ML20072F170
| ML20072F170 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/17/1994 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072F172 | List: |
| References | |
| NUDOCS 9408230237 | |
| Download: ML20072F170 (12) | |
Text
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,it UNITED STATES
[. [i.g ' i 'j NUCLEAR REGULATORY COMMISSION
, jg WASHINGTON. D C. 20666-0001
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p THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by The Cleveland Electric illuminating Company, Centerior Service Company, Duquesne Light Company,-Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated June 25, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application,'the provisions of the' Act, and the rules and regulations 'of the-Commission; C.
There is reasonable assurance (i) that the activities authorized by-this amendment can be conducted. without endangering the health -and safety of the public, and (ii) that such activities will. be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 1
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.
1 2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
9408230237 940817 PDR ADOCK 05000440 P
T" (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 65 are hereby incorporated into this license.
The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[ 77 t
O-don B. Hopkins, Sen'ior Project Manager
/ Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 17, 1994
d ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE N0, NPF-58 QQCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 6-1 6-1 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-14 6-14 6-15 6-15 6-16 6-16 l
l l
6.0 ADMINTSTRATIVE CONTROLS 6.1 RESPONSIBillTY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Supervisor or, during his absence from the control room, a designated individual shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President - Nuclear shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be a.
established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the USAR and updated in accordance with 10 CFR 50.71(e).
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President - Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
PERRY - UNIT 1 6-1 Amendment No. 77,76,#,65
ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety.
The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means i
of improving unit safety to the Engineering Department Head.
I COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers or technically oriented individuals located onsite.
Each shall have either (1) a bachelor's degree in engineering or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or (2) equivalent work experience as described in Section 4.1 of ANSI /ANS 3.1, December 1981.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Engineering Department Head.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in j
unit design and layout, including the capabilities of instrumentation and controls in the control room.
6.3 UNIT STAFF OVALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971** for comparable positions, except for the Plant Health Physicist who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
- Not responsible for sign-off function.
- The active duties of Manager, Perry Operations Section, can be conducted without the designated individual holding an SR0 License until issuance of an SRO License upon completion of the August 1995 License Examination.
PERRY - UNIT 1 6-7 Amendment No. ft, (7, (7,65
i ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Section Head, and shall meet l
or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980, NRC letter l
to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 BfVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters l
related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Operations Review Committee (PORC) shall be composed of at least six but not more than eleven members of the Perry Nuclear Power Plant onsite management organization.
The members shall be Section heads or above, except for selected Professional-Technical disciplines which report directly to Section heads, collectively having experience and competence in at least the following disciplines:
operations, maintenance, technical, reactor engineering, instrumentation and controls, and radiation protection, plus any other areas as determined by the Plant Manager.
The PORC membership shall be designated in writing by the Plant Manager.
The PORC members shall meet the applicable unit staff qualifications for their respective discipline (s) as stated in Specification 6.3.1.
The PORC Chairman shall be drawn from the PORC members and shall be designated in writing by the Plant Manager.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
tiEETING FRE0VENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designee.
l OU0 RUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of a majority of the members.
The Chairman (or his designee) and voting alternate members may be utilized to meet the quorum requirement.
PERRY - UNIT 1 6-8 Amendment No. 22,36,42,65
ADMINISTRATIVE CONTROLS
~
RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:
a.
Review of all Administrative Procedures; b.
Review of the safety evaluations for (1) proposed procedures /
instructions, (2) changes to procedures / instructions, equipment, systems or facilities, and (3) tests or experiments performed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question; c.
Review of proposed procedures / instructions and changes to procedures /
instructions, equipment, systems or facilities which involve an unreviewed safety question as defined in 10 CFR 50.59; d.
Review of proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; e.
Review of proposed changes to Technical Specifications or the Operating License; f.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear and to the Nuclear Safety Review Committee; g.
Review of all REPORTABLE EVENTS; h.
Review of the plant Security Plan and Security Contingency Instructions; i.
Review of the Emergency Plan and implementing instructions; j.
Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems; k.
Review of any accidental, unplanned or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Plant Manager, the Nuclear Safety Review Committee and the Vice President - Nuclear; 1.
Review of Unit operations to detect potential hazards to nuclear safety; m.
Investigations or analysis of special subjects as requested by the Chairman of the Nuclear Safety Review Committee; and n.
Review of the Fire Protection Program and implementing procedures.
PERRY - UNIT 1 6-9 Amendment No. Af,M,# 65
ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) 6.5.1.7 The PORC shall:
Recommend in writing to the Plant Manager, approval or disapproval of l
a.
items considered under Specifications 6.5.1.6a. through e.,
h.,
i.,
J., and k., above prior to their implementation; b.
Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6b. through e.,
- above, constitutes an unreviewed safety question; and Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -
c.
Nuclear and the Nuclear Safety Review Committee of disagreement between the PORC and the Plant Manager, however, the Plant Manager l
shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1. above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility provisions of these Technical Specifications.
Copies shall be provided to the Vice President - Nuclear and the Nuclear Safety Review Committee.
6.5.2 NUCLEAR SAFETY REVIEW COMMITJfE (NSRC)
FUNCTION 6.5.2.1 The NSRC 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, d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, 9
Mechanical and electrical engineering, h.
Quality assurance practices and administrative controls, and i.
Nondestructive testing.
The NSRC shall report to and advise the Vice President - Nuclear on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
PERRY - UNIT 1 6-10 Amendment No. 22, A6, /2,65
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The membership of the NSK shall be composed of at least eight personnel appointed by the Vice President - Nuclear to provide collective experience and competency in the following areas:
Nuclear power plant operations Nuclear engineering Chemistry and radiochemistry Metallurgy Nondestructive testing Instrumentation and control Radiological safety Mechanical and electrical engineering Administrative controls and quality assurance practices The Chairman, appointed by the Vice President - Nuclear shall have 10 years of power plant experience, of which 3 years shall be nuclear power plant experience. The NSRC members shall hold a bachelors' degree in an engineering or physical science field, or equivalent experience, and a minimum of 5 years of technical experience of which a minimum of 3 years shall be in one or more of the disciplines in Specification 6.5.2.1.
Competent alternates may be designated in advance and consultants may be used for in-depth expertise if desired by the committee.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NSRC Chairman to serve on a temporary basis, however, no more than two alternates shall participate as voting members in NSRC activities at any one time.
CONSULTANTS 6.5.2.~4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert. advice to the NSRC.
MEETING FRE0VENCY 6.5.2.5 The NSRC shall meet at least once per 6 months.
OU0 RUM 6.5.2.6 The quorum of the NSRC necessary for the performance of the NSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designee and at least four but not less than one-half of l
the NSRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
PERRY - UNIT 1 6-11 Amendment No. W,65
@MINISTRATIVE CONTROLS 6.5.3 TECHNICAL REVIEW AND CONTROL 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:
a.
Procedures / instructions required by Specification 6.8 and other procedures / instructions which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure / instruction or procedure / instruction change shall be reviewed by a qualified individual (s) other than the individual (s) which prepared the procedure / instruction or procedure / instruction change, but who may be from the same section as the individual (s) which prepared the procedure / instruction or procedure / instruction change.
Instructions shall be approved by appropriate management personnel as designated in writing by PORC, and approved by the appropriate Section heads. The Plant Manager shall approve Administrative Procedures.
b.
Proposed modifications to plant structures, systems and components that affect nuclear safety shall be reviewed by individuals designated by the Engineering Department Head.
Each such modification shall be reviewed by a qualified individual (s) other than the individual (s) which designed the modification, but who may be from the same section as the individual (s) which designed the modifications.
Proposed modifications to plant structures, systems and components that affect nuclear safety shall be reviewed by PORC and approved prior to implementation by the Plant Manager.
l c.
Proposed tests and experiments which affect plant nuclear safety shall be prepared, reviewed, and approved.
Each such test or experiment shall be reviewed by a qualified individual (s) other than the individual (s) which prepared the proposed test or experiment.
Proposed tests and experiments shall be approved before implementation by the Plant Manager, d.
Sections responsible for reviews, including cross-disciplinary reviews, performed in accordance with Specifications 6.5.3.la. and 6.5.3.lc., shall be designated in writing by PORC and approved by the Plant Manager.
The individual (s) performing the review shall meet or exceed the qualification requirements of appropriate section(s) of 1
ANSI N18.1-1971-e.
Each review shall include a determination pursuant to 10 CFR 50.59 of whether or not the potential for an unreviewed safety question exists.
If such a potential does exist, a safety evaluation per 10 CFR 50.59 to determine whether or not an unreviewed safety question is involved shall be performed.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to implementation; and i
PERRY - UNIT 1 6-14 Amendment No. ft, 41,65
ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) f.
The Plant Security Plan and Emergency Plan, and implementing instructions, shall be reviewed at least once per 12 months.
Recommended changes to the Plans and implementing instructions shall be reviewed pursuant to the requirements of Specification 6.5.1.6 and approved by the Plant Manager. NRC approval shall be obtained as
[
appropriate.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of the review submitted to the NSRC and the Vice President - Nuclear.
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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President -
Nuclear and the NSRC 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 PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRC, and the Vice President - Nuclear within 30 days of the violation.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 Written procedures / instructions 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.
PERRY - UNIT 1 6-15 Amendment No. 22',M,47,65
ADMINISTRATIVE CONTROLS 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS (Continued) b.
The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto.
c.
Security Plan implementation.
d.
Emergency Plan implementation.
e.
PROCESS CONTROL PROGRAM implementation.
f.
OFFSITE DOSE CALCULATION MANUAL implementation.
g.
Radiological Environmental Monitoring Program implementation.
h.
Fire Protection Program implementation.
6.8.2 Each administrative procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the PORC and shall be approved by the Plant Manager prior to implementation. All procedures / instructions shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temocrary chanaes Temporary changes to procedures / instructions which do not change the intent of the approved procedures / instructions shall be approved for implementation by two members of the plant management staff, at least one of whom holds a Senior Operator license.
These temporary changes shall be documented. The temporary changes shall be approved by the original approval authority within 14 days.
For changes to procedures / instructions which may involve a change in intent of the procedures / instructions, the original approval authority shall approve the change prior to implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary 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 systems include the HPCS, RHR, RCIC, LPCS, feedwater leakage control system, the hydrogen analyzer portion of Combustible Gas Control, and post-accident sampling systems.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less.
PERRY - UNIT I 6-16 Amendment No. 22,42E5