ML20079B853
| ML20079B853 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1991 |
| From: | Essig T, Meinke W Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-1302, NUDOCS 9106180015 | |
| Download: ML20079B853 (127) | |
Text
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NU R EG-1302 O:':? site Dose Ca:cu a': ion Manua Guicance: 6:anc arc Racio.ogica E:?:?Luerr: Contro s for Boi ing Water Reactors Generic Letter 89-01, Supplement No. I 1
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U.S. Nuclear Regulatory Commission l
1 Ofnce of Nuclear Reactor Regulation W. W..sieinke. T. I1. Essig p "ov
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61 910430 130D H P1)R
AVAILABILITY NDTICE Avadability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following i
sources:
1.
The NRC Public Document Room. 2120 L Street, IN, Lower Level, Washington, DC 20$55 1
2.
The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013 7082 3.
The National Technical information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents Cited in NRC publica-i tions, it is not intended to be exhaustive.
j Referenced documents available for inspection and copying for a fee from the NRC Public Document Room includo NRC correspondence and internal NRC memoranda; NRC Office of Inspection and Enforcerhent bulletins, circulars, information notices, inspection and investi-pation notices; Licensee Event Reports; vendor reports and correspondence: Commission papers; and applicant and licensee documents and correspondence.
The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC sponsored confeience proceed.
ings, and NRC booklets and brochures. Also available are Regulatory Guides NRC regula-tions in the Code of Federal Regulations, and Nuclear Regulatory Commission issuances.
Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by l
the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission, Documents available from public and special technical libraries include all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these libraries.
l Documents such as theses, dissertations, foreign reports and translations, and non NRC l
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publication cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Information Resources Management Distribution Section, U.S.
l Nuclear Regulatory Commission, Washington, DC 20555.
I Copies of industry codes and standards uscd in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and l
are available there for reference use by the public. Codes and standards are usually copy-j righted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018.
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NUREG-1302 Offsite Dose Caletbation Manual Guidance: Standard Radillogical Effluent Controls for Boiling Water Reactors Generic Letter 89-01, Supplement No.1 Date l'ublished: April 1991 W. W. Meinke, T. I1. lissig Division of Radiation l'rotection and Emergency l'reparedness Omce of Nuclear Reactor Regulation i
U.S. Nuclear Regulatory Commission Washington, DC 20555 l
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k ABSTRACT i
This report contains guidance which may bo voluntarily used by licensees who choose to iniplement the provision of Generic Letter 89-01, which allows i.aoio-
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logical Ef fluent Technical Specifications (RETS) to be removed from the raain i
body of the Technical Specifications and pieced in the Offsite Dose Calculation j
Mariual(0DCM).
Guidance is proviced for Standard Lffluent Controls definitions, 1
Controls for effluent rionttoring instrumentation, Controls f or effluent releases, j
Cortrols for radiologicci environmental monitoring, and the basis for Controls.
Guidance on the ferrolation of RETS has been available in craf t forra (NUREG-0472
)
ano -C473) for a number of years; the current effort siniply recasts those RETS i
into Standard Radiological Effluent Controls f or application to the ODCH. Also 1
included for completeness are:
(1) radiological environmental monitoring program i
guidance previously which had been avaliable as a Branch Technical Position 1
(Rev.1. Novenber 1979); (2) existing ODCh guidance; ano (3) a reproduction of j
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PREFACE This compilation of Standard Radiological Effluent Controls (SREC) contains all of the controls addressed in Generic Letter 89-01, to be incorporated into a licensee's Offsite Dose Calculation Manual (0DCM) at the time the procedural details of the current Radiological Effluent Technical Specifications (P.ETS) are transferred out of the licensee's Technical Specifications (TS).
It has been developed by recasting the RETS of the most current Standard Technical Specifications f rom the "LC0" format intn the " Controls" format of an OOCH entry. Note that these GE-SREC have been patterned after the W-SREC. The following text guidance incorporates the wording of the most recent SREC, however,noattempthasbeenmadetotranslateRECnumberingoftheB-SREC into that of the BWR numbering system.
The following GF-SREC provide the latest version of staff guidance, and docu-ment current practice in the g(a) rating procedures required by 10 CfR 20.106, e
40 CfR Part 190,10 CFR 50.36
, and Appendix ! to 10 CFR Part 50.
This document contains no new requirements and its use is completely voluntary.
V
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table Of CONTENTS
- f. age ABSTRACT...............................................
iii PRErACE................................................
Y f0 REWORD...............................................
[1]
1 DEFINITIONS............................................
[5]
3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS.................
'15; 3/4.0 Applicability..........................................
,16, 3/4.3 Instrumentation........................................
[18]
3/4.11 Radioactive Effluents..................................
I39;i 3/4.12 Radiological Environmental Monitoring..................
- 59; 3/4 BASES..................................................
[74]
APPEhDlx A:
Radiological Assessment Branch Technical
[85]
Position Revision 1, November 1979 APPENDlX B: General Contents of the Offsite Dose
[94]
Calculation Manual APPENDIX C:
[98]
r GE-SREC vii
FOREWORD RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Licensee Technical Specification (TS) amendment requests for incorporation of Radiological Effluent Technical Specifications (RETS) pursuant to 10 CFR 50.36a and Appendix 1 to 10 CFR Part 50 were approved in the mid 1980s for most operating reactors licensed before 1979 (ors).
Plants licensed after 1979 (NT01.s), included the RETS as part of their initial Technical Specifications.
By Nover.ber 1987, the RETS were implemented by(all licensees of operating power reactors. Detailed Safety Evaluation Reports SERs) documented the accept-ability of the plant-specific RETS of the ors, while the acceptance of the RETS for the HT0Ls followed the regular pattern of the Standard Technical Specifi-cations (STS). Thus, for all operating plants, the compliance of the licensee with 10 CFR 50.36a and Appendix ! to 10 CFR Part 50 is a matter of record.
Early draft revisions of model RETS, distributed to licensees in mid-1978, contained equations for dose calculations, setpoint determinations and meteoro-logical dispersion factors, as well es the procedural details for complying with Appendix 1 to 10 CFR Part 50, in later revisions, including Revision 2 used as the bench mark for the NRC staff's acceptance of OR RETS, the equations were removed and incorporated into an Offsite Dose Calculation Manual (ODCM) prepared by the licensee and provided to NRC for review along with the proposed RETS.
Early guidance for preparation of the Radiological Effluent Technical Specifi-cations (RETS) and Offsite Dose Calculation Manual (ODCM) was published in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants " October 1978. Copies of model RETS, however, have been available only in draft form as NUREG-0472, Revision 2, " Radiological Effluent Technical Specifications for PWRs," February 1,1980; NUREG-0473, Revision 2,
" Radiological Effluent Technical Specifications for BWRs," February 1,1980; and succeeding draft revisions.
Staff guidance for the Radiological Environmental Monitoring Program is contained in the Radiological Assessment Branch Technical Position (RAB-BTP), originally issued in March 1978 and upgraded by Revision 1 in November 1979 as a result of the accident at Three Mile Island. This Revision 1 to the RAB-BTP was forwarded to all operating reactor licensees in November 1979 and remains in effect at the present time.
Since this BTP was never incorporated into the Regulatory Guide System, a copy is reproduced in this document as Appendix A.
Even though it has been used extensively in reviewing ODCHs, guidance for the contents of the ODCH is found only in an appendix to a paper presented at an Atomic Industrial Forum confer-ence in 1981, and has had only informal distribution since that time.
OFFSITE DOSE CALCULATION MANUAL The potential for augmentation of a licensee's ODCM through transfer of the procedural details of the RETS following the guidance of Generic Letter 89-01, provides an opportunity to assemble in one set of documents the staff guidance for the ODCM.
GE-SREC
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The current overview guidance for development of the 00CM was prepared origi-nelly in July 1978 and revised in February 1979 af ter discussions with comit-tees of the Atomic Industrial Forum. This guidance was r'ade generally ava11eble as " Appendix B - General Contents of the Offsite Dose Calculation Manual (OKM) (Revision 1, February 1979)* to the paper authored by C. A. Willis and F. J. Congel, " Status of NRC Radiological Effluent Technical Specification Activities" presented at the Atomic Industrial Forum Conference on kEpA and huclear Regulation. October 4-7, 1981, Washington, D.C.
A copy of this guidance that continues in effect to date, is reproduced in this document as Appendix E.
During the discussions leading up to the implementation of the RETS by the ors, it became important to record in a "living" document certain interpretations and undtrstandings reached in these discussions.
The ODCM thus beetme a repository for such interpretations, as well as for other information requested by the staff in connection with its evaluation of licensee's comitments and performance under 10 CFR 50.36a and Appendix ! to 10 CFR Part 50.
TECHNICAL SPFCIFICATION IMPROVEMENT PROGRAM Recently, the NRC staff has examined the contents of the RETS in relation to the Comission's Interim Policy Statement on Technical Specification Improve-ments. The staff has determined that programatic controls can be implemented in the Administrative Controls section of the Technical Specifications (TS) to satisfy existing regulatory requirements for RETS. At the same time, the procedural details of the current TS on radioactive effluents and radiological environmental monitoring can be relocated to the Offsite 00se Calculation Manual (0DCM).
To initiate the change, new programatic controls for radioactive effluents and radiological environmental monitoring are incorporated in the TS to conform to the regulatory requirements of 10 CFR 20.106, 40 CTR Part 190 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50.
Theproceduraldetailsincludedin licensees' present TS on radioactive effluents, environmental monitoring, and associated reporting requirements will be relocated to the ODCH.
Licensees will handle future changes to these procedural details in the ODCM under the administrative controls for changes to the ODCH. Detailed guidance to effect the transfer of the RETS to the ODCM is given in Generic Letter 89-01, repro-duced in its entirety as Appendix C.
GUIDANCE FOR THE TRANSFER OF RETS TO ODCM
! of Generic Letter (GL) 89-01 of Appendix B provides detailed i
guidance for the preparation of a license amendment request to implement the j
transfer of RETS to ODCH.
Page 1 of the enclosure states:
"The NRC staff's intent in recomending --- the relocation of procedural details of the current RETS to the CDCH is to fulfill the goal of the Commission Policy Statement for Technical Specification Improvements, it is not the staff's intent to reduce the level of radiological effluent a
control.
Rather, this amendment will provide programatic controls for i
RETS consistent with regulatory requirements and allow relocation of the procedural details of current RETS to the ODCH."
l GE-SREC (2) l L
Page 2 of Enclosure 1 states:
...the procedural details covered in the licensee's current RETS, consisting of the limiting conditions for operation, their ap>lica-bility, remedial actions, surveillance requirements, and the 3ases section of the TS for these requiren,ents, are to b2 relocated to the ODCH --- in a manner that ensures that these details are incorporated in alant operating procedures. The HRC staff does not intatnd to repeat tecinical reviews of the relocated procedural details because their consistency with the applicable regulatory requirements is a matter of record from past NRC reviews of RETS."
DISCUSSION for the purpose of the transfer described in GL 89-01 of Appendix B, the RETS will consist of the specifications rom the STS listed in Enclosure 2 of Appen-dix B of GL 89-01.
Licensees with
' standard TS chould consider the analogous 15 in their format.
It is suggested that the most strait.
.orward method of transferring a licensee's counitments in the RLTS to the ODCH it accordance with GL 98 01 is to recast the RETS in the licensee's present TS from the "Limitir.g Condition for Opera-tion (LCO)" format of the TS into the " Controls" format of the ODCH entry.
The accompanying package provides an example of this recasting into Standard Radio-logical Lf fluent Controls (SREC) f rom the model RETS for boiling Water Reactors (BWRs). This recasting is in format only.
The TS pages have been transferred to the ODCM without change except for the substitution of " Controls" for "LCO."
Plants that have RETS that closely follow the STS format will be able to use the accompanying examples directly as guidance, for plants with nonstandard RETS, the transf er of TS coaunitments to the ObCH should be made similarly page by page, again with the substitution of
- Controls" for "LCO."
This NUREG report contains no new requirements; licensee isnplementation of this guidance is completely voluntary.
SUMMARY
As part of the license amendment request for TS improvement relative to the RETS, a licensee cor. firms that the guidance of,,.. * 'etter 89-01 has been followed. This guidance includes the following "The procedural details covered in the li, turrent RETS, con-m sisttog of the limiting conditions for opere - *, their applicability, remedial actions, surveillance requirements and the Bases section of theTSfortheserequirements,aretoberelocatedtotheODCH---in a manner that ensures that these detcils are incorporated in plant operating procedures."
The Standard Radiological Effluent Controls (SREC) compiled in this report document current staff practice in the operating procedures required by 10 CFR 20.106, 40 CFR part 190,10 CFR 50.36(a), and Appendix 1 to 10 CFR Part 50. Thus they contain all of the controls required by Generic Letter 89-01, to be incorporated into a licensee's ODCH at the time the procedural details of the current RETS are transferred out of the licensee's TS.
GE-SREC
[3]
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These GE-SREC have been
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patternedaftertheB-SREC.
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The following text gu# dance incorporates the j
wording of the most recent SREC; however, no attempt has been made to translate the REC numbering of the W-SREC into that i
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of the BWR numbering system
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GE-SREC
[4]
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SECTION 1.0 DEFINITIONS 1
GE-SREC (5)
1.0 DEFINITION 5 i
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The defined terms of this section spear in capitalized type and are applicable i
throughout these Controls.
ACTION 1
l 1,1 ACTION shall be that pr.rt of a Control that prescribes remedial measures j
required under designated r.onditions, t
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l CHANNEL CALIBRATION I
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1.4 An CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed j
by any series of sequential, overlapping, or total channel steps such that the j
entire channel is calibrated.
CHANNEL CHECK i
1, 5 A CHANNEL CHECK shi.11 be the ouslitative assessment of channel behavier during operation by observation.
1his determination shall include, where l
possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels j
measuring the same parameter, h
CHANNEL FUNCTIONAL TEST
^
1 1.6 A CHANNEL FUNCTIONAL TEST shall be:
[
Analog channels - the injection of a simulated signal into the a.
j channel as close to the sensor as practicable to verify OPERABILITY l
including alarm and/or trip functions and channel failure trips.
4 b.
Bistable channel;. the injection of a simulated signal into the j
sensor to verify OPERABILITY including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential.
overlapping or total channel steps such that the entire channel is tested.
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GE-SREC (6) i
.,.---_--.u-
I DEFINITIONS l
DOSE EQUlVALENT 1-131 1.10 DOSE EQUIVALENT l-131 shall be tnat concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in (Table 111 of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109. Revision 1, October 1977).
GE-SREC
[f)
DEFINITIONS j
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FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Survei11ance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE TREATMENT SYSTEM 1.14 A GASEOUS RADWASTE TREATMENT SYSTEM (e.g., the " augmented offgas system") is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the main condenser evacuation system and providing for delay or holdup for the purpost of reducing the total radioactivity prior to release to the environment.
MEMBER (S) 0F THE PUBLIC 1.16 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.
This category does not include employees of the licensee, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include perspns who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL i
1.17 The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM shall also contain I
(1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by TS 6.9.1.3 and 6.9.1.4.
GE-SREC (8)
OEFIN!T10NS OPERABLE OrERAB1tlTY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERAElL11Y when it is capable of performing its specified function (s),
and when all necessary attendant instrurrentation, controls, electriegl power, cooling or seal water, lubrication or other auxiliary equipment that are j
requireo for the system, subsystem, train, cortponent, or device to perform its f unction (s) are also capable of performing their related support f unction (s).
OPERATIONAL CONDITION - CONDITION 1.19 An OPERATIONAL COND1110N, i.e., CONDITION, shall be any one inclusive corr.bination of rnode switch position and average reactor coolant tertperatures as specified in Table 1.2.
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PURGE - PURGING 1.23 PURGE or PURGING shall be any controlled process of discharging air or gas f rom a confinement to rnaintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
GE-5 REC
[9)
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DEFINITIONS i
RATED 1HIRMAt POWER 1.25 RATED THERHAL POWER shall be a total reactor core heat transfer rate to the reactor Coolant of MWt.
REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part $0.
1 SITE BOUNDAy 1,3L The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
GE-SREC
[10)
OfFINITIONS SOLIRCE CHICK 1.33 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
THERMAL POWER 1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
Ji-SREC
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UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the $1TE BOUNDARY
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access to which is not controlled by the licensee for purposes of protection of l
individuals f rom esposure to radiation and radioactive materials, or any area J
within the SITE BOUNDARY used for residential quarters or for industrial, j
commercial, institutional, and/or recreational purposes.
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VENTIL ATION EXHAU$1 TRE ATMENT SYSTEM 1
1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and J) installed to reduce gaseous radiciodine or radioactive material in particulate form in ef fluents by passing ventilation or vent exhaust gases through charcoal 1
adsorbers and/or HEPA filters for the purpose of removing iodines or particu-j lates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any ef fect on noble gas ef fluents.
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Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENT]LATION !XHAUST TREATMENT SYSTEM components, f
VENTING i
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1.40 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other I
operating condition, in such a manner that replacement air or gas is not pro-l vided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
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GE-SREC
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l TABLE 1.1 FREQUENCY NOTATION NDTATION FREQUENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
5A At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
N.A.
Not applicable.
P Completed prior to each relea:e.
GE-5 REC
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j TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR i
i CONDITION POSITION COOLANT TEMPERATURE i
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POWER OPERATION Run Any temperature j
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STARTUP Startup/ Hot Standby Any temperature 3.
HOT SHU100WN Shutdown #'
> 200'T 4.
COLD SHUTDOWN Shutdown ' #'
5 200'f S.
REFUELING
- Shutdown or Refuel" '#
5 140'F I
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- The reactor noce switch may be placed in the Run or Startup/ Hot Standby
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position to test the switch interlock functions provided that the control i
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rods are verified to remain fully inserted by a second licensed operator or other technically Qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per j
Specification 3.9.10.1.
" fuel in the reactor vessel with the vessel head closure bolts less than I
fully tensioned or with the head removed.
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- See Special Tests Exceptions 3.10.1 and 3.10.3.
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- The reactor mode swit,ch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.
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GE-SREC
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l SECTIONS 3.0 AND 4.0 CONTROLS AND
- l,5URVEILLANCE REQUIREMENTS
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GE-SREC (15]
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3/4 CONTROLS AND SURVE!LLANCE REQUIREMENTS 3/4.0 APPLICABILITY l
CONTROLS j
3.0.1 Compliance with the Controls contained in the succeeding controls is required during the OPERATIONAL CONDIT10h5 or other conditions specified therein; except that upon failure to meet the Control, the.usociated ACTION requirements shall be met.
3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals, if the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a Control is not met, except as provided in the associated ACTION i
requirements, within 1 bour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the control does not apply by placing it, as applicable, in:
1.
At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control.
Exceptions to these requirements are stated in the individual controls.
This control is not applicable in OPERATIONAL CONDITIONS 4 or 5.
3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made unless the conditions for the Control are met without reliance on provisions contained in the ACTIDH requirements.
This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.
Exceptions to these requirements are stated in the individual controls.
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GE-SREC (163
APPLICAE1LITY SURVEllLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL' COND]TIONS or other conditions specified for individual Controls unless othermise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with; a.
A maximum allowable extension not to exceed 25% of the surveillance interval, but b.
The combined time interval for any three con.ecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Control.
Exceptions to these requirements are stated in the individual controls.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Control has been performed within the applicable surveillance interval or as otherwise specified.
GE-5 REC
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INSTRUMENTATION RADI0 ACTIVE L] QUID EFFLUENT HON]TORING INSTRUMFNTATION CONTROLS 1
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3.3.3.20 In accordance with (plant name) TS 6.0.4.g.1), the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3 12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 4
Control 3.11.1.1 art: not exceeded.
The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and l
parameters in the OFFSITE DOSE CALCULATION MANUAL (00CH).
APPLICABILITY:
At all times, j
ACTION:
1 With a radioactive liquid effluent monitoring instrumentation channel a.
Alarm / Trip Setpoint less conservative than required by the above i
control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3 12.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
1.
c.
Report all deviations in the Semiannual Radioactive Effluent Release Report.
i SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.
GE-SREC (18)
TABLE 3.3-12 r",
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RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION A
o MINIMUM CHANNEt5 INSTRUMENT OPERABLE ACTION 1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluent Line 1
35 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Service Water System Effluent Line 1
37 b.
Component Cooling Water Systes Erfluent tine 1
37 G
3.
(Not Used) m 4
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line 1
38 b.
Discharge Canal 1
38
)
i 5.
Radioactivity Recorders
- a.
Liquid Radwaste Effluent Line 1
39 l
l
- Required only if Alarm / Trip Setpoint is based on recorder-controller.
l 1,
i
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5 5
NO I
5 7
7 8
8 9
T 3
3 3
3 3
3 C
A SE N
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1 1
1 1
1 T
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so s
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ot S
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ta t
ta l
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in r
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n e
s i
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a c
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r e
w T
Mmd Mmt I
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r t
a ic d
ic c
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i d
l vi i
vi i
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A it u
it v
p d e
u c
i v
ta q ta r
m e
t q
s t
o f
cm i
cm e
o s
a i
i c
i i
ao L
ao S
C U
R L
D a
L ot ot o
y iu iu t
w i
l dA dA o
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n a
a N
l a
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a R
a b
(
F a
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a d
er i
1 2
3 4
5 uqe R
EERn G.,..
li1
,liiil1l
w N
4 (NOT USED)
GE-SREC (20]
l 1
TABLE 4.3-8 l
m J.
RADI0 ACTIVE LIQUID EFFLUENT MDNITORING INSTRIENTATION SURVEILLANCE REQUIREMENTS f
i5; n
f CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL l
I INSTRUMENT CHECK _
CHECK CALIBRATION TEST 1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release i
a.
Liquid Radwaste Effluent Line D
P R(3)
Q(1) i 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Service Water System Effluent Line D
M R(3)
Q(2)
C b.
Component Cooling Water System Effluent m
Line D
M R(3)
Q(2)
{
i 3.
(Not Used) i 4.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
b.
Discharge Canal D(4)
N.A.
R Q
i 5.
Radioactivity Recorders
- I a.
Liquid Radwaste Effluent Line D
N.A.
R
'Q
]
- Required only if Alarm / Trip Setpoint in based on recorder-controller.
TABLE 3.3-12 (Continued)
ACTION STATEMENTS l
ACTION 35 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway n.ay continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluer.t releases via this pathway may continue provided that, at least once pter 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radio-activity at a lower limi+ of detection of no more than 10 7 microcurie /ml.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump perfor-mar.ce curves generated in place may be used to estimate flow.
ACTION 39 -
With the nuttber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the radioactivity level is determined at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
GE-SREC
[p1]
m.-
a w----
a m
1 i
i 1
i 1
-l J
e i
i i
l (NOT USED) l GE-SREC
[233 i
1
TABLE 4.3-8 (Continued) l TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isole-tion of this pathway and control room alarm annunciation occur tf any of the following conditions exists:
a.
Instrument indicates measured levels above the Alarm / Trip Setpoint, or b.
Circuit failure, or c.
Instrument indicates a downscale failure, or d.
Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicates measured levels above the Alarm Setpoint, or b.
Circuit failure, or c.
Instrument indicates a downscale failure, or d.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHEC" shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
I i
l 1
i GE-SREC (24]
d I
I INSTRUMENTATION RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
{
,C_0NT RO L S 3
j 3.3.3.11 In accordance with [ plant name) TS 6.8.4.g.1), the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded.
The Alarm / Trip Setpoints of these channels J
shall be determined and adjusted in accordance with the methedclogy and parameters in the ODCH.
APPLICABILITY:
As shown in Table 3.3-13 ACTION:
'i a.
With a radioactive gaseous effluent monitoring int umentation channel Alarm / Trip 5etpoint less conservative than required by the i
above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably f
conservative.
l b.
With less than the minimum number of radioactive gaseous. effluent monitoring instrumentation channels OPERABLE, take the ACTION shown l
in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-I annual Radioactive Effluent Release Report pursuant to Control l
6.9.1.4 why this inoperability was not corrected in a timely manner.
c.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
1 Report all deviations in the Semiannual Radioactive Effluent Release Report.
1 i
SURVEILLANCE REQUIREMENTS i
4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE i
CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9.
l i
l GE-SREC
[25)
- = _ -
}
I TABLE 3.3-13
[
,m h
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
[
E MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION r
1.
Main condenser Offgas Treatment System Effluent Monitoring System a.
Noble Gas Activity Monitor -
l Providing Alarm and Automatic Termination of Release 1
47 b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 i
d.
Effluent System Flow Rate l
Measuring Device 1
46 m
e.
Sampler Flow Rate Measuring Device 1
^
46 2A. NOT USED
- 28. NOT USED I
t i
TABLE 3.3-13 (Continued)
E A
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
=
n MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 3.
Reactor Building Ventilation / Purge System a.
Noble Gas Activity Monitor 1
48 b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 d.
Flow Rate Monitor 1
46 e.
Sampler Flow Rate Monitor 1
46 4.
Main Stack System ru U
a.
Noble Gas Activity Monitor 1
47 b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 d.
Flow Rate Monitor 1
46 e.
Sampler Flow Rate Monitor 1
46 5.
Turbine Building Ventilation System a.
Noble Gas activity Monitor 1
47 I
b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 i
M
t TABLE 3.3-13 (Continued) l l
M L
J.
RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
=
n MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION i
5.
Turbine Building Ventilation l
System (Continued) d.
Flow Rate Monitor 1
46 l
Sampler Flow Rate Monitor 1
e.
46 6.
Auxiliary Building Ventilation System a.
Noble Gas Activity Monitor 1
47 P
b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 d.
Flow Rate Monitor 1
46 l
e.
Sampler Flow Rate Monitor 1
46 7.
Fuel Storage Area Ventilation System a.
Toble Gas Activity Monitor 1
47 i
b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 i
d.
Flow Rate Monitor 1
46 c.
Sampler Flow Rate Monitor 1
46 i
4 1
s-
- ~ n
TABLE 3.3-13 (Continued)
R J.
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION mR MINIMLH CHANNELS INSTRUMENT
-OPERABLE APPLICABILITY ACTION 8.
Radwaste Area Ventilation System a.
Noble Gas Activity Monitor 1
47 b.
Iodine Sampler 1
51 c.
Particulate Sampler 1
51 d.
Flow Rate Monitor 1
46 e.
Sampler Flow Rate Monitor 1
46 to 9.
Turbine Gland Seal Condenser Vent and 3
Mechanical Vacuum Pump Exhaust System 47 a.
Noble Gas Activity Monitor 1
51 b.
Iodine Sampler 1
c.
Particulate Sampler 1
51 46 d.
Flow Rate Monitor 1
e.
Sampler Flow Rate Monitor 1
46
- 10. Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup l
System) 45 a.
Noble Gas Activity Monitor 1
d l
1 l
(NOT USED)
GE-5 REC
[303
1 A
i TABLE 3.3-13 (Continued TABLE NOTATIONS 1
"At all times.
l "During main condenser offgas treatment system operation.
- "During operation of the main condenser air ejector.
ACTION STATEMENTS I
ACTION 46 -
With the number of channels OPERABLE less than required by the
]
Minimum Channels OPERABLE requirement, releases to the environment may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:
4 l
a.
The offgas system is not bypassed, and b.
The offgas delay system noble gas activity effluent
]
(downstream) monitor is OPERABLE; J
Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
]
ACTION 46 -
With the number of channels OPERABLE less than required by the j
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 47 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 48 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend release of radioactive effluents via this pathway.
ACTION 49 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed l
within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 50 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days, ACTION 51 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are contin-l uously collected with auxiliary sampling equipment as required in Table 4.11-2.
l f
GE-SREC
[31)
ee
,4w-e A-----
a-l l
l e
(NOT USED) l GE-SREC
[32]
TABLE 4.3-9 Ea RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
n CHANNEL MODES FOR milch CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST 15 REQUIRE 0 1.
Main Condenser Offgas Treatment Syste Effluent Monitoring System
- a. Moble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release D
D R(3)
Q(1) l
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Effluent System Flow Rate D
N.A.
R Q.
g Measuring Device f
- e. Sampler Flow Rate Monitor D
N.A.
R Q
2A. NOT USED
- 28. NOT USED i
I I
I
1 I
TABLE 4.3-9 (Continued)
L M
i J,
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
=
o CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST 15 REQUIRED l
3.
Reactor Building Ventilation / Purge System i
- a. Noble Gas Activity Monitor D
M R(3)
Q(1)
(
- b. Iodine Sampler W
M.A.
M.A.
M.A.
i I
- c. Particulate Sampler W
M.A.
N.A.
N.A.
I
- d. Flow Rate Monitor D
N.A.
R Q
i
[
- e. Sampler Flow Rate Monitor D
N.A.
R Q
4.
Main Stack System i
- a. Noble Gas Activity Monitor D
M R(3)
Q(2) l
- b. Iodine Sampler W
N.A.
M.A.
N.A.
I
- c. Particulate Sampler W
N.A.
N.A.
N.A.
i
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
et Q
i h
e q
j TABLE 4.3-9 (Continued)
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 5.
Turbine Building Ventilation System
- a. Noble Gas Activity Monitor D
H R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
g
- e. Sampler Flow Rate Monitor D
N.A.
R Q
6.
Auxiliary Building Ventilation System
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N. A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
lE
l TABLE 4.3-9 (Continued)
E RADI0 ACTIVE GASEOUS tFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
n, i
n CHANNEL MODES FOR WHICH i
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 7.
Fuel Storage Area Ventilation System i
i f
- a. Noble Gas Activity Monitor D
M R(3)
Q(2) i
- b. Iodine Sampler W
N.A.
N.A.
N.A.
l
- c. Particulate Saapier W
N.A.
N.A.
N.A.
j
- d. Flow Rate Monitor D
N. A.
R Q
e, g
- e. Sampler Flow Rate Monitor D
N.A.
R Q
us 8.
Radwaste Area Ventilation System
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
1,
- c. Particulate Sampler W
N.A.
N.A.
M.A.
i
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
M.A.
R Q
l I
I i
I I
~
i TABLE 4.3-9 (Continued)
E A
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRIMENTATION SURVEILI ANCE REQUIRENENTS i
E n
CHANNEL MODES FOR WHICH
)
CHANNEL SOURCE CI'ANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 9.
Turbine Gland Seal Condenser Vent and Mechanical Vacuum Pump f
t Exhaust System
+
- a. Noble Gas Activity Monitor D
M R(3)
Q(2) f
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
(
- d. Flow Rate Monitor D
N.A.
R Q
h
- e. Sampler Flow Rate Monitor D
N.A.
R Q
10.
Condenser Air Ejector Radioactivity i
Monitor (Prior to Input to Holdup System) l a.
Noble Gas Activity Monitor D
M R(3)
Q(2) i r
1 f
l i
j l
TABLE 4.3-9 (Continued)
I TABLE NOTATIONS i
- At all times.
- During main condenser offgas treatment system operation.
"*During operation of the main condenser air ejector.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicates measured levels above the Alarm / Trip Setpoint, or i
b.
Circuit failure, or c.
Instrument indicates a downscale failure, or d.
Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists; a.
Instrument indicates measured levels above the Alarm Satpoint, or b.
Circuit failure, or c.
Instrument indicates a downscale failure, or d.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent hydrogen, balance nitrogen, and b.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent oxygen, balance nitrogen, and l
b.
Four volume percent oxygen, balance nitrogen.
GE-SREC
[38)
l
]
3/4.11 RADI0 ACTIVE EFFLUENTS l
3/4.11.1 LIQUID EFFLUENTS CONCENTRATION i
l CONTROLS l
3.11.1.1 In accordance with (plant name) 15 6.8.4.g.2) and 3), the concentra-a tion of radioactive material released in liquid effluents to UNRESTRICTED AREAS j
(see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR j
Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved 5,
or entrained noble gases.
For dissolved or entrained noble gases, the concen-tration shall be limited to 2 x 10 4 microcurie /mi total activity, i
j APPLICABILITY:
At all times.
ACTION:
)
a.
With the concentration of radioactive material released in liquid q
effluents to UNRESTRICTED AREAS exceeding the above.imits, immediately restore the concentration to within the above limits, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
l l
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according l
to the sampling and analysis program of Table 4.11-1.
j 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
ll 4
i 4
\\
GE-SREC
[39]
4 f
v,
TABLE 4.11-1 I
RADIOACTIVE L10010 WASTE SAMPL}NG AND ANALYSIS PROGRAM
. LJ)WER LIMIT HINIMUM Of DETECTION LIQUID RELEASE SAMPL]NG ANALYSIS TYPE OF ACTIVITY (LLD)(1)
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml) 1.
Batch Waste P
P Release Each Batch Each Batch Principal Gamma 5x10 7 I3)
Tanks (2)
Emitters 1-131 1x10 6 a.
P H
Dissolved and 1x10 5 One Batch /M Entrained Gases (Gamma Emitters)
P H
H-3 1x10 5 Each Batch
~'posite(4)
Gross Alpha 1x10 7 c.
P Q
Sr-89, Sr-90 5x10 8 I4)
Each Batch Composite Fe-55 1x10 S 2.
Continuous W
Principal Gamma 5x10 7 Releases (5)
Continuous (6) Composite (0)
EmittersI3) 1-131 1x10 6 a.
H H
Dissolved and 1x10 5 Grab Sample Entrained Gases (Gamma Emitters)
N H-3 1x10 5 Continuous (6) Composite (6)
Gross Alpha 1x10 7 c.
0 Sr-89, Sr-90 5x10.s Continuous (6) Composite (6)
Fe-55 1x10 8 GE-SREC
[40)
TABLE NOTATIONS
]
II)The LLD is defined, for purposes of these controls, as the smallest I
concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability i
with only 5% probability of falsely concluding that a blank bbservation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
l 4.66 s D LLD =
E V
2.22 x 106 Y exp (-Aat)
]
Where:
LLD = the "a priori" lower limit of detectir. (microcurie per unit mass or volumo),
s = the standard deviation of the background counting rate or of b
the counting rate of a blank sample as appropriate (counts per minute),
E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
a 2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (set 1), and at = the elapsed time between the raidpoint of semple collection and the time of counting (sec).
5 Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capaoility of a measurecent system and not as an a posteriori (after the fact) limit for a particular measurement.
I2)A batch release is the disenarge of liquid wastes of a discrete volume.
Prior to sampling for snalyses, each batch shall be isolated, and then l
thoroughly mixed by a method described in the ODCM to assure l
representative sampling.
GE-SREC
[4j3
TABLE 4.11-1(Continued}
TABLE NOTATIONS (Continued)
I )The orincipal gamma emmiters for which the LLD control applies include the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Ce-144 shall also be measured, but with an Cs-134, Cs-137LLD of 5 x 10 d.and Ce-141.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 in the format outlined in Regulatory Guide 1,21, Appendix B, Revision 1, June 1974.
I )A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
(5)A continuous release is the discharge of liquid wastes of a nondiscreta volume, e.g., from a volume of a system that has an input flow during the continuous release.
(6)To be representative of the quantities and concentrations of radioattive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
s I
1
)
GE-SREC
[42)
l RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with (plant name) TS 6.8.4.g.4) and 6.8.4.9.5), the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
This Special Report shall also include:
(1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Orinking Water Act.*
b.
The provisions ef Controls 3.0.3 and 3.0.4 nre not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
- The requirements of ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.
In the case of river-sited plants this is 3 miles downstream only.
GE-SREC (43)
RADIOACTIVE EFFLUENTS Liquid RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with [ plant name] TS 6.8.4.g.6), the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
j APPLICABILITY:
At all times.
ACTION:
a.
With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commis-sion within 30 days, pursuant to Control 6.9.2, a Special Report that includes the following information:
1.
Explanation of why liquid redwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Liquid Radwaste Treatment Systems are not being fully utilized.
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
GE-SREC
[44]
RADIOACTIVE EFFLUENTS 3/4.11.1.4 (NOT USED) 4
}
1 i
I i
l 1
k i
i, J
4
}
i 4
i i
d I
I l
l t
f l
GE-SREC
[45) i l
l
RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 In accordance with [ plant name) TS 6.8.4.g.3) anJ 7), the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b.
For Iodine-131, for Iodine-133, for tritium, and for all rt io-L nuclides in particulate form with half-lives greater than 6 days:
Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS-4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits'in accordance with the methodology and par & meters in the ODCH.
4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all I
radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
GE-SREC
[46)
TABLE 4.11-2 RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM R
d, MINIMUM LOVER LIMIT OF A
SAMPLING ANALYSIS TYPE OF DETECTION (LLO)II)
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCl/ml)
- 1. Offgas Treatment M
M Principal Gama Emitters (2) 1x10 4 System Grab Sample
- 2. Containment PURGE P
P I3) Each PURGE (3) Principal Gamma Emitters (2) 1x10 4 OR VENT Each PURGE Grab Sample M
H-3 (oxide) 1x10
- 3)'
Principal Gamma Emitters (2) 1x10 *
- 3. a.
(List other M
release points M(3) where gaseous Grab Sample effluents are released from the facility)
H-3 (oxide) 1x10 5
,,. s 4.
All Release Types Continuous""
W"'
I-131 1x10 "
2 as listed in 1.,
Charcoal 3
2., and 3. above Sample Continuous (6) y(D Principal Gamma Emitters (2) 1x10 82 l
Particulate Samo1e Continuous (6)
M Gross Alpha 1x10 88 Composite Par-ticulate Sample Continuous (6)
Q Sr-89, Sr-90 1x10 88 Composite Par-ticulate Sample Continuous (6) Noble Gas Noble Gases Monitor Gross Beta or Gamma Ix10 8 l
i
TABLE 4.11-2 (Continued)
TABLE NOTATIONS (1)The LLO is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5'4 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical seoaration:
4'
$ D LLO =
E V
- 2.22 x IOS
- Y exp (-Aat)
Where:
LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume),
s r the standard deviation of the background ccunting rate or of b
the counting rate of a blank sample as appropriate (counts per minute),
E = the counting efficiency (counts per disir.tegration).
V = the sample size (units of mass or volume),
2.22 x 108 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec 1), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec).
Typical values of E. V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
GE-SREC
[48]
1ABLE 4.11 2 (Continued)
TABLE N01AT10NS (Continued)
I }The principal gamma emitters for which the LLO control applies include the following radionuclides:
Kr*87, Kr 88, Xe 133 s Xe 133m, Xe 135, and Xe 138 in noble gas releases and Mn-54, Fe 59, Co 58, Co 60, 2n;65, Ho 99, 1 13), Cs 134 Cs 137, Ce 141 and Ce-144 in lodine and particulate releases. This list does not mean t, hat only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the 5emiannual Radioactive [ffluent Release Report pursuant to Control 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix 8 Revision 1 June 1974.
(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.
(4)Not asplicable.
Ib) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
(6)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Cor.trols 3.11.2.1, 3.31.2.2. and 3.11.2.3.
U )Samp185 shall be changed at least once per 7 days and analyses shall be completed within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> af ter chan0 ng, or af ter removal from sanpler.
i Sampling shall also be performea at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change eFCeeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LL0s may be increased by a factor of 10.
This requirement does not apply if:
(1) analysis shows that the DOSE EQUlVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) tha noble gas monitor shows that effluent activity has not increased more than a factor of 3.
GE-5 REC
[49)
Il 1
RADICACTIVE EFFLUENTS 00$E NDBLE GASES CONTROLS l
3.11.2.2 In accordance with (plant name) TS 6.8.4.g.5) and 8) the a'ir dose duetonoblegasesreleasedingaseouseffluents,fromeachunlt,toareasat and beyond the SITE 80VHDARY (see Figure 5.1 3) shall be limited to the following:
a.
During any calendar quarttr*:
Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mradt for beta radiction, and b.
During any calendar year:
Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY:
At all times.
ACTION With the calculated air dose from radioactive noble gases in gaseous s.
effisents exceeding any of the above Itmits, prepara and submit to l
the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure i
that subsequent releases will be in compliance with the above limits.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l i
F l
I l
l GE-SREC (503
RADIDACTIVE EFFLUENTS p0SE - 1001NE-131, 100!NE 133. TRITlUM. AND RADI0 ACTIVE MATERIAL IN tETICULATEFOR>j CONTROLS 3.21.2.3 In accordance with (plant name) TS 6.8.4.g.5) and 9), the dose to a MEMBER OF THE PUBLIC from lodine 131, lodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the $1TE BOUNDARY I
(see Figure 5.1-3) shall be limited to the following:
l a.
During any calendtr quarter:
Less than or equal to 7.5 mrems to any j
organ and,
{
b.
During any calendar year:
Less than or equal to 15 mrems to any
{
organ.
5 APPLICABILITY:
At all times.
l l
ACTION:
a.
With the calculated dose from the release of lodine-131, lodine 133,
]
tritium, and radionuclides in particulate form with half-lives l
greater than 8 days, in gaseous effluents exceeding any of the above t
limits, prepare and submit to the Commission within 30 days, pursuant 4
l to Control 6.9.2, o Special Report that identifies the cause(s) for i
exceeding the limit (s) and defines the corrective actions that have been taktn to reduce the releases and the proposed corrective actions j
to be taken to assure that subsequent releases will be in compliance j
with the above limits.
i j
b.
he provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANZ REQUIREMENTS i
4 l
4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for lodine 131, lodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined l
in accordance with the methodology and pcrameters in the ODCM at least once i
per 31 days, i
i j
l l
GE-SREC
[51)
RADIDACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT $)LTEM CONTROLS 3.11.2.4 The GASEOUS RA0 WASTE TREATMENT SYSTEM shall be in operation.
APPLICABILITY:
Whenever the main condenser air ejector (evacuation) system is in operation.
ACTION:
a.
With gaseous radweste from the main condenser air ejector system being discharged without treatment for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of the relevant instruments shall be checked every 12 i
hours when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.
i i
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GE-SREC i
[52]
1 i
RA010ACT!vt ErrLUENT$
VENT!tATION ExHAtt$T TREATHENT $YSTEM CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERAr;E and appropriate portions of this sysiem shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see figure 5.1-3) would exceed:
a.
0.2 mrad to air f rom gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 mrem to any organ of a MEMBER OF 1HE PUBLIC.
APPLICABit!TY:
At all times.
ACTION:
a.
With radioactice gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Repert that includes the following information:
1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the mettodology and parameters in the ODCM when the Ventilation Exhaust Treatment System is not being fully utilized.
i 4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1, and either 3.11.2.2 or 3.11.2.3.
\\
GE-SREC
[53)
l l
i RAD 10ACT!vt trFtVENTS 3/4.11.2.6 (NOT USED) 2 GE-SREC
[54)
E D10 ACTIVE [FFLUENT$
3/4.33.?.7 (NOT USED) f I
GE-SREC
[55)
RADIOACTIVE EFFLUENTS
, MARK 1 or 11 CONTAlNMENT CONTROLS 3.11.2.8 VENTING or PURGING of the Mark I or 11 containment drywell'shall be through the Standby Gas Treatment System.
~
APPLICABlllTY:
Whenever the drywe t is vented or purged.
ACTION:
a.
With the requirements of 6.ie above control not satisfied, suspend all VENTING and PURGING of the drywell.
b.
The provisions of dentrols 3.0.3 and 3.0.4 are not applicable.
SURVElLLANCE REQUIREMENTS 4.11.2.8 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.
l GE-SREC
[56)
i OtAD10 ACTIVE EFFLUENTS 3/4.33.3 (NOT USED)
GE-SREC (57)
RADI0 ACTIVE EFFLU[NTS 3/4.11.4 TOTAL 00$E QNTROLS 3.11.4 In accordance with (plant name) TS 6.8.4.g,11), the annual (calendar year) dose or dose cornmitment to any MLHBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABlllTY:
At all times.
ACTION:
a.
With the calculated doses from the releans of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks etc.) to determine whether the above limits of Control 3.11.4 have been exceeded.
If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC f rom uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
If the estimated dose (s) excerds the above limits, and if the release condition result-s ing in violation of 40 CFR Part 190 has not already been corrected, the Special f:eport shall include a request for a variance in accor-dance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEllLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous ef fluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the tiethodology and parameters in the ODCH.
l 4.11.4.2 Cumulative dose contributions from direct radiation from the units I
(including outside storage tanks etc.) shall be determined in accordance with the methodology and parameters in the ODCH.
This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.
GE-SREC (58)
= - - _ - __
i 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING I
j 3/4.12.1 MDNITORING PROGRAM l
CONTROLS 3.12.1 in acccrdance with (plant Nme) TS 6.8.4.h.1), the Radiological Environmental Monitoring Program shall be conducted es specified in
- Table 3.12-1.
1 APPLICABILITY:
At all times.'
)
ACTION:
j l
a.
With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-3 prepare and submit to j
theCommission,intheAnnualRadiologicalEnvironmentalOperating Report required by Control 6.9.1.3, a description of the reasons i
for not conducting the program as required and the plans for preventing j
a recurrence.
b.
With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that identifies the cause(s) l for exceeding the limit (s) and defines the corrective actions to be taken to reNee radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, or 3.11.2.3.
When more than one of the radionuclides in Table 3.12 2 are detected in the sampling medium, this report shall be submitted if:
concentration (13 concentration (2)
+ *> 1.0 reporting level (L), reporting level (2)
When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if i
the potentfal annual dose
- to a MEMBER OF THE PUBLIC from all radio-nuclides is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report, GE-5 REC (59)
RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS ACTION (Continued) c.
With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.
The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Control 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples, d.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVE1LLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
GE-SREC
[60)
I I.
TABLE 3.17-1 i
E g
RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM
- m" NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY
[
AND/OR SAMPLE SAMPLE LOCATIONS ( )
COLLECTION FREQUENCY OF ANALYSIS I2}
1.
Direct Radiation Forty routine monitoring stations Quarterly.
Gamma dose quarterly.
(DRl-DR40) either with two or more l
dosimeters or with one instrument I
l for measuring and recording dose j
rate cen*Invously, placed as y
follows-t i
t I
An inner ring of stations, one in each meteorological sector in the general area of the SITE BCUNDARY q
(DR1-DR16);
f 1
E An outer ring of stations, one in
(
cach meteorolo
- cal sector in i
i the 6-to 8-km range from the site (DR17-DR32); and i
The bala xe of the stations I
(DR33-DR40) to be placed in i
special interest areas such i
as population centers, nearby l
residences, schools, and in one i
i or two areas to serve as control i
stations.
i l
1 i
- The number, media, frequency, and location of samples may vary from site to sito. This table pre'sents an i
acceptable minimum program for a site at which each entry is applicable.
Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's 7
dose and should be included in the sample program. The code letters in parentheses, e.g.,
DRI, A1, provide 1
one way of defining sample locations in this control that can be used to identify the specific locations
(
in the map (s) and table in the 00CM.
TABLE 3.12-1 (Continued)
- m RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM m'
NUMBER OF REPRESENTATIVE EXPOSURE PATlWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY l
III AND/OR SAMPLE SAMPLE LCCATIONS COLLECTION FREQUENCY OF ANALYSIS 2.
Airborne Radiofodine and Samples from five locations Continuous sampler oper-Radiciodine Cannister:
Particulates (Al-AS):
ation with sample collec-1-131 analysis weekly.
tion weekly, or more Three samples (Al-A3) from frequently if required by close to the three SITE dust loading.
Particulate Sampler:
BOUNDARY locations, in Gross octa radioactivity i
different rectors, of the analysis following highest calculated annual gjg
,(3) g average ground-level D/Q:
g,ma 93,g,p;c an,3y393(4) of composite (by One sample (A4) from the location) quarterly.
vicinity of a commnity ru having the highest calcu-lated annual average ground-level D/Q; and One sample (AS) frem a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
3.
Waterborne Surface (5)
One sample upstream (Wal).
Composite saeple over Gama isotopic analysis #3 I
a.
One sample downstream (Wa2).
1-month period.(5)
C b.
Ground Samples from one or two sources Quarterly.
Gama isotopic #) and I
(Wbl, Wb2), only if likely to be tritium analysis quarter 1y L
affected 3
TABLE 3.12-1 (Continued) i E
{
J, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
M n
NfJMBER OF REPRESENTAi1VE EXPOSURE PAThvAY SAMPLES AND SAMPLING AND TYPE AND FREQU[NCY I}
AND/OR SAMP4.E SAMPLE LOCATIONS COLLECTION FREQUENCY Of ANALYSIS
{
3.
Waterborne (Contint,ed) c.
Drinking One sample of each of one to Composite sample over I-131 analysis on each three (Wcl - Wc3) of the nr
- s t ek grim (6) composite when the dose water supplies that could af fet. Led by its discharge. '
I-131 analysis is per-C*'C"!'
I'"
C'"-
I forsned; monthly com-y on water l
posite otherwise.
'* 9"**t*" th*" I ""*"
One sample from a control per year (8). Coriposite location (We4).
for gross beta and gasura isotopic analyses monthly. Composite for tritium analysis quarterly.
cs d.
Sediment One sample free downstream area Semiannually.
Gawaa isotopic analysis (4) v from with existing or potential semi..muaPy.
Shoreline ecreational value (Wdl).
4.
Ingestion a.
Milk Samples from milking animals Semimonthly when Gaarsa isotopicI4) and in three locations (Ia1 - la3) animals are on pastura; I-13I analysis s m i-I within 5 km distance having the monthly at other times.
monthly when aniwals highest dose poten*.ial.
If are on pasture; monthly there are none, then one at other times.
sample from milking animals in each of thrre areas (Ia1 - Ia3) between 5 to 8 be distant where cosas are calculated t than 1 arem per yr$. 89 eater One sample from milking aalmals at a control location (la4),
15 to 30 km distant and in the least prevaient wind direction.
l TABLE 3.12-1 (Continued)
\\
R J.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM M
NUMBER OF REPRESENTATIVE EXPOSURE PATINAY SAMPLES AND SAMPLING AND TYPE AND FREQ*vTNCY i
I}
AN0/OR SMtPLE SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS I
4.
Ingestion (Continued)
N b.
Fish and One sample of each coewnercially Sample in season, or Gamma isotopic analysis i
Inverte-and recreationally important semiannually if they on edible portions.
l brates species in vicinity of plant are not seasonal.
I discharge area.
(Ib1 - Ib_ ).
j One sample of same species in I
areas not influenceo by plant discharge (Ib10 - Ib_ ).
IN c.
Food One samole of each principal At tim of harvest Gamma isotopic analyses Products class of food products from on edible portion.
7 g
any area that is irrigated by water in which liquid a
plant wastes have been discharged (Ic1 - Ic_ ).
I Samples of three different Monthly during Gamma isotopic ") and 1-131 kinds of broad leaf vegeta-growirg season.
analysis.
tion grown nearest each of I
two different offsite loca-L tions of highest predicted f
annual average ground level D/Q if milk sampling is not performed (Ic10 - Ic13).
One sample of each of the Monthly during Ganna isotopic #) and I-131 I
similar broad leaf vegeta-growing season.
analysis.
tion grown 15 to 30 km dis-tant in the least prevalent wind direction if milk sam-i pling is not performed (Ic20 -
i Ic23).
l
TABLE 3.12 1 (Continued)
TABLE NOTATIONS t
(1) Specific parameters of distance and direction sector from the centerline i
of one reactor, and additional description where pertinent, shall be pro-l vided for each and every sample location in Table 3.121 in a table and figure (s) in the ODCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of auto-matic sampling equipment.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action i
prior to the end of the next sampilng period.
All deviations from the sampling schedule shall be documented in the Annual Radiological Environ-i mental Operating Report pursuant to control 6.9.1.3.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutiuns made within 30 days in the Radiological Environmental Monitoring Program given in the ODCH.
Pursuant to Control 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the ODCM reflect-ing the new location (s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selec-tion of the new location (s) for obtaining samples.
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addi-tion to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or mere phosphors in a packet are considered as two.or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation.
(The 40 stations is.not an absolute number.
The number of direct radiation monitoring stations may be reduced according to geographical. limitations; e.g., at an ocean site, some sectors will be over water so that the number r
of dosimeters may be reduced accordingly.
The frequency of analysis or I
readout for TLD systems will depend upon the characteristics of the speci-j' fic system used and should be selected to obtain optimum dose information with minimal fading.)
I l
(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and l
thoron daughter decay.
If gross beta activity in air particulate semples is greater than 10 times the yearly mean of control samples, gamma I
l isotopic. analysis shall be performed on the individual samples.
GE-5 REC
[65)
TABLE 3.12-1 (Continued)
TABLE NOTATIONS (Continued)
(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.
($) The "costream sample" shall be taken at a distance beyond significant influence of the discharge.
The " downstream" sample shall be taken in an area beyond but near the mixing Zone.
" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
Salt water shall be sampled only when the receiving water is utilized for recreational activities.
(6) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow.
In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCH.
(9) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
If harvest occurs continuously, sampling shall be monthly.
Attention shall be paid to including samples of tuberous and root food products.
GE-SREC
[66)
mm
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[67]
i I
TABLE 4.12-1 DETECTIDM CAPA81LITIES FOR ENVIRONMENTAL SAMPLE ANALYSISI ) (2) f LOWER LIMIT OF DETECTION (LLD)(3)
{
WTER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/1)
OR GASES (pCi/m )
(pci/kg, wet) (pCi/1)
(pci/kg, wet) (pci/kg, dry) 3 i
Gross Beta 4
0.01 H-3 2000*
\\
Mn-54 15 130 i
Fe-59 30 260 4
i Co-58,60 15 130 i
t i
E Zn-65 30 260 f
s f
Zr-N5-95 15 I-131 1**
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 l
Ba-La-140 15 15 i
- If no drinking water pathay exists, a value of 2000 pCi/1 may be used.
If no drinking water pat hay exists, a value of 15 pCi/1 may be used.
i i
l t
1 h
TABLE 4,32-1 (Continued)
_ TABLE NOTATIONS (2)This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual RadioTogical Environmental Operating Report pursuant to Control 6.9.1.3.
I (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in 4ccordance with the tecommenda-tions of Regulatory Guide 4.13.
(3)The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 51 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD =
E V
2.22 exp(-Aat)
Y a
a Where:
1.LD = the "a priori" lower limit of detection (picoCuries per unit mass or volume),
s
= the standard deviation of the background counting rate or of the b
counting rate of a blank sample as appropriato (counts per minute).
E
= the counting ef ficiency (counts per disintegration),
V
= the sample size (units of mass or volume),
2.22 = the number of disintegrations per minute per picocurie, Y
= the fractional radiochemical yield, when applicable.
A
= the radioactive decay constant for the particular radionuclide (sec 1), and At
= the elapst.1 time between environmental collection, or end of the sample collection period, and time of counting (sec).
Typical values of E, V, Y, and At should be used in the calculation.
I GE-SREC (69]
TABLE 4.1? 1 (Continued) 1ABLE NOTATIONS (Continued)
It should be recognized that the LLD is defined as an a priori (before the f act) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidable small sample sites, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
i In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to I
Control 6.9.1.3.
i i
l l
b I
GE-$ REC
[70) i
t i
l l
RADIOLOGICAL ENVIRONMENTAL HONITORING i
j 3/4.12.2 LAND USE CENSU$
1 l
CONTROLS 3.12.2 ln accordance with (plant name) 15 6.8.4.h.2), a Land Use Ce'nsus shall i
be conducted and shall identify within a distance of 8 km (5 miles) the i
location in each of the 16 meteorological sectors of the nearest milk animal I i
the nearest residence, and the nearest garden
- of greater than 50 m8 (500 ft )
l producing broad leaf vegetation.
[For elevated releases 45 defined in Reguia-l tory Guide 1.111. Revision 1, July 1977 the Land Use Census shall also identifywithinadistanceof5km(3 miles)thelocationsineachofthe I
16 meteorological sectors of all milk animals and all gardens of greater than
{
50 me producing broad leaf vegetation.)
APPLICABILITY:
At all times.
ACTION:
6.
With a land Use Census identifying a location (s) that yields a
]
calculated dose or dose commitment greater than the values currently 1
being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4, I
identify the new location (s) in the next Semiannual Radioactive Effluent Release Report.
i b.
With a Land Use Census identifying a location (s) that yields a i
calculated dose or dose commitment (via the same exposure pathway) j 20% greater than at a location from which samples are currently j
being obtained in accordance with Control 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-i toring Program given in the ODCH.
The sampling location (s), exciud-i ing the control station location, having the lowest calculated dose j
or dose commitment (s), via the same exposure pathway, may be deleted i
from this monitoring program after (October 31) of the year in which this Land Use Census was conducted.
Pursuant to Control 6.14, 1
i submit in the next Semiannual Radioactive Effluent Release Report I
documentation for a change in the ODCH ir,cluding a revised figure (s) and table (s) for the ODCH reflecting the new location (s) with informa-j tion supporting the change in sampling locations.
I c.
The provisions of Controis 3.0.3 and 3.0.4 are not applicable, f
i
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lisu of the garden census, j
Controls for broad leaf vegetation sampling in Table 3.12-1, Part 4.c., shall l
be followed, including analysis cef control samples.
l GE-SREC
[733 I
MD10LOGICALENVIRONMENTALMONITORING
$URVEILL ANCE REQUIREMENTS 4.12.2 The Land 'Jse Census shall be conducted during the growing season at least once per 12 nionths using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by conruiting local agriculture authorities.
The results of the Land Use Cen50s shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.
l i
t l
GE-SREC (72)
. _ - - ~
i RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 1
CONTROLS 4
3.12.3 in accordance with (plant name) TS 6.8.4.h.3), analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory i
Comparison Program that has been approved by the Commission, that correspond to 1
samples required by Table 3.12-1.
J APPLICABILITY:
At all times.
1 4
ACTION:
i 4
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence tu the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.
J b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
1 SURV[ILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCH.
A summary of the results obtained as part of the above required Interlaboratory i
Comparison Program shall be included in the Annual Radiological Environmental l
Operating Report pursuant to Control 6.9.1.3.
i f
a GE-SREC (73) 1
1 BASES FOR
$ECTIONS 3.0 AND 4.0 CONTROLS AND SURVElLLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 3.0 and 4.0, but are not part of these Controls.
GE-SREC (74)
l 1
t INSTRUMINTATION BASES 4
I r
l J
l 3/4.3.3.10 RADI0 ACTIVE L10U10 EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor 1
and control, as applicable, the releases of radioactive materials in liquid t
j effluents during actual or potential releases of liquid effluents.
The q
Alar:n/ Trip 5etpoints for these instruments shall De calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The i
4 OPERABIL11Y and use of this instrumentation is consistent with the requirements l
of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
l l
3/4.3.3.11 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
)
The radioactive gaseous effluent instrumentation is provided to monitor and control,ing actual or potential releases of gaseous effluents.as applicable, the releases l
ents dur The Alarm / Trip i
i Setpoints for these instruments shall be calculated and adjusted in accordance j
with the methodology and parameters in the ODCM to ensure that the alarm / trip j
will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY j
and use of this instrumentation is consistent with the requirements of General j
Design Criteria 60, 6?, and 64 of Appendix A to 10 CFR Part 50.
i e
i l
GE-SREC
[75)
.. ~.. ~.. _, - _ _ _. _ _. -.. _ _ _ _ _., _.. _ _ _. _....,. _, _ _,.. _ -.
....... _.. _., - ~ ~ _ _ -. -,
3/4.11 RADIOACTIVE [FFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Table 11, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within:
(1) the Section II. A cesign objectives of Appendix 1,10 CFR Part 50, to a HEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air (submersion) was converted to an equiva tent concentration in water using the methods described in International CommissL>n on Radiological Protection (ICRP) Publication 2.
This control applies to the release of radiosctive materials in liquid effluents from all units at the site.
The required detection capabilities for redioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., " Lower Limit of Detection:
Definition and Elaboration of a P.oposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR 4007 (September 1984), and in the HASL Procedures Manual, HA5L-300, 3/4.11.1.2 005E This control is provided to implement the requirements of Sections 11. A, Ill.A, and IV.A of Appendix 1, 10 CFR Part 50.
The Control implements the guides set forth in Section II.A of Appendix 1.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix ! to assure that the releases of radio-active material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can bc potentially affected by plant operations, there is reasonable assurance that thi operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in exce.s of the requirements of 40 CFR Part 141.
The dose calculation methodology and parameters in the ODCH implement the requirements in Section III.A of Appendix 1 that conformance with the guides of Appendix ! be shown by calcu-lational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substan-tially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 3.109, " Calculation of Annual Doses to Man from Routine Releases of GE-SREC
[76]
RADI0 ACTIVE EFFLUENTS BASES 005E (Continued)
Reactor Effluents for the Purpose of Esalcating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 o : Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from A:,1.Nntal and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.
This control applies to the release of radioactive materials in liquid effluents from eLch unit at the site.
For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEH The OPERABILITY of the Liquid Radwaste Trestment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." Thi' control implements the requirements of 10 CFR 50.06a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Sectica II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquia effluents.
This control applies to the release of radioactive materials in liquid effluents from each snit at the site.
For units with shared Radwaste Systams, the liquid effluents from the shared system are to be proportioned among the units sharing the+ "estem, i
l
[773 GE-SREC
RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS, The annual dose limits are the doses associated with the concentrations of 10 Cr'R Part 20, Appendix B, Table II, Column I.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF 1HE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupency of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the $1TE BOUNDARY.
Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.
The specified release rate lirrits restrict, at all times, the corresponding gamma and beta dose rates abose background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin.
These release rate limits also restrict, at all timet, the corresponding thyroid dose rate above btckground to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.
This control applies to the release of radioactive materials in gaseous effluents from all units at the site.
The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., " Lower Limit of Detection:
Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4037 (September 1984), and in the HASL Procedures Manuc1, HASL-300, 3/4.11.2.2 DOSE - NOBLE GASES This control is provided to implement the requirements of Sections 11.3 III.A and IV.A of Appendix I, 10 CFR Part 50.
The control implements the guides set forth in Section I.B of Appendix 1.
The ACTION statements provide the required operating fler.ibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radio-active material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformence with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The dose calculation CE-SREC
[78)
)
i
[
RADIOACTIVE EFFLVENTS 1
i BASES l
DOSE-NOBLE GASES (Continued) methodology and parameters established in the ODCM for calculating the doses j.
due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routi n Releases of Reactor Efficents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
i Revision I, October 1977 and Regulatory Guide 1.111 " Methods for Estimating i
Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases
)
from Light-Water Cooled Reactors," Revi'sion 1. July 1977.
The ODCM equattor.s j
provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This control appifes to the release of radioactive materials in gaseous
}
effluents from each unit at the site.
For units with shared Radwaste Treatment i
Systems, the gaseous of fluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.3 DOSE - 10 DINE-131. 10 DINE-133. TRITIUM, AND RADIOACTIVE MATERIAL l
IN PARTICULATE FORM l
4 This control is provided to implement the requirements of Sections II,C, III. A and IV. A of Appendix 1,10 CFR Part 50.
The Controls are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive naterials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is j
reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calcu-lational procedures based on models and data such that the actual exposure of a
~
MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substan-l tially underestimated.
The ODCM calculational methodology and parameters for calculating the doses due to the. actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from-Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,"
Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating i
Atmospheric Transport and Disnersion of Gaseous Effluents in Routine Releases i
from Light-Water-Cooled Reactors," Revision 1 July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
Tha release rate controls for Iodine-131 Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the l
GE-SREC E793 O
RADIDACTIVE EFFLUENTS BASES DOSE - 10 DINE-131, 10 DINE-133, TRITlUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM (Continued) areas at and beyond the SITE BOUNDARY.
The pathways that were examined in the development of the calculations were:
(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat prnducing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
This control applies to the release of radioactive materials in gaseous effluents from each unit at the site.
For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RA0 WASTE TREATHENT SYSTEM AND VENTILATION EKHAUSl TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLOUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.
This control applies to the release of radioactive materials in gaseous effluents Nom each unit at the site.
For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
GE-! REC
[s0]
RADI0 ACTIVE EFFLUENTS BASES 3/4 11.2.6 NOT USED 3/4 11.2.7 NOT USED 3/4.11.2.8 MARK I CONTAINMENT This specification provides reasonable assurance that releases from drywell purgir.g operations will not exceed the annual dose limits of 10 CFR part 20 for unrestricted areas.
3/4.11.3 NOT USED i
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l 3/4.11.4 TOTAL DOSE This control is provided to mest the dose limitations of 10 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.
The controi j
requires the preparation and submittal of a Special Report whenever the
{
calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mren.s.
l For sites containing up to four reactors, it is highly unlikely that the i
resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the units l
[81]
GE-5 REC
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RADl') ACTIVE EFFLUENTS B AS'.S IOTAL DOSE (Continued) 1 (including outside storage tanks, etc.) are kept small.
The Special' Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that the dose commitment to the' MEMBER of the PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km caust be considered.
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is com-pleted.
The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
l GE-SREC
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l 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING i
BASES l
3/4.12.1 PONITORING PROGRAM i
I The Radiological Environmental Monitoring Program required by this i
control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to i
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the highest poten*ial radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation.
This monitoring program implementsSection IV.B.2 i
of Appendix 1 to 10 CFR Part 50 aad thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of l
radioactive materials and levels of radiation are not higher than expected on i
the basis of the effluent measurements and the modeling of the environmental exposure pathways.
Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, 2
i Revision 1, November 1979.
The initially specified monitoring program will be effective for at least the first 3 years of commercial operation.
Following l
this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are i
tabulated in terms of the lower limits of detection (LLDs).
The LLDs required j
by Table 4.12-1 are considered optimum for routine envirormental measurements in industrial laboratories.
It should be recognized that the LLD is defined I
as an a priori (before the fact) limit representing the capability of a measure-ment system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in Currie, L. A., " Lower Limit of Detection:
Definition and Elaboration of a i
Proposed Position for Radiological Effluent and Environmental Measurements,"
j NUREC/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300.
1 i
3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made'if required by the results of this census.
The best information from the i
j door-to-door survey, from aerial survey or from consulting with local agri-l cultural authorities shall be used.
This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to 2
l gardens of greater than 50 m provides assurance that.significant exposure j
pathwayt via leafy vegetables will be identified and monitored sinu a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were made:
i (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar 2
l to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m.
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GE-SREC
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERL ABORATORY COMPARISON PROGRM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental rnonitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.
GE-SREC
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APPEND 1X A i
4 Radiological Assessment Branch Technical Position, Revision 1, November 1979 1
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[85]
i
Revision 1 November 1979 Branch Technical Position Backcround Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, issued for comment in December 1975, is being revised based on comments received.
The Radiological Assessment Branch issued a Branch Position on the radiological portion of the environmental monitoring program in March, 1978.
The position was formulated by an NRC working group which considered comments received after the issuance of the Regulatory Guide 4.8.
This is Revision 1 a
of that Branch Position paper.
The changes are marked by a vertical line in the right margin.
The most significant change is the increase in direct radiation measurement stations.
10 CFR Parts 20 and 50 require that radiological environmental monitoring 4
programs be established to provide data on measurable levels of radiation and radioactive materials in the site environs.
In addition, Appendix ! to 10 CFR Part 50 requires that the relationship between quantities of radioactive material released in effluents during normal operation, including anticipated operational occurrences, and resultant radiation doses to individuals from principals pathways of exposure be evaluated.
These programs should be con-ducted to verify the effectiveness of in plant measures used for controlling the release of radioactive materials.
Surveillance should be established to identify changes in the use of unrestricted areas (e.g., for agricultrual purposes) to provide a basis for modifications in the monitoring programs for evaluating doses to individuals from principal pathways of exposure.
NRC Regulatory Guide 4.1, Rev.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants " provides an acceptable basis for the design of programs to monitor levels of radiation and radioactivity in the station i
envi rer.s.
This position sets forth an example of an acceptable minimum radiological monitoring program.
Locel site characteristics must be examined to determine if pathways not covered by this guide may significantly contribute to an individual's dose and should be included in the sampling program.
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2 AN ACCEPTABLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j
i Procram Reesirements Environmental samples shall be collected and analyzed according to Table 1 at i
locations shown in Figure 1.1 Analytical techniques used shall be such that the detection capabilities in Table 2 are achieved.
The results of the radiological environmental monitoring are intanced to supr' ament the results of the radiological effluent monitoring by verifying that'";he measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measure-sents and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radio-active materials in those exposure pathways and for those radionuclides which 4
1ead to the highest potential radiation exposures of individuals resulting from the station operation.
The initial radiological environmental monitoring program should be conducted for the first three years of commercial operation (or other period corresponding to a maximum burnup in the initial core cycle).
Following this period, program changes may be proposed based on operational experience.
The specified detection capabilities are state-of-the-art for routine environ-mental measurements in industrial laboratories.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens j
are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
All deviations from the sampling schedule shall be documented in the s
l annual report.
The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)
Environmer.tal Racioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program or equivalent program.
This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.
Ti.e results of analysis of these crosscheck samples shall be included in the annual report.
The participants in tha EPA crosscheck program may provide their EPA program code so that the NRC can review the EPA's participant cata directly in lieu of submission in the annual report.
'It may Le necessary to require special studies on a case-by-case and site specific basis to establish the* relationship between quantities of radioactive material released in effluents, the concentrations in environmental media, and the resultant doses for import. ant pathways.
[87)
3 If the results of a determination in the EPA crosscheck program (or equivalent pregram) are outside the specified control limits, the laboratory shall inves-tigate the cause of the problem and take steps to correct it.
The results cf this investigation and corrective action shall be included in the annual report.
The requirement for the participation in the EPA crosscheck program, or similar program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in o der to demonstrate that the results are reasoryably valid.
A census shall be conducted annually during the growing season to determine the location of the nearest silk animal and nearest garden greater than 50 square noters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).8 For elevated releases as defined in Regulatory Guide 1.111 Rev.
1., the census shall also
, identify the locations of all milk animals, and gardens greater than 50 square noters producing broad leaTvegetation out to a distance of 5 km. (3 miles) for each radial sector.
If it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in the radioactive effluent technical specifications for dose calculations, a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction).
Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
The sampling location (excluding the control sample location) having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was con-ducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program af ter notifying the NRC in writing that they are no longer obtainable at that location.
The results of the land-use census shall be reported in the annual report.
The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to pemit stodifications in monitoring programs for evaluating dt.ses to individuals from principal pathways of exposure."
The consumption of milk from animals grazing on contaminated pasture and of 1* fy vegetation contaminated by airborne Broad leaf vegetation sampling r.sy be perfonned at the site boundary in a sector with the highest D/Q in i.eu of the garoen cansus.
[88]
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i radiciodine is a major potential source of exposure.
Samples from milk, animals are considered a better indicator of radioiodine in the environment than vegetation.
If the census reveals milk animals are not present or are i
unavailable for sampling, then vegetation must be sampled.
The 50 sovere meter garden, considering 20% used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/a8, j
will produce the 26 kg/yr assumed in Regulatory Guide 1.109 Rev 1.,
for child j
consumption of leafy vegetation.
The option to consider the garden to be j
broad leaf vegetation at the site boundary in a sector with the highest D/Q 1
should be conservative and that location may be used to calculate doses due to i
radioactive effluent releases in place of the actual locations which would be i
determined by the census.
This option does not apply to plants with elevated j
releases as defined in Regulatory Guide 1.111 Rev. 1.
The increase in the number of direct radiation stations is to better characterize i
the individual exposure (arem) and population exposure (man-rem) in accordance 2
with criterion 64 - Monitoring radioactivity releases, of 10 CFR Part 50, 1
Appendix A.
The NRC will place a similar amount of stations in the aren between the two rings designated in Table 1.
i NOTE Assessment Branch Technical Position (pages a through 16 of the RadiologicalRAB-Guidance on the subjects contained on i
based on operating Experience since Revision 1 was published in 1979.
The j
current staff guidance for the following items has been incorporated in the Section 3/4-12 and Section 6 Controls of NUREG-1301 and 1302.
Reporting Requirement l
Table 1: Operational Radiological Environmental Monitoring Report l
Table 2: Detection capabilities for Environmental Sample Analysis Table 4: Reporting Levels for Radioactivity Concentrations in Environmen-l tai Sar.ples l
The following items remain unchanged:
Footnote to Table 1 on page 10 l
Tabic 3 of page 14 f
Figure 1 of page 16 l
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Pages 5, 6, 7, 8, 9,11,12,13,15 The above pages have been superceded by text and tables in NUREG-1301 and 1302, j
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[90]
f IABLE t (Continued)
Note:
In addition to the above guidance for operational monitoring, the following material is supplied for guidance on preoperational programs.
l Preoperational Environmental Surveillance Program f
A Preoperational Environmental Surveillance Program should be instituted two years prior to the institution of station plant operation.
The purposes of this program are:
1.
To measure background levels afwl their variations along the anticipated critical pathways in the area surrounding the station.
2.
To train personnel 3.
To evaluate procedures, equipment and techniques The elements (sampilng media and type of analysis) of both preoperational and operational programs should be essen-l tially tne same. The duration of the preoperational program, for specific media, presented in the following table chould be followed:
Duration of Preoperational Sampling Pre 2 ram for Specific Media g
6 months 1 year 2 years
. altborne lodine
. airborne particulates
. direct radiation
. fodine in milk (whfie
. milk (remaining analyses)
. fish and invertebrates animals are in pasture)
. surface water food products i
. groundwater
. sediment from shoreline j
. drinking water
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TA8tf 3 f
[NVIR0094 ENTAL RADIOLOGICAL 100I10 RING PROGRAM ANNUAL SUPO4ARY Name of Facility Docket No.
Location of Facility Reporting Peric,d _y (County, State)
Medium or Type and tower Limit All Indicator tocation with Highest Controllocatgons Number of -
Pcthway 5ampled Total Number of location Annual Mean Mean (f)
Nonroutine f
(tinit of of Analyses Detection, Mean(f)g Name Mean (f)b Range Reported
}
Measurement)
Performed (LLO)
Range Distance &
Range Measurements j
Ofrection t
I Air Partica-
[
Ictes (pCl/m )
Cross p 416 0.01 0.06(200/312) Middletown 3.10 (5/52) 0.08 (8/104) 1 j
i (0.05-2.0) 5 miles 340' (0.08-2.0)
(0.05-1.40) l
~ y-5pec. 32 137
- 0.01 0.05 (4/24)
Smithyllie 0.08 (2/4)
<LLO 4
e U
(0.03-0.13) 2.5 miles 160* (0.03-2.0) l r
- 131, 0.07 0.12 (2/24)
Podunk 0.20 (2/4) 0.02 (2/4) 1 5
i (0.09-0.18) 4.0 alles 270* (0.10-0.31)
Fish pCl/kg
[
(wet weight) y-Spec. 8 L
137,
IM
<M g
<M M (1/4) 0
{
t 134,
1M
<M g
<M 0
l 60 1
( 4)
Iver He o unn 4 0
Co i
(150-225)
- See Table 2, note b.
l hanandrangebasedupondetectablemeasurementsonly. Fraction of detectable measurements at specified locations is indicated in parentheses.
(f)
Note: The example data are provided for.111estrative purposes only.
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1 Figure 1 (This figure shall be of a suitable scale to show the dista.'.ce and direction j
of each monitoring station.
A key shall be provided to indicate what is sampled at each location.)
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[93]
APPENDIX B
" Appendix B - General Contents of the Offsite Dose Calculation Manual (ODCM) (Revision 1, February 1979)" to the paper authored by C. A. Willis and F. J. Congel, " Status of NHC Radiological Effluent Technical Specification Activities" presented at the Atomic Industrial Forum Conference on NEPA and Nuclear Regulation, October 4-7, 1981, Washington, D.C.
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[943
APPENDIX B GENERAL CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (ODCM*)
(Rev.1. Fitbruary 1979)
Section 1 - Set Points 4
Provide the equations and methodology to be used at the station or unit for each alarm and trip set point on each ef fluent release point according to the i
Specifications 3.3.3.8 and 3.3.3.9., The instrumentation for each alarm and trip set point, including radiation monitoring and sampling systems and ef fluent control features, should be identified by reference to the FSAR (or Final Hazard Summary). This infomation should be consistent with the recommendations of Section 1 of Standard Review Plan 11.5, NUREG-75/087, (Revision 1).
If the alarm and/or trip set point value is variable, prwide the equation to determine the set point value to be used, based on actual release conditions, that will assure that the Specification is met at each release point; and provide the value to be used when releases are not in progress.
If dilution or dispersion is used, state the onsite equipment and measurement method used during release, the site related parameters and the set points used to assure that the Specification is met at each release point. The fixed and variable set points should consider the radioactive ef fluent to have a radionuclide distribution represented by nomal and anticipated operational occurrences.
Section 2 - Liquid Effluent Concentration Prwide the equations and methodology to be used at the station or unit for each liquid release point according to the Specification 3.11.1.1.
For cystems with continuous or batch releases, and for systems designed to monitor and control both continuous and batch releases, prwide the assump-tions and parameters to be used to compare the output of the monitor with the liquid concentration specified. State the limitations for combined i
discharges to the same release point.
In addition, describe the method and assumptions for obtaining representative samples from each batch and use of previous post-release analyses or composite sample analyses to meet the Specification.
Section 3 - Geseous Effluent Dose Rate, Provide the equations and methodology to be used at the station or unit for each gaseous release point according to Specification 3.11.2.1.
Consider the various pathways, release point elevations, site related parameters and radionuclide contribution to the dose impact limitation. Prwide the
- The format for the ODCH is lef t up to the licensee and may be simplified by tables and grid printout. Each page should be numbered and indicate the l
facility approval and effective date.
[95]
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2-dose factors to be used for the identified radienuclides released.
Provide the annual average dispersion values (X/Q and D/Q), the site specific para-meters and release point elevations.
Section 4 - Liquid Effluent Dose Provide the equations and methodology to be used at the station or unit fer each liquid release point according to the dose objectives given in Speci-fication 3.11.1.2.
The section should describe how the cose contributions are to be calculated for the various pathways and release points, the equa-tions and assumptions to be used, the site specific parameters to be measured and used, the receptor location by direction and distance, and the method of estimating and updating cumulative doses due to liquid releases. The dose factors, pathway transfer factors, pathway usage factors, and dilution fac-tors for the points of pathway origin, etc., should be given, as well as receptor age group, water and food consumption rate and other factors assumed or measured.
Provide the method of determining the dilution factor at the discharge during any liquid effluent release and any site specific parameters used in these determinations.
Section 5 - Gaseous Effluent Dose Provide the equations and methodology to be used at the station or unit for each gaseous release point according to the dose objectives given in Specifications 3.11.2.2 and 3.11.2.3.
The section should describe how the dose contributions are to be calculated for the various pathways and release points, the equations and assumptions to be used, the site specific parameters to be measured and used, the receptor location by direction and distance, and the method to be used for estimating and updating cumulative doses due to gaseous releases. The location, direction and distance to the nearest resi-dence, cow, goat, adat animal, garden, etc., should be given, as well as receptor age group, crop yield, grazing time and other factors assumed or measured. Provide the method of determining oispersion values (X/Q and D/Q) for releases and any site specific parameters and release point elevations used in these determinations.
Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projecting doses due to effluent releases for the normal and alternate pathways of treatment according to the specifications, describing the com4 ponents and subsystems to be used.
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Section 7 - Operability of Equipment I
Provide a flow diagram (s) defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems that are l
to be maintained and used, pursuant to 10 CFR 50.36a, to meet Technical Specifications 3.11.1. 3, 3.11. 2. 4 and 3.11. 3.1.
Subcomponents of packaged i
equipment can be identified by a list. For operating reactors whose con-i struction permit applications were filed prior to January 2,1971, the flow diagram (s) shall be consistent with the infomation prwided in confonnance with Section V.B.1 of Appendix ! to 10 CFR Part 50.
For OL applications whose construction permits were filed af ter January 2,1971, the flow diagram (s) shall be consistent with the infomation prwided in Chapter 11 j
of the Final Safety Analysis Report (FSAR) or amendments thereto.
Section 8 - Sample Locations Provide a map of the Radiological Environmental Monitoring Sample Locations indicating the numbered sampling locations given in Table 3.12-1.
Further clarification on these numbered sampling locations can be prwided by a list, indicating the direction and distance from the center of the building com-1 plex of the unit or station, and may include a discriptive name for identi-fication purposes.
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APPENDjXC GENERIC LETTER 89-01 IMPLEMENTATION OF PROGRAMMATIC CONTROLS FOR RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN THE ADMINISTRATIVE CONTROLS SECTION OF THE TECHNICAL SPEClflCATIONS AND THE RELOCATION OF PROCEDURAL DETAILS OF RETS TO THE OFFSITE DO5E CALCULATION MANUAL OR TO THE PROCESS CONTROL PROGRAM
[98]
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umTro STATES NUCLE AR REGULATORY COMMISSION e
,f usmorow, o. c. rosso l
k *%
/
January 31, 1989 i
i TO ALL POWER REACTOR LICENSEES A!1D APPLICANTS
SUBJECT:
IMPLEMEF1ATION OF PROGRAMMATIC C0ldTROLS FOR RADIOLOGICAL EFFLUENT TECHb! CAL SFECIFICAT10fiS IN THE ADMINISTP.ATIVE CONTROLS SECTION OF THE TECHNICAL SPECIFICATIONS AND THE RELOCATION OF PROCEDURAL DETAILS OF RETS TO THE OFFSITE OOSE CALCULATION MANUAL OR TO THE PROCESS E0hTROL PROGRAM (GENERIC LETTER 89-01)
The NRC staff has examined the contents of the Radiological Effluent Technical Specifications (RETS) in relation to the Comission's interim Policy Statement en Technical Specification Improvesnents. The staf f has determined that pro-gramatic controls can be imp (lemented in the Administrative Controls section of the Technical Specifications TS) to satisfy existing regulatory reouirements for RETS. At the same time, the procedural details of the current TS on radio-active effluents and radiological environmental monitoring can be relocated to theOffsiteDoseCalculationManual(ODCM).
Likewise, the procedural details of the current TS on solid radioactive wastes can be relocated to the Process Control Program (PCP). These actions staiplif.y the RETS, meet the regulator.y recuirements for radioactive effluents and radiological environLental monitor-ing, and are provided as a line-item improvenient of the TS, consistent with the goals of the Policy Statement.
New programatic controls for radioactive effluents and radiological environ-mental monitoring are incorporated in the TS to conform to the regulatory recuirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix !
to 10 CFR Part 50.
Existing programatic reouirements for the PCP are being retained in the TS. The procei ral details included in licensees' present TS on radioactive effluents, solid radioactive wastes, environmental monitoring, and associated reporting reouirements will be relocated to the ODCM or PCP as appropriate. Licensees will handle future changes to these procedural details in the ODCM and the PCP under the administrative controls for changes to the ODCH or PCP. Finally, the definitions of the ODCM and PCP are updated to reflect these changes. provides guidance for the preparation of a license amendment re-ouest to implement these alternatives for RETS. provides a list-ing of existing RETS and a description of how each is addressed. Enclosure 3 provides model TS for programatic controls for RETS and its associated report-ing reavirements.
Finally, Enclosure 4 provides model specifications for retaining existing reoutrements for eFplosive gas monitoring instrumentation recuirements that app 1v en a plant-specific basis. Licensees are encouraged to propose changes to TS that are consistent with the guidance provided in the enclosures. Conforming acendment reouests will be expeditious 1v reviewed by l
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January 31, 1989 the NRC Project Manager for the facility.
Proposed amendments that deviate from this guidance will require a longer, more dettiled review.
Please contact the appropriate Project Manager if you have questions on this matter.
Sincerely, av a Acting Associate D ctor for Projects Office of Nuclear Reactor Regulation
Enclosures:
1 through 4 as stated
[100)
Generic Letter 89-01 ENCLOSURE 1 GUIDANCE FOR THE IMPLEMENTATION OF PROGRAKMATIC CONTROLS FOR RETS IN THE ADMINISTRATIVE CONTROLS ".ECTION OF TECHNICAL SPECIFICATIONS AND THE RELOCATION OF PROCEDURAL DET/1LS OF CURRENT RETS TO THE l
OFFSITE DOSE CALCULATION MANUAL OR PROCESS CONTROL PROGRAM i
INTRODUCTION l
This enclosure provides guidance for the preparation of a license amendment request to implement programmatic controls in Technical Specifications (TS) for radioactive effluents and for radiological environmental monitoring con-i forming to the applicable regulatory requirements.
This will allow the reloca-tion of existing procedural details of the current Radiological Effluent Technical Specifications (RETS) to the Offsitt Dose Calculation Manusi (ODCH).
Procedural details for solid radioactive wastes will be relocated to the Process Control Program (PCP).
A proposed amendment will (1) incorporate pro-grammatic controls in the Administrative Controls section of the TS that sat-isfy the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a. and Appendix I to 10 CFR Part 50, (2) relocate the existing procedural details in current specifications involving radioactive ef fluent monitoring instrumenta-tion, the control of liquid and gaseous effluents, equipment requirements for liquid and gaseous effluents, radiological environmental monitoring, and radio-logical reporting details from the TS to the ODCM, (3) relocate the definition of solidification and existing procedural details in the current specification on solid radioactive wastes to the PCP, (4) simplify the associated reporting requirements, (5) simplify the administrative controls for changes to the ODCM and PCP, (6) add record retention requirements for changes to the ODCH and PCP, and (7) update the definitions of the ODCM and PCP consistent with these changes.
The NRC staff's intent in recommending these changes to the TS and the reloca-tion of procedural details of the current RETS to the ODCH and PCP is to ful-fill the goal of the Commission Policy Statement for Technical Specification Improvements.
It is not the staff's intent to reduce the level of radiological effluent control.
Rather, this amendment will provide programmatic controls for RETS consistent with regulatory requirements and allow relocation of the procedural details of current RETS to the ODCH or PCP.
Therefore, future changes to these procedural details will be controlled by the controls for changes to the ODCM or PCP included in the Administrative Controls section of the TS. These procedural details are not required to be included in TS by 10 CFR 50.36a.
DISCUSSION
- to Generic Letter 89-provides a summary listing of specifica-tions that are included under the heading of RETS in the Standard Technical Specifications (STS) and their disposition.
Most of these specifications will be addressed by programmatic controls in the Administrative Controls section of the TS. Some specifications under the heading of RETS are not covered by the new programmatic controls and will be retained as requirements in the existing plant TS.
Examples include requirements for explosive gas monitoring instru-centation, limitations on the quantity of radioactivity in liquid or gaseous holdup or storage tanks or in the condenser exhaust for BWRs or limitations on explosive gas mixtures in offgas treatment systems and storage tanks.
i I
[101)
Generic Letter 8 b 01 Enclosure 1 Licensees with nonstandard TS should follow the guidance provided in Enclo-sure 2 for the disposition of similar requirements in the foreat of their TS.
Because solid radioactive vastes are addressed under existing programatic controls for the Process Control Program, which is a separate program from the new programmatic controls for liquid and gaseous radioactive effluents., the requirements for solid radioactive wastes and associated solid waste reporting requirements in current TS are included as procedural details that will be relocated to the PCP as part of this line-item improvement of TS.
Also, the staff has concluded that records of licensee reviews performed for changes made to the ODCM and PCP should be documented and retained for the duration of the unit operating license.
This approach is in lieu of the current requirements that the reasons for changes to the ODCM and PCP be addressed in the Semiannual Effluent Release Report.
The following items are to be included in a license amendment request to imple-ment these changes.
First, the model specifications in Enclosure 3 to Generic Letter 89-should be incorporated into the TS to satisfy the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50.
The definitions of the ODCM and PCP should be updated to reflect these changes.
The programmatic and reporting requirements are general in nature and do not contain plant-specific details.
Therefore, these changes to the Administrative Controls section of the TS are to replaer corresponding requirements in plant TS that address these items.
They should be proposed for incorporation into the plant's TS without change in substance to replace existing requirements.
If necessary, only changes in format should be proposed.
If the current TS include requirements for explosive gas monitoring instrumentation as part of the gaseous effluent monitoring instrumentation requirements, these require-rents should be retained. to Generic Letter 89-provides model specifications for retaining such requirements.
i Second, the procedural details covered in the licensee's current RETS, consist-ing of the lim..ing conditions for operation, their applicability, remedial actions, surveillance requirements, and the Bases section of the TS for these requirements, are to be relocated to the ODCM or PCP as appropriate and in a manner that ensures that these details are incorporated in plant operating pro-cedures. The NRC staff does not intend to repeat technical reviews of the re-located procedural details because their consistency with the applicable regula-tory requirements is a matter of record from past NRC reviews of RETS.
If licensees make other than editorial changes in the procedural details being transferred to the ODCM, each change should be identified by markings in the margin and the requirements of new Specification 6.14a.(1) and (2) followed.
Finally, licensees should confirm in the amendment request that changes for relocating the procedural details of current RETS to either the ODCM or PCP have been prepared in accordance with the proposed changes to the Administra-tive Controls section of the TS so that they may be implemented imediately upon issuance of the proposed amendment.
A complete and legible copy of the revised ODCM should be forwarded with the amendment request for NRC use as a reference. The NRC staff will not concur in or approve the revised ODCH.
[102)
l Ceneric Letter 89-01 Enclosure 1 I
l Licensees should refer to ' Generic Letter 89- " in the Sub.iect line of license amendrent recuests irplementing the guidance of this Generic Letter. This will j
facilitate the staff's tracking of licensees' responses to this Generic Letter.
I
SUMMARY
l The license amenerrent recuest for the line-item improvements of the TS relative to the RETS will entail (1) the incorporation of progracrutic controls for radioective effluents and radiological environmental monitoring in the Admin-istrative Controls section of the T5, (2) incorporatation of the procedural i
4 details of the current RETS in the ODCM or PCP as appropriate, and (3) confirm.
i ation that the guidance of this Generic Letter has been followed.
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[103)
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DISPOSITION OF SPECIFICATIONS AND ADMINISTRATIVE CONTROLS INCLUDED UNDER IHE HEADihG OF RLi$ IN THE SIANDARD lt0Hhl0AL $PECIFICATIONS T
E SPECIFICATION TITLE DISPOSITION OF EXISTING SPECIFICATION i
1.17 0FFSITE DOSE CALCULATIDM MANUAL Definition is updated to reflect the change in scope l
of the ODCM.
O 1.22 PROCESS CONTROL PROGRAM Definition is updated to reflect the change in scope of the PCP.
?
o
~
1.32 SOLIDIFICATION Definition is relocated to the PCP.
t 3/4.3.3.10 RADIDFCTIVE LIQUID EFFLUENT Progresumatic controls are included in 6.8.4 g. Item 1).
l MONITORING INSTRUMENTATION Existing specification procedural details are relocated l
to the 00CM.
i 3/4.3.3.11 RADI0ACTI?E GASEOUS EFFLUENT Prograsenatic controls are included in 6.8.4 g. Item 1).
MONITORING INSTRUMENTATION Existing specification procecural details are relocated i
to the 00CM. Existing reevirements for explosive gas
[
monitoring instrumentation should be retained. Model C
specifications for these reovirements are provided in g
m 3/4.11.1.1 LIQUID EFFLUENTS: CONCENTRATION Prograssistic controls are included in 6.8.4 g. Items 2) and 3). Ex1 sting specification procedural details are i
relocated to the 00CM.
3/4.11.1.2 LIQUID EFFLUENTS: DOSE Prograsenatic controls are included in 6.8.4 g. Items 4) and 51. Existing specification procedural details are relocated to the 00CM.
3/4.11.1.3 LIQUID EFFLUENTS: LIQUID Prograsumatic controls are included in 6.8.4 g. Item 6).
RADWASTE TREATMENT SYSTEM Existing specification procedural details are relocated to the 00CM.
3/4.11.1.4 LIQUID NOLDUP TANKS Existing specification reevirements to be ret'ained.
S 9
P@
- = _..=.
1 1
~4 DISPOSITICW OF SPECIFICATIONS M0 ADMINISTFATIVE CONTROLS l
IKt03ED UNDER THE HEADIE OF RE15 In 1M STANDAFD TEcMulcAt SrtrIFicATIONS (Cont.)
T SPECIFICATION TITLE DISPOSITION OF EX1 STING SPECIFICATION 3/4.11.2.1 CASEOUS EFFt K NTS: DOSE RATE Programmatic controls are included in 6.8.4 g. Items 3) 7 i
and 71. Existing specification pouc;Liel details are j
relocated to the ODCM.
4 c
3/4.11.2.2 GASEOUS EFFLUENTS: DOSE-WOBLE Programmet1c controls are included in 6.8.4 g. Items 51 7
l GASES and 8). Existing specification procedural details are S
relocated to the CDCM.
q 3/4.11.2.3 GASEOUS EFFLUENTS: DOSE-10 DIRE-Progrannetic controls are included in 6.8.4 e. Items 5) j 131,10 DINE-133. TRITIUM, MD and 9). Esisting specification pi-GL.al dete11s are i
RADI3 ACTIVE MRTERIAL IN PARTICU-relocated to the ODCM.
i LAIE FOM I
3/4.11.2.4 GASEDUS EFFLUENTS: GASEOUS L.y. _
tic controls are included in 6.8.4 g. Item 61.
I RADMRSTE TREATMENT or Existing specification proc.ederal details are relocated i
VENTILATION EInp55T TREATMNT to the (WCM.
=
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6 ST5 TEM
=
3/4.11.2.5 EXPLOS1 E GAS MIITURE Existing specification reestrements should Le retained.
I 3/4.11.2.6 GAS 3TORAGE T3 K S Existing specificatten reestrements shesid be retained.
l 3/4.11.2.7 MIN CONDERSER (ONR)
Existing specification reemirements shesid me retained.
3/4.11.2.8 FilRGING MO ENTING (OUR Mark Il programmatic coctrals are incleded in 6.8.4 s. Item 10).
containments)
Eatsting specif t:.r-at procedural details are relocated j
to the 00CM.
i 3/4.11.3 SOLIO RMIORCTIM istSTES Existing specification procedural details are relocated i
to the PCP.
t y
3/4.11.4 R2010ACTIE EFFLOENTS: TOTAL F..,. -
_ tic controls are included in 6.8.4 3. Item 111.
DOSE Existing specification procedural details are relocated,
3 to the 00CM.
4 i
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[106)
_______u
Generic Letter 89-01 TECHNICAL SPECIFICATIONS TO BE REVISED 1.17 DEFINITIONS: OFFSITE DOSE CALCULATION KANVAL 1.22 DEFINITIONS: PROCESS CONTROL PROGRAM 6.8.4 g.
PROCEDURES AND PROGRAM 5: RADI0 ACTIVE EFFLUENT CONTROLS 6.8.4 h.
PROCEDURES AND PROGRAMS: RADIOLOGICAL ENVIRONMENTAL HONITORING 6.9.1.3 REPORTING REQUIREMENTS: ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.4 REPORTING REQUIREMENTS: SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT 6.10 RECORD RETENTION E
6.13 PROCESS CONTROL PROGRAM (PCP) 6.14 0FFSITE DOSE CALCULATION KANUAL (ODCH)
MDDEL TECHNICAL SPECIFICATION REVISIONS (lo supplement or replace existing specifications) 1.0 DEFINITIONS OFF51TE DOSE CALCULATION MANUAL 1.17 The OFFSITE DOSE CALCULATION MANUAL (00CH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and itquid ef fluent monitoring Alarm / Trip Setpoints, anti in the conduct of the Environ-mental Radiological Monitoring Program.
1he ODCH shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the inforsation that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specificationt 6.9.1.3 and 6.9.1.4.
1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinatione to be made M ensure that process-ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground raquirements, and other requirements governing the disposal of solid radioactive waste.
(107)
Gentric Letter 89 01 Enclosure 3 6.0 ADMINISTRATIVE CONTROLS 6.8 FROCEDURIS AND PROGRAMS 6.8,4 The following programs shall be established, implemented, and maintained:
g.
. Radioactive Effluent Controls Prooram A program shall be provided confoming with 10 CFR 50.36a for the control of radioactive effluents and for naintaining the doses to HEMBER$ OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCH, (2) shall be implemented by operating procedures, and (3) shall in-clude renedial actions tn be taken whenever the program limits are exceeded.
The program shall ine.lude the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the
- ODCH, 2)
Limitations on the concentrations of radioactive material released in liquid ef fluents to UNRESTRICTED AREAS confoming to 10 CFR Part 20 Appendix B, Table !!, Column 2, 3)
Honitoring, sampling, and analysis of radioactive liquid sad gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCH, 4)
Limitations on the annual and quarterly doses or dose comitment to a MEMBE1 0F THE PUBLIC from radioactive materials in liquid ef fluents released from each unit to UNRESTRICTED AREAS confom-ing to Appendix 1 to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calindar quarter and current calendar year in accordance with the methodology and parameters in the ODCH at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous offluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
- i. imitations on the dose rate resulting f rom radioactive material released in gaseous effluents to areas beyond the SITE BDUNDARY conforming to the doses associated with 10 CFR Part 20 Appendix B. Table !!, Column 1, (108) t
Generic Letter 89 01 Enclosure 3 ADMIN 151RATIVE f.ONTROLS 6.8.4 g.
Radioactive Effluent Controls Program (Cont,)
8)
Limitations on the annt,a1 and quarterly air doses resulting from no*ie p ies released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Apoendix ! to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a HEMBER OF THE PUBLIC from lodine-131, Iodine 133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the Si1E BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,
- 10) Limitations on venting and purging of the Mark !! containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable (BWRs w/ Mark 11 containments),
and
- 11) Limitatinns on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
h.
Radiological Environmental Monitorina Program A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall previde (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in th' 00CH, (2) conform to the guidance of Appendix 1 to 10 CFR Part 50, and (3) include the following:
1)
Honitoring, sampling, analysis, and repor'ing of radiation and radionuclides in the environment in accorc.ance with the method-ology and parameters in the ODCH, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the maasurements of radioactive enterials in environmental sample matrices are performed as part of the quality assurance pro-gram for environmental monitoring.
(109]
unusa usu a
Generic Letter 89t1 Enclosure 3 ADHlNISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.3 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Honitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCH and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR Part FO.
SEM1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT **
6.9.1.4 The semiannual Radioactive Effluent Reiease Report cover'ing the oper-ation of the unit during the previous 6 months of operation shall be submitted within 00 days af ter January 1 and July 1 of each year.
The report shall in-clude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCH and PCP and (2) in con-formance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 50, 6.10 RECORD RETENTION 6.10.3 The following records shall be retained for the duration of the unit Operating License:
Records of reviews perforced for changes made to the OFFSITE DOSE o.
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
6.13 PROCESS CORTROL PROGRAM (PCP)
Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retain-ed as required by Specification 6.10.30.
This documentation shall contain:
1)
Suf ficient information to support the change together with the appropriateanalysesorevaluationsjustifyingthechange(s)and
- A single submittal may be made for a multi-unit station.
- A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to ell units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
[1103
Ceneric Letter 89 01 Enclosure 3 f
AD41N15TRAT!vE CONTROLS 6.13 PROCts$ CONTROL PROGRAM (PCP) (Cont.)
2)
A determination that the change will maintain the overall con-formance of the solidified waste product to existing require-ments of Federal, State, or othsr applicable regulations.
b.
Shall become ef fective af ter review and acceptance by the (URG) and the approval of the Plant Manager.
6.14 OrFSITE 00$E 0;ALCULATION MANUAL (ODCM)
Changes to the ODCH:
a.
Shall be dccumented and records of reviews perfomed shall be retain-ed as required by Specification 6.10.30.
This documentation shall contain:
1)
Suf ficient infomation to support the change together with the appropriate analyses or evaluations justifying the change (s) and
=
2)
A determination that the change will maintain the level of
(
radioactive ef fluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adverseiy impact the accuracy or reliability of effluent, dose, or setpoint calculations, b.
Shall become ef fe tive af ter review and acceptance by the (URG) and the approval of the Plant Manager.
c.
Shall be submitted to the Comission in the fom of a complete, legible copy of the entire ODCH as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCH was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
[111)
1 Generic Letter 89 01 MODIFICATION OF THE SPECIFICATION FOR RADIDACTIVE GASEOUS
[FFLUENT MONITORING INSTRUMENTATION 10 RETAIN REQUIREMENTS FOR EXPLOSIVE GAS H3NITORING INSTRUMENTATION
_ INSTRUMENTATION E X Pl.051VE RAB16AETIVE GA$EeWS EFFtBENT MONITORING INSTRUMENTAT10N LIMITING CONDITION FfR OPERATION explosive 3.3.3.11 The radienttive gaseens-effinett monitoring instrumentation channels shown in Table 3.3-13 shall be OFERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications-S;11;t:1-and 3.11.2.5 are not exceeded.
The Aiarm/ Trip Setpoints-of-these-channeis meeting 5pecification 5:11;Ett theti be determined and edjusted in accordance with-the methodoiegy and parcmeters-in the 6BEHr APPLICABILITY: As shown in Table 3.313 ACTION:
explosive a.
With an radioactive gaseous effinent monitoring instrumentation channeT Alarm / Trip Setpoint less conservative than required by the above specification;-immediately-sespend-the release-of radioactive gaseens-efficentsamenitored by the effected channeit-or declare the channel inoperable and take the ACTION shown in Table 3.3 13.
explosive b.
With less than the minimum number of radioactive gaseous-effisent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3 13.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful explain in the-next-Semi-annesi Radioactive Effisent Reiense-Report prepare and submit a Special Repor$ to the Commission pursuant to 5pecification 679:!;4 6.9.2 to explain why this inoperability was not corrected in a timely
- manner, The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS explosive 4.3.3.11 Each radienetive gaseens effisent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, 56WREE EHEEK; CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.
Sample STS 3/4 3-(n)
[112]
i
TABLE 3.3-13 e
y EXPT 051YE pap 49A644VE GASEQUE FEFLUFNT NORITORING INSTFLEENTATION g
o h
MIKIMtH CI:ANNEL%
7 INSTRtmENT OPERABLE APPLICAElliTy ACTION 1.
(Notused) 7 o
2A. WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System (for systems designed to withstand the effects of a hydrogen explosion) 49 Hydrogen Monitor (Automatic Control) 1 a.
49 b.
HydrogenorOxygenMonitor(Process) 1 l
- 28. WASTE GAS HOLDUP SYSTEM Explosive Gas
%nitoring System (for systems not designed m
l y
A to withstand the effects of a hydrogen i
g explosion) j 50, 52 l
~
C a.
Hydrogen Monitors (Automatic Control.
2 redundant) 50 b.
Hydrogen or Oxygen Monitors (Process, 2
dual)
E S
S
.'i b
l Generic Letter 89-01 Enclosure 4 TABLT' 3l3-13 '(L' nt'i6ui3) o (Not used)
During WASTE GAS HOLDUP $YSTEM operation.
ACTION STATEMENTS ACTION 45 -
(Not used)
ACTION 46 -
(Not used)
ACTION 47 -
(Not used)
ACTION 4B -
(Not used)
ACTION 49 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this WASTE GAS HOLDUP SYSTEM may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 50 -
With the number of channels OPERABLE one less than requf*ed by the Minimum Channels OPERABLE requirement, operation of his system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With both channels inoperable, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassie; operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
ACTION 51 -
(Not used)
ACTION 52 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.
Sample STS 3/4 3-(n+2)
[114)
TABLE 4.3-9 3
m EXPtosIVE rap 4pAGuv; LASECUS FFFLUFMT MONITORING INSTRtFE*:TATION SURYElttAMCE REQUIREMEMTS g
5 CHAMMEL MODES FOR WICH h
CHAMMEL 50VRG5 CHAMMEL OPERATIONAL SURTElttANCE 4
INSTFtHENT CHECK _
GWEGr. _ CALIBRATION TEST IS FEQUIRED a>
S 1.
(Not used) 2A. WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System (for systems designed to withstand the effects of a hydrogen explosion) a.
Hydrogen Monitor D
N.A, Q(4)
M (Automatic Control) o 1
s C
b.
N.A, Q(4) or Q(5)
M A
(Process) a
- 25. WASTE GAS HOLDUP SYSTEM E7 plosive ei Gas Monitoring System (for systems not designed to withstand the effects of a hydrogen cipioston) a.
Hydrogen Monitors D
N,A, Q(4)
M (Automatic Control, redundant) b.
N,A, Q(4)orQ(5)
M (Process, dual) 7 2.
Gweric Letter 89- 01 Enclosure 4 TABLE 4.3 9 (Continued)
TABLE NOTATIONS a
(Not used)
During WASTE GAS HOLDUP SYSTEM operation.
(1) (Not used)
( 2 ',
(Not used)
(3) (Not used)
(4) The CHANNEL CALIBRA110N shall include the use of standard gas samples containing a nominal:
a.
One volume percent hydogen, balance nitrogen, and c.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent oxygen, balance nitrogen, and b.
Four volume percent oxygen, balance nitrogen.
Sample STS 3/4 3-(n+4) c (116)
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Standard Radiological Effluent Controls for Boiling Water Reactors 3
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This report contains guidance which nuy be voluntarily used by licensees who choose to inplenent the provision of Generic Letter 89-01, which allows Radiological Ef flu-ent hchnical Specifications (RETS) to be renoved from the main body of the Technical Speci21 cations and placed in the Of fsite Dose Calculation ihnual (ODCM). Guidance is provided for Standard Ef fluent Controls definitions, Controls for effluent nonitoring instru.nentation, Controls for ef fluent releases, Conti.ols for radiological environ-mental nonitoring, and the basis for Controls.
Guidance on the formulation of RETS has been available in draf t form (!JUREG-0472 and
-0473) for a number of years; the current offort simply recasta those RETS into Standard Radiological Effluent Controls for application to the ODOM. Also included for completeness ares (1) radiological environmental nonitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, !bvember 1979); (2) exieting OD'M guidance; and (3) a reproduction of Generic Letter 89-01.
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