ML20106A077
| ML20106A077 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/31/1984 |
| From: | Duce S, Mandler J, Serrano W EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML20101M069 | List: |
| References | |
| CON-FIN-A-6459 EGG-PBS-6628, NUDOCS 8406270044 | |
| Download: ML20106A077 (36) | |
Text
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EGC-?BS-6528 pat!0 LOGICAL EFFLUEtiT TECHNICAL SPECIFICATIONS (RETS) If7LEP'ENTAT10N - ARKANSAS NUCLEAR ONE UNITS 1 AfD 2 William Serrano Stephen M. Duce John W. i'andler Ferrol B. Sirrpson Thomas E. Young Published
?tay 1984 EG&G Idaho, Inc.
l Prepared for the i
NUCLEAR REGULATORY C0fNISSION Under DOE Contract No. DE-AC07-76lC01570 j
FIN No. A6459 i
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d ABSTFACT A review of the Radiological Effluent Technical Specifications (RETS) of the Arkansas Nuclear One Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, " Preparation of Radiclogical Ef fluent Technical Specifications for Nuclear Power Plants," and Draf t 7
of NUREG-0472, Revision 3, " Radiological Ef fluent Technical Specifications fer Pressurized llater Reacters." Draft submittals were discussed with the Licensee by both EG&G and the NRC staf f until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dese Calculation Manual and Process Control 11anual were reviewed and generally found to be in compliance with the f;RC review guidelines.
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FCRENCRD This Technical Evaluation Report was prepared by EG&G Idaho,'inc, under a contract with the U, S. FJuclear Regulatory Commissicn (Of fice of fluclear Reactor Regulation, Division of Systems integration) for technical assistance in support of NRC operating reacter IIcensing actions. The
' technical evaluation was conducted in accordance with criteria established by the NRC, O
11
C0riTEi1TS E.1 1 ABSTEAC~..............................
I FC R E r:C RC..............................
1.
INTRODUCTION..........................
1 1.1 Purpose of the Technical Evaluation............
1 1.2 Generic issue Background I
1.3 P l ant-Speci f ic Background.................
4 2.
REVIEW CFITEFIA 6
3.
TECHN I CA L E VA L UAT I ON,,
8 3.1 General Description of Radiological Ef fluent System.
8 3.2 Radictogical Effluent Technical Specifications 10 3.3 Of f site Dose Ca lcu lation t'anua l..............
22 3.4 Process Control Program.
24 4
CONCLU$l0NS 25
- 5. REFERENCES...........................
29 FIGURES 1.
Arkansas Units 1 and 2 radicactive liquid effluent release paths 9
2.
Arkansas Units 1 and 2 radioactive gaseous effluent release paths 11 TAELES 1.
CORRESPCNDEf;CE OF PROVISIONS OF NUREG-0472. TFE LICENSEE'S CURRENT TECHNICAL SPECIFICATICNS AND TPE LICENSEE'S PROPOSAL FCR ARKANSAS fiUCLEAR CNE UNIT 1 27 2.
COPPESP0f!CENCE OF PROVI SICNS OF t;UPEC-C472. THE LICEi1SEE'S CLRRENT TECHiilCAL SPECIFICATIONS AND THE LICEllSEE'S PEOPOSAL FOR ARKANSAS MUCLEAR ONE UNIT 2...............
23 iii
9 1.3 INTRODUCTICN 1.1 Puroese of the Technical Evaluation The purpose of this Technical Evaluation Report (TER) is to review and evaluate the proposed changes in the Technical Specifications of the Arkansas fluclear One Units 1 and 2 with regard to Radiological Effluent Technical Specifications (PETS), the proposed Offsite Dese Calculation l'anual (00CM) and the proposed Process Control Prograrr (PCP).
This evaluation used criteria proposed by the Nuclear Regulatcry Commission (NRC) staff in the model Technical Specifications for pressurized water reactors (PWRs), ilCREG-0472,[12 and subsequent revisions. This effort is directed toward the NRC objective of Implementing RETS which comply with the regulatory requirements, primarily those of 10 CFR Part 50, Appendix 1 [2] Other regulations pertinent to the control of effluent releases are also included within the scope of ccmpItence.
1.2 Sgnerte issue Backcround Since 1970, 10 CFR Part 50, Section 50.36.a,[3] " Technical Specifications en Effluents from Nuclear Power Reacters," has required licensees to provide Technical Specifications which ensure that radicactive releases will be kept as low as is reasonably achievable (ALARA).
In 1975, numerical guidance for the ALARA requirerrent was issued in 10 CFR Part 50, Appendix 1.
The IIcensees of all operating reacters were required [4] to submit, no later than June 4, 1976, their proposed ALARA Technical Specifications and information for evaluation in accordance with 10 CFR Part 50, Appendix 1 However, in February 1976, the fRC staff recorcended that proposals to modify Technical Specifications be deferred until the NRC corpleted the model RETS.
1
The ecdel RETS deal with radicactive waste management systems and environmental ronitoring. Although the model RETS address the 10 CFR Part 50, Appendix ! requirements, subsequent revistens include provisicns for addressing issues not covered in Appendix 1.
These provisions are stipulated in the folicwing regulations:
10 CFR Part 20,[5] " Standards for Protection Against e
. Radiation," Sections 20.105.c, 20.106.g and 20.405.c which require that nuclear power plants and other Licensees comply with 40 CFR Part 190,[6] " Environmental Radiation Protection Standards for Nuclear Power Operations," and submit reports to the NRC when the 40 CFR Part 190 limits have been or may be
- exceeded, 10 CFR Part 50, Appendix A,[7] " General Design Criteria for e
Nuclear Pcwer Plants," which contains Criterien 60--Control of releases of radicactive materials to the environment; Criterion 63- "onitoring fuel and waste storage; and Critericn 64- '.fonitoring radioactive releases.
10 CFR Part 50, Appendix B,[8] which establishes the quality e
assurance required for nuclear power plants.
The NRC position on the model RETS was established in f?ay 1978 when the NRC's Regulatory Requirements Review Committee approved the model RETS: NUREG-0472 for PWRs and NUREG-0473 for BWRs. Copies of the model RETS were sent to licensees in July 1978 with a request to submit proposed site-specific RETS on a staggered schedule over a six-month period.
Licensees respended with requests for clarifications and extensicns.
The Atomic Industrial Forum (AIF) formed a task force to cerment on the mcdel RETS. NRC staf f members first met with the AIF task ferce on June 17,1978. The model RETS were subsequently revised (Revisicn 1) to 2
reflect coerrents from the AIF and others. A principal change was the transfer cf much of the material concerning dose calculations from the rodel FETS to a separate document, the CDCI-1, Revistor. 1 of the model RETS was sent to licensees on Novemoer 15 and 16, 1978 with guidance (NUREG-0133)[93 for preparation of the RETS and the CDCfi and a new schedule for responses, again staggered over a six-month period.
Four regional seminars on the RETS were conducted by the NRC staff during November and December 1978. Subsequently, a preliminary copy of Revislen 2 of the model RETS and additional guidance on the ODCM and a PCP were issued in February 1979 to each utility at Individual meetings.
NUREG-0472, Revision 2[1] and NUREG-0473, Revision 2[10] were published in July 1979 and updated in January 1980 and February 1980, in response to the NRC's request, operating reactor licensees subsequently submitted initial proposals on plant CETS and the 00Cl1 Review leading to ultimate implementation of these d0cueents was initiated by the NRC in Septenber 1981 using subcontracted independent teams as reviewers.
As the RETS reviews progressed, feedback from the licensees led the f:RC to modify some of the provisions in the February 1, 1980 versicn of Revision 2 to clarify specific concerns of the licensees and thus expedite the reviews. Starting In April 1982, the NRC distributed revised versions
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of RETS In draf t form to the licensees during the site visits. The new guidance en these changes was presented in an AlF meeting on ffay 19, 1782.[113 Sone Interim changes regarding the Radiological Environrental l
"onitoring Section were Issued in August 1982.[123 With the l
Incorporation of these changes, the NRC issued Draf t 7 of Revisicn 3 of NUREG-0472[133 and NUREG-0473[143 in September 1982 to serve as new l
guldence fer the review teams.
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1.3 PIant-heet f f e Background j
By letters dated f* arch 9, 1979[15'J (ay 10,1979,[163 ' Arkansas Power and Light Company (AP&L), the Li a for linits 1 (Af0-1) 'and 2 (ANO-2) at the Arkansas ?!uclear One (Al-site, submitted proposed RETS for ANO-1 and ANO-2, respectively. A modified RETS proposal was l
resubmitted in July 1979. By letter dated July 9,1979, AP&L submitted the Of f s tte Dese Calculation ?'anual (ODC'4) for Af0-1&2. Revision A to the OCCM was submitted by letter dated October 22, 1979. A meeting on October 23, 1979 in Bethesda, t/aryland was held to discuss with AP&L the NRC's position on the submittals and the changes necessary to make the RETS and ODCM acceptable to the staff.[173 EG&G Idaho,'Inc. (EG&G), selected as an Independent task review team, Inittsted a review and evaluation of the July 1979 RETS submittals. The submittals were compared to the model RETS and assessed for compliance j
with the requirements of 10 CFR Part 50, Appendix ! and 10 CFR Part 50,
}
Appendix A.
The July 1979 ODC"4 submittal was reviewed and corrpared to the guIdeiInos of NUREG-0133.
Copies of the review comments on the ef fluent Technical Specifications j
and the CDC'.' were transmitted to NRC and the Lfcensee by letter dated t'ay 4,1982.[18] On June 22-24, 1982, a site visit to the AfD site was made for the purpose of discussing the comments and the changes necessary to l
the submittals ident! fled in the May 1982 review. The site visit discussion was sumtnerized in letter dated July 15,1982.[193 l
At the site visit it was agreed that AP&L would provide EGLG with l
draf t RETS and 00C5' submittels for revf ew and comment.[20] As egreed at the site vistt, EG&G would provide an annotated copy of the draf t i
submittal to AP&L prior to transmittal to NRC.[213 ft was also agreed at the site visit that EG&G would attempt to resolve via telephone t
conference with AP&L personnel the ccmments on the annotated copy. A telephone ccnference was made on November 22,1982E223 to discuss the t
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annotated ORTS subnittals and the 00C!t. 9ased on this telecen APal requested an extension to a response date In latter dated 'bvenbar 30, 1992.[23l A surmary of the subjects discussed during the flovember 22, 1982 telecon was transmitted to fiRC In letter dated Decenbar 15, 1982.[242 The unresolved RETS issues were discussed between EG&G personnel and fir. C. A. NIllis at a meeting in Albuquerque, flew fiexico on January 11, 1993. A summary of the discussion was prepared and transnitted to f:RC in letter dated January 24, 1c83.[253 in a letter dated September 30,19E3,[26] AP&L In response to an t'RC letter dated "ay 10, 19A3, submitted to NRC revised RETS for Atl0-1 and ANO-2 and an updated 00C*t. These proposals superceded all previous subnittals. EG&G reviewed the September 1983 submittels and transmitted review conments to f;RC In letter dated f!ovember 4, 1983.[273 The review coments were resolved between NRC and AP&L resulting in another RETS and 00C't submittal dated April 13,196:[28] and supplemented on April 26, 1984.[293 These April subnittals superceded all previcus subnittels. A surmary of the RETS resolutions agreed upon was transmitted in a memo to EG&G dated "ay 8,1984[303 allowing the E0aG review tea i to corrplete a TER for transmittal to NRC.
The April 13, 1984 CDC'A was reviewed and review comments transmitted
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to NRC In letter dated ffay 29,1984.[313 It was concluded that the CDC" contains methodology consistent with the guidelines of f!UREG-0133.
AP&L submitted a process Control Program (PCo) In letter dated February 21,1990.[323 The February 1980 2CP was not reviewed as it ccnststed of a vendors solidification procedures. A modified DCP was transnitted April 13,1984[283 which was cenparec[313 to the flRC review guidelines contained in letter dated January 3,1983.[332 It was j
concluded that the PCP contains a descriptive overview wnich provices I
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controlled guidance on the appropr! ate handling and solidifIcaticn of set radicactive wastes at Afl0 and is consistent with t'RC criterfs.
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1 2.0 REVIEN CRITERI A i
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j Review criterla for the RETS were provided by the NRC in three documents:
i 1.
IIUFEG-0472, RETS for P irs I
2.
f'UREG-0473, RETS for T.les 1
l 3.
fJUREG-0133, Preparation of RETS for Nuclear Power Plants Twelve essential criteria are given for the RETS and 00CM:
i-1.
All significant releases of radioactivity shall be controlled and 4
1 tsonitored.
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j 2.
Of fsite concentrattens of radioactivity shall not exceed the 10
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CFA Part 20, Appendix 3, Table 2 limits.[ d i
l 3.
'Offsite radiation doses shall be ALARA.
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4 Equipment shall be r9aintalned and used to keep of fsite doses
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ALAPA.
l 5.
Radwaste tank inventories shall be limited so that failures would l
not cause offsite deses exceeding 10 CFR Part 20 limits.
ydrogen and/or Oxygen concentrations in the waste gas system 5.
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shall be controlled to prevent explosive mixtures.
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'lastes shall be processed te shipping and burial ground criterle l
under a docurrented program, subject to quellty assurance 1
l verification.
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8.
An environmental monttcring program, including a land use census, shall be Implemented.
9.
The redwaste management program shall be subject to regular audits and reviews.
- 10. Procedures for control of IIquid and gaseous effluents shall be maintained and followed.
- 11. Periodic and special reports on environmental monitoring and on releases shall be submitted.
- 12. Offsite dose calculations sha!I be performed using documented and approved methods consistent with NRC methodology.
In addition to NUREG-0172 and NUREG-0473 and their subsequent revisions, the NRC staf f Issued guidelines,[35,36] clarif f cations,[37,383 and branch positions [39,40,413 establishing a pollcy that requires the licensees of operating reactors to meet the Intent, If not the letter, of the model RETS requirements. The NRC branch positions issued since the RETS Implementation review began havo clarlf f ed the rnodel RETS for operating reacters.
Review criteria for the CDCM are based on the following fiRC guidelines:
Branch Technical Position, " General Content of the Of fsite Dose Calculation fJanual";[42] HUREG-0133;[93 and Regulatory Guide 1.109.[433 The format for the 00Cf1 is lef t to the licensee and n.ay be slepilfled by tables and grid printouts.
Review criteria for the PCP is based on NRC review guldelines contained in letter dated January 3,1983.[333 7
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i 3.
TEOFI'ICAL EVALUATIO!!
C nerg' *escafotten of Cediclo-ical Effluent Fusten 3.1 9
This section briefiy describes the Ilquid and gaseous radwaste effluent treatment systens, release paths, and control systems installed at ANO-1 and Ail 0-2.
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3.1.1 Aadicac+fve Licuid Effluents There is a si1gle liquid radwaste release point for l' nit 1 and a single release' point for Unit 2; the liquid radweste discharge line.
The liquid radwaste discharge line at Unit 1 is the common release line to the circulating water discharge canal from the treated waste monitor tank, filtered waste monitor tank and the laundry drain tank.
The liquid radweste discharge line at Unit 2 is the common release line to the circulating water discharge canal from the boric acid condensate tank, waste condensate tanks, and the non-radioactive regenerative holdup tank.
The turbine ficer drains at each unit are normally released directly to the discharge canal. However, a high 16N activity in the nein stean lines from a primary-to-secondary leak will autenatically divert the ficor drain discharge to a neutralizing tank which is grab sampled before discharge, in addition, the condenser air ejecter noble gas monitor also triggers the administrative controls for isolation of the tank and grab samples on the turbine building surp.
A bicek diagram description of the systens is shcwn in Figure 1.
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-et-2 2 Ei di a 5 aE Figure 1.
Arkansas Units 1 and 2 radioactive liquid effluent release paths.
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The service water at both units is released directly to the dischargs canal. The corpenent ecoling water systen at each unit is a cicssd system and is cooled by the service water system. The radicactive components, I. e., the reacter building air cooler and decay heat cociers have process nonitors which provide alarm and will isolate these legs of the system from the discharge header.
The intermediate cooling water system is only drained during an outage and is sampled prior to release. This systex is also cooled by the service water system.
3.1.2 Radicactive Caseous Effluents There are three radioactive gaseous effluent release points for Unit 1 and four for Unit 2:
1.
The auxillary building ventilation system.
2.
The spent fuel pool area ventilation system.
3.
The reacter building purge and ventilation systen.
4 The Unit 2 auxiliary. building extension ventilation system.
The auxiliary building vent is also the release point for gaseous effluents from the radweste area, the condenser air ejector, and the waste gas holdup system.
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A block diagran description of the gaseous effluent discharge pathways is shown in Figure 2.
3.2 Rad'elecical E**iuant Technical ?neefficettens The following subsections describe the primary objectives of each section of the model RETS and a surrery of the commitments of the Licensee's RETS. A cross-reference between the numbering in the model PETS and the Licensee's RETS is contained in Table 1.
The chronologica; i
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ANO-1 or ANO-2 A
Auxiliary Suilding vent O
Auxiliary l
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, Building g
Waste Gas Holduo System Condenser Air Ejector Racwaste Area O^
A!O-1 or A!O-2 l
Spent Fuel Pool 7ent System A?O-1 or ANO-2 i
l Reactor Building
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P-and vent OA ANO-2 Auxiliary
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l Building E nension veat Eve e-Figure 2.
Arkansas Units 1 and 2 radioactive gaseous effluent release paths.
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sequence of the RETS review was described in the Plant-Specific Packground, Section 1.3 of this report.
3.2.1 Effluent instrurentatten The objective of the model RETS with regard to effluent instrumentation is to ensure that all significant liquid and gaseous radicactive effluents are monitored. The model RETS specify that all effluent monitors be operable with periodic surveillance and that alarm / trip setpoints be determined in order to ensure that offsite radioactive effluent concentrations do not exceed maximum permissible concentration (EPCs) listed in 10 CFR Part 20.
The licensee has provided radiation monitors for all ef fluent lines with potential for release of significant amounts of radioactivity in liquid or gaseous effluents.
3,2.1.1 Radicactive Licutd Effluent Instrumen+atten All liquid ef fluents from ANC-1 and ANO-2 that are potentially high in radioactivity are released through their respective liquid radweste effluent line and monitored with provisions for autcmatic termination of release. There is a flow monitor for the liquid radwaste discharge line and adequate instrument surveillance is performed on the monitoring system.
There are no steam generator blowdown monitors for either unit as they are once-thrcugh generators at ANO-1 and the blowdown is a closed system at ANC-2.
There are no mcniters on the service water discharge as the process monitors in the component cooling water system to isclate the source would have to fail and a leak in the component cooling-to-service water system would have to occur. Thus, it was determined the emission of service water nonitors met the intent of NUREG-0472.
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There are no monitors for the turbine building sumps as the sumps are pumped to a neutralizing tank upon a high 16N reading in the main steam lines. The neutralizing tanks are grab sampled and analyzed before discharge which was determined to meet the in+pnt of NUREG-0472.
3.2.1.2 Radioactive Casecus Effluent Irstrumentetien The radioactive gaseous ef fluent release points for ANO-1 and ANC-2 are fully monitored with adequate survelliance requirements.
The waste gas holdup system has a noble gas monitor which is operable during releases. The system discharges through the auxiliary building ventilation system which supplements the monitoring requirements.
The steam generator blowdown closed system at ANO-2 is off-gassed through the main condenser air ejector. Consequently the off-gasses are fully monitored at the auxiliary building vent.
3.2.1.3 Licuid and Gasecus frstrumente+ien Se+coints The licensee's Technical Specifications require that the concentration of radioactive material will be monitored "during releases via this pathway" for all monitored effluent paths. The setpoints at each release peint are established to prevent exceeding the release concentrations for l
liquid releases or corresponding dose rates for gaseous releases of 10 CFR Part 20 in unrestricted areas. The setpoints for the liquid and gaseous i
effluent instrumentation will be determined according to the Offsite Dose Calculation Manual (CDCM).
The !!censee's RETS submittal en IIquid and gaseous ef fluent i
i monitoring instrumentation has satisfied the provisions and meets the intent of NL' REG-0472.
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3.2.2 Cenc?n+r3+ ten end Oese m tes of Effluen+s e
3.2.2.1 Ltcufd Effluent Concentratten The Licensee's RETS Include a commitment to naintain the concentration cf radicactive liquid effluents released from the site to the unrestricted areas to within 10 CFR Part 20 limits, and if the concentration of liquid effluents to the unrestricted crea exceeds these limits, Imrediate action will te taken to restore concentrations to a value equal to or less than the siPC values specified in 10 CFR Part 20. Satch releases are sampled and analyzed periodically in accordance with an acceptable sempling and analysis program.
Therefore, the Licensee's RETS stbmittal on liquid ef fluent concentrations meets the intent of NUREG-0472.
3.2.2.2 Gasecus Effluent Dose e +e s
The Licensee's RETS include a commitment to maintain the gasecus dose rate from the site to within NUREG-0472 limits and if the concentration of gaseous ef fluents exceeds these limits or the equivalent dose rate values, it will be restored without delay to a value wittin these limits.
The radicactive gaseous waste sampling and analysis program provides adequate sampling and analysis of the discharges.
Therefore, the Licensee's RETS submittal en gaseous effluent dose rates meets the intent of NUREG-0472.
3 ?.3 Offsite Coses fece Effluen+s The cbjectives of the model PETS with regard to of fsite doses fron ef fluents are te ensure that of f site doses are kept ALARA, are in 14
compliance with the dose specifications of NUREG-0472 and are In accordance with 10 CFR Part 50, Appendix I and 40 CFR Part 190.
The Licensee's RETS Include a conmitment to:
1.
Limit the quarterly and annual dose due to liquid effluents to within the NUREG-0472 criteria 2.
Limit the quarterly and annual air dose due te noble gas releases to within the NUREG-0472 criteria 3.
Limit the quarterly and araual dose to any organ due to release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than eight days to within the NUREG-0472 criter.fa and to 4.
Limit the dose to any member of the public so as not to exceed the 40 CFR Part 190 requirements.
Therefore, the Licensee's RETS submittal on offsite doses from radicactive effluents meets the intent of MUREG-0472.
3.2.4 Effluent Treatrent The objectives of the model RETS wit'h regard to effluent treatment are to ensure that the radioactive waste treatment systems are used to keep releases ALARA and to satisfy the provisions for Technical Specificatiens
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l governing the maintenance and use of radweste treatment equipment.
The Licensee's RETS commits to using the liquid radweste treatment equipment when it is projected that the cumulative dose during a calendar quarter would exceed C.18 mrem to the total body or 0.625 mrem to any i
crgan. The dose projections shall be made in accordance with the ODCM at least once every 31 days.
The Licensee's RETS commits to using the ventilation exhaust treatment system when projected air doses due to gaseous effluent releases 15
would exceed 0.625 mrad for gamma radietion and 1.25 mrcd for beta radiation or when the projected dose due to lodine-131, tritium, and radienuclides in particualte ferm with half-lives greater than eight days would exceed 1.0 mrem to any organ over a calendar quarter.
When degasifying the reacter coolant system the gaseous radweste treatment system shall be used when projected air doses due to gaseous releases to unrestricted areas would exceed 0.625 mrad for gamma radiation and 1.25 mrad for beta radiation over a calendar quarter.
The dose projections due to gaseous releases shall be made in accordance with the 00CM at least once every 31 days.
Therefore the Licensee's RETS submittal on the usage of liquid and gaseous radweste treeteent systems meets the intent of NUREG-0472.
3.2.5 Tank Inventerv Limf+s The objective of the model RETS with regard to a curie limit on liquid-containing tanks is to ensure that in the event of a tank rupture, the concentrations in the nearest potable water supply and the nearest surface water supply in an unrestricted area would not exceed the limits of 10 CFR Part 20, Appendix B Table II. The objective of the model RETF with regard to a curie limit en gas-containing tanks is to ensure that in the event of an uncontrolled release of the tank's contents the resulting total body exposure to an Individual at the nearest exclusion area boundary will not exceed 0.5 rem.
l The Licensee's RETS include a commitment to limit the quantity of radioactivity in temporary radweste storage tanks to less than or equal tc 10 curies, excluding tritium and dissolved or entrained noble gases.
The Licensee's RETS include a commitment to limit the quantity of radicactivity contained in each gas storage tank to 300,000 curies noble l
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16 l
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gases (Xe-133 equivalent). This is a suitable fraction of the quantity of radicactive material which if released over a two hour period, would-result in a total body exposure to a eember of the public at the exclusion area boundary of 500 mrem.
Therefore, the Licensee's RETS submittal en tank inventory limits meets the intent of.'!UREG-0472.
3.2.6 Exclestve Gas "txtures The objective of the model RETS with regard to explosive gas mixtures is to prevent hydrogen explosions in the waste gas system.
The requirement ta monitor hydrogen and oxygen to guard against explosive gas concentrations is being addressed as a separate issue by the NRC for A?O-1 and ANO-2 and is not addressed in this review.
Solid m dweste sys+en 3.2.7 e
The objective of the model RETS with regard to the solid radwaste system is to ensure that radwaste will be properly processed and packaged before it is shipped from the plant to the burial site to satisfy the recurrements of 10 CFR Part 20, Section 20.301 and 10 CFR Part 71.[35]
The Licensee's RETS include a commitment to use the solid radwaste system in accordance with a Process Control Program to process wet radicactive wastes to neet shipping and burial ground requirements.
Therefore, the Licensee's RETS submittal on solid radioactive waste meets the Intent of MU4EG-0472.
17
3.2.8 Radioicoteal Environmental Monitorina Procram The objectives of the mcdel RETS with regard to a radiolegical envircnmental monitoring program are to ensure that (a) an adequate full-area coverage environnental monitoring program exists, (b) there is an appropriate land use census, and (c) an acceptable Interlaboratory Comparison Program exists. The monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50, the land use census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50, and the requirement for participation in an approved Interleboratory Comparison Program is provided to ensure that independent checks are performed as part of the quality assurunce program for environmental monitoring to demcnstrate that valid results are obtained for Section IV.B.2 of Appendix l to 10 CFR Part 50.
The Licensee's RETS on a radiological environmental monitoring program have folicwed the model RETS and the Eranch Technical Position on the subject issued November 1979,[313 as applicable to the site, and have provided an adequete number of sample locations for pathways identified.
The L!censee's method of sample analysis and maintenance of the monitoring program satisfies the requirements of Appendix I, 10 CFR Part 50. The Licensee's RETS contain a land use census specification which requires the apprcpriate annual information for a Ph'R.
The RETS also state that the Licensee will participate in an NRC approved Interlaboratory Comparison Program.
Thus, the Licensee's RETS submittal for a radiological environmental monitoring program meets the intent of NUREG-0472.
3.2.9 Audf+s and Reviews The objective of the mode: RETS with regard to audits and reviews is to ensure that audits and reviews of the radweste end environmental monitoring programs are preperly conducted.
18
The Licensee's administrative structure identifies the Plant Safety Committee (FSC) and the Safety Review Committee (SRC) as the two groups comparable te the Unit Review Group (URG) and the Company Nuclear Review and Audit Group (CNRAG), respectively.
The PSC is respons!ble for reviewing all changes to the OCCM and the PCP.
It was determined the requirement to review accidental, unplanned or uncontrolled radioactive releases was satisfied by the existing Specificaticns.
The SRC is responsible for auditing the radiological environmental monitoring program and the results thereof at least once per 12 months; fer auditing th'e offsite dose calculation manual and process control program and Implementing procedures at least once per 24 months; and the performance of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50 Appendix e at least once per 24 months.
Therefore, the PSC and the SRC encompass the total responsibil'ty for reviews and audits and meet the Intent of NUREG-0472.
3.2.10 Procedures and Records The objective of the model RETS with regard to procedures is to ensure that written procedures be established, implemented, and maintained for the PCP, the ODC?f, and the QA program for ef fluent and environmental l
nonitorfng. The objective of the model RETS with regard to records is to j
ensure that documented records perteining to the radioicgical environmental monitoring program are retained for the duration of the operating license.
The Licensee's RETS. Include a commitment to establish and implement precedures for the ODCM and the PCP. The establishment and implementations of procedures for the Quality Assurance Program fer the i
1 19
effluent and environnental monitoring program was determined tc be a requirement of 6.8.1.a of the existing Specifications.
The Licensee's RETS state the " Records of enalyses results r'equ
- red by the Radiologica! Environmental Monitoring Program," shall be retained for the duration of the Facility Operating Licerise.
Therefore, the Licensee's RETS submittal on procedures and records meets the Intent of 14UREG-0472.
3.2.11 Pecorts The objective of the model RETS with regard to reporting requirements is to ensure that appropriate annual and semiannual periodic reports and special reports are submitted to the NRC.
The Licensee's RETS Include commitments to submit the following reports:
Anrual m dic!cotcal Environmental Ooeratino Recort 1.
e This report includes sunmaries, Interpretations and analysis of trends of the results of the radiological environmental monitoring surveillance program. The report also includes the results of the land use census and results of participation in the Interlaboratory Comparison Program. The report will be submitted prior to May 1 of each year.
i 2.
Semienquel Radioac+fve Effluen+ Pelease Recert This report contains a sumnery cf the quantities of radicactive i
liquid and gaseous effluents released and is submitted within 60 days after January 1 and July 1 of each year. The repcrt also includes a sunmary of solid waste shipped offsite, an assessment of of fsite doses, and doses te Individuals due to their activities inside the unrestricted area. The report may include 20 3
the prescribed meteorological data. The report shall also con'iln a listing of new locations required by the land use census as well as any changes to the ODC4 and the FCP. The report may include-a description of major changes to the radicactive waste systems -(liquid, gases, and solid) during the previous calendar year.
3.
Scecial Reoorts The Licensee's RETS include a commitment to file a special report under the following conditions:
e Exceeding the liquid ef fluent dose limits according to ANO-1 Specif~Ication 3.15.1.2.B and ANO-2 Specif ication 3.11.1.2 within 30 days of determination.
e Exceeding the gaseous effluent dose limits according to ANC-1 Speci fications 3.25.2.2.B and 3.25.2.3.B and ANO-2 Specif ications 3.11.2.2 and 3.11.2.3 within 30 days of determination, e
When radioactive liquid or gaseous effluents are discharged without treatment and in the excess of the projected dose limits according to A!C-1 Specif ications 3.15.1.3.C and 3.25.2.4.C and 10-2 Specifications 3.11.1.3, 3.11.2.5 and 3.11.2.6.
Exceeding the total dose limits according to ANO-1 Specification e
3.25.3.2 and ANO-2 Specification 3.11.3 within 30 days, o
Exceeding the reporting levels for the radioactivity measured in ANO-1 environmental sampling program Specification 4.30.1.2.b and ANO-2 Specification 3.12, within 30 days.
Therefore, the Licensee's RETS submittal en reports meets the Intent of NUREG-0472.
21
0+Fer Adminr trative Centrols 3.2.12 s
Addit!cnal objectives of the model RETS in the administrative controls section are to ensure that ar.y changes to the PCP and ODCM and major changes to the radioactive waste treatment systems are reported to the NRC.
The Licensee's RETS require that changes to the ODCM and FCP be reported to NRC in the semiannual radioactive ef fluent release report.
Notification of Licensee initiated major changes to the radioactive waste systems (IIquid, gaseous and solid) may be reported in the semiannual report or included in the next FSAR update.
Therefore, the Licensee's RETS submittal for these administrative controls meets the Intent of NUREG-0472.
3.3 OFFSITE DOSE CALCULATION "ANUAL As specified in NUREG-0472, the ODCM is to be developed by the Licensee to document the methodology and approaches used to calculate offsite vu es and maintain the operability of the effluent system. As a minimus, the 3DCM should provide equations and methodology for the following topics:
e alarm and trip setpoints for effluent instrumentation e
liquid effluent concentration in unrestricted areas e
gaseous ef fluent dose rate or concentrations at or beyond the site boundary e
liquid and gaseous effluent dose contributions e
total dose compliance, including direct shine e
liculd and gaseous effluent dose projections In addition, the ODCM should contain flow diegrams, consistent with the systens being usec at the station, defining the treatment paths and l
22 l
tFe components of the radicactive liquid, gaseous, and solid weste management systems. A description and the location of samples in support of the environmental monitoring program are also needed in the ODCM.
3.3.1 Evaluation The Licensee's ODCM satisfies the equation in the addendum of NUREG-0133 to determine the alarm and trip setpcints for the liquid effluent monitors. This assures that the alarm and trip actions will occur prior to exceeding the 10 CFR Part 20, Appendix B, Table 11 values at the discharge point to the unrestricted area.
The alarm and trip setpoints for the gaseous effluent monitors are calculated to assure that alarm and trip actions w!!! occur prior to exceeding the limits set in 10 CFR Part 20 for annual dose rates to unrestricted areas. The Licensee uses equations similar to those contained in NUREG-0133 with the dose rate values identified in NU7E G-0472.
l l
Liquid radweste is released by batch mode only. The Licensee's CDCM contains the methods and calculational relationships that are used to j
compare the radioactivity concentrations in liquid releases at the point of release to the 10 CFR Part 20 limits prior to release for gamme emitters. The OCCM does not state the same methodology will be used to demonstrate that alpha and beta emitters are also assured to be within their respective b'PC limits.
The Licensee's ODCM demonstrates that noble gas discharges are assured to be within the NUREG-0472 dose rate limits by correctly determining the setpoints for the noble gas monitors. The dose rate due to the release of l-131, tritium, and particulates with half-lives greater than eight days is assured to be within the NUREG-Ca72 limit of 1500 mrem per year by l
calculating the dose rate to an infant via the inheletion, food and ground pathways due to the actual release using a dispersicn parameter of 2.9 E-6 23
sec/m3 for the inhalatten pathway and a value of 1.4 E-9 m-2 for the food and ground piene pathways.
The OCCM contains methodology for demonstrating compliance with 10 CFR Part 30, Appendix I by calculating dose commitments for IIculd and gesecus effluents. Cumulative calculations shall be made at least once per 31 days.
"ethodology is included to project the monthly doses due to anticipated liquid and gaseous releases to determine if the liquid or gaseous radwaste treatment equipment must be operated.
Specific parameters of distance and the direction sector from the plant and additional Infornation have been provided for each and every sample location in RETS Environmental Monitoring Table 4.30-1.
The sample lccatiens are described in ODC'.1 Table 4-1 and locations Illustrated in Figures 4-la and 4-1b.
Powever, Figure 4-1b is illegible and should be replaced.
The 00C*1 does not contain block diagram descriptions of the flow paths and treatment systems for radicactive IIquid, gaseous, and solid wastes.
The ODCM does not include methodology to demonstrate compliance to 40 CFR 190. i'cre specifically, the direct radiation ecmponent to arrive at the total dose is not included.
The Licensee's ODCM for ANO-1 and ANO-2 is genera t iy in compliance with the NRC guidelines and uses methods consistent with the methodology and guidance of NUREG-0133.
l I
3.4 Drocess Centrol Droccan NUREG-0472 specifies that the Licensee develco a PCP to ensure that the precessing and packaging of solid radioactive wastes will be accerolished in compliance with 10 CFR oart 20, 10 CFR 3srt 71, and other 24
Federal and State regulations or recuirements governing the offsite disposal of the Icw-level radioactive waste.
The PCP is not intended to contain a set of detailed procedures; rather, it is the source of basic criteria for the detailed procedures to be develcped by the Licensee. The criteria used for the PCS are to address only today's requirements. The uncertainty about PCP requirerrents results from the recent promulgation of 10 CFR Part 51, " Licensing Requirements for Land Disposal of Radioactive Maste."
3. 4.1 Evaluation The PCP submitted with letter dated April 13,1984[28] was reviewed and it was concluded the PCP was generally in compliance with NRC guidelines contained in a letter dated January 3, 1983.[33]
4.0 CCNCLUSIO!!S The Licensee's proposed RETS, CDCM and PCP were rev!ewed, evaluated and it was concluded that:
e The Licensee's proposed RETS for AIO-1 and AIO-2 submitted April 13, 1984 and supplemented April 26, 1984 meet the intent of the f1RC staff's " Standard Radiological Effluent Technical l
Specifications for Pressurized Weter Reactors," t!UPEG-0472.
e The Licensee's ODCM submitted April 13, 1984 uses docunented and approved methods that are appi! cable to the Arkansas Muclear One site and are generally consistent with the guidelines of fiUREG-0133 with the following exceptions:
25
i.
"ethodology is not included to de=cnstrate that alpha and beta emitters released in radioactive licuid discharges are.
within the 10 CFR Part 20 MPC limits as recuired in ANO-1 Specificaton 4.29.1.1.E and ANO-2 Specif ication 4.~1 1.1.1. 2.
2.
Figure 4-1b should be replaced with a more legible figure.
3.
Elock diagram descriptions of the flow paths for the liquid or gaseous release paths and the' radioactive solid waste systen are not included.
4.
\\'ethodology to demonstrate compliance to 40 CFR 190 with the direct radiation component is not included.
5.
Three food locations are required in the APO technical specifications whereas, only two locations are identified in the ODCM.
o The Licensee's PCP submitted April 13, 1984 is generally in compliance with the NPC guidelines contained in NRC letter dated January 3, 1983.
A correspondence betweeen (a) NUREG-0472, (b) the Licensee's current RETS, and (c) the Licensee's proposed RETS for ANC-1 and ANO-2 are shown in Tables 1 and 2.
26
TABLE 1.
CORRESFONDENCE OF PROVISIOiJS CF NUPEG-C472, THE LICENSEE'S CURRENT TECHMICAL SPECIFICATICf1S, ATO THE LICEiJSEE'S PROPOSAL FCR ANC-1 Current Technical Licensee RETS Tecuirement MUPEG-0472 Sosefficatters Prooosaf Effluent Instrumentation 3.3.3.10 2.4.1.4 3.5.6 3.3.3.11 2.4.2.5, 2.4.2.8 3.5.7 Concentrations 3.11.1.1 2.4.1.1, 2.4.1.3 3.25.1.1 3.11.2.1 2.4.2.3, 2.4.2.4 3.25.2.1 Offsite Coses 3.11.1.2 3.25.1.2 3.11.2.2 3.25.2.2 3.11.2.3 3.25.2.3 3.11.4 3.25.3 Radweste Treatment 3.11.1.3 2.4.1.5 3.25.1.3 3.11.2.4 2.4.2.6, 2.4.2.7 3.25.2.4 Tank Inventory Limits 3.11.1.4 2.4.1.6 3.25.1.4 3.11.2.6 2.4.2.2 3.25.2.5 Explosive Gas Mixtures 3.11.2.5 Solid Radweste 3.11.3 3.25.4 Environmental Monitoring 3.12.1 4.2 4.30.1 Land Use Census 3.12.2 4.30.2 Interlaboratory Comparison 3.12.3 4.30.3 l
Feviews 6.5.1 6.5.1.7 i
Audits 6.5.2 5.3.2 6.5.2.8 6.8.1 Procedures 6.8 Pecords 6.10 5. 8.1. b 6.9 Reports 6.9.1.11 5.6.1 6.12.2.5 l
6.9.1.12 6.12.2.6 6.12.2.6 PCP 6.13 l
CDCM 6.14 6.12.2.6 l
Radwaste Treatment 6.15 5.7.3.A 6.12.2.6 l
l l
i l
27 l
t
TABLE 2.
C0FF.ESPONDENCE OF PROVISICliS GF f,'UREG-0472, THE LICENSEE'S CURRENT TECHNICAL SPECIFICATIONS, ATO THE LICENSEE'S P90POSAL FOR ANO-2 Current Technical Licensee RE S cecuire-ent NOREG-O a72 Soeciffeatiens Procesel Effluent Instrumentation 3.3.3.10 2.2.1.4 3.3.3.10 3.3.3.11 2.2.2.5,2.2.2.6,2.2.2.7 3.3.3.9 Concentrations 3.11.1.1 2.2.1.1, 2.2.1.3 3.11.1.1 3.11.2.1 2.2.2.3, 2.2.2.4 3.11.2.1 Offsite Deses 3.11.1.2 3.11.1.2 3.11.2.2 3.11.2.2 3.11.2.3 3.11.2.3 3.11.4 3.11.3 Radwaste Treatment 3.11.1.3 2.2.1.5 3.11.1.3 3.11.2.4 3.11.2.4,3.11.2.5 Tank Inventory Limits 3.11.1.4 2.2.1.6 3.11.1.4 3.11.2.6 2.2.2.2 3.11.2.6 Explosive Gas Flixtures 3.11.2.5 Solid Radweste 3.11.3 3.11.4 Environmental tienitoring 3.12.1 3.1, 3.2 3.12, 6.14 Land Use Census 3.12.2 6.14 Interlaboratory Comparison 3.12.3 3.12, 6.14 Reviews 6.5.1 6.5.1.6 Audits 6.5.2 5.3.2.d 6.5.2.8 Procedures 6.8 6.6.1 Records 6.10 5.8.1.5 i
Annual Report 6.9.1.11 5.6.1 Semiannual Report 6.9.1.12 6.9.3 PCP 6.13 ODCft 6.14 6.15 Racwaste Treatment 6.15 5.7.3.A 28
I 5.
REFERENCES 1.
United States iluclear Regulatory Commission, Sta,dard Pedfefocieel Efffuent TechnIcel Scecifications for Pressurized We+er Reac+ ors, rJUREG-0472, Revision 2, July 1979.
2.
United States Of fice of The Federal Register, Title 10, Code of Federei Peculations, Part 50, Appendix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterien
'As Low as is Reasonably Achieveble' for Radioactive Staterial in Light-liater-Cocied Nuclear Power Reactor Effluents."
3.
United States Office of the Federal Register, Title 10, Code of Federal Reculations, Part 50, Sectlen 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors."
4 United States Office of the Federal Regsiter, Title 10, Code of Federal Seculations, Part 50, Appendix I,Section V.B.,
" Effective Dates."
5.
United States Of fice of the Federal Register, Title 10, code of Federal Peculettens, Part 20, " Standards fer Protection Against Radiation."
6.
United States Office of the Federal Register, Title 40, Code of Federaf ceculettens, Part 190, " Environmental Radiation Protecticn Standards for Nuclear Power Operations."
7.
United States Office of the Federal Register, Title 10, Code o#
Federal Reculations, Part 50, Appendix A, " General Design Criteria for Nuclear Pcwer Plants."
8.
United States Of fice of the Federal Register, Title 10, Code of Federe t Reculations, Part 50, Appendix B, " Quality Assurance Criteria j
for Nuclear Power Plants and Fuel Reprocessing Plants."
9.
United States Nuclear Regulatory Commission, Precare +1on of Rediefocical Technical Scecifications for Mucleqr ower plants, l
NUREG-Oi33, October 1978.
l l
- 10. United States Nuclear Regulatory Commission, Standard Redfetcotcal Effluent Technical Sceciffeetions fer DetI!nc We+er Reactors, NUREG-0473, Revis ion 2, Ju l y 1979.
- 11. C. A. '#illis and F. J. Congel, " Summary of Craf t Contractor Guidance of RETS, "A IF Envf ronmenta l SubcommI+ tee Pfeetinc. Washinc+on. D.
C.",
May 19,1982.
i l
l
- 12. F. J. Congel, emo to RAB Staf f (NRC), frterie Chances in the Pfode t R.E_T.1, August 9, 1982.
- 13. United States ?!uclear Regulatory Conmissien, Stendard Cad f e!ccical E*ffuen+ Technfeel Erecificettens der Pres sur i zed 'cleter Peac'c s,
NUPEG-0472, Revision 3, Draf t 7, September 1982.
29
}
- 14. United States tiuclear Regulatcry Commissicn, S+anderd Cae f e fcetcal Effluent Technfeal Soecif' cat' ens for Boilinc '.later Reac^ ors, NUREG-0473, Revis !on 3, Craf t 7 , September 1982.
- 15. W. Cavanaugh li t, Letter to R. W. Reid, Arkansas Nuclear One - Unit 1 Oceket 30. 50-313 L* cense No. CDE-51 Procesed Techn f eel Scecif ications (DTte:
1511.1 1511.3), March 9,1979.
- 16. W. Cavanaugh lil, Letter to J. F. Stolz, Arkansas Nuclear One - Unit 2 Decket No. 50-368 L f cense Yo. NPF-6 Procesed Radic locica l Techn ica l Soecifications (Fife:
2-1511.1 ), May 10, 1979.
- 17. G. S. Vissing, Letter cf Transmittal, Summarv of Meetino of October
- 23. 1979. In Dethesds. t/aryland. Recardine Radiclocical Ef f luent Techn ical Sceci f ications (PETS), November 15, 1979.
- 16. W. Serrano, Letter to C. A. Willis, Transmittet of Ouestions for Arkansas RETS Peview - Serr-8-82, May 4,1982.
- 19. G. S. Vissing, Letter of Transmittal, Summarv of June 22-24. 1e82 ffee+f na with AP&L Concernine the Accendix I Review f o r A NO-1 & 2, Ju l y 15, 1982.
- 20. J. R. Marshall, Letter to tl. Serrano, Arkanses Muc teer One - Units 1 4 2 Docket Nos. 50-313 end 50-368 License Nos. OPP-51 and PPF-6 AF4L Transmittal of e Draft Revision of the RETS and 00CV fer Review and Cc-rent, September 15, 1982.
- 21. S. W. Duce, Letter to J. R. Marshall, ANO 1 & 2 RETS Submittal and ODCM - SWD-6-82, October 1, 1982.
- 22. W. Serrano (EG&G), G. Fiser and R. Pool ( AP&L), Personal Communication, flovember 22, 1982.
- 23. J. R. fiarshall, Letter to J. F. Stolz and R. A. Clark, Arkansas Nuclear One - Units 1 and 2 Cocket tbs. 50-313 and 50-368 License Nos.
DDP-51 and MPF-6 Recuest for Extensfon te Transmf + cur Revised Aeoendix I Subnfttet to NPC, November 30, 1982.
- 24. W. Serrano, Letter to C. A. Willis, Review cf Arkanses CETS and 000 -
Serr-21-82, December 15, 1982.
- 25. S. W. Duce, Letter to C. A. Willis, Transmittal of Unresolved issues ce Arkansas Nuclear One - SWC-4 A3, January 24, 1983.
e
- 26. J. M. Grif fin, Letter to J. F. Stolz and J. R. f/ Iller, Arkansas Muclear One - Units 1 and 2 Decket Nos. 50-313 and 50-368 L f censa Ye s.
DPR-51 and NPF-6 Prooosed Technical Soecification Chance Revis ten -
Accendiv i ( ETS), September 30, 1983.
1 and 2 :STS end
- 27. W. Serrano, Letter to C. L. Miller, Arkanses Uni +s OCC Pev'ews - ? err-29-83, November 4,1983.
30
- 28. J. M. Grif fin, Letter to J. F. Stolz and J. R. Miller, Arkansas l'ucteer One - Units 1 anc 2 Decket t1os. 50-311 and Sn-3A A License Nos.
PDP "1 and f.'De-6 Frocesed Techn ica l Sceci f ication Chance Devis ten Aonandiv i (RETS), Apr i l 13, 1984
- 29. J. ft. Orf f fin, Letter to J. F. Stolz and J. 9. IIllier, Arkansas Nuclear One - Units 1 and 2 Socket tbs. 50-313 and 60-3A A License Noc.
DDR-51 and i422-6 Orcoosed Techn ical Soecifications, April 26, 1984
- 30. C. L. Miller, Ttemo to W. Serrano, Summary of Final Resolutions Pasad on Acril 13, toRZ and A0rif 26. 1084 Submittefs, May 8, 1984
- 31. N. Serrano, Letter to C. L. Miller, Review of the Arkanses Oncv and PCP - Serr-18-84, May 29, '984
- 32. D. C. Trimble, Letter to D. G. Eisenhut, Arkensas fluc teme One - Units 1 and 2 Oceket 'bs. 50-313 end 50-368 Lfcense Nos. DDR-51 and NPF-6 Lew level Pedicactive Waste Discosal (File: 3o05. 2-3005. 3c3n, 2-3c30. 1511.3. 2-1511.3), February 21, 1980.
- 33. C. A. !!Illis, Letter of Transmittal, Guidance on +Fe revt. of
+8.
Process Cen+ro! Procreas (PCP), January 3,1983.
- 34. United States Of fice of The Federal Register, Title 10, Code of 4
Federal Reculattens, Part 20, Appendix 9, " Concentrations in Air and
' dater Above Natural Packground."
- 35. C. A. VIIIIs, Letter to F. E. Simpson (summarizing changes to RETS requirements following meeting with Atomic Industrial Forum), Nover.ber l
20, 1981.
- 36. W. E. Kreger (NRC), itemo to R. J. T'attson (NRC), Plans fer Deeline with +5e Exo f osiva Gas issue in inoferentine the Radiclocical Ef f luent Technical Scec i + f cat f ors (RETS), December 14, 1981.
l
- 37. C. A. Willis and F. J. Congel, " Status of NRC Radiological Effluent Technical Specification Activities," Atente indus+ rial Forum Conference on LEPA and ffuclear Reculations, October 4-7, 1981.
l 3 8. C. A. Wi l l i s, "emo to c. C. Vagner, ofens for imetemen+tne l
Padiolocical Effluent Technical Scecifica+fons for Ceeratine Peacters, liovember 4, 1981.
i
- >. W. P. Gamm i l (NRC), f3eno to P. C. '4agner (NRC), Current positten on Pedfolecical Ef f luent Techn ica l Scecifications (RETS) includino i
l Exetosive cas Con +rels, October 7, 1981.
l
- 40. United States Nuclear Regulatory Commission, Radiological Assesseent Eranch Technical Position, An Acceotebfe Radic!ccical Enviren-ertet
c- ! +or t n c c reccom, TJovember 1979.
i i
31 i
_. ~.
- 41. United States P!uclear Regulatcry Conmissien, ?.'ethods fer Derenstratine Lt!R Ceno l t =nce w f +h the EDA Ilranfum Fuel O'icle 9+andard fa0 CFR Par +
~
1S22., HUREG-C543, February Ic60.
- 42. United States.' uclear Regulatory Ocnmission, Scanch Technical Position, Genera! Centents of the O*4 site Dese Calculatten Manual, Revision 1, February 8,1979.
- 43. Regulatory Guide 1.109, " Calculation of Annual Coses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Conpliance with 10 CFR Part 50, Appendix I, "Revisten 1, U. S. Nuclear Regulatory Conmission, Washington, D. C.
20555, October 1977.
- 44. United States Office of the Federal Register, Title 10, Ecde of Federal Reculations, Part 71, " Packaging of Radicactive Material for Transport and Transportation of Radioactive Material Under Certain Conditlens."
a f
32 i
4-
aus3s
- 1. EEPO;iT NUMEEG IAmpieJ oy DOCJ I,",,y a u.s. NuctEAn nEcutArony commission BIBUOGRAPHIC DATA SHEET EGG-PBS-6628 4 TITLE AND SusTITLE
- 2. Iteme ei val RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)
IMPLEMENTATION - ARKANSAS NUCLEAR ONE UNITS 1 AND 2 3 RECIPIENT'S ACCESSION NO
- 7. AUTHOR tS)
- 5. DATE REPORT COMPLE TED W. Serrano, S. W. Duce, J. W. Mandler, F. B. Simpson we~T" I"
May 1984 T.
F.
Ynung 9 PE RFORVING ORGANIZATION N AME AND MAluNG ACORESS tractuor 2,0 Cooes DATE REPORT ISSUED uCNTM l YEAR Radiation Measurements Section May 1984 EG&G Idaho, Inc.
,,t,,,,,,,,,
Idaho Falls, ID 83415 e Itene a-,
o a SPONScRiNG ORGANi:ATION N AVE AND M AluNG ADDRESS tincewoe I,a CooeJ 10 PROJECT.TASOWORK UNIT NO Division of Systems Integration
- ]
Office of Nuclear Regulatory Research ii nN No U.S. Nuclear Regulatory Commission Washington, DC 20555 13 TYPE OF REPORT
- E RICO COVE RE O Itactus<re asest 15 SUPPLEVENTARY NOTES to tiene a s*as 16 ABSTR ACT T200 *oras or <essi A review of the Radiological Effluent Technical Specifications (RETS) of the Arkansas Nuclear One Units 1 and 2 was performed. The principal review guidelines I used were NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," and Draft 7 of NUREG-0472, Revision 3 " Radiological Effluent Technical Specifications for Pressurized Water Reactors." Draft suomittals were discussed with the Licensee by both EG&G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines.
The proposed Offsite Dose Calculation Manuel and Process Control Manual were reviewed and generally found to be in compliance with the NRC review guidelines.
l l
' 17
- E v e.OR O$ AND OOCLVE NT AN A LYSIS 17a DESCR!PTCRS l
l l
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17e
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