'44.....,o DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.148 License No. NPF-9
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated November 11, 1993, as supplemented February 23, April 12 and July 29, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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.
9410040076 940922 fDR ADOCK 05000369 PDRx
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 148, 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
/
Herbert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
Technical Specification Changes Date of Issuance: September 22, 1994 i
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UNITED STATES y!
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. 20666-0001
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
)
Amendment No. 130 License No. NPF-17
- 1. The Nuclear Regulatory Comission (the Comission) 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 November 11, 1993, as supplemented February 23, April 12 and July 29, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations set forth in 10 CFR Chapter I; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have eeen satisfied.
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- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license an:endment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through i
Amendment No.
130, 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 Herbert N. Berkow, Director
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Project _ Directorate 11-3 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: September 22, 1994 b
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4 i
ATTACHMENT TO LICENSE AMENDMENT NO.148 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 m
TO LICENSE AMENDMENT NO. nn FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 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 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 3/4 11-7 3/4 11-7 t
P ADMINISTRATIVE CONTROLS 55 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES 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 qualified individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /
group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.
6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.
The preparation of each pro-posed Technical Specifications change shall be reviewed by an individual / group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the pro-posed change.
Proposed changes to the Technical Specifications shall be approved by the Station Manager.
i
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6.5.1.3 Proposed modifications to unit nuclear safety-related structures, sys-tems and components shall be designed by a qualified individual / organization.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager or the Manager of Engineering; or for the Station Manager by the Mechanical Maintenance Superintendent, the Operations Superintendent, the I and E/ Maintenance Support Superintendent, or the Work Control Superintendent, as previously designated by the Station Manager.
6.5.1.4 Individuals responsible for reviews performed in accordance with Specifications 6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the site supervisory staff, 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.
6.5.1.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or for the Station Manager by the Mechanical Maintenance Superintendent, the Operations Superintendant, the I and E/ Maintenance Support Superintendent, or the Work Control Superintendent, as previously designated by the Station Manager.
McGUIRE - UNITS 1 and 2 6-8 Amendment No. 148 (Unit 1)
Amendment No. 130 (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.
The Manager, Safety Assurance shall assure such reports are developed and transmitted to the Site Vice President, or designee, who approves such reports, and to the Director of the Nuclear Safety Review Board.
6.5.1.7 The Manager, Safety Assurance shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Site Vice President.
6.5.1.8 Deleted i
l 6.5.1.9 Deleted 6.5.1.10 The Manager, Safety Assurance shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radioactive material to the environs including the preparation and forward-ing of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Site Vice President, and to the Nuclear Safety Review Board.
6.5.1.11 The Manager, Safety Assurance shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.
6.5.1.12 The Manager, Safety Assurance shall ensure the performance of a review by a qualified individual / organization of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Nuclear Safety Review Board and Manager, Human Resources.
6.5.1.13 Reports documenting each of the activities performed under Specifica-tions 6.5.1.1 through 6.5.1.12 shall be maintained.
Copies shall be provided to the Site Vice President, and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The NSRB shall function to provide independent rcvicw and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, McGUIRE - UNITS 1 and 2 6-9 Amendment No. 148 (Unit 1)
Amendment No.130 (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 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.
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, 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.
5.2.5 Staff assistance may be provided to the NSRB in order to promote the per, timely, and expeditious performance of its functions.
2.6 The NSRB shall meet at least once per calendar quarter during the i
~ial year of unit operation following fuel loading and at least once per 1ths thereafter.
7 The quorum of the NSRB necessary for the performance of the NSRB md audit functions of these. Technical Specifications shall consist of
. ctor, or his designated alternate, and at least four other NSRB members i
'" M c. w alternates. No more than a minority of the quorum shall have line l
R ility for operation of McGuire Nuclear Station.
1 JNITS 1 and 2 6-10 Amendment No. 148 (Unit 1)
Amendment No. 130 (Unit 2)
)
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.
Proposed changes in Technical Specifications or this Operating License; e.
Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; g.
All REPORTABLE EVENTS; h.
All recognized indications of an unanticipated deficiency iii some aspect of design or operation of structures, systems or components that could affect nuclear safety; i.
Quality Assurance Program audits relating to station operations and actions taken in response to these audits; and J.
Reports of activities performed under the provisions of Specifications 6.5.1.1 through 6.5.1.12.
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 license conditions; b.
The performance, training, and qualifications of the entire station staff; McGUIRE - UNITS 1 and 2 6-11 Amendment No.148 (Unit 1)
Amendment No.130 (Unit 2)
i ADMINISTRATIVE CONTROLS AUDITS (Continued) c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety; d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50; e.
The Emergency Plan and implementing procedures; f.
The Security Plan and implementing procedures; g.
The Facility Fire Protection programmatic controls including the implementing procedures; h.
The fire protection equipment and program implementation utilizing i
either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside indepen-dent fire protection consultant shall be used at least every third year; i.
The Radiological Environmental Monitoring Program and the results thereof; j.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures; k.
The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes; 1.
The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring and; m.
Any other area of site operation considered appropriate by the NSRB or the Senior Vice President, Nuclear Generation.
AUTHORITY 6.5.2.10 The NSRB shall report to and advise the Senior Vice President, Nuclear Generation on those areas of responsibility specified in Specifications 6.5.2.8 and 6.5.2.9.
l McGUIRE - UNITS 1 and 2 6-12 Amendment No. 148 (Unit 1)
Amendment No. 130 (Unit 2) i
ADMINISTRATIVE CONTROLS 2
RECORDS 6.5.2.11 Records of NSRB activities shall be prepared, approved, and i
distributed as indicated below:
j a.
Minutes of each NSRB meeting shall be prepared, approved, and forwarded to the Senior Vice President, Nuclear Generation and to the Site Vice President, within 14 days following each meeting;
)
b.
Reports of reviews encompassed by Specification 6.5.2.8 above, shall l
be prepared, approved and forwarded to the Senior Vice President, i
Nuclear Generation, and to the Site Vice President, within 14 days following completion of the review; and i
c.
Audit reports encompassed by Specification 6.5.2.9 above, shall be i
forwarded to the Senior Vice President, Nuclear Generation and to the i
Site Vice President, and to the management positions responsible for l
the areas audited within 30 days after completion of the audit by the 1
auditing organization.
6.6 REPORTABLE EVENT ACTION i
6.6.1 The following actions shall be taken for REPORTABLE EVENTS a.
The Commission shall be notified and a report submitted pursuant to j
the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Station Manager; or for the Station Manager by:
(1) the Operations Superintendent, (2) i the Maintenance Superintendents, or (3) the Work Control Super-intendent, as previously designated by the Station Manager, and the results of the review shall be submitted to the NSRB and the Site Vice President.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Site Vice President, and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Operations Superintendent and the Station Manager.
This report shall describe:
(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence; McGUIRE - UNITS I and 2 6-13 Amendment No. 1A8 (Unit 1)
Amendment No. 130 (Unit 2)
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ADMINISTRATIVE CONTROLS l
SAFETY LIMIT VIOLATION (Continued) c.
The Safety Limit Violation Report shall be submitted to the Commis-l sion, 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 i
Guide 1.33, Revision 2, February 1978; b.
The applicable procedures required to implement the requirements of NUREG-0737; i
c.
Deleted d.
Deleted l
e.
PROCESS CONTROL PROGRAM implementation;
{
f.
OFFSITE DOSE CALCULATION MANUAL implementation; and g.
Quality Assurance Program for effluent and environmental monitoring.
h.
Fire Protection Program implementation.
i.
Commitments contained in FSAR Chapter 16.0 3'
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 /
l manager, or one of their designated direct reports prior to implementation and i
shall be reviewed periodically as set forth in administrative procedures.
For procedures which impicment offsite environmental, technical, and laboratory activities, the above review and approval may be performed by the General j
Manager, Environmental Services or designee.
i 6.8.3 Temporary changes to procedures of Specification 6.8.1 above may be made provided:
1 a.
The intent of the original procedure is not altered; i
i b.
The change is approved by two members of the plant management staff, j
at least one of whom holds a Senior Operator license on the unit affected; and McGUIRE - UNITS I and 2 5-14 Amendment No.
148 (Unit 1)
Amendment No.
130 (Unit 2)
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMJ (Continued) i c.
The change is approved by an appropriate division manager, l
superintendent / manager, or one of their designated direct reports within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, and i
maintained:
a.
Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to.as low as practical levels.
The i
systems include RHR, Boron Recycle, Refueling Water, Liquid Waste, Waste Gas, Safety Injection, Chemical and Volume Control, Containment Spray, and Nuclear Sampling. The program shall include the following:
1)
Preventive maintenance and periodic visual inspection requirements, and 1'
2)
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitorina i
A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1)
Training of personnel, 2)
Procedures for monitoring, and 3)
Provisions for maintenance of sampling and analysis equipment.
[
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
1)
Identification of a sampling _ schedule for the critical variables
,j and control points for these variables,
-2).
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, UNITS 1 and 2 6-15 Amendment No. 148 (Unit 1) i Amendment No. 130 (Unit 2) l
RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS
- LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive. material in any of the above 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 Annual Radioactive Effluent Release Report.
b.
The provisions of Specification 3.0.3 are not applicable.
t SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a represen-tative 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 surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to i
the liquid Radwaste Treatment System.
McGUIRE - UNITS 1 and 2 3/4 11-7 Amendment No. 148 (Unit 1)
+
Amendment No. 130 (Unit 2)
.