ML19337A700
| ML19337A700 | |
| Person / Time | |
|---|---|
| Issue date: | 09/22/1980 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Capawana S AFFILIATION NOT ASSIGNED |
| References | |
| FOIA-80-474 NUDOCS 8009290443 | |
| Download: ML19337A700 (2) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION y7 g
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E WASHINGTON, D. C. 20555 gh POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET N0. 50-286 INDIAN POINT STATION UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. DPR-64 The Nuclear Regulatory Commission (the Commission) has found that:
l.
A.
The applications for amendment by Power Authority of the State of New York (the licensee) dated November 2,1978, October 2, 7
1979, November 28, 1979 and May 23, 1980, conply 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 4
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;
,^
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requiremei. s have been satisfied.
i e
4 8009299gjg
. 1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-64 is hereby amended to read as follows:
4 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
32, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A.Vbrga,C e
Operating Reactors anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 5,1980 6
1 i
1 ATTACHMENT TO LICENSE AMENDMENT N0. 32 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET N0. 50-286 e
Revise Appendix A as follows:
Remove Pages Insert Pages i
1-2 1-2 6-2 6-2 s
6-7 6-7 i
6-8 6-8 6-9 6-9 6-10 6-10 4
6-11 6-11 6-12 6-12 6-13 6-13 i
i Revise Appendix B as follows:
i 5.3 5.3 5.12 5.12 I
I s
4 e
- 1
1.2.3 Reactor Critical When the neutron chain reaction is self-sustaining and k,ff = 1.0.
1.2.4 Power Operation Condition When the reactor is critical and the neutron flux power range instrumentation indicates greater than 2% of rated power.
1.2.5 Refueling Operation Condition When the reactor is suberitical by at least 10%
ak/k and T,yg is < 140 F and core alterations are being made with the head completely unbolted.
1.3 REFUELING OUTAGE An outage in which core alterations are performed in order to compensate.
for fuel burnup.
1.4 CORE ALTERATION The addition, removal, relocation or other movement of fuel, controls, or installed equipment or material in a reactor core, except for functions normally performed during conventional reactor operation in accordance with intended design of equipment, such as control rod or instrument detector movement or performance of flux scans.
1.5 OPERABLE Properly installed in the system and capable of performing the in-tended functions in the intended manner as verified by testing and I
tested at the frequency required by the Technical Specifications.
Implicit in this definition shall be the assumption that all neces-sary attendant controls, electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform I
its function (s) are also capable of performing their related support function (s).
1-2 Amendment No. 32
PRESIDENT &
CHIEF OPERATING OFFICER EXECUTIVE V.P.
EXECUTIVE V.P.
& CHIEF ENGINEER
& DIRECTOR OF POWER OPERATIONS I
SAFETY REVIEW l
COMMITTEE l
- DIRECTOR OF l
SAFETY / SECURITY SENIOR VICE PRESIDENT l
NUCLEAR l
GENERATION RESIDENT l
MANAGER i
to y
- RESPONSIBLE FOR POWER AUTHORITY g
DIRECTION OF FIRE PROTECTION PROGRAM 8n O
ADMINISTRATIVE FIGURE 6.2-1 g
MANAGEMENT ORGANIZATION CHART FUNCTIONAL INDIAN POINT 3 NUCLEAR POWER PLANT
'l
Review of all proposed changes to the Operating License c.
and Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical e.
Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Resident Manager, who will forward the report to the Chairman of the Safety Review Committe'e and Senior Vice. President-Nuclear Generation.
l f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the I
Commission.
g.
Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Resident Manager or the Chairman of the Safety Review Committee (SEC).
i.
Review of the Plant Security Plan and implementing procedures annually.
i j.
Review of the Emergency Plan and implementing procedures annually.
AUTHORITY 6.5.1.7 The Plant Operating Review Committee shall a.
Recommend to the Resident Manager approval or dis-approval of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
Provide notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Chairman of c.
the SRC and the Senior Vice President-Nuclear Generation of dis-l agreement between the PORO and the Resident Manager; however the Resident Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
6-7 Amendment No. 32
RECORDS 6.5.1.8 The Plant Operating Review Committee shall maintain minutes of each meeting and copies shall be provided to the Chairman of the SRC and Senior Vice President-Nuclear Generation.
l 6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall collectively have the competence required to review problems in the following areas:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control f.
Radiological safety g.
Mechanical engineering h.
Electrical engineering i.
Administrative controls and quality assurance practices j.
Environment k.
Civil / Structural Engineering 1.
Other appropriate fields associated with the unique characteristics of a nuclear power plant.
m.
Licensing l
6-8 Amend.nent No. 32
Q i
i MEMBERSHIP 6.5.2.2 The SRC shall be composed of the following voting men.bers:
Cnairman:
Director-Nuclear Design and Analysis l
'/ ice-Chairman :
Director-Quality Assurance Member:
Manager-Nuclear Technical Support Member:
Radiological Engineer-Design and Analysis (Secretary of SRC)
Senior Vice President-Nuclear Generation Member Director-Electrical Design and Analysis Member:
Member:
Director of Environmental Programs Director-Civil / Structural Design and Analysis Member:
Senior Inservice Inspection Engineer-Nuclear Member:
Technical Support Member:
Manager-Nuclear Licensing Senior Nuclear Engineer-Design and Analysis Member:
Member:
Director-Mechanical Design and Analysis ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman; however, no more than two alternates shall participate as voting f
members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING' FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following initial fuel loading and at least once per six months, thereafter.
[ORg
- i 6.5.2.6 A quorum of SRC shall consist of the Chairman or Vice-Chairman and five members, including alternates. No more than a minority of the l
quorum shall have a direct line responsibility for the operation of the plant.
i 6-9 Amendment No. 32-
REVIEW 6.5.2.7 The SRC shall review:
a.
The safety evaluations for
- 1) changes to procedures, equipment or systems and 2) tests or experiments com-pleted under the provision of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unre'iewed safety question as defined in Section 50.59, 10 CFR.
Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications of this Operating License.
Violations of codes, regulations, orders, Technical e.
Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnoralities or deviations from normal and expected performance of plant equipment that affect nuclear safety, Events requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
g.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
1.
Reports and meetings minutes of the Plant Operating Review Committee.
i 6-10 Amendment No. 32
.i i
AUDTTS 6.5.2.0 Audits of facility activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The coniormance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
c.
The results of acticns taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
e.
The Facility Emergency Plan and implen.enting procedures at least once per 24 months, f.
The Facility Security Plan and implementing procedures at least once per 24 months.
g.
Any other area of facility operation considered appropriate by the SRC or the Executive Vice President.
l h.
The Facility Fire Protection Program and implementing procedures at luast once per two years.
1.
A fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss pre-vention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
AUTHORITY 6.5.2.9 The SRC shall report to and advise the Executive Vice President and Director of Power Operations (to be referred to in the Tech Spec. as Executive Vice President) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
6-11 Amendment No. 32
RECORDS 6.5.2.10 Records will be maintrined in accordance with ANSI 18.7-1972.
The followi.ig shall be prepared, approved and distributed as indicated below:
Minutes of each SRC meeting shall be prepared, approved and a.
forwarded to the Executive Vice President within 14 dr.ys l
after the date of the.neeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Executive Vice President within 14 days following completion of the review.
Audit reports encompassed by Section 6.5.2.8 above, shall be c.
forwarded to the Executive Vice President and to the manage-l 1
ment positions responsible for the areas audited within 30 days after completion of the audit.
CHARTER 6.5.2.11 Conduct of the committee will be in accordance with a charter, approved by the Executive Vice President, setting forth the mechanism for j
implementat. ion of the comunittee's responsibilities and authority.
6.6 REPORTABLE OOCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
The Commission shall be notified and/or a report submitted a.-
pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PORC and a report submitted by the Resident Manager to the Chairman of the SRC and Senior Vice President-Nuclear Generation.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit I
is violated:
t The reactor shall be shut down and reactor operation shall only a.
be resumed in accordance with the provisions of 10 CFR 50.36(c) (1) (i).
b.
The Safety Limit violation shall be reported immediately to f
the Commission. The Chairman of the SRC and Senior Vice President-Nuclear Generation will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 4
6-12 Amendment No. 32
A Safety Limit Violation Report shall be prepared by the PORC.
c.
This report shall describe (1) applicable circumstances pre-ceding the occurrence, (2) effects of the occurrence upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Conunission, the Chairman of the SRC and the Senior Vice ll President-Nuclear Generation by the Resident Manager.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of a.
Regulatory Guide 1.33, November, 1972.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Security Plan implementation.
Emergency Plan implementation.
e.
6.8.2 Temporary changes to procedures above may be made provided:
a.
The intent of the original procedures is not altered.
b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected, The change is documented, reviewed by the PORC and approved c.
by the Resident Manager within 14 days of implementation.
6.8.3 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Resident Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
6.9 REPORTING REQUIREMENTS' ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
6-13 Amendment No. 32
Revicw propoccd changan' in tlio Opernting Licenso c.
and Technical Specifications relating to environ-mental concerns.
d.
Make or cause to be made periodic audits of plant operation to verify conformance with the
' Environmental Technical Spacifications.
e.
Review violationis of the Environmental TW4r al Specifications.
5.5 PROCEDURES 5.5.1 Detailed written procedures, including applicable checklists and instructions, shall be prepared and followed for all activities involved in carrying out the environmental monitoring program.
Procedures include sampling, data recording and storage, instrument calibration, measure-ments and analyses, and actions to be taken when limits are approached or exceeded.
Testing frequency of alarms, as determined from experience with similar instrumen'ts in similar environments and from manufacturers'tachnical manuals, have also been included.
5.5.2 Plant Operating Procedures include provisions, in addition to the proceduras specified in Section 5.5.1, to an-sure that all plant syst' ens and components are operated in compliance with the limiting conditions for operations established as part of the Environmental Technical Specifi-cations.
n n na Drocedures a b e l
PNakde kdN:n n-Yhe intent of the original procedures is not altered.
a.
b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
c.
The change is documented, reviewed by the PORC and approved by the Resident Manager within 60 days of implementation.
l 5.6 PLANT REPORTING REQUTREMENTS 5.6.1 Routine Reports Annual Environmental Operating Report a.
Part A:
Nonradiological Report.
A report on the environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, ' Office of Nuclear Reactor Regulation) as a separate document within 120 days after January 1 of each year.
The report shall include summaries, interpretations., and statistical evalua-tion of the results of the nonradiological environmental serveillance activities (Section 3) and the environmental J
monitoring programs required by limiting conditions for for the report period, including a j
operation (Section 2) comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance 5.3 Amendment No. E
i PRESIDENT & CHIEF OPERATING OFFICER EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT
& DIRECTOR OF
& CHIEF ENGINEER POWER OPERATIONS SAFETY REVIEW COMMITTEE SENIOR VICE PRESIDENT-DIRECTOR OF NUCLEAR GENERATION ENVIRONMENTAL PROGRAMS STAFF STAFF N
FIGURE 5.2-2 m
5 MANAGEMENT ORGANIZATION ENVIRONMENTAL INDIAN POINT 3 NUCLEAR POWER PLANT z
~~ N
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5.12 l
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION 3
4l WA SHING TON, D. C. 20555
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Power Authority of the State of New York (the licensee) dated October 2,1979 and December 6, 1979 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 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; ^
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.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-59 is herehy amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 50, are hefehy incorporated in the license.
The licensee shall operate the faci'.ity in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
/q;geven Am
)(i f
. Va ga, Operating Reactors ranch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 5,1980 s--
ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET N0. 50-333 Revise Appendix A as follows:
Remove Pa g Insert Pages 247 247 249 249 250 250 251 251 252 252 252a 253 253 259 259 1
Replace page 44 of the Appendir B Technical Specifications with the enclosed i
i page 44.
9
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y
6.0 ADMINISTRATIVE CONTROLS Administrative Controls are the means by which plant opera-tions are subject to management control.
Measures specified in this section provide for the assignment of responsibilities, plant organization, staffing qualifications and related re-quirements, review and audit mechanisms, procedural controls and reporting requirements.
Each of these measures are neces-sary to ensure safe and efficient facility operation.
l 6.1 RESPONSIBILITY The Resident Manager is responsible for safe operation of the plant.
During periods when the Resident Manager is un-available, the Superintendent of Pcwer will assume his respon-sibilities.
In the' event both are unavailable, the Resident Manager may delegate this responsibility to other qualified i
supervisory personnel.
The Resident Manager reports directly to the Executive V.P. and Director of Power Operations for l
administrative matters and functionally to the Sr. Vice President Nuclear Generation for operational related matters, as shown in Fig.
6.1-1.
6.2 PLANT STAFF ORGANIZATION The plant staff organization is shown graphically in Fig.
6.2-1 and functions as follows:
1.
A licensed senior reactor operator shall be on site at all times when there is fuel in the reactor.
2.
In addition to item 1 above, a licensed reactor operator shall be in the control room at all times when there is fuel in the reactor.
3.
In addition to items 1 & 2 above, a licensed reactor operator shall be readily available on site whenever the reactor is in other than cold condition.
4.
Two licensed reactor operators shall be in the con-trol room during start-ups and scheduled shutdowns.
5.
A licensed senior re "'or operator shall be respon-sible for all movement of new and irradiated fuel within the site boundary.
A licensed reactor operator will be required to manipulate or directly supervise the manipulation of the controls of all fuel moving equipment, except the reactor building crane.
All fuel movements by the reactor building crane, except new fuel movements from receipt through dry storage, shall be under the direct supervision of a licensed reactor operator.
All fuel movements within the core shall be direct y) monitored by a member of the reactor a
analyst group.
Amendnient No. 50 247 SEE NEXT FAM FOR FOOTNOTE
s c
l Superintendent and Reactor Analyst.
Special consultant to provide expert advice may be utilized when the nature of a particular problem dictates.
(B)
Alternates 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 in PORC activities at any one time.
(C)
Meeting Frequency Meetings will be called by the Chairman as the occasions for review or investigation arise.
Meetings will be no less frequent than once a month.
(D)
Quorum The Chairman or Vice Chairman and four members, including designated alternates, shall constitute a quorum.
(E)
Responsibilities 1.
Review plant procedures, and changes thereto, re-quired by Specification 6.8.
2.
Review proposed tests and experiments that affect nuclear safety.
3.
Review proposed changes to the Operating License and Technical Specifications.
4.
Review proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5.
Investigate violations of the Technical Specifications and prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Resident Manager, who will forward the report to the Senior Vice President - Nuclear Generation and to the l
Chairman of the Safety Review Committee.
6.
Review plant operations to detect potential safety hazards.
7.
Review the Security Plan and implementing procedures annually.
249 Amendnent No. 50
8.
Raview the Emnrgcncy Plan end impicmanting pro-cedures annually.
9.
Perform special review and/or investigations at the request of the Resident Manager.
10.
Review of those reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC, in accordance with Specification 6.9.
(F)
Authority The PORC shall function to advise the Resident Manager on all matters related to nuclear safety and environmental operations.
The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 lE (1) through (4) and determine if items considered in 6.5 lE (1) through (5) constitute unreviewed safety questions, as defined in 10 CFR 50.59.
In the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the Sr. Vice President - Nuclear Generation, or their designated alternates, shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
(G)
Records Minutes of all meetings of the PORC shall be recorded and numbered.
Copies will be retained in file.
Copies will be forwarded to the Chairman of the SRC and the Sr. Vice President - Nuclear Generation.
(H)
Procedures Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the per-tinent Administrative Procedures.
6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall collectively have the competence required to review problems in the following areas:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control t
i i
Amendment No. 50 250 l
l
f.
' Radiological safety g.
Mechanical engineering h.
Electrical engineering, i.
Administrative controls and quality assurance practices j.
Environment k.
Civil / Structural Engineering 1.
Other appropriate fields associated with the unique characteristics of a nuclear power plant m.
Licensing MEMBERSHIP 6.5.2.2 The SRC shall be composed of the following voting members:
Chairman:
Director-Nuclear Design and Analysis Vice-Chairman:
Director-Quality Assurance Member:
Manager-Nuclear Technical Support Member:
Radiological Engineer-Design and Analysis (Secretary of SRC)
Member:
Senior Vice President-Nuclear Generation Member:
Director-Electrical Design and Analysis Member:
Director of Environmental Programs Member:
Director-Civil / Structural Design and Analysis Member:
Director-Mechanical Design and Analysis Member:
Senior Inservice Inspection Engineer-Nuclear Technical Support Member:
Manager-Nuclear Licensing Member:
Senior Nuclear Engineer-Design and Analysis ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following initial (
fuel loading and at least once per six months, thereafter.
N Amendment No. 50 251
QUORUM 6.5.2.6 A quorum of SRC shall consist of the Chairman or Vice-Chairman and five members, including alternates.
No more than minority of the quorum shall have a direct line responsibility for the operation of the plant.
REVIEW 6.5.2.7 The SRC shall review:
a.
The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments com-pleted 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 un-reviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications of this Operating License, e.
Violations of code, 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 plant equipment that affect nuclear safety.
g.
Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or compenents.
i.
Reports and meetings minutes of the Plant Operating Review Committee.
AUDIT 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
Amendment No. 50 252 y-4
The results of actions taken to correct deficiencica c.
occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Opera-tional Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
The Facility Emergency Plan and implementing procedures e.
at least once per 24 months.
f.
The Facility Security Plan and implementing procedures at least once per 24 months.
g.
Any other area of facility operation considered appropriate by the SRC or the President.
h.
The Facility Fire Protection Program and implementing procedures at least once per two years.
i.
An independent fire protection and loss of prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
AUTHORITY 6.5.2.9 The SRC shall report to and advise the Executive Vice President and Director of Power Operations on those areas of responsi-bility specified in Section 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records will be maintained in accordance with ANSI 18.7-1972.
The following shall be prepared, approved and distributed as indicated below:
Minutes of each SRC meeting shall be prepared, approved a.
and forwarded to the Executive Vice President within 14 days after the date of the meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.0 above, shall be forwarded to the Executive Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.
I Amendment No. 50 252a L
CHARTER 6.5.2.11 Conduct of the committee will be in accordance uith a charter approved by the Executive Vice President l
setting forth the mechanism for implemer:tation of the committee's responsibilities and authority.
6.6 REPORTABLE OCCURRENCE ACTION (A) In the event of a Reportable Occurrence, the NRC shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
(B) Each Reportable Occurrence requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC shall be reviewed timely by the PORC and a report submitted by the Resident Manager to the Senior Vice President-Nuclear Generation and the SRC.
6.7 SAFETY LIMIT VIOLATION (A) If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36 (c) (i).
(B) An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager.
The Senior Vice President-Nuclear Generation and Chairman of the SRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(C) The PORC shall prepare a complete investigative report of each safety limit violation and include appropriate analysis and evaluation of: (1) applicable circumstances preceding the occurrence, (2) effects of the occurrence upon facility components systems or structures and (3) corrective action required to prevent recurrance.
The Resident Manager shall forward this report to the Senior Vice President-Nuclear Generation, Chairman l
of the SRC and the NRC.
6.8 PROCEDURES (A) Written procedures and adminstrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5 "Facitity Administrative Policies and Procedures" of ANSI 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972.
In l
addition, procedures shall be established, implemented and maintained for the Fire Protection Program.
(B) Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.
(C) Temporary changes to nuclear related procedures may be made provided:
1.
The intent of the original procedure is not altered.
l Amendment No. 50 253
PRESIDENT &
CHIEF OPERATING k
OFFICER o
k EXECUTIVE V.P.
EXECUTIVE V.P.
3
& CHIEF ENGINEER
& DIRECTOR OF POWER OPERATIONS I
on SAFETY REVIEW l
COMMITTEE I
- DIRECTOR OF l
SAFETY / SECURITY SENIOR VICE PRESIDENT l
NUCLEAR GENERATION l
l RESIDENT l
MANAGER e
- RESPONSIBLE FOR POWER AUTHORITY DIRECTION OF FIRE PROTECTION PROGRAM I
ADMINISTRATIVE FIGURE 6.1-1 M7diAGEMENT ORGANIZATION CHART FUNCTIONAL JAMES A.
FITZPATRICK NUCLEAR POWER PLANT
N l
o.
5 PRESIDENT & CHIEF E+
OPERATING OFFICER EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT i
& DIRECTOR OF
& CHIEF ENGINEER POWER OPERATIONS SAFETY REVlod l
COMMITTEE 1
SENIOR VICE PRESIDENT-DIRECTOR OF NUCLEAR GENERATION 1
ENVIROf5(ENTAL q's PROGRAMS i
b A
STAFF STAFF FIGURE 5.2-2 MANAGEMENT ORGANIZATION ENVIRONMENTAL JAMES A. FITZPATRICK NUCLEAR POWER-PLANT l
i e
l
.