ML20245F156

License NPF-83,authorizing Fuel Loading & Precriticality Testing of Plant

ML20245F156
Person / Time
Site:	Limerick
Issue date:	06/22/1989
From:	Murley T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245F045	List: ML20245F040 ML20245F156 ML20245F161 ML20245F177
References
NUDOCS 8906280049
Download: ML20245F156 (23)

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UNITED STATES g ((. .g. NUCLEAR REGULATORY COMMISSION

,- '5 j WASHINGTON, D. C 20555

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Q PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICKGENERgINGSTATION,_ UNIT _2 FACILITY OPERATING LICENSE-License No. NPF-83

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for license filed by Philadelphia Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth.in 10 CFR Chapter I, and all required notifica-tions to other agencies or bodies have been duly made; B. Construction of the Limerick Generating Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit'Ho. CPPR-107 and the application, as amended, the provisions of the Act and the regulations of the Commission; C. The facility will operate in conformity with the app',1 cation, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0. below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Cha Section2.0.below)pterI(exceptasexemptedfromcompliancein E. The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements,"

of the Commission's regulations; G. The issuance of this license will not be inimical to the common defense and security or to i.he health and safety of the public;

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H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-83, 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 nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.

2. Based on the foregoing findings and.the Decision of the Atomic Safety and  ;

Licensing Board, LBP-85-25, dated July 22, 1985 and the Commission's Order '

dated June 8,1989, regarding this facility, Facility Operatin NPF-83 is hereby issued to the Philadelphia Electric Company (g Licensethe license to read as follows A. This license applies to the Limerick Generating Station, Unit 2, a boiling water nuclear reactor and associated eauipment, owned by Philadelphia' Electric Company. The facility is located on the licensee's site in Montgomery and Chester Counties, Pennsylvania on the banks of the Schuylkill River approximately 1.7 miles southeast of the city limits of Pottstown, Pennsylvania and 21 miles northwest of the city limits of Philadelphia, Pennsylvania, and is described in the licensee's Final Safety Analysis Report, as supplemented and amended, and in the licensee's Environmental Report-0perating License Stage, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein,, the l Commission hereby licenses Philadelphia Electric Company:

(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to-possess, use, and operate the facility at the designated location in Montgomery and Chester Counties, Pennsylvania, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and 4 to 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 j Report, as supplemented and amended; <

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; 1

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(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, I possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) 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 specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.

below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Philadelphia Electric Company is authorized to load fuel and conduct precriticality tests and startup tests, in accordance with the conditions specified herein. This license and the authorization herein is restricted to fuel loading and precritical operations.

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. PEco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection (Section 9.5, SSER 2)*

The licensee shall maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Revision 57 and as approved in the SER through Supplement 8, and in the Fire Protection Evaluation Report through Revision 11, subject to the following provisions a and b below;

a. The licensee shall make no change to features of the approved fire protection program which would decrease the level of fire protection in the plant without prior approval of the Commission. To make such a change the licensee must submit an application for license amendment pursuant to 10 CFR 50.90.

• The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

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b. The. licensee may make changes to features of the approved fire protection program which do not decrease the level of fire protection without' prior Commission approval after I

'such features have been installed as approved, provided 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). However, the licensee shall niaintain, in an auditable form, a current record of all such changes including an evaluation i of the effects of the change on the fire protection 1 program and shall make such records available to NRC l inspectors upon request. All changes to the approved program made without prior Comission approval shall be reported to the Director of the Office of Nuclear Reactor '

Regulation, together with supporting analyses, annually.

(4) physical Security and Safeguards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR50.54(p). The plans, which contain Safeguards Information -

protected under 10 CFR 73.21, are entitled: " Limerick Generating I Station, Units l'8 2, Physical Security Plan," with revisions submitted through March 28,1989; " Limerick Generating Station, Units 1 & 2, Plant Security Personnel Training and Qualification Plan," with revisions submitted through October 1,1985; and

" Limerick Generating Station, Units 1 & 2, Safeguards Contingency Plan," with revisions submitted through November 15, 1986.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) exemption from the requirement of paragraph III.D.2.(b)(ii) of Appendix J, the testing of containment air locks at times when the containment inte (b) grity is not required exemption (Section 6.2.6.1 from the requirements of the SERII.H.4 of paragraphs and SSER-3) and III.C.2 of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption from the requirements of paragraph III.C.3 of Appendix J that the measured MSIV leak rates be included in the summation for the local leak rate test (Section 6.2.6.1 of SSER-3), (c) exemption from the requirement of paragraphs II.H.1 and III.C.2 of Appendix J, l

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the local leak rate testing of the Traversing Incore Probe Shear Valves (Section6.2.6.1oftheSERandSSER-3)and(d)anexemption from the schedule requirements of 10 CFR 50.33(k)(1) related to availability of funds for decommiss Sning the facility (Section 22.1, SSER 8). The special circumstances regarding exemptions (a), (b) and (c) are identified in Sections 6.2.6.1 of the SER and SSER 3.

An exemption from' the criticality monitoring requirements of 10 CFR 70.24 was previously granted with NRC materials license No.

SNM-1977 issued November 22, 1988. The licensee is hereby exempted-from the requirements of 10 CFR 70.24 insofar as this requirement applies to the handling and storage of fuel assemblies held under this license.

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items a, b, c, and d above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in i conformity with the application, as amended, the provisions of the i Act, and the rules and regulations of the Commission.

E. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license-in the following 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 i Notification System with written followup within thirty days in i accordance with the procedures described in 10 CFR 50.73(b), (c),

and(e).

F. The licensee 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. '

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-G. iThis license is effective as of the date of issuance and shall expire at midnight ~on June.22 , 2029..

FOR THE NUCLEAR REGULATORY COMMISSION 4

Thomas E. Murley, Director-

, 0ffice of Nuclear Reactor Regulation

Enclosures:

. I .- Appendix A - Technical Specifications (NUREG-1360)

2. Appendix'.B - Environmental Protection Plan

.Date of Issuance: June 22,-1989 g '4' Y'

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G. This' license is effective as of the date of' issuance and shall expire at midnight on June' 22 , 2029.

FOR THE NUCLEAR REGULATORY COMMISSION' 4 2- = - E Thomas E. Murley, Director Office'of Nuclear Reactor Regulation

Enclosures:

1.- Appendix A - Technical Sp'ecifications (NUREG-1360)

2. ' Appendix B - Environmental Protection Plan Date of. Issuance: June 22, 1989 i

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NUREG-1360 Technical Specifications Limerick Generating Station, Unit No. 2 Docket No. 50-353 Appendix "A" to License No. NPF-83 Issued by the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation June 1989 p*"%,

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APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-83 LIMERICK GENERATING STATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY DOCKET NOS. 50-352 AND 50-353 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

June 22, 1989 l

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LIMERICK GENERATING STATION UNITS-1 AND 2 ENVIRONMENTAL PROTECTION PLAN I (NON-RADIOLOGICAL)

TABLE OF CONTENTS Section Page

.0 0BJECTIVES OF'THE ENVIRONMENTAL PROTECTION PLAN . . . . . 1-1 F

l 2.0 ' ENVIRONMENTAL PROTECTION ISSUES . . ... . ... . . . . . . 2-1 2.1 Aquatic Issues... . .;... . . . . . . . . . . . . . . . . 2-1 2..2 Terrestrial Issues.'. . . . . . . . . . . . . . . . . . . 2-2 2.3 Noise Issues.-. . . . . . . . . . . . . . . . . . . . . . 2-2 i

3.0 CONSISTENCY ' REQUIREMENTS. . . . . . . . . . . . . . . . . 3-1 3.1 Plant Design and Operation. . . . . . . . . . . . . . . . 3-1

. 3.2 Reporting Related to the NPDES Permit and State Certifications. . . . . . . . ... . . . . . . . . . . . 3-2 3.3 Changes Required for Ccmpliance with Other Environmental Regulations . . . . . . . . . . . . . . . 3-2 L

4.0 ENVIRONMENTAL CONDITIONS. . . . . . . . . . . . . . . . . 4-1 4.1 Unusual or Important Environmental Events . . . . . . . . 4-1 4.2- Environmental Monitoring. . . . . . . . . . . . . . . . 4-1 5.0 ~ ADMINISTRATIVE PROCEDURES . . . . . . . . . . . . . . . . 5-1 5.1. Review a nd Audi t. . . . . . . . . . . . . . . . . . . . . 5-1 5.2 Records Retention . . . . . . . . . . . . . . . . . . . . 5-1

. 5.3 Changes in Environmental Protection Plan. . . . . . . . . 5-1 5.4 Plant Reporting Requirements. . . . . . . . . . . . . . . 5-2 a _.,_.__a, . - - - - - - -- a- - -w---a--- - ' - - - -

4 1.0 OBJECTIVESOFTdEENVIRONMENTALPROTECTIONPLAN The Environmental Protection Plan (EPP) is to provide for protection of non-radiological environmental values during operation of the nuclear facility.

The principal objectives of.the EPP are as follows:

(1) Verify that the facility is operated in an environmentally acceptable manner, as established by the Final Environmental Statement-0perating License 3tage (FES-OL) and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other. Federal, State and local requirements for environmental protection.

(3) Keep 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-OL which relate to water quality matters are regulated by way of the licensee's NPDES permit.

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. 2.0 ENVIRONMENTAL PP0TECTION ISSUES In the FES-OL dated April,1984, the staff considered.the environmental impacts associated with the operation of the two unit Limerick Generating

. Station. .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 Aquatic Issues (1) During operation, the station blowdown temperature will exceed the maximum permissible temperatures set by the applicable water quality standards.

L However, the affected area of the Schuylkill River is expected to be smaller than the maximum area permitted by the Delaware River Basin Commission. (FES Section 5.3.2.2)

(2) The water quality of the station discharge, after initial mixing with the Schuylkill River, is predicted to, at times, exceed the applicable quality criteria for some constituents, based on source water maximum constituent concentrations. These exceedances are expected for constituents whose maximum river concentrations also exceed the applicable criteria.

(FESSection5.3.2.3)

(3) Chlorination of station cooling waters for condenser and cooling tower biofouling control may result in some adverse impacts to Schuylkill River biota in.the vicinity of the station discharge. (FESSection5.3.2.3)

. (4)- Operation of the Point pleasant Diversion will alter the hydrolo.gy, aquatic habitats, and water quality of the headwater section of the East Branch of Perkiomen Creek but the diversion waters are expected to provide beneficial dilution of waste loads entering the stream in its middle and lower reaches. (FES Sections 5.3.2.3 and 5.2.2)

(5) The supplemental cooling water withdrawal from Perkfomen Creek using state-of-the-art technology will result in localized effects from entrainment of fish larvae. (FES Section 5.5.2) 2-1

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No specific' terrestrial issues were identified by the NRC staff in the FES-OL.

2.3 Noise Issues (1) Tones from the Point Pleasant pumphouse transformers are predicted to be L audible and may cause annoyance at a nearby residence. Noise monitoring and, if necessary, mitigative measures to make the tones inaudible have been mandated by the ASLB. (FES Sections 5.12.1 and 5.14.4.1)

(2) Noise from transformers and pumps in the Bradshaw Reservoir pumphouse may be audible at nearby residences. The licensee has committed to ambient and operational noise level monitoring and implementation of identified mitigative measures, if necessary, to reduce noise levels below those likely to cause annoyance and complaints. (FES Sections 5.12.2 and 1

5.14.4.2)

(3) Offsite noise. levels in the vicinity of the Limerick site during station operation are not expected to be high enough above ambient levels to annoy nearby residents. But because of uncertainties in the assessment, a confirmatory noise monitoring program and implementation of mitigative measures, if necessary, will be undertaken. (FES Sections 5.12.3 and 5.14.4.3)

NRC requirements with regard to noise issues are specified in Section 4.3 of this EPP.

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3.0 CONSISTENCY REQUIREMENTS 3.1 Plant Design and Operation The licensee may make changes in station design or operation or perform tests or experiments affecting the environment provided such activities do not involve an unreviewed environmental question.and do not involve a change in the EPP.* Changes in station design or operation or performance of tests or experiments which do not affect the environment are not subject 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 significantly affect the environment, the licensee shall prepare and record an environmental evaluation of such activity. Activities are excluded from this requirement if all measurable non-radiological environmental effects are confined to the on-site areas previously disturbed during site preparation and plant construction. When the evaluation indicates that such activity involves an unreviewed environmental question, the licensee shall provide a written evaluation of such activity and obtain prior NRC approval. When such activity involves a change in the EPP, such activity and change to the EPP may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3 of this EPP.

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 environmental impact previously evaluated 1 in the FES-OL, environmental impact appraisals, or in any decisione of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or

• This provision does not relieve the licensee of the requirements of 10 CFR 50.59 3-1 I

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power level; or (3) a matter not previously reviewed and evaluated in the

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documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of the EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of the Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations and evaluations of such changes, tests and experiments.

3.2 Reporting Related to the NPDES Permit 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 entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

The licensee shall notify the NRC of changes to the effective NPDES Permit proposed by the licensee by providing the 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 agency.

3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State and local environmental regulations are not subject to the requirements of Section 3.1.

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lt i' 4.0 ENVIRONMENTAL CONDITIONS 4.1 Unusual or Important Environmental Events ,

Any' occurrence of an unusual or important event that' indicates or could result in significant environmental impact causally related to plant operation j

- shall be recorded and 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 Subsection 5.4.2. The following are examples: excessive i

bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 19733 fish kills, increase in nuisance organisms or conditions, and unanticipated or emergency discharge of waste water or chemical substances.

No routine monitoring programs are required to implement this condition.

4.2 Environmental Monitoring 4.2.1 Aquatic Monitoring The certifications and permits required under the Clean Water Act provide

. mechanisms for protecting water quality and, indirectly, aqcatic biota. The NRC will rely on the decisions made by the Commonwealth of Pennsylvania, under the authority of the Clean Water Act, for any requirements for aquatic monitoring.

4.2.2 Terrestrial Monitoring No terrestrial monitoring is required.

4.2.3 Maintenance of Transmission Line Corr 10'rs The use of herbicides within the Limeric. den .c.i.ng Station transmission line corridors (Limerick to Cromby, Cromby to Plymouth Meeting, Cromby to North Wales, and Limerick to Whitpain) shall conform to the approved use of selected herbicides as registered by the Environmental Protection Agency and approved by Commonwealth authorities and applied as directed on the pesticide

. label.

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Records shall be maintained in the licensee's Electric Transmission and Distribution Department concerning herbicide use. Such records shall include the following information: commercial and chemical names of materials used; concentration of active material in formulations for field use; diluting substances other than water; rates of application; method of application; location; and the date of application. Such records shall be maintained for a period of 5 years from the date they are prepared and shall be made readily available to the NRC upon request. There shall be no routine reporting requirement associated with this condition.

4.2.4 Noise Monitoring 4.2.4.1 General Requirements for Sound Level Surveys Surveys shall be conducted to quantify the ambient (i.e., background) and the operational sound levels that exists at various locations in the vicinity of the LGS site and supplemental cooling water system facilities, as specified below. The ambient sound level surveys shall be conducted during the time period when significant station or supplemental cooling water system outdoor construction activity has ended, and with no operation of the cooling system or other significant noise sources (e.g., transformers) so that measured sound levels are not affected by such activities. The operational sound level surveys shall be conducted as soon as practice'leo within the first year of the operational phase of the various station associated facilities, when transformers are energized or when the cooling towers are operating with their design water flow rates, as appropriate for the facility under study. For the LGS site, one survey shall be conducted for one unit normal operation and a second survey for two unit normal operation. The conduct of the surveys for both phases shall be such that the results are comparable.

For each of the surveys, except as otherwise specified below or in LBP-83-11, sound level data shall be collected at several sites, the exact number and location to be selected by the licensee after consideration of (1) exist ,g onsite and nearby offsite noise sources and barriers; (2) noise sensitivt land uses in the site vicinity (e.g., residences, schools churches, cemeteries, huspitals, parks); and (3) previously conducted noise surveys in the site vicinity.

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The selection, calibration and use of equipment, conduct of the surveys, and

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the analysis and reporting of data shall conform to the provisions of the applicable American National Standards Institute Standards.

The results of the surveys conducted under this program shall be summarized, interpreted and reported in accordance with Section 5.4.1 of this EPP.

The final report of this program shall present a brief assessment by the licensee of the environmental impact and supplemental cooling water system operation on the various offsite acoustic environments, and shall describe the mitigative measures, if any. nat have been, or are to be taken to reduce the impact of plant or supplements 1 cooling water system noise levels on the offsite environments. This report shall also contain a list of noise-related complaints or inquiries received by Philadelphia Electric Company concerning the Limerick Generating Station or its supplemental cooling water system subsequent to issuance of the operating license along with a description of the action taken by Philadelphia Electric Company to resolve these complaints or inquiries.

This program shall terminate upon completion of the collection of the specified sound level data for each phase and submission of an acceptable final report.

4.2.4.2 Point Pleasant Pumphouse An ASLB ruling (LBP-83-11; March 8,1983) requires that the licensee conduct a one-time field study after the transformers are placed in operation at Point Pleasant. The noise from operation of the transformers shall be reduced to a level so that the transformer core tones will be inaudible (i.e., not above the masking level, as defined below) at the site boundary.

The licensee shall determine, based on onsite measurements, the delta L(ex)

(i.e., the noise level in excess of the masking level) for each tone. The masking level is defined as "N" dB above the ambient spectrum level, where "N" is defined as follows:

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4 Masking- Level "Ni ', Tone Frequency,

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dB Hz 17.5 120 17.4 240 17.8 360 18.2 480 The steps to be carried out are:

(l) Measures the broadband (nontonal) ambient nighttime (midnight to 4 a.m.)

levels in all octave bands of frequency when the transformers are not energized (stepAintheASLB. ruling). From these, tone-masking sound levels (thresholds of audibility) at each tone frequency shall be calculated.

(2) Measure the level of the tones that exist when the transformers are energized (step B) in the one-third-octave bands that contain them for comparison with the calculated masking levels from step A to determf ne audibility. Transformer tones should not be greater than the masking level for specific one-third-octave bands.

If, for any reason, it is not practicable to de-energize the transformers at any time during the prescribed measurement time period (midnight to 4 a.m.),

alternative measurements shall be made. In that event, only one measurement of the entire spectrum need be made, but it must be done entirely in one-third-octave bands. Any measured octave band sound level that includes a  ;

tone or tones cannot be used to determine the true background ambient sound level for that octave band. In such cases, the background ambient level in any one-third-octave band containing a tone shall be approximated by interpolating between those adjacent one-third-octave band levels that do not contain.any tones.

If audible tones, defined as any delta L(ex) value greater than 0, are found at the site boundary, mitigative measures, such as a three-sided barrier or a i

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fu11'enclosurearoundthe. transformers,shallbeimplemented(andtheir performance verified by noise measurement) so that tones are not greater than the masking level as previously determined.

4.2.4.3 Bradshaw Reservoir The noise measurements proposed for the Point Pleasant site shall be made at the Bradshaw pumphouse site boundary while energized, on the line between the transformers and residences B, D, and F, to determine if the tones would be audible at those points (see Figure 5.6, LGS Final Environmental Statement, j NUREG-0974, p. 5-140). Measures to render these tones inaudible to these points shall then be applied, as necessary, and their performance verified.

The measurement program recommended for Bradshaw to test for audible tones from the transformers shall also be extended to include audible tones in the 1000-Hz octave band at the southeast site boundary in the direction of

. residence B.

4.2.4.4 Limerick Site The operational measurement program to be applied to the Point Pleasant area shall be applied to the area immediately beyond the northern boundary of the Limerick site as well. If audible tones are found to be present at the northern site boundary after Unit 1 transformers are energized, mitigative measures shall be taken and their performance verified, as required for the Bradshaw Reservoir, to cause those tones to be inaudible.

For the LGS. site only, data shall be collected from each sampling site during the time of year when foliage of deciduous trees is present and also during the time of year when such foliage is largely absent. Data collected from each sampling location shall encompass both the daytime and nighttime periods.

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9 5.0 ADMINISTRATIVE PROCEDURES l

5.1~ Review and Audit The licensee shall provide for review and audit of compliance with the EPP.

The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A description of the organizational structure utilized to achieve the independent review and raait function and results of the audit activities shall be maintained and made available for inspection.

5.2 Records Retention Records and logs relative to the environmental aspects of station operation shall be made and retaintd in a manner convenient for review and inspection.

- These records and logs shall be made available to NRC on request.

Records of modifications to station structures, systems and components l determined to potentially affect the continued protection of the environment shall be retained for the life of the station. All other records, data and logs relating to this EPP shall be retained for five years or, where ar.plicable, in accordance with the requirements of other agencies.

5.3 Changes in Environmental Protection Plan

' Request for changes in the EPP 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 EPP.

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5.4. Plant Reporting Requirements

'5.4.1 Routine Reports An AnnualcEnvironmental' Operating Report describing implementation of this EPP for the previous year shall be submitted to.the NRC prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following issuance of the operating license.

j The report shall include summaries and analyses of the results of the environ-

-mental protection activities as required by Subsection 4.2 of this EPP for the report period, including a comparison with related preoperational studies, operational-controls (asappropriate),andpreviousnon-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 mitigating action.

The Annual Environmental Operating Report shall also include:

l (1) A list of EPP noncompliance and the corrective actions taken to remedy them.

(2) A list of all changes in station design or operation, tests, and experiments made in accordance with Subsection 3.1 which involved a potentially significant unreviewed environmental question.

(3) A list'of nonroutine reports submitted in accordance with Subsection 5.4.2.

In the event that some results are not available by the report due date, the report shall be submitted noting and explain Mg the missing results. The missing results shall be submitted as soon as possible in a supplementary report.

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5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within'30 days of occurrence of a nonroutine event. The report shall (a) describe, analyze, and evaluate the-event, including extent and magnitude of the impact and plant operating characteristics,(b)describetheprobablecauseoftheevent,(c)indicatethe action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems,_ and (e) indicate the agencies notified and their preliminary responses.

Events reportable under this subsection 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 subsection. The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.

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