ML20004D818
| ML20004D818 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/26/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004D819 | List: |
| References | |
| NUDOCS 8106100137 | |
| Download: ML20004D818 (20) | |
Text
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O ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE N0. DPR-64 DOCKET NO. 50-286 Revise Appendix B as follows:
Remove Pages Insert Pages Part I Cover Sheet Part I Table of Contents j
1-1 2-1 2-2 3-1 through 3-4 4-1 5-1 through 5-4 4
I Cover Sheet Part II Cover Sheet i through v i through y l-l_through 1-6 1-1,,,.
1-6 2.1-1 through 2.1-13 2.0-1 l
2.2-1 through 2.2-6
' 2. 2-1 2.3-1 through 2.3-22 2.3-1 4.1 -1 4.1-1 4.1-9 through 4.1-38 4.1 -9 5.1 through 5.12 5-1 through 5-8 l
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TAllLE OF CONTENTS Page 1-1 1.0 DEFINITIONS 2.0-1 2.0 LIMITING CONDITIONS FOR OPERATION
'2.1 Thermal QELETED 2.2
!!ydraulic DELETED DELETED 2.3, Chemical I
2.4-1 2.4 Radioactive Discharges 3
2.4-3 2.4.1 Specifications for Liquid Waste Effluents 2.4.2 Specifications for Gaseous Waste Effluents 2.4-U.
2.4.3 Specifications for Solid Waste llandling and Disposal 2.4-17 2.0-1 3.0 MONITORING REQUIREMENTS 3.1 Thermal DELETED DELETED 3.2 Ilydraulic 3.3 Chemical DELETED 2.4-1 3.4 Radioactive Discharges 3.4.1 Specifications for Liquid Waste Sampling and 2.4-3 Monitoring 3.4.2 Specifications for Gaseous Haste Sampling and 2.4-8 Monitoring i
Amendment No. 35
TARLE OF CONTENTS (Cont'd)
Page 4.1-1 4.0 EtWIRONMENTAL SURVEI'...ANCE PROGRAMS 4.1-1 d.1 Nonradiological Surveillance 4.1-1
. 4.1.1 Abiotic Thermal Plume Mappings DELETED a.
4.1-1 b.
Meteorological Studies i
DELETED 4.1.2 Diotic
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s 4.2-1 4.2 Radiological Surveillance 4.2-1 4.2.1 Radiological Environmental Monitoring Survey 5-1 5.0 ADMINISTRATIVE CONTROLS 5-1 5.1 Responsibility 5-1 5.2 Orgen i za t-ion Review and Audit by Plant Operating Review Committee (PORC) 5-2 5.3 5.4 Review and Audit by Safety Review Committee (SRC) 5-3 5-4 5.5 Procedures 5-5 5.6 Plant Report Requirements 5-6 5.7 Records Retention 11 Amendment No. 35
LIST OP FIGURES Title _
Page Figure No.
4.2-la nadiation Sampling Site Locations (Near Indian Point) 4.2-13 4.2-lb Radiation Sampling Site Iocations (10 Miles) 4.2-14 5-7 5.2-1 Plant Orgenization Chart 5-8 5.2-2 Mt wgement Organization Chart
'2.1-1 DELETED 4.1-1 DELETED DELETED 4.1-2 i
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~2.3-1 Deleted 4
i 2.3-2 Deleted 2."-19 2.4-1 Radioactive Liquid Waste Sampling and Analysia 2,4-2 Radioacttve Caneous Waste Sampling and Analysia 2.4-21 l.
2.4-3 PWR - 1,ocation of Proccan and Effluent Honitors.and Sampler Required by i
j Technical Specificationa
_ l 2.4-23 2.4-4 PWR - Caneous Waste System 1.ocation of Proccan and Effleunt Honitors and 2,4-24 Sampleta Required by Tecimical Specifications j
2.4-5 Cassaa and Beta Done Factors for Indian Point Unita Hoa. 1, 2 and 3 2.4-25 4.1-1 Del eted 4
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l.0 DEFINITIOliS t
'l.14 Dele *;ed i
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s 20, Haximum Periaissible Concentration (HPC) - la that.co.. centration of a icadionuclide according to 10 CFR Part 1.16 Appendix Bj Table II in air (HPC ) or water (HPC ).
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3 1.17 _ Deleted the Indian Point Units, Nos. 1, 2 and 3 ayatem.at
'The dealgn of the shared liquid radioactive vaate treatment b,
precludes monitoring the actual relenae ratea per reactor as specified in Specifications 2 L.18 2.4.1.c, 2.4.1.f.and 2.4.1.h.
the site irrespective of the actual release rate from the number of reactors producing radioactive ef fluents at each reactor through the chared 11guld radioactive waste treatment system.
f Deferences 3
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Amendment No. 35 i
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2.0 LIMITING CONDITIONS 3.0 M0lllTORIllG REQUIREMENTS FOR OPERATION Applicability Applicability Applies to the controlled re,
Applies to routine sampling and lease of radioactive liquid, analysis of the Station ef fluents gaseous waste ef'luents and and to an analytical evaluation isolid waste from.he Indian of the" data collected from tha
' Point Station, environmental monitoring survey.
Obj ec tive Obj ec tive To-define the conditions for To establish a sampling and controlled release of radioactive analysis program which will liquids to the Hudson River assure that all effluents are and radioactive gases to the kept within applicable Federal atmosphere in order to assure regulations.
compliance with applicable Federal mgulations.
2 2.1 TIIEIGIAL 3.1 T11ERMS Deleted Deleted 1
2.0-1 Amendment No. 35 i
(. 0 1.1 TILTING C0;lf.iT10il5 F0it 01'ERAY10ll 3.0 !!0!ll'10 RING RI:QUIRf.IIENTE,,
2.2 IlYDRAtII.ICS OF CIRCUI.ATIllG UATER SYSTDI (CWS).3g, 3.2 ITYDMULICS OF CIP.CULATIllG WATEll SYSTDI (CilS)
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2.2-1 Anendnent No. 35
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3.0 H0tilTORillG REQUIRDiEt{TS 1.1HITIllC Coll!)lT10lls FOR OPERAT10ll 2.0 l.
3.3 CllDfICAI.
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'q 4.0 EllVIR0fDIEllT*.i. SURVEILI.AllCE l'It0CRAHS llOllRADIOLOGICAI. EtlVIR0llHEllTAL SURVEll.LAtlCE 4.1 4.1.1.a Tlicrmal Plume Happing Dqleted i
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4.1-1 knendment No. 35 (tiext page is 4.1-8)
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P00R ORIGINAL 5.0 ADMINISTRATIVE CCNTROLS Administrative and management controls have been established to provide continuing protection to the environ-through implementation of the Radiological Environmental ment Technical Specifications (RITSs).
This section describes the assignment of responsibilities,' organizational structure.
review and audit functions and recorting cperaticns, procedures,For the purposes of this section the term'" Rad-specifications.
iological Environmental" also includes meteorological studies (4.1) performed under the non-radi'ological surveillance subsection of Appendix 3, Part II.
5.1 RESPONSIBILITY 5.1.1 The Resident Manager, the Plant'cperating Review Committee and headquarters' engineering and operations persennel have responsibility for review of the RITSs.
l The Resident Manager shall have direct rescons-5.1.2 ibility for assuring the operation of the Indian Point No. 3 Plant is conducted in such a manner as to oro-vide continuing protection to the environmert.
During periods when the Resident Manager is unavailable, he shall delegite his responsibilities to the Superintendent of Power, or in his absence, to other qualified super-visory personnel.
The implementation of the RITSs is the respens-l 5.1.3 ibility of the Superintendent of Power, with the assistance of the plant staff organization.
The plant staff organization is shown in Figure 6.2-1 of Appendix A.
Monitoring of radiological e.iironmental pro-l 5.1.4 and grams will be performed by site technical personnel, when necessary, by environmental consultant personnel.
staff will be available Engineers frem the headquarters' for assistance when required.
5.2 ORGANIZATION _
l Organization relative to radiological environmental s.
matters at the' plant and headquarters' levels are pre-sented in Figure 5.2-1 and 5.2-2 respectively.
REVIEW AND AUDIT 3Y PLAST OPERATING REVIEW COMMITTEE 5.3 (FORC)
Review and audit of radiological environmental l
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5.3.1 matters by PORC shall be performed as described below and in Section 6.5 of Appendix A.
The responsibilities of the Plant Operating l
5.3.2 Review Committee as related to the RETSs are as follows:
Am ndment No. 35 5-1
0 E00R ORIGINAL
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Review results of radiological environmental f
a.
monitoring programs prior to submittal in each annual radiological environmental monitor-l F
ing report.
b.
Peview propose'd chEnges to the RETSs and the l
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evaluated impact of the change.
Review proposed changes or modifications to c.
i the plant systems or equipment and the evaluated impact which would adversely affect the evalua-tion of the plant's radiological environmental l
impact.
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d.
Review the RETS development with the Safety
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Technigal Specifications to avoid conflicts and for consistency.
Review all proposed procedures or changes there-e.
to which pertain to these RETS requirements.
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Re6iew' all reported violations of RETSs.
review' warrants, prepare and forward a report covering their evaluation and recommendation to prevent rec'urrence to the Resident Manager and the Chairman of the Safety Review Committee.
The Plant Operating Review Committee will make 5.3.3 tentative determination as to whether or not proposals submitted to the committee involve a change in the plant's l radiological environmental impact.
This determination i
is subject to review by the Safety Reyjew Committee.
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REVIEW AND AUDIT SY SAFETY REVIEW COMMITTEE (S RC_)
5.4 Review and audit of radiological environmental l
5.4.1 matters by the SRC shall be as described below and in Section C.5.2 of Appendix A.
l The responsibilities of the Safety Review l
5.4.2 Committee as related to the RETs are as follows:
Review proposed changes and/or modifications a.
to procedures, equipment or systems which l
adversely affect the plant's radiological environmental impact.
Review proposed tests and experiments which l
b.
adversely af fect the plant's radiological enviro:rnental impact.
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5-2 Icendment No. 35 t
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P00R ORIGINAL
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Revino proposed changes in the Operating c.
License and Technical s'ecifications re-p lating to radiological environmental concerns.
c use to be made p'eriodic audits of d.
Make:or a
plant operation to verify conformance with the l
Review violations of the RETSs.
e.
5.5 PROCEDURES 5.5.1 Detailed written procedures, including applic-able checklists and instructions, shall be prepared and followed for all activities involved in carrying out the l
l radiological environmental monitoring program.
Proce-dures include sampling, data recording and storage, in '
strument calibratien', measurements and analyses, and actions to be taken when limits are approached or exceeded.
Testing fregnency o.f alarus, as determined from experience with similar instruments in similar environments and from manufadtures's technical manuals, have also been included.
Plant Operating Procedures include provisions, 5.5.2 in addition to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in comoliance with the limiting conditions for cperation established as part of the RETSs.
5.5. 3
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5.6 PLAST REPORTING REQUIREMENTS 5.6.1 Routine Repcrts Annual Environmental Operating Report a.
Part A:
DELETED Part 3:
Radiological Report.
A report on the l
radiological environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Of fice of Nuclear Reactor Regulation) as a separate document within 120 days after January 1, shall include summaries, The reports of each year.
and statistical evaluation of the results interpretations, of the radiological environmental surveillance activities for the rep ~ ort period, including a comparison with pre-operational studies, operational controls (as app,ropriate)
- and previous environmental surveillance reports and an i
, assessment of the observed impacts of the plant operat on a
5-3 Amendment No. 35 G
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P00R.0RIGINAL on the environment.
The reporto chall also includa the results of land use censuses required by the Technical Specifications.
If harmful effect or evidence of irreversible damage are detected by the menitoring, the licensee shall provide an analysis of the problem and a propo, sed course of
- action to alleviate the problem.
Results of 'all radiological environ:1 ental samples ' taken shall be summarired and tabulated on an annual basis.
In the event that some results are not available within the 120 day period, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
5.6.1 b.
Semiannual, and/or Specical Evironmental Operating Reports DELETED 5.6.1 Radioactive Effluent Release Report c.
A report on'the radioactive discharges released from the plant during the previous 6 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Of fice of Nuclear Reactor Regulation) within 60 days after January 1 and The period of the first report July 1 of each year.
The shall begin with the date of initial criticality.
report shall include a summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as outlined in Rev. 1, " Measuring, Evaluating, Regulatory Guide 1.21, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gasesous Effluents from Light-Water-Cooled Nuclear Power Plants," with format data su=marired on c. quarterly basis following the of Appendix B,thereof.
The report shall include a summary of the meteorological conditions concurrent with the release of gaseous ef fluents during each quarter as outlined in Regulatory Guide 1.21, Rev.1, with data summarized on a quarterly basis following the format of Appendix 3 thereof.
'5.6.2 Nonroutine Reports
.al Operating Reports Non. routine Environce:
a.
DELETED Amendment No. 35 5-4 w
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P00R.0RIGINAL Nonroutine Radiological Environmental Operating 5.6.2
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b.
Reports If a con-Inomalous Measurement Report.
mental medium ~ exceeds ten times the control statio (1) a written report shall be submitted to the(with a copy to the
- value, Director of the NRC Regional Of fice within Director, Of fice of Nuclear Reactor Regulation) 14 days after confirmation if said radioactivity isThis report shall 3.*
caused by operation of Unit No.
mental factors, or other aspects necessary to explainin the anomalous result.
(2)
Milk Pathway Measurements
'If cow or goat milk samples coll.ected (a) over a calendar quarter show average concentrations ofand if said radio-4.8 picocuries per liter or greater, 3, a plan activity is caused by operation of Unit No.
shall be suEmitted within 30 days advising the Director of Of fice of Inspectica and Enforcement of the proposed action to ensure the )lant-related annual doses will be id within the design objective of 15 mrem /yr to the thyro of any individual.
When pasture grass is sampled rather (b) h than goat milk, if individual pasture grass samples s ow I-131 concentrations of 0.022 picoeuries per gram (weto weight) 3, a plan shalT be submitted by operation of t, nit No.
within 30 days advising the Director of Office.of Inspec-ht tion and Enforcement of the proposed action to ensure t a plant-related annual doses will be within the design Nonroutine_ Radioactive Effluent Recort (3)
The reporting requirements for nonroutine radioactive discharges are specified in Section 2.4 and 3.4 of these specifications.
Changes in Radiological Environmental Technical 5.6.3 Specifications A report shall be made to the NRC prior to impicsan-in plant operation, or tation of a change in plant design,in procedures described a.
tne original, a duplicate, or a oA ccnfirmarcry reanalysis of The results of the samole'may be desireable as appropriate.
i cenfirmatory analysis shall be completed at the earliest t me 30 days.
consistent with the analysis, but is any case,within
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P00R ORIGINAL have a significant adverse radfological effect on the The report shall include a description environment.
,uation of the change and supporting information.
and e-b.
Requ'est for changes in the'RITSs shall be submitted to the Director, Civisica of Operating Reactors, fc review and authorization.
c.
DELETED 5.7 RECORDS RETENTION Records and logs relative to the follcaing 5.7.1 areas shall be made and retained for the life of the plant:
Records ar.d drawings detailing plant design a.
changes hnd modifications made to system and equipment as described in Section 5.6.3.
Re, cords of all data from radiological environ-b.
mentaf monitoring and surveillance required by these RETSs.
All other' records and logs relating to the RETSs c.
shall be retained for five years following logging or recording.
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Amendment No. 35 5-6 l
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o P00R ORIGINAL RESIDENT t".ANAGER fPLANTOPERATING
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Indian Point 3 Nuclea.- Power Plant I
Amendment No. 35 5-7 e
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EXECU' DIVE VICE PitESIDENT SAFETY REVIEW SENIOR VICE PilESIDENT AND CllIEF ENGINEER COMMITTEE 3
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'y PIGunP. 5.2-2 MANAGEMENT ORGANIZATIOri-OFIMTTE ENVIRONMENTAL Amendment No. 35