ML20069F761

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Amends 72 & 40 to Licenses DPR-51 & NPF-6,respectively, Revising App B ETS Re Nonradiological Water quality-related Requirements of Federal Water Pollution Control Act Amends of 1972
ML20069F761
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 03/11/1983
From: Clark R, Stolz J
Office of Nuclear Reactor Regulation
To:
Arkansas Power & Light Co
Shared Package
ML20069F766 List:
References
DPR-51-A-072, NPF-06-A-040 NUDOCS 8303240073
Download: ML20069F761 (34)
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7e UNITED STATES NUCLEAR REGULATORY COMMISSION

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d ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-51 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Arkansas Power & Light Company (the licensee) dated February 15,1983, complies 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 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 L

requirements have been satisfied.

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- 2. ; Accordingly, the license'is amended.by changes to the Technical i

-Specifications as indicated in the attachment to this-license amendment, and paragraph 2.c.(2) of Facility 0perating License No. DPR-51 is'hereby amended to read as follows:

(2) 7 echnical Specifications T

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The Technical-Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporatef in the license. Thel licensee shall operate-the facility in accordance with the Technical Specifications.

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This license amendmeht is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION (f

Jo n F. Stolz, Chie 0 erating Reactors Branch f4 ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 11, 1983 f

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ATTACHME11T TO LICEllSE AMENDf1EM-T N0'. 72

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FACILITY OPERATING-tICENS& N0v-DPR y.

DOCKET NO. 50-3131

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Replace; the,-following pages of_ the Appendix "B" Technical Specifications

. with the enclosed pages. The revised pages are identified.by amendment f number and contain vertical lines indicating the area of change.

Remove pages Insert pages 1-i' ii

'11 111 111 iy iv v

v 1-1 1-1 1-2~

2-l' thro 0gh 2-6 2-1 3-1 through 3-4 3-1 4 ;

4-1 4-6 through 4-13 4-13 4-18 4-18 4-29 through 4-32 4-29 1 through 5-6 5-1-through 5-6 6 6-1 6-2 B

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Effective January 19, 1975, activitfenndd'r 35T.'~S'."AtoiHE Energy Commis'sion

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regulatory program were assumed by the U. S. Nuclear Regulatory Commission in

.accordance with the Energy Reorganization Act of 1974. Any references to the

-Atomic Energy Commission-(AEC)Jcontained herein should be interpreted as

-Nuclear Regulatory. Commission (NRC).

TABLE OF CONTENTS Section Page 1.0' DEFINITIONS................................................

1-1 1.1.

Deleted 1.2 Gamma Isotopic Analysis...............................

1-1

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1.3 Environmental Samples................................ 1 1.4 Deleted *)

1.5 Deleted 1.6 Deleted 1.7 Deleted 1.8 Deleted 1.9 Radiation Monitor Checks, Tests, and Calibration......

1-2 1.10 Equivalent Decay Time................................

1-2 2.0 LIMITING CONDITIONS FOR OPERATION..........................

'2-1 l

2.1 Deleted 2.2 Deleted

2. 3 Deleted

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2.4' Radioactive Discharge................................

2-9 2.4.1 Liquid Discharge..............................

2-10 2.4.2 Gaseous Discharge.............................

2-12 9

Amendment No. 65, 72 I

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Section~

Page.

3.0

. DESIGN FEATURES AND OPERATING PRACTICES....................

3-1 3.1 Deleted

~3.2 Deleted 3.3 Deleted

'3.4 Deleted-3.5

. Land Management 3-1 4.0 ENVIRONMENTAL SURVEILLANCE.................................

4' l 4.1 Deleted 4.1.1 Deleted 4.1.2 Deleted 4.2 Radiolog'ihal Environmental Monit'oring................

4-13 4.2.1' Air Sampling..................................

4-13 4.2.2 Direct Radiation...............................

4-13 4.2.3 Precipitation Sampling........................

4-13 4.2.4 Lake Dardanelle'...............................

4-14 4.2.5 Ground Water Sampling.........................

4-14 4.2.6 Russellville City Water.............~..........

4-14

'4.2.7 Reservoir Bottom Sediments....................

4--14 4.2.8 Aquatic Biota.................................

4-14 4.2.9 Fish Bone...................................

4-14' 4.2.10 Milk Sampling.................................

4.2.11 Vegetation Sampling...........................

. 4-15 4-15 4.2.12 Soil Sampling.................................

4-15 5.0 ADMINISTRATIVE CONTROLS....................................

5-1

-5.1 Responsibility.......................................

5-1 5.2 Organization.........................................

5-1 5.3 Review...............................................

5 _.

5.3.1 Plant Safety Committee........................

5-1 5.3.2 Safety Rev.iew Committee.......................

5-2 5.4 Deleted l_

Amendment No. 37, 72

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Table of Contents (Cont'd)

Section Page 5;5 Procedures............................................

5-3 5.6 S tation Reporting Requirements........................

5-4 5.6.1 Routine Reports.................................

5-4

~5.6.2 Non-Rou tine Rep o r ts............................

~5-5 5.7 Changes....'..........................................

5-6 5.7.1 Changes in Environmental Technical Specifications 5-6

5. 7. 2-Changes. in Permits and Certifications..........

'5. 5.7.3. Changes in Procedures, Station Design or Operation......................................

5-7 5.8 Records Retention.....................................

5-8' 5.8.1 Records and Logs Retained for Life of the Plant.

5-8~

5. 8. 2 ' All O th e r Rec ords..............................

5-8 6.0 DELETED

-6.1 Deleted 6.2 Deleted 6.3 Deleted 6.4 Deleted 6&

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Amendment No. 37, 72 y-

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ENVIRONMENTALTECHNICLSPECIFICATI0RSi,,[-

LIST'0F' TABLES Table No.

Title

Page 2-1

- DELETED............................... 15 2-2

- MINIMUM' SAMPLING FREQUENCY............

2-17 2-3

' DELETED.............-.................. 20 3-1 DELETED...............................

3-3' l

4-1 RADI0 ANALYSES :- LISTED BY SAMPLE TYPE._

' 4-19 4-la

- DETECTION LIMITS......................

4 23 2

4-2 SAMPLE-LOCATION AND SCHEDULE..........

4-25'-

_ 4-3 DELETEDf..............................

_4-29 74-4 DELETED...............................

4 4-5 DELETED...............................

4-29 4. DELETED...............................

~ 4-29 4

5-1~

REPORTING 0F RADI0 ACTIVITY IN THE

- ENVIRONS..............................

5-7

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ENVIRONMENTAL TECHNICAL SPECIfl'C'A'TI6N5'

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SA PLING' LOCATIONS....................

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1 RADIOLOGICAL SAMPLING POINTS..........

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.4-3 DELETED............................... 18

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.' 5-l' ENVIRONMENTAL SURVEILLANCE-ORGANIZATION CHART.................................

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1.0.~DEFIt1ITIONS

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Listed' below are terms u'sid'i'nDiese# ElfonEeifal' ~TEhnical e

t Especifications that could be considered _as having a unique definition-.as applied to-Arkansas Nuclear One-Unit 1.

1.1 Deleted 1.2 ~ Gamma I'sotopic' Analysis Identification of gamma emitters 1 plus quantitative -

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results for radionuclides attributable to the station that contribute a significant amount to the total activity.of the sample. -

1. 3 Environmental Samples Samples of soil, Lair, water, biota, or biological material colfected outside of.the plant buildings for the purpose;of analysis.
1'. 4 -

Deleted 1.5 Deleted c

-1.6 Deleted.

'1.7 Deleted 1.8 Deleted l.9~

Radiation Monitor Checks, Tests, and Calibrations

a. - Check - Visual; inspection of monitor readout.

tb.

Test - Use of check source to determine operability.

c.

Calibrate - Use of known source to determine accuraev.

1.10 Equivalent Decay Time Equivalent decay time is equal to holdup _ time plus one-half fill.

- 7 time with respect to '.3aste gas decay tanks.

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2. 0 LIMITIf1G C0f4DITI0flS FOR'0PE5ATIdf[ ~' '

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2.2 Deleted 2.3 Deleted

,t.iendment flo. 72 2-1 (next,page 2-9)

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DESIGN FEATURES AND OPERATING. PRACTICES,...,_

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Deleteu

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' 3.4

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1.and Management 3.5

-Transmiss. ion'line rights-of-way.have low growing species of cedar,.

sumac, oak 'and shrubs las' a ' scree'n and to assist with erosion control.

Planting' of grass and. clover'shall be carried out to.further prevent.

erosion. - Further plantings of game food 'and cover shall ba made in cooperation with landowners and the' Arkansas Game'and Fish Commission.

No herbicides shall be used for-land management on'transmissioniline

. rights-of-way.-

4.

The grounds;in the :immediate' vicinity of the plant building shall be.

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landscaped. Remaining portions of.the plant site shall be allowed to-remain in their.present wild state with the exception of the area on which the visitors center will be located. This area is located approximately:0.7 mile northeast of the Reactor Building on a hill i

overlooking the plant.

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, Amendment No. 72

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.4.0 ENVIRONMENTAL SURVEILLANCE

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The env i ronmenta li s ude i l T5hY'p rTgY5I *foF La kE20'ardane l l e provides1information on air,' precipitation, ground water, soil,u vegetation andJmilk-by' radiological analysis of samples. in the ~

. area.of.the plant.

Since.the aq'atic ecosystem could be affected radiologically by.

u plant operation,. emphasis has'been placed on its-surveillance.

~The waters of' Lake Dardanelle are subjected to' frequent radiological testing.

.Resu'lts of the program, including the reports submitted in accordance with Specification 5.6, will_ be reviewed as specified' in 5.3.

4.1 Deleted I

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4. 2 Radiolooical Environmental Monitoring Objective:

To provide informatin on the radiological effects of station operation on the en'vironment.

Specification:

An environmental radiological monitoring program shall be carried out as d'efined in Tables 4-1 and 4-2 at locations defined in Figure 4-1 and Table 4-2.

4.2.1 Air Sampling' Continuous air sampling shall be performed at four locations onsite, two off-site within a ten-mile radius of the Plant, and on reference location.

Locations have been selected near site boundaries and in existing populated areas for evaluation of possible exposure to airborne particulate and halide radioactivity resulting from station operation.

The collection devices for iodine-shall contain potassium iodide impregnated charcoal or equivalent, and shall be constructed and operated so as to retain quantitatively the iodine in the air passing tiirough the device.

Appropriate analyses of particulate filters and halide collection devices shall be performed on all samples in accordance with i

accepted techniques and nuclides of interest.

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'4.2.2 Direct Radiation Ambient levels of direct external radiation shall be measured at~

L the same locations as air particulate.

Measurements shall be made by exposing thermoluminescent dosimeters for periods of three months and six months:

4.2.3 Precipitation Samplir)g Precipitation sampling shall be carried out at four locations; two-onsite, one within a ten-mile radius, and one reference location approximately miles southwest of the plant.

Analysis shall be performed as given in Table 4-1.

l Arend:ent No. 72 4-13 l-

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Table _4-5 Deleted Table 4-6 Previously Deleted l

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5.0'

' ADMINISTRATIVE ~ C0h'TROLS..

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7E" 5.1 Responsibility Corporate responsibility for implementation of the Environmental'

. Technical Specifications, and for assuring that st'ation operations

.are' controlled to provide protection for the environment has been-assigned to the' Senior Vice President. Energy Supply.

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The ANO Generaf Manager, through the Engineering and Technical Support Manager', and Technical Analysis Superintendent shall be responsibl,e for compliance with the En'ironmental Technical Specifications at the plant level.

'i The Manager of Technical Analysis shall be responsible for radiological analysis of environmental samples.

- 5.2 organization

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Figure 5-1 shows the organization chart at both plant and corporate levels relative to environmental matters.

. 5.3 Review 5.3.1 The Plant Safety Committee The Plant Safety Committee (PSC) ~ shall be responsible for review

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of the fol,lowi~ng:

a.

Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes.

b.

Proposed written' procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's l

radiological environmental impact.

Amendment No. 31, 42, 58, 72 5-1 t

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Proposed changes or modifications to plant systems or equip-

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.c ment which would affect the plant's environmental. impact..

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. lResultsofthe. Radiological ~Environmen'talbdbitoringPrograms.

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Investigation of all. reported instances of violations of Environmental Technical Specifications. Where investigation warrants, instances shall be evaluated and recommen,datidns formulated to prevent recurrence.

5.3.2 Safety Review Ce mittee The-Safety ' Review' Committee (SRC) shall be responsible for review of the following':

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- a.

The environmental evaluations-for 1) changes to procedure',s equipmend or systcae und'2) tests or experiments completed under Section 5.7.3, to verify that,such actions did not constitute;an unreviewed environmental question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed environmental question as. defined in Section 5.7.3.B.

Proposed changes to the Environmental Technical Specifications c.

and the evaluated impact of the changes, d.

Results of the Radiological Environmental Monitoring Programs. l Investigation of all reported instances of violations of e.

$v Environmental Technical Spcifications.

Amendment No. 37, 72 5-2 i

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Detailed written procedures shall be prepared and followed for all

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' activities performed by Arkansas Power and Light, involved in 7

carrying out the sampling, instrument calibration,~ analysis, and-

. actions to be taken when limits are~ approached'or exceeded.

Testing frequency--ofiany alarms shall be included.

These frequencies shall be.determiied from experience with similar instruments in similar environments and from manufacturers

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- technical manuals.

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_ Plant standard operating procedures shall include. provisions to.

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ensure the' plant and all its systems'and components are_ operated in compliance..with the limiting _ conditions for operations'as part of the environmental ~ technical specifications..

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. station ReporEing' Requirements r,

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5.6.1

, Routine Reports Annual Environmental Operating' Report A single report on the environmental monitoring programs conducted in association with ANO-l'(Docket No. 50-313)'and ANO-2'(-Docket.No. 368) operations for the previous calendar year shall be submitted-t

'to the NRC by May 1 of each year.

The report shall include summaries, analyses,1 interpretations, and, where appropriate,~ statistical evaluation of the results of.the environmental. monitoring and'an assessment of = the observed impacts of the station operatf 7n on the

-environment. If harmful effects or evidence of' irreversible damage are' suggested by'the monitoring or special programs,- the licensee shall provide a more detailed analysis of the data and a proposed course.of action to alleviate the problem.

The Annual Report shall also include a-summary of:

All ETS noncompliances and the corrective actions taken to 1) remedy them.

2)

Deleted 3)

Changes made to the procedures or design described in accordance

'with Subsection 5.7.3.

'4)

Changes in ETS.

, Amendment No. 37, 72 5-4

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5.6 2 Nonroutine Recorts~

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.A~ report shall be. submitted in?the' event't' hat'aY".... Limiting.

Condition for 0peration" (Section 2), is,excee'de'd, a report lev.el' as specified'.in Section.4.is reached, orLif an unusual event' l.

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Nl involving a.significan~t radiological environment.a1 impact occurs.

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'ReportsLshall:be. submitted under one of. thel report schedules described - bel ow.'

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,5.6.2.a'

Prompt Report' Those events ~specified as' prompt: report' occurrences'shall be+-

ireported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile' transmission to the-NRC'followed by a written report to the NRC s wi thin days.

5.6.2.b.

Thirty Day'Reporti Non-routine ~ events not requiring a' prompt report as ' described:in-Subsection 5.6.2.a, shall be reported to NRC-within'30 daysiof

.their occurrence.

l5.6.2.c Content of Non-routine Reports.

Written 30-day reports,and.o:to the extent possible, the :

preliminary telephone, telegraph, or facsimile reports.shalif (a) describe,nanalyze, and1 evaluate the occurrence, including

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extentDand magnitude of the. impact",'(b) describe =the cause of occurrence, and.(c) indicate'the corrective action-'(including any

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significant changes made.in procedures).taken'to preclude-repetition ofithe' occurrence and to prevent similar occurrences

' involving'similar components or systems.:.

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v 5.7 Changes 5.7.1 Changes'in Environmental ~ Technical Specifications

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Request for. changes in environmental technical specifications

-shall be submitted to the NRC for review and authorization'per

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10.CFR 50.90.

The request shall include an evaluation of'the environmental impact of-the' proposed changes and a supporting justification. ~

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5.7.2 Changes in Permits and Certifications Changes or additions to required' federal, state, local,'and

. regional authoyity permits and certificates for the protection of the environment that pertain to the requirements of these ETS.

shall be reported to the NRC within130 days.

If the proposed change is initiated by the licensee, the notification to the'NRC shall include an evaluation of the environmental' impact of the revised requirement, limit or value being sought.

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UNITED STATES j'

'y i NUCLEAR REGULATORY COMMISSION -

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- ARKANSAS POWER & LIGHT COMPANY-DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 fiENDMENTTOFACILITYOPERATINGLICENSE Amendment No. 40 License No. NPF-6

' 1.

The Nuclear Regulatory Comission (the Comis'sion) has found that:

A.

The application 'for amendment by Arkansas Power & Light Company (the licensee) da.ted February 15, 1983, complies 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 tnis 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 Commission's regulations and all applicable requirements' have been satisfied.

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2.

'Accordingly, the' license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,. and paragraph 2.C.(2). of Facility Operating License No. NPF-6 is hereby amended to read as follows:

(2) Technical Specifications

.The Technical Specifications contained in Appendices A'and B, as revised through Amendment No. 40, 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.

k c-obertA.dlark, Chief Operating Reactors Branch #3

- Division of Licensing

- Attachmenti Changes to the Technical Specifications Date of Issuance:

March 11, 1983 i

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2 ATTACHMENT TO~ LICENSE 'AMEriDPatiT f!0r40 s y -

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FACILITY OPERATING ~ LICENSE'ti0. NPF-6 DOCKET NO. 50-368 e

-Redlace the..following pages of the Appendix -"B" Technical Specifications with.the enclosed pages. The revised pages are identified by Amendment.-

number and contains-vertical lines indicating the: area of. change.

Remove Pages Insert Pages Li

-1 11 11 1-1 1-l'

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'3-1 3-1 3-2 ej 5-1 5-1 5-3 5-3 5-4 5-4 5-5 5-5 5-6 5-6 O

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- TABLE OF C0tlTENTS,,g.,_.,

Section-Page

-1.0 Definitions 1-1

- 2. 0 Limiting Conditions fo'r Operation 2-11 L2.1 ~ Non-Radiological (not applicable) 2.2 Radiological 2-1

'2.2.1 Liquid Discharge-12-2 2.2.2' Gaseous Discharge-2-6 3.0 Environmental ' Sur eillance 3-1 3.1 Surveillance for ANO 1 I

3.2 Deleted

,l 3.3 Aerial Remot Sensing 3-4 o4. 0.

Special' Studies 4-1 4.1 Unusual or Important Environmental Events 4-1 5' 0 ;

Administra tive' Control s 5-1 5.1 Responsibility' 5-1 5.2 Organization 5-1 5.3 Review 1-5.3.1 Plant Safety Committee-5-1

5. 3. 2-Safety Review Committee 5-2 Amendment No. af, 40 i

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TABLE ' 0F' CONTENTS iC.o.ntinu.e.d) '

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iSection Page 5.4 Deleted -

55.5. Procedures 5-3

~ 5.61 Station Reporting Requirements

'5-4 15.6.1 Routine Reports:

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5.6.2 monroutine Reports :

5-5 5.6'.2.a PromptLReport;-

~5.6.2.b Thirty Day Report

' 5.6.2.c : Cont'ent of Non-routine Reports

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5.7 Changes

5.7.1 Changes

in Environmental Technical

-S;ecifications 5-6 5.7.2 Changes in Permits and Certifications 5-6

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5.7.3 ' Changes-in Procedures,. Station Design-or Operation 5 i.

5.7.4 NRC Authority to Require Re' visions 5,

l-l 5.8 Records Retention 5-8 5.9 Special Requirements-5-9 APPENDIX 4.1.A DescHption of Bipd Collision Monitoring

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l on'ANO-2 Cooling Tower

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5-11 o

-Amendment No. 40 11 L

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- l.0 iDEFINITIONS

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Enviromnental -Sampl es :

Samples of' soil, air,: water, biota, or biological materia 1' collected outside'of the plant building for

- the ~ purpose of. analysis.

~~ Gamma Isotopic-Analysis Identification of gamma: emitters plus

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quantitative,results for radionuclides attributable to the

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station-that contribute a significant amount.to the total activity of-the sample.

Radiation Monitor Checks. Tests, and Calibration

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a.

Check Visual inspection of monitor readout.

b.. Test - Use of chec'k source to determine operability, c.

Calibrate - Use of known source.to determine accuracy.

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. Station ~ and Unit':

Station refers to ANO Units 1 and 2.

Unit

-refers'only to ANO-1 or ANO-2 as defined by its usage, e

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~ Amendment No 40-1-1 l-l

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' ENVIRON!! ENTAL SURVEICLAikE " '~2' " '~~~~~

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3.1.

Surveillance for ANO-

~The: surveillance program associated with ANO-1-(Docket No.

50-313). operation provides information _on air, precipitation, -

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ground. water soil,-vegetation and' milk by radiological analysis ;

of samples 3 1n the area of. the -~ plant. That program will-provi'de adequate information for ANO-2 operation and shall be ca'rried out at all times that the ANO-2 Environmental Technical Specifications apply.

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Amendment No. 40 3-1 (next page is 3-3) 1 O

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5.0 ADSINISTRATIVE CONTROLS

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5'.1 Resconsibility Corporate responsibility for implementation o'f. $he Environmental

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Technical Specifications, and for' assuring that. station operations-

'are controlled to provide protection for. the environment has been assigned to the Senior Vice-President Energy Supply. The ANO General Manager, through the' Engineering and Technical-Support-tianager, and Technical Analysis Superintendent, shall be responsible for compliance with the Environmental sTechnical: Specifications at

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the plant l'evel.

The 11anager-of Technical Analysis s. hall be responsible for radio-logical analysis of environmental samples.

5.2 Organization Figure 5-1 shows the organization chart at both plant and corporate levels relative to environmental matters.

5.3 Re'vi ew 5.3.1 Plant Safety Committee i

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The Plant Safety Committee (PSC) shall'be responsible for review l

of the following:

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Proposed changes to the Environmental Technical. Specifications and thd_ evaluated" impact of the changes.

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Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's radiological environmental impact.-

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Procedures

-Detail' d ' written -procedures -shall be prepared _and.followed for all e

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activities-. performed by Arkansas Power)and Light. involved.in'--

1 carrying out.the sampling, tinstrumenticalibration, analysis, and.

actions to~ be'taken'when limits are approached or exceeded. -Testing:

! frequency of anf alarms'shall be included. These frequencies shall Lbe determined from experience with similar instruments in similar' environment; and from manufacturers' technical manuals.

Plant sta'ndard Vperating procedures _ shall include' provisions l to; ensure the' plant and all ;its ' systems and = components are operated ~

in~ compliance with the limiting conditions for operations ~

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established as part' of; the environmental technical specifications.

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.5.6-Station Reporting Requirements 3

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5. 6.1

~ Routine Reports Annual Environmental Operating Report A single report on the environmental monitoring programs conducted.

in association with ANO-l _ (Docket No. 50-313) and ANO-2 (Docket No. 50-368) operations for the previous calendar year shall be submitted _ to the NRC by itay 1 of each year. -The report shall include-summaries, analyses, interpretations, and where appropriate,'statis -

tical evaluation of the results of.the environmental monitoring and an assessment of the observed impacts of the station operation on the-enviro nment. ~ If harmful effects or. evidence of-irreversible damage are suggested by the' monitoring or special programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem.

The Annual Report shall also include a summary of:

-1) ~ All ETS noncompliances and the corrective actions taken to remedy them.

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3)

Ch&nges made to the procedures'or design described in accordance with Su,bsection 5.7.3.

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4) Changes in ETS.

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5. 6.' 2 No'nroutine Reports ' * *'
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A report.shall be submitted in the event that a." Limiting Condition

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Reports shall be submitted under one of the report schedules described below.

5.6.2.a.

Prompt Report h

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-T ose events spec fied as prompt report occurrences shall be reported within' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile, transmission to the NRC followed by a written-report to the NRC within 30 days.

5.6.2.b.

Thirty Day Report Non-routine eyents. not requiring a prompt. report as described in Subsection 5.6.2.a. shall be reported to NRC.within 30 days -

of their occurrence.

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5.6.2.c.

Content of Non-routine Reports Written 30-day reports and, to t_he extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact. (b) describe the cause of, occurrence, and '(c) indicate

' the corrective action (including any significant changes made in procedures) taken to preclufe repetition of the ' occurrence and to prevent similar occurrences involving similar components or ' systems.

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5.7 Changes 5.7.1

- Changes in-Environmental Technical Soecifications Requests for changes in environmental-technical specifications shall be submitted to' the NRC for review and authorization per 10.CFR 50.90.

The request shall include an evaluation of the environmental. impact of the proposed _ changes.and a supporting justificati.on.

5.7.2

' Changes in P'ermits and Certifications'-

Changes or additions. to required Federal, State, local, and regional.

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authority permits and certificates for the protection of the ' environ-ment that pertaVn to the requirements of-these ETS shall be reported to the NRC within 30 days.

If the proposed change is. initiated lby the licensee, the notification to the NRC shall include an evaluation of the _ environmental : impact of the revised requirement, limit or value being sought.

5-6 Amendment No. 40 t.

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