ML20134J893
| ML20134J893 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/15/1985 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134J896 | List: |
| References | |
| NUDOCS 8508290514 | |
| Download: ML20134J893 (21) | |
Text
.
,e
/ p a afo g #o UNITED STATES g.
NUCLEAR REGULATORY COMMISSION c.
{
WASHINGTON, D. C. 20555
/
DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 FACILITY OPERATING LICENSE License No. NPF-43 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for license filed by the Detroit Edison Company and Wolverine Power Supply Cooperative Incorporated (licensees) complies with the standards and requirements of the Atomic Energy Act of 1954,
-~
as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies
.or bodies have been duly made; B.
Construction of Fermi-2 (the facility) has been substantially com-pleted in c m formity with Construction Permit No. CPPR-87 and the appli-cation, as amended, the provisions of the Act, and the regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Com-mission, (except as exempted from compliance in Section 2.D below);
D.
There is reasonable assurance: (1) that the activities authorized e
by this operating license can be conducted without endangering the L-'
4 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 (except as exempted from compliance in Section2.0.below);
E.
The Detroit Edison Company
- is technically qualified to engage in the i
activities authorized by this license in accordance with the Comis-sion's regulations set forth in 10 CFR Chapter I; F.
Detroit Edison Company and Wolverine Power Supply Cooperative, Incor-porated, have satisfied the applicable provisions of 10 CFR Part 140
" Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations;
- Detroit Edison Company is authorized to act as agent for Wolverine Power Supply Cooperative, Ir.corporated, and has exclusive responsibility and control over the j -
physical construction, operation and maintenance of the facility.
l 05082905'14 850715 PDR ADOCK 05 3i P
.= --
,.G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; i~
H.
After weighing the environmental, economic, technical and other bene-fits of the facility against environmental and other costs and con-sidering available alternatives, the issuance of this Facility Oper-ating License No. NPF-43, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nu-clear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Pursuant to approval by the Nuclear Regulatory Connission at a meeting on July 10, 1985, the License for Fuel Loading and Low Power Testing, License No. NPF-33, issued on March 20, 1985, is superseded by Facility Operating License No. NPF-43 hereby issued to Detroit Edison Company and the Wolverine Power Supply Cooperative, Incorporated (the licensees) to read as follows:
1 A.
The license applies to Fenni-2, a boiling water nuclear reactor and as-sociated equipment (the facility), owned jointly by the Detroit Edison 4
Company, and Wolverine' Power Supply Cooperative, Incorporated. The facilityislocatedinFrenchtownTownship,MonroeCounty, Michigan, and is descriLed in the licensees' " Final Safety Analysis Report. as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirementr. incorporated herein, the r
Contission hereby it;.enses:
v (1)
The Detroit Edison Company (Deco), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Monroe County, Michigan, in accordance with the procedures and limitations set forth in this license; (2)
Wolverine Power Supply Cooperative, Incorporated, to possess the facility and special nuclear material as nuclear fuel at the designated location in Monroe County, Michigan, in accordance with the procedures and limitations set forth in this license; (3)
DECO, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
=b
a
' (4)
Deco, pursuant to the Act and 10 CFR Parts 30, 40 arid 70, to re-ceive, possess, and use at any time any byproduct, source and special nuclear material such as sealed neutron sources for reactor startup. sealed sources for reactor instrumintation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Deco, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chem-ical or physical form, for sample analysis or instrument cali-bration or associated with radioactive apparatus or components; and (6) DECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions cm specified in the Comission's regulations set forth.in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level DECO is authorized to operate the facility at reactor core power levels not in excess of 3292 megawatts thermal (IM% power) in accordance with the conditions specified herein and in Attach- -
ment I to this license. The items identified in Attachment I to'
~
this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions DECO shall abide by the agreements and interpretatiops between it and the Department of Justice relating to Article I, Paragraph 3 of the Electric Power Pool Agreement between Detro4t Edison Company and Consumers Power Company as specified in a letter
m
, from DECO to the Director of Regulation, dated August 13, 1971, and the letter from Richard W. McLaren, Assistant Attorney General, Antitrust Division, U. S. Department of Justice, to.,Bertram H. Schur, Associate General Counsel, Atomic Energy Comissionl dated August 16, 1971.
(4) Safety / Relief Valve In-Plant Testing (Section 3.8.1, SSER #5)*
Prior to completing the startup test program, Deco shall per-fom a series of in-plant tests of the safety / relief valves (SRVs). The acceptance criteria for these tests are contained in Section 2.13.9, "SRV Load Assessment by In-Plant Tests" of NUREG-0661, "NRC Acceptance Criteria for the Mark I Containment Long-Term Program." The results of these tests shall be reported to the NRC staff within six months of completing this test series.
(5)
Suppression Pool Temperature Measurements (Section 3.8.1, 55ER #5)
DECO shall accomplish during the first fuel cycle, all the tasks described in its letter dated March 6, 1985, regarding the series of SRV tests which will confim its methodology for measuring the suppression pool bulk temperature.
(6) Environmental Qualification (Section 3.11, SSER #5)
No later than November 30, 1985 Deco shall environmentally qualify all electrical equipment according to the provisions of 10 CFR 50.49.
r (7) Control Room Habitability (Section 6.4.1, SSER #6)
.g Prior to startup following the first refueling outage, Deco shall provide assurance to the NRC staff that potential contamination pathways through those portions of the control room air-conditioning system which are external to the con-trol room zone will not have a significant *dverse impact on control room habitability, or will propose a technical specification which provides for periodic leakage testing to assure the integrity of those external portions of the control room air-conditioning system.
- The parenthetical notation following the title of many license coYiditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
[
i h
, (8) Study of Multiple Control System Failures (Section 7,7.2, SER)
Prior to startup following the first refueling outage, DECO shall provide the NRC staff for its review and approval, the necessary analysis or modifications needed to resolve the impact of control system failures due to a failure or malfunction of power sources or sensors which provide power or signals to two or more control systems.
(9) Modifications for Fire Protection (Section 9.5.1, SSER #5 and 55ER #6)
(a) Deco shall implement and maintain in effect all provisions of the approved fire protection program as described in its Final Safety Analysis Report for the facility through Amend-ment 60 and as approved in the SER through Supplement No. 5, subject to provisions (b) and (c) below.
(b) DECO may make no change to the approved fire protection pro-o-
gram which would significantly decrease the level of fire protection in the plant without prior approval of the Commis-sion. To make such a change, DECO must submit an application for a license amendment pursuant to 10 CFR 50.90.
(c) DECO may make changes to features of the approved fire pro-tection program which do not significantly decrease the level of fire protection without prior Commission approval provided:
(i) such changes do not otherwise involve a change in a license condition or Technical Specification or result in an unreviewed safety question (see 10 CFR 50.59), and (ii) such changes do not result in failure to complete the fire protection program approved by the Commission prior to license issuance.
Deco shall maintain, in an auditable fonn, a current record of all such changes, including an analysis of the effects of the changes on the fire protection program, and shall make such records available to NRC inspectors upon request.
All changes to the approved program shall be reported to the Director of the Office of Nuclear Reactor Regulation, together with the FSAR revisions required by 10 CFR 50.71(e).
(d) Deco shall install and make operational, the in5ependent alternate shutdown system in accordance with the schedule contained in its letter dated July 5,1985. The interim
procedures and measures described in Section 9.3.1 and Appen-dix E of SSER #5'and #6 shall continue to be implemented, including removal of power from the Division 1-cooling tower bypass valve (No. E1150-F603A) and from either'the single series valve--(No. E1150-F008) in the reactor heat removal (RHR)' system or the two parallel RHR suction valves (Nos.
E1150-F608 and E1150-F009) during normal plant operation until the independent alternate system-is declared opera-tional.
(10) Emergency Diesel Generator Lube Oil Surveillance Program i
(Section 9.5.7, 55ER #5)
DECO shall implement its commitments regarding the surveillance program for the lubricating oil system of the emergency diesel-generators as described in its letters dated March 6. March 14 and March 15, 1985.
.(11) Low-Pressure Turbine-Dise Inspection (Section 10.2.2. SER) g Deco shall perform an inspection of the low-pressure. turbine-discs during the second refueling outage, including volumetric examination of the disc base using ultrasonic techniques. The frequency of subsequent inspections shall be in accordance with the turbine manufteturer's recomendations.
(12) Retention of Persons with BWR Operating Experience on Shift (section 13.1, 55ER #5)
I At all times-the plant is in an operating condition other than cold shutdown or refueling, Deco shall have a licensed senior L
c' operator on each shift who has had at least six months of hot operating experience on a similar type plant, including at least six weeks at power levels greater than 20 percent of full power, and who has had start-up and shutdown experience. For those shifts where such an individual is not available on the plant staff. DECO shall provide an advisor who has had at least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility.
Use of advisors who were licensed only at the reactor operator level or who otherwise do not fully meet the criteria for shift advisor, will be evaluated by the NRC staff on a case-by-case basis. As a minimum Deco shall train these advisors on the procedures, Technical Specifications and plant systems for the Fermi-2 facility and DECO shall examine the advisorsion these topics at a level which will assure their familiarity with the plant. For each shift, the remainder of the shift crew shall
i be trained in the role of the advisors. These advisers, or suit-ably qualified replacements, shall be retained until at least one of the senior operators on each shift has the required experience.. The NRC staff shall be notified at least 30 days prior to the release of any special assigned advisor who has been provided in accordance with this license condition.
-(13). Inservice Inspection Program Prior to September 30, 1985, DECO shall submit an initial inservice inspection program for NRC staff review and approval.
(14) Initial Test Program (Section 14. SER)
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 i
shall be reported in accordance with 50.59(b) within one month of such change.
l 0-(15) Iodine / Particulate Sampling System (Section 22. Item II.F.1(2),
55ER #6)
Prior to startup following the first refueling outage, DECO shall demonstrate that the operating iodine / particulate sampling system will perfom its intended function.
(16) Emergency Planning In the event that the NRC finds that the lack of progress in completing the procedures in the Federal Emergency Management r
Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or naintaining an adequate state of emergency preparedness, the provisions of Section 50.54(s)(2) of 10 CFR Part 50 will apply.
(17) Emergency Response Capability (NUREG-0737, Supplement No. 1)
Deco shall complete the required emergency response capabilities j
as described in Attachment 2 to this license, which is incor-i porated into this license.
(18) Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem ATW5 Events)
DECO shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is cons G tent with that given in its letters dated November 3, 1983, and November 29, 1984.
r
)..
t D.' Exemptions from certain requirements of Appendices E and J to 10 CFR Part 50, are described in supplements to the SER. These include:
(a) an exemption from the requirement of Section IV.F of Appendix E
'that a full participation emergency planning exercise be conducted within one year before issuance of the first operating license for full power and prior to operation above five percent of rated power (Section-13.3 of SSER #6); sb) an exemption from the requirement of
' Paragraph III.C.2(b) of Appendix J.--the testing of the main steam isolation valves at the peak calculated containment pressure asso-ciated with the design basis accident (Section 6.2.7 of SSER #5);
and (c) an exemption from the requirement of Paragraph III.D.2(b)(ii)-
of Appendix J, the testing of containment air locks at times when con-tainment integrity is not required (Section 6.2.7 of SSER #5). These exemptions are authorized by law and will not endanger life or prop-erty or the common defense and security and are otherwise in the public interest. Therefore. these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and cy, regulations of the Commission.
E.
The licensee shall. implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualif-ication, and safeguards contingency plans, including all amendments and revisions made pursuant to the authority of 10 CFR 50.90 and 10 CFR50.54(p). These plans, which contain Safeguards Information pro-tected under 10 CFR 73.21, are entitled: "Enrico Fermi Atomi: Power L
Plant, Unit 2 Physical Security Plan", "Enrico Fermi Atomic Power Plant, Unit 2 Security Personnel Training and Qualification Plan,"
and "Enrico Fermi Atomi: Power Plant, Unit 2 Safeguards Contingency Plan."
~~
F.
Except as otherwise provided in the Technical Specifications or Envi- ~
ronmentel Protection Plan, DECO shall report any violations of the requirements contained in Section 2.C of this license in the following 6
manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written-l followup within thirty days in accordance with the procedures described in10CFR50.?3(b),(c)and(e).
u l-
-G.
The licensees shall have and maintain financial protection of such type and in. such amounts as the Commission shall require in accordance with
~
Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
P c
E e
F" a,,.
s
.g.
H.
Thislicenseiseffectiveasofthedateofissuanceandsia11 expire at Midnight on March 20, 2025.
FORTHENUCLEARREGULATORYCdMMISSION
.46 f
Harold R. Dadon, irector*
Office of N# clear Reactor Regulation Attachments / Appendices:
- 1. - Work Items to be Completed
- 2. - Emergency Response Capabilities
~
3.
Appendix A - Technical Specifications (NUREG-1141) cr-4.
Appendix B - Environmental Protection Plan Date of Issuance: July 15,1985 r
C c'
I
ATTACHMENT 1 PREOPERATIONAL TEST, STARTUP TESTS AND OTHER ITEMS FERMI-2 DOCKET I40.: 50-341 7
This attachment identifies certain preoperational tests and other items which must be completed to the Commission's satisfaction and identifies the required timing for their completion.
1.
The preoperational tests and testing deficiencies identified in
. Attachments A and B, respectively, to the July 8, 1985, letter from Wayne H. Jens to James G. Keppler shall be completed in accordance with the scheduled commitments contained in those attachments.
- 2.. Prior to startup following the first refueling outage, correct all remaining drawing deviations identified during walkdowns associated with the resolution of 10 CFR 50.55(e), Item No. 143, " Deviations of cy' As-Built Plant from Design Documents." Demonstrate that all design documents related to the subject 50.55(e), Item No. 143, are reconciled to the as-built configuration of the plant.
ATTACHMENT 2 EMERGENCY RESPONSE CAPABILITIES
=
Deco shall complete the following requirements of NUREG-0737, Supplement No. 1, on the schedule noted below:
f-1.
Detailed Control Room Design Review (Section 22 Item I.D.1. SSER No. 5)
(a)
Deco shall comply with the NRC staff requirements for the conduct of a detailed control room design review (DCRDR) contained in Supplement No. I to NUREG-0737. DECO shall submit a sumary report of its DCRDR prior to November 30, 1986.
(b)
Deco's sumary report shall describe the resolution of each control room design findings identified in the NRC staff's
" Control Room Design Review / Audit Report," dated May 26, 1981, as having a Priority 3 rating. This sumary report shall also describe the disposition of those findings which
~
~
Deco, in its letters to the NRC staff dated June 4, 1981; July 31, 1981; July 25, 1984; and September 27, 1984, committed cy, to evaluate and/or implement after issuance of this operating license.
2.
Regulatory Guide 1.97, Revision 2 Compliance Deco shall submit by September 30, 1985, a preliminary report describing how the requirements of Regulatory Guide 1.97, Revision 2, have been or will be met.
3.
Upgrade Emergency Operating Procedures (EOPs)
(a)
Prior to July 31, 1986, Deco shall provide for NRC staff review and approval, a Procedures Generation Package (PGP) to meet the L
requirements of Section 7 to Supplement I to NUREG-0737.
(b)
Prior to startup following the first refueling outage, Deco shall complete training on, and have implemented, emergency operating procedures based on the PGP.
4.
Safety Parameter Display System The safety parameter display system (SPDS) shall be operational by December 31, 1985.
f r
APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-43
?'
FERMI-2 DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 ENVIRONMENTAL PROTECTION PLAN c
~
(NON-RADIOLOGICAL) o-e e
' Sp 9'
e f
e e
o k
4 FERMI-2 ENVIRONMENTAL PROTECTION PLAN
?'
(NON-RADIOLOGICAL)
TABLE OF CONTENTS
- Section Page 1.0 Objectives of the Environmental Protection Plan.......
1-1 2.0 Environmental Protection Issues...............
2-1 2.1 Aquatic Issues.......................
2-1 2.2 Terrestrial Issues.....................
2-1 3.0 Consistency Requirements..................
3-1
~4.-1 Plant Design and Operation.................
-$-1 3-
~
3.2 Reporting Related to the NPDES Permits and State Certification.....................
3-1 3.3' Chang'es Required for Compliance with Other
. ct' Environmental Regulations..................
3-2 4.0 Environmental Conditions,..................
4-1 4.1 Unusual or Important Environmental Events..........
4-1 4.2 Terrestrial Monitoring...................
4-1 4.2.1 Aerial Remote Sensing................
4-1 4.2.1 Herbicide Applicatnen................
4-1 3.0 Administrative Procedures..................
5-1 5.1 Review and Audit.....................
5-1 5.2 Records Retention......................
5-1 5.3 Changes in Environmental Protection Plan...........
5-1 5.4. Plant Reporting Requirements................
5:1 a-5.4.1 Routine Reports. '..................
5-1 5.4.2 Non-routine Reports.................
5-1 f
I i
4 s
k
~
1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protectJon of environ-mental values during construction and operation of the nuclear fa'cility. The principal objectives of the EPP are as follows:
(1). Verify that the station is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments.
(2) Coordinate NRC requirements and maintain consistency with other Federal, State and locas requirements for environmental protection.
(3) Keep the NRC informed of the environmental effects of facility construction and operation and of actions taken to control those effects.
Environmental concerns identified in the FES which relate to water quality
.7
~
matters are regulated by way of the licensee's NPDES permit.
C7~
9 h>
a
- ~ _
9 I
3_1
2.0 Environmental protection Issues In the FES-OL dated-August, 1981, the staff considered the environmental impacts:
associated with the operation of the Fermi-2 facility. Certain environmental issues were identified which required study or license conditions:to resolve environmental concerns and to assure adequate protection of the environment.
2.1 Acuatic Issues The NRC will rely on the Michigan Department of Natural Resources for the pro-tection of the aquatic environment from non-radiological operational impacts via the NPDES permit (FES-OL Section 6.b, Summary and Conclusions). The NPDES permit provides effluent limitations for thermal and chemical discharges, as well as requirements for a one year monitoring of entrainment and impingement at the general service water pumphouse (FES-OL Section 5.3.2).
The NPDES per-mit is reproduced in Appendix D of the FES-OL.
2.2 Terrestrial Issues Those issues requiring monitoring programs previously identified.are listed
_b.el ow.
(1) The need to detect long-term or sudden changes in vegetation'due to cr.
operation of the Fermi-2 facility (FES-OL Section 5.3.3).
(2) The need for controlled use of herbicides on transmission rights-of-way (FES-OL Section 4.2.2).
NRC requirements with regard to terrestrial issues are specified in Section 4.2 of this EPP.
r T--
O e
2-1 l
3.0 Consistency Reauirements 3.1 Plant Design and Ooeration Thelicenseemaymakechangesinstationdesignoroperationorkrformtests or experiments affecting the environment provided such changes, tests or experi-monts do not involve an unreviewed environmental question, and di~not involve a change in the Environmental Protection Plan. Changes in plant design or operation or performance of tests or experiments which do not affect the envi-ronment are not subfact to the requirements of this EPP. Activities governed by Section 3.3 are not subject to the requirements of this section.
Before engaging in additional construction or operational activities which may affact the environment, the licensee shall prepare and record an environmental evaluation of such activity.
When the evaluation indicates that such activity involves an unreviewed environmental question, the licensee shall provide a written evaluation of such activities and obtain prior approval from the Direc-tor, Office of Nuclear Reactor Regulation.
Activities are excluded from this requirement if all measurable non-radiological effects are confined to the on.
site areas previously disturbed during its preparation and plant construction.
When such activity involves a change in the Environmental Protection Plan, such activity and change to the Environmental _ Protection Plan may be implemented only in accordance with an appropriate license amendment as set forth in Cr' Section 5.3 of this appendix.
l
^
A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns:
(1) a matter which may result in a significant increase in any adverse eavironmental impact previously evaluated in the final environmental statement, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level; or (3) a matter not previously reviewed and evaluated in the documents specified in Item (1) of this section, which may have a significant adverse environmental impact.
r The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this section. These e
records shall include a written evaluation which provides bases for the deter-mination that the change, tests, or experiment does not involve an unreviewed environmental question nor constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0.
The licensee shall include as part of its Annual Environmental Operating Report (per Section 5.4.1), brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.
3.2 Reportino Related to the NPDES Permits and State Certification Changes to, or renewals of, the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change or renewal is approved. If a permit or certification, in part or in its entiftty, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.
3-1
The licensee shall notify the NRC of changes to the effective NPDES Permit proposed by the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency. The licensee shall
- provide the NRC a copy of the application for renewal of the NPDES Permit at the same time the application is submitted to the permitting agenti.
3.3 Changes Required for Compliance With Other Environmental Reow1ations Changes in plant design or operation and performance of tests or experiments which are required to achiave compliance with cther Federal, State, or local environmental regulations are not subject to the requirements of Section 3.1.
s..t._
w w
~
- 9 h
S S
P
- ~
3-2
4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event which indicates,%r could result in, significant environmental impact causally related to plant operation, shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report per Section 5.4.2.
The following are examples: excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, and an increase in nuisance organisms or conditions.
No routine monitoring programs are required to implement this condition.
4.2 Terrestrial Monitorina
~
A special surveillance program will be conducted to measure key terrestrial parameters after startup of the Fermi-2 facility for comparison with corres-
-ponding measureme'nts obtained prior to startup. These studies focus on effrets h'-
due to the operation of cooling towers' at the Fermi-2 site.
~
4.2.'1 ~Aer~ial Remote Sensino cm Vegetative communities of the site and vicinity within 1 kilometer of the
~
cooling towers in all directions shall be aerially photographed to detect and assess the significance of damage, or lack thereof, as related to cooling tower drift dispersions. Photography shall be done by aerial overflight prior to harvest. Monitoring shall include a program of low altitude, color infrared photography. The scale for full coverage shall be adequate to enable identi-fication of vegetative damage over relatively.small areas of terrain. Some circumstances may warrant inspection of photographs discerning individual trees.
Such scale should be adequate to resolve impacted features. Photographs shall
.be compared with baseline data to ascertain changes in vegetation. Photogra; phic interpretations shall be verified by ground inspection surveys to confirm nio,eas of stress and non-stress. This program shall require aerial photographic ar nitoring during the first July-September period after the statinn has been -in operation for one year and the program shall be repeated once the following year and alternate years for three (3) additional periods. A report shall be submitted as part of the annual report following each aerial photographic moni-toring period. -The report shall contain a description of the program, results, and interpretative analyses of environmental impacts. Results reported shall contain information encompassing but not limited to the following: sampling data; time of day; film types; and one (1) set of resultant color transparen-cies encompassing an area within about a one kilometer (1 km) radius of the cooling tower.
4.2.2 Herbicide Application The use of herbicides within the corridor rights-of-way of this itation shall conform to the approved use of selected herbicides as registered by the Environmental Protection Agency and approved by State authorities and applied as directed by paid authorities.
4-1
Records shkil be maintained at the site concerning herbicide use. Such records shall include the following information: commercial and chemical names of materials used, concentration of active material in formulations diluted for field use; diluting substances other than water; rates of application; method and frequency of application; location; and the date of applicat4cn. Such
!~
records shall be maintained for a period of five years and be made readily avail-able to the NRC upon request. Thereshallbenoroutinereportygrequirement associated with this condition.
W ESM
ME G
O 6
F wy e
L e'
e e
9 e
4-2
5.0 Administrative Procedures 5.1 Review and Audit The licensee shall provide for review and audit of compliance with_the Environ-mental Protection Plan. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A des-cription of the organizational structure utilized to achieve the fndependent review and audit function and the results of the audit activities shall be main-tained and made available for inspection.
5.2 Records Retention Records and logs relative to the environmental aspects of plant operation shall be made and retained in a manner convenient for review and inspection. These records and logs shall be made available to the NRC on request.
Records of modifications to plant structures, systems and components determined to potentially affect the continued protection of the environment shall be
" ' ~ ' ' ~ ~
7et'afned for th'e life of the plant. All other records, data and logs relating
. to this EPP shall be retained for five years or, where applicable, in accordance "with the. requirements of other agencies, cr-5.3 Changes in the Environmental Protection Plan A request for change in the Environmental Protection Plan shall include an assessment of the environmental impact of the proposed change and a supporting justification. Implementation of such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the Environmental Protection Plan.
5.4 Plan Reporting Requirements 5.4.1 Routine' Reports r
An Annual Environmental Operating Report describing implementation of this EPP r
for the previous year shall be submitted to the NRC prior to May 1 of each yeat.
The initial report shall be submitted prior to May 1 of the year following issuance of the operating itcenses. The period of the first report shall begin with the date of issuance of the operating license.
The report shall include summaries and analyses of the results of the environ-mental protection activities required by Section 4.0 of this Environmental Pro-tection Plan for the report period, including a ' omparison with preoperational c
studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.
If harmful effects or evidence of trends towards irreversible damage to the environment are observed, the licensee shall provide a detailed analysis of the data and a proposed course of ggtion to-alleviate the problem.
e 5-1 e-
The Annual Environmental Operating Report shall also include:
(a) A list of EPP noncompliances and the corrective actions taken to remedy i
them.
i (b) A list of all changes in station design or operation, tests, and experi-ments made in accordance with Section 3.1 which involved a potentially
.significant unreviewed environmental issue.
(c) A-list of nonroutine reports submitted in accordance with Section 5.4.2.
In the event that some results are not available by the report due date, the report shall be submitted noting and explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
'5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of the occurrence
.-wrf an unusual or'important environmental event. The report shall: (1) describe, e'-at analyze, and evaluate the event, including the extent and magnitude of the impact-
,_and the plant operating characteristics; (2) describe the probable cause of the event; (3)' indicate the action taken-to correct the reported event.; (4) indicate cy, the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems; and (5) indicate
~
. the agencies notified and their preliminary responses.
1 Events reportable under this section which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this section. The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.
l s
e--
~
4 4
4+
t 5-2
-