ML20215M230
| ML20215M230 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/06/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M217 | List: |
| References | |
| NUDOCS 8610300119 | |
| Download: ML20215M230 (8) | |
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UNITED STATES
/
NUCLEAR REGULATORY COMMISSION y
WAS,*lNGTON, D. C. 20006
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.108 TO PROVISIONAL OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET N0. 50-219
1.0 INTRODUCTION
By letter dated June 1,1979, as revised by letters dated November 25, 1983, October 22, 1984, and August 13, 1986, GPUNuclear(thelicensee) requested an amendment to Provisional Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek). This amendment would authorize changes to the Appendix A Technical Specifications (TS) to incorporate the radiological effluent technical specifications (RETS) required by Appendix 1. Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As low as is Reasonably Achievable" for Radioactive Materials in... Effluents, to 10 CFR Part 50.
These changes are (1) to ievise TS Section 1.0, Definitions; TS Sections 3.1 and 4.1, Protective Instrumentation; TS Sections 3.6 and 4.6,) Radio-active Effluents; TS Section 6.0, Administrative Controls; and (2 to add the new TS Sections 3.14 and 4.14, Solid Radioactive Waste; TS Sections 3.15 and 4.15. Radioactive Effluent Monitoring Instrumentation; and TS Section 4.16. Radiological Environmental Surveillance. These changes revise the existing requirements on radioactive effluents and radwaste management in the TS.
2.0 DISCUS $10N To comply with Section V of Appendix ! of 10 CFR Part 50, the licensee submitted by letters dated June 1, 1979, and October 22, 1984, proposed RETS for the purpose of keeping releases of radioactive materials from Oyster Creek to unrestricted areas during normal operations, including expected operational occurrences, as low as is reasonably achievable (ALARA). The proposed TS update TS Sections 3.6 and 4.6 which address radioactive waste management to make them consistent with the current staff positions as expressed in NUREG-0473 Radiological Effluent Technical Specifications for Boiling Water Reactors. These revised TS l
would reasonably assure compliance, in radioactive waste management, with l
the provisions of 10 CFR 50.36a as supplemented by A pendix ! to 10 CFRPart50;with10CFR20.105[c),106(g),and405(c;with10CFR Part 50, Appendix A, General Design Criteria 60, 63 and 64; and with 10 CFR Part 50, Appendix 8.
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i 2.1 Regulations J
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10 CFR Part 50, " Domestic Licensing of Production and Utilization i
Facilities," Section 50.36a, " Technical Specifications on Effluents j
from Nuclear Power Reactors," provides that each license authorizing operation of a nuclear power reactor will include technical specifica-l tions that (1) require compliance with applicable provisions of Part 1
20.106, " Radioactivity in Effluents to Unrestricted Areas"; (2) require that ooerating procedures developed for the control of effluents be i
l established and followed; (3) require that equipment installed in the i
radioactive waste system be maintained and used; and (4) require the i
periodic submission of reports to the NRC specifying the quantity of each of the principal radionuclides released to unrestricted areas in
)
liquid and gaseous effluents, any quantities of radioactive materials released that are significantly above design ob,iectives, and such other l
information as may be required by the Commission to estimate maximum j
potential radiation dose to the public resulting from the effluent l
releases.
l 10 CFR Part 20. " Standards for Protection Against Radiation " paragraphs i
20.105(c), 20.106(g), and 20.405(c), require that nuclear power plant and other licensees enmply with 40 CFR Part 190. " 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.
l 10 CFR Part 50, Appendix A - General Design Criteria for Nuclear Power Plants, contains Criterion 60 Control of releases of radioactive i
i materials to the environment; Criterion 63 Monitoring fuel and waste l
storage; and Criterion 64, Monitoring radioactivity releases. Criterion 60 requires that the nuclear power unit design include means to control 4
suitably the release of radioactive materials in gaseous and liquid i
effluents and to handle radioactive solid wastes produced during normal reactor operation, including anticipated operational occurrences.
j Criterion 63 requires that appropriate systems be provided in radioactive i
waste systems and associated handling areas to detect conditions that i
may result in excessive radiation levels and to initiate appropriate safety actions. Criterion 64 requires that means be provided for l
monitoring effluent discharge paths and the plant environs for radio-activity that may be released from normal operations, including anticipated operational occurrences and postulated accidents.
i 10 CFR Part 50, Appendix B, establishes quality assurance requirements for nuclear power plants.
10 CFR Part 50, Appendix 1,Section IV, provides guides on technical l
specifications for limiting conditions for operation for light-water-i cooled nuclear power reactors licensed under 10 CFR Part 50.
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2.2 Standard Radiological Effluent Technical Specifications i
NUREG-0473 provides RETS for boiling water reactors which the staff finds to be an acceptable standard for TS. Further clarification is provided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications of Nuclear Power Plants." NUREG-0133 describes gethods i
acceptable to the staff for the calculation of certain key values required j
in the preparation of proposed RETS.
It also describes staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems. The NUREG documents address the j
RETS needed to assure compliance with the regulations cited.
Table 1 indicates RETS that are needed to assure compliance with the l
regulations in Section 2.1.
t 3.0 EVALUATION 3.1 Proposed RETS The attached technical evaluation report (TER-C5506-106) was prepared for the staff by Franklin Research Center as part of the staff's technical assistance contract program. The contractor's TER provides its technical evaluation of the compliance of the licensee's proposed RETS for Oyster Creek in the licensee's letter dated October 22, 1984, with NRC-provided criteria based on the regulations in Section 2.1.
The staff has reviewed this TER and agrees with the conclusions of the TER that:
(1) the J
licensee's proposed RETS meet the intent of NUREG-0413. (2) the licensee Offsite Dose Calculation Manual (00CM) uses documented and approved methods that are consistent with the criteria of NUREG-0133 and the Oyster l'
Creek plant and site, and (3) the licensee's comitment to implement a Process Control Program (PCP) - the licensee refers to the PCP as the Process Control Plan - to ensure proper processing and packaging of solid radwaste before shipment offsite meets the intent of NUREG-0473. The ODCM and PCP are discussed in Sections 3.3 and 3.2.7, respectively, of the attached TER.
3.2 Minor Additional Technical Specificatio,n_ Changes In its letter dated August 13, 1986, the licensee proposed minor additional changes to its proposed RETS. These changes are the following:
(1) add the word " dose" to the Basis section of TS Section 3.6, (2) delete 1
Action 121 in Table 3.15.2 because it is not referred to in the table, (3) spell ODCM correctly in TS 3.15.A.2, (4) delete the installation date from Item I.C in Table 3.15.1 because this date has no meaning in the TS,(5)replaceTable3.1.5.1byTable3.15.1inTS4.6.I.2asthecorrect reference to the table, (6) add the phrase "after the holdup line" to Note e of Table 3.1.1 to make Item I.1 of the table consistent with TS 3.6.E and (7) correct the Bases for TS 3.15.B. These seven changes are l
minor clarifications and/or corrections of the proposed RETS.
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These clarifications and/or corrections are minor and do not change either i
the substance of the licensee's application dated October 22, 1984 or the i
basis of the staff's proposed detemination that the proposed RETS do not involve a significant hazards consideration.
3.3 RETS Software and Hardwcre Imolementation i
On July 31 and August 1, 1985, meetings were held at the Oyster Creek j
site with the licensee to discuss implementing the RETS at Oyster Creek.
In its letter dated October 22, 1984, the licensee had requested 90
)
days after the proposed RETS were issued for the RETS to become effective.
j This was to provide time for the licensee to complete the procedures to implement the RETS.
In the meeting, the licensee explained its problems with software and hardware to fully implement the RETS at Oyster Creek.
The meeting sumary is dated August 22, 1985.
1 In its letter dated August 13, 1986, the licensee further explained its problems with the software and hardware needed to implement the RETS at 3
Oyster Creek.
In this letter, the licensee stated the following:
(1) the computer software needed to be developed for the ODCM will be available prior to the restart from the current Cycle 11 Refueling (Cycle 11R) outage (2) the three liquid effluent radioactivity monitors listed in RETS Table 3.15.1-are inoperable and (3) hardware and software problems exist which prevent the gaseous effluent monitoring instrumentation to completely satisfy the equipment operability requirements for monitoring l
the stack and turbine building effluent pathways.
The three liquid effluent radioactivity nonitors in RETS Table 3.15.1 l
are the liquid radwaste effluent discharge monitor, the Turbine Building j
Sump No.1-5 radioactivity monitor and the service water system discharge j
line radioactivity monitor. The licensee plans to propose the deletion of the liquid radwaste effluent discharge monitor. The Turbine Building l
Sump No. 1-5 radioactivity monitor is to be installed prior to the restart from the current Cycle 11R outage. The existing service water system discharge line radioactivity monitor requires an equipment upgrade to be considered operable by the RETS requirements. This upgrade is to be completed in the Cycle 12R outage in 1988. An alarm setpoint for this monitor will be established to provide an indication that effluent radioactivity has increased to an unacceptable level between effl9ent sampling and analysis.
j In its letter dated August 13, 1986, the licensee also explained the hardware and software problems which currently exist and preclude the i
ability of the radioactive gaseous effluent monitoring instrumentation to completely satisfy the equipment operability requirements in the proposed RETS for monitoring the stack and turbine building effluent pathways. This monitoring system, which has been referred to as RAGEMS, was designed in 1977/1978 to meet Appendix I to 10 CFR Part 50.
It was modified to meet 1
post-accident monitoring and sampling requirements in NUREG-0737. RAGEMS i
i was originally to provide on-line analysis to identify the principal noble gas radionuclides; however, this capability has not been made functional. The RAGEMS was discussed in the meeting of April 2, 1986, with the licensee. The meeting sumary is dated May 22, 1986.
At present, the licensee-uses ventilation fan capacity curves to estimate stack effluent flowrate.
It stated that equipment flow measurement capability will be provided during operating Cycle 11.
The instrumentation for continuous monitoring of the turbine building ventilation exhaust effluent is scheduled for modifications during operating Cycle 11. Approximately one half of the turbine building l
ventilation flow is exhausted to the main stack, which is monitored.
The other half is exhausted from the turbine building vents. This flow normally comes from the feedwater and condensate pump area and the turbine lube oil bay. The turbine building operating floor vent will be administrative 1y closed during power operation.
If this vent is needed due to operational concerns, or if it is necessary to operate this vent to support the modification / testing of the turbine building gaseous effluent nonitoring system during the next operating cycle, the licensee states i
that appropriate administrative controls will be applied. This is also discussed in the meeting sumary dated May 22, 1986.
i At the August 1, 1985 meeting, the licensee stated that modifications to provide stack effluent flow measurement and continuous monitoring of the turbine building vent gaseous effluent would be accomplished i
during the Cycle 11R outage, if management review resulted in concurrence.
After further review of this addition to the planned workscope of the Cycle 11R outage by the licensee, it stated in its August 13, 1986, letter that available resources and lead time could support the scheduling of l
this work during the outage without significantly impacting outage i
duration.
Thestaffhasreviewedthefactsconcerning(1)theinoperableradioactive liquid and gaseous effluent monitoring instrumentation and (2) the computer software needed to be developed with the licensee. This wes done in the meeting with the licensee on August 27 and 28,1986, on the status of licensing actions for Oyster Creek. The software should be in place prior to the restart from the Cycle 11R outage and all the inoperable equipment discussed above will be operable no later than the restart from the Cycle 12R outage. This is acceptable to the staff because the Action statements in the RETS for inoperable equipment are acceptable until this equipment becomes operable.
3.4 Conclusion Based on the TER, the proposed RETS for Oyster Creek have been reviewed, evaluated, and found to be in compliance with the requirements of the regulations in Section 2.1 and with the intent of NUREG-0133 and NUREG-0473
(the Oyster Creek plant is a boiling water reactor). Therefore, the proposed RETS fulfill all the requirements of the regulations related to RETS and are acceptable.
The proposed RETS will not remove or relax any existing requirement related to the probability or consequences of accidents previously con-sidered and do not involve a significant hazards consideration. They also will not remove or relax any existing requirement needed to provide reasonable assurance that the health and safety of.the public will not be endangered by operation of Oyster Creek in the proposed manner.
The staff, therefore, based on the above, finds the licensee's ODCM and the proposed changes to the TS acceptable.
The staff also concludes that the licensee's commitment to implement its PCP before shipment of any solid radwaste offsite is acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes to requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance require-ments. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant i
increase in individual or cumulative occupational radiatior, exposure.
l The Comission has previously issued a proposed finding that this amend-ment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, this amendment meets the eligibility criteria for categcrical exclusion set forth in 10 CFR l
51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
The Environmental Assessment issued April 10,1986 (51 FR 12754 April 15, 1986) in connection with the Full Term Operating License for Oyster Creek addresses the environmental considerations of radiological effluents from Oyster Creek.
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5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
a (1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security nor to the health and safety of the public.
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6.0 REFERENCES
1.
NUREG-0133, " Preparation of Radiological Effluent Technical Speci-fications for Nuclear Power Plants," dated October 1978.
2.
NUREG-0473, " Radiological Effluent Technical Specifications for Boiling Water Reactors," Revision 2, dated July 1979.
3.
Letter from J. R. Finfrock, Jr. (JCP&L) to Director of Nuclear Reactor Regulation (NRC), Technical Specification Change Request No. 69, June 1, 1979.
4 Letter from P. B. Fiedler (GPUN) to D. M. Crutchfield (NRC),
Radiological Effluent Technical Specifications and Offsite Dose Calculation Manual, November 25, 1983.
5.
Letter from P. B. Fiedler (GPUN) to W. A. Paulson (NRC), TSCR No. 69, Revision 1, dated October 22, 1984.
6.
Meeting Sumary of June 1985 Progress Review Meeting on Licensing Actions dated August 22, 1985.
j 7.
Meeting Sumary for April 2,1986, Meeting to Discuss the Post-Accident NUREG-0737 Items II.F.1.1 And II.F.1.2, dated May 22, 1986.
8.
Letter from P. B. Fiedler (GPUN) to J. A. Zwolinski (NRC),
Radiological Effluent Technical Specifications (RETS), dated August 13, 1986.
Principal Contributors:
F. Congel, J. Donohew, W. Meinke and C. Willis.
Dated:
October 6, 1986 i
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TECHNICAL EVALUATION REPORT NRC DOCKET NO. 50-219 FRC PROJECT C6506 NRC TAC NO. 3100 PRC ASSIGNMENT 4 NRC CONTRACT NO. NRC OHt.130 FRCTASK 106 RADIOLOGICAL EFFLUENT TECHNICAL i
SPECIFICATION IMPLEMENTATION (A-2) l GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION TER-C5506-106 1
Preparedfor Nuclear Regulatory Commission FRC Group Leader:
S. Pandey Washin0 ton,D.C. 20555 NRC Lead EnDineer:
F. Congel C. Willis June 25, 1985 This report was prepared as an account of work sponsored by an seency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, of the results of such use, of any information, appa.
retus, product or procese disclosed in this report, or representa that its use by such third party would not infringe prlystely owned rights.
Prepared by:
Reviewed by:
Approved by:
E W
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/ Principal Author Group Leader' Departmentpirepor Date: A2M8U
~ Date: 4[89/ES Date: 6 -15*- ts*
FRANKUN RESEARCH CENTER DIVISCN OF Am4N/CALSPAN
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TER-C5506-106 j
l CONTENTS section Title Page 1
INTRODUCTION 1
1 1.1 Purpose of Review.
1.2 Generic Background.
1 1.3 Plant-specific Background.
3 2
REVIEW CRITERIA.
5 3
TECHNICAL EVALUATION 7
3.1 General Description of Radiological Effluent System 7
3.2 Radiological Effluent Technical Specifications.
10 3.3 Offsite Doce calculation Manual 17 4
CONCLUSIONS.
lI.
20 5
REFERENCES.
22 111
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TER-C5506-106 FIGURES Number Title Page 1
Liquid Radwaste Treatment Systems, Effluent Paths, and controls for Oyster Creek Nuclear Generating Station 8
2 Gaseous Radweste Treatment Systems, Effluent Paths, and controls for Oyster Creek Muclear Generating Station 9
TABLE N aber Title Page 1
Evaluation of Proposed Radiological Effluent Technical Specifications (RETS), Oyster Creek Nuclear Generating Station. 21 1
1 iv
TER-C5506-106 i
FOREWORD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NN: operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NK:.
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TER-C5506-106 1.
INTRODUCTION 1.1 PURPOSEdFREVIEW The purpose of this technical evaluation report (TER) is to review and evaluate the proposed changes in the Technical Specifications of Oyster Creek Nuclear Generating station with regard to Radiological Effluent Technical specifications (RETS) and the Offsite Dose Calculation Manual (CDCM).
The evaluation uses criteria prooosed by the NRC staff in the Model Technical specifications for boiling water reactors (BWRs), MUREG-0473 [1].
This effort is direct'd toward the NRC objective of inqplementing RETS which e
comply principally with the regulatory requirements of the Code of Federal Regulations, Title 10, Part 50 (10CFR50), " Domestic Licensing of Production and Utilisation Facilities," Appendix I [2]. Other regulations pertinent to the control of affluent releases are also included within the scope of compliance.
1.2 GENERIC BACKGROUND since 1970, 10CFR50, section 50.36a, " Technical specifications on Effluents from Nuclear Power Esactors," has required licensees to provide technical specifications which ensure that radioactive releases will be kept as low as reasonably achievable (ALARA). In 1975, numerical guidance for the ALARA requirement was issued in 10CFR50, Appendix I (3). The licensees of all operating reactors were required to submit, no later than June 4,1976, their proposed ALARA Technical specifications and information for evaluation in accordance with 10CFR50, Appendix I.
Bowever, in February 1976, the NRC staff roccumnended that p'roposals to modify Technical specifications be deferred until the NRC completed ths model RETs. The model RETS deals with radioactive waste management systems and environmental monitoring. Although the model RETS closely parallels 10CFR50, Appendix I requirements, it also includes provisions for addressing other issues. -.
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TER-C5506-106 I
These other issues are specifically stipulated by the following regulations:
i o 10CFR20 [4), ' Standards for Protection Against Radiation," Paragraphs 20.105(c), 20.106(g), and 20.405(c) require that nuclear power plar.ts and other licensees comply with 40CFR190 15), " Environmental Radiation Prctaction Standards for Nuclear Power Operations," and submit reports to the NRC when the 40CFR190 limits have been or may be exceeded.
o 10CFR50, Appendix A [6), " General Design Criteria for Nuclear Power Plants," contains Criterion 60 - Control of releases of radioactive materials to the environment: Criterion 63 - Monitoring fuel and waste storage; and Criterion 64 - Monitoring radioactivity releases, o 10CFR50, Appendix B [73, establishes the quality assurance required
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for nuclear power plants.
The NRC position on the model RETS was established in May 1978 when the NRC's Regulatc,ry Requirements Review Committee approved the model RETS:
NUREG-0473 [1] for BWRs and NURIG-0472 for pressurised water reactors,(PWRs)
(8). Copies were sent to licensees in July 1978 with a request to submit proposed site-specific RETS on a staggered schedule over a 6-month period.
Licensees responded with requests for clarifications and extensions.
The Atomic Industrial Forum (AIF) formed a task force to comment on the model RETS. MRC staff members first met with the AIF task force on June 17, 1978. The model RETS was subsequently revised to reflect comments from the AIF and others. A principal change was the transfer of such of the material concerning dose calculations from the model RETS to a separate GDCM.
The revised model RETS was sent to licensees on November 15 and 16, 1978 with guidance (NUREG-0133 [9]) for preparation of the RETS and the ODCM and a new schedule for responses, again staggered over a 6-month period.
Four regional seminars on the RETS were conducted by the WRC staff during November and December 1978. Subsequently, Revision 2 of the model RETS and additional guidance on the CDCM were issued in February 1979 to each utility at individual meetings. In response to the NPC's request, operating reactor licensees subsequently submitted initial proposals on plant RETS and the CDCM.
Review leading to ultimate Asiplementation of these documents was initiated by the NRC in 1981 using subcontracted indeper. dent teams as reviewers. -
TER-C5506-106 As the RN5i review process has progressed since September 1981, feedback from the licensees has led the NRC to believe that modification to some of the 4.
guidelines inf the current version of Revision 2 is needed to clarify specific concerns of the licensees and thus expedite the entire review process.
Starting in April 1982, NRC distributed revised versions of RETS in draft form to the licensets during site visits. The new guidance on these changss was presented at the AIF meeting on May 19, 1982 [10]. Some interim changes regarding the Radiological Environmental Monitoring Section wara issued in 1982 Ill, 12]. Nith the incorporation of these new changes, NBC issued, in December 1983, a draft version of NUREG-0473, Revision 3 [13], to serve as new guidance for the review teams.
1.3 PLANT-EPECIFIC BACEGROUND In response to the NRC's request, the Licensee, General Public Utilities (GPU) Nuclear Corporation, submitted a RETS proposal in 1979 [14] on behalf of Oyster Creek Nuclear Generating Station, which included a sulunittal of the ODCM [15]. In the RETS submittal, the Licensee had used a non-etandard format. 'In an initial evaluation by the Franklin Reseach Center (FRC), an independent review team, the Licensee's RETS submittal was evaluated against the model RETS (NUREG-0473, Draft Revision 2 [1]) and assessed for compliance
(
with the stipulated provisions. Review of the ODCM was conducted in accordance with NRC-issued guidelines (NUREG-0133). Copies of the draft review, dated January 27, 1982 [16, 17), were delivered to 'the NN: and the Licensee prior to a site visit by the reviewers.
Se' site visit was conducted on February 2-3, 1982 by the reviewers with the participation of plant personnel and the NRC staff. Discussions focused on the initial review of the proposed changes to the RETS and on the technical approaches for an CDCM. S e deficiencies in the Licensee's proposed RETS were considered, deviations from NRC guidelines were pointed out, many differences were clarified, and only a few items remained unresolved pending justification by the Licean.a. These issues are susmarised in Reference 18.
e TER-C5506-106 In a letter transmittal dated November 25, 1983 [19), the Licensee submitted to NRC a revised RETS for review. The submittal also included ODCM
[20]. Both sulinittals were reviewed by FRC, and discrepancies were documented
[21, 22] and transmitted to NBC.
The final version of the Oyster Creek Nuclear Generating Station RETS dated October 22, 1984 [23) was submitted to the NRC and transmitted to the FRC reviewers together with explanations provided by the Licensee. These documents were subsequently reviewed. The final evaluation of the RETS was detailed in a comparison report [24] which used RUREG-0473, Draft Revision 3
[13] to evaluate the Licensee's submittal. The comparison report also incorporates NRC coesments [25] which serve as additional guidelines regarding plant-specific issues.
Evaluation of the Licensee's ODCM is based on the submittal of Reference 20.
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TER-C5506-106 2.
REVIEW CRITERIA Review c iteria for the RETS and ODCM were provided by the NRC in three documente:
NUREG-0472, RETS for PWRs NUREG-0473, RETS for BWRs NUREG-0133, Preparation of RETS for Nuclear Power Plants.
Twelve essential criteria are given for the RETS and ODCM 1.
All significant releases of radioactivity shall be controlled and monitored.
2.
Offsite concentrations of radioactivity shall not exceed the 10CFR20, Appendix B, Table II limits.
3.
Offsite radiation doses of radioactivity shall be ALARA.
4.
Equipment shall be maintained and used to keep offsite doses ALARA.
'5.
Radwaste tank inventories shall be limited so that failures will not cause offsite doses exceeding 10CFR20 limits.
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6.
Hydrogen and/or oxygen concentration in the waste gas system shall be controlled to prevent explosive mixtures.
7.
Nastes shall be processed to shipping and burial ground criteria under a documented program, subject to quality assurance verification.
B.
An environmental acnitoring program, including a land-use census and an interlaboratory comparison program, shall be implemented.
9.
The radwaste management program shall be subject to regular audits and reviews.
10.
Procedures for control of liquid and gaseous affluents shall be maintained and followed.
11.
Periodic and special reports on environmental monitoring and on releases shall be submitted.
e 12.
Offsite dose calculations shall be performed using documented and approved methods consistent with NRC methodology.
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1 TER-C5506-106 Subsequent to the publication of NUREG-0472 and NUREG-0473, the NRC staff issued guidelin'es [26, 27), clarifications [28, 29), and branch positions [30, esbblishing a policy that guides the licensees of operating 31, 32, 33) reactors to meet the intent, if not the letter, of the model RETS provisions.
She ERC branch positions issued since the RETS implementation review began have clarified the model RETS implementation for operating reactors.
Review of the ODCM was based on the following NRC guidelines Branch Technical Position, " General Content of the Offsite Dose Calculation Manual"
[34]; NUREG-0133 [9]s and Regulatory Guide 1.109.[35). The CDCM format is left to the licensee and may be simplified by tables and grid printouts.
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TER-C5506-106 3.
TECHNICAL EVALUATION f
3.1 GENERAL hESCRIPTIG3 OF RADICLOGICAL EFFLUENT SYSTEM This section briefly describes the liquid and gaseous affluent radwaste treatment systems, release paths, and control systems installed at Oyster Creek Nuclear Generating Station, a EWR.
He plant is located in Lacey Township, New Jersey.
3.1.1 Radioactive Liquid Effluent The potentia 11y' radioactive liquid wastes processed by the liquid radwaste system are broadly classified into two categories: high purity waste system and chemical / floor drain waste system.
The high purity waste system collects and processes chemically clean radwaste characterized by low mineral content and relatively high radioactivity level. H e system consists of high purity filters and a pair of high purity waste domineralizers operated in series (see Figure 1).
He chemical / floor drain waste system collects and processes. liquid radweste of relatively high mineral content and/or suspended matter and l
varying levels of radioactivity. The system consists of a dewatering i
flitration system, radwaste concentrators, and domineralizers.
He processed wastes from the high purity waste system. and the t
chemical / floor drain waste system then form the radwaste affluent line and are released to the environment through the discharge canal.
Also joining the circulation water and released through the discharge canal are the affluent streams from the turbine building sump and the service water.
3.1.2 Radioactive Gaseous Effluent he offgases from the Oyster Creek Nuclear Generating station are processed'and routed to the plant stack for dilution and elevated release for discharge to the atmosphere (see Figure 2).
He radwaste processing system consists of high pfficioney particulate air (EEPA) filters, a 60-minute delay pipe, and the auf.mented of{ gas (AOG) treatment system. Also routed to the -
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Figure 1.
Liquid Radweste Treatstent Systems, Effluent Paths, and Controls for Oyster Creek Nuclear Generating Station
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i TER-C5506-106 plant stack for discharge are the. effluents from the turbine building, the l
radweste building, and the reactor building.
Other relkase points separated from the plant stack are the roof top vents, which discharge effluents from the turbine building and the offgas r
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3.2 RADIG,0GICAL EFFLUENT TECHNICAL SPECIFICATIONS The evaluation of the Licensee's proposed RETS against the provisions of NUREG-0473 included the following (1) a review of information provided in the Licensee's 1979 and 1983 submittals [14,15,19, 20], (2) a discussion of problem areas in those submittals by means of a site visit [18), and (3) a review of the Licensee's 1984 final RETS submittal [23].
3.2.1 Effluent Instrumentation The objective of the RETS with regard to effluent instrumentation is to ensure that all significant releases of radioactivity are monitored. The RETS specify that all effluent monitors be operable and alarm / trip setpoints be determined to ensure that radioactivity levels do not exceed the maximum permissible concentration (MPC) set by 10CFR20. To further ensure that the instrumentation functions properly, surveillance requirements are needed in the specifications.
i 3.2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation A radiation monitor has been installed for the liquid radwaste effluent line (Figure 1) which combines effluent streams from the releases of high purity wastes and chemical / floor drain wastes. The Licensee hat also provided monitors for the turbine building pump and the reactor building service water system, which combine with the circulation water at the discharge canal.
These existing monitoring capabilities have provided adequate assurance that the provisions of WUREG-0473 for the radioactive liquid effluent monitoring instrsonentation are met. __
TER-C5506-106 3.2.1.2 Radioactive Gaseous Effluent Monitoring Instruentation The Lice (see has provided noble gas monitors for the following effluent pathways: main stach, turbine building vent, and offgas building exhaust vent. For each of the pathways, sampling of iodine and particulates is also provided on a continuous basis.
The existing monitoring capabilities provided by the Licensee have met the intent of NUREG-0473 for radioactive gaseous effluent monitor instrumentation.
3.2.2 Concentration and Dose Rates of Effluents 3.2.2.1 Liquid Effluent Concentration In Section 3.6.1 of the Licensee's submittal, a commitment is made to maintain the concentration of radioactive liquid effluents released to unrestrict.ed areas to within 10CFR20 limits, and, if the concentration of liquid effluents exceeds these limits, the concentration will be restored without delay to a value equal to or less than the NPC specified in 10CFR20.
All batches of radioactive liquid affluents from the release tanks are sampled and analyzed in accordance with a sampling and analysis program (Table 4.6-1 of the Licensee's submittal) which meets the intent of NUREG-0473.
It was determined that the Licensee-proposed specification meets the
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intent of NUREG-0473.
L 3.2.2.2 Gaseous Effluer.t. Dose Rate In Section 3.6.K of the Licensee's submittal, a comitment is made to maintain the offsite dose rate from radioactive gaseous effluent's to areas at and beyond the site boundary within 10CFR20 limits, or the equivalent dose rate values prescribed by Section 3.11.2.1 of NUREG-0473. If the dose rate of gaseous effluents exceeds these limits, it will be restored without delay to a value equal to or less than these limits. If the gaseous effluent release rate cannot be reduced to meet the limits, the reactor shall be in at least shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless corrective action has been completed and the release rate restored to below the limit. This commitment satisfies the provisions of NUREG-0473. _.-
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TER-C5506-106 ne radioactive gaseous waste sampling and analysis program (Table 4.6-2 of the Licensef's submittal) prcevides adequate sampling and analysis of the f
plant stack discharges, including the substreams, and therefore meets the intent of NUREG-0473.
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3.2.3 offsite Doses from Effluents 1
The objective of the 2ETS with regard to offsite doses from effluents is
'to ensure that offsite doses are kept ALARA and are in accordance with 10CFR50, Appendix 2, and 40CFR190. The Licensee has made a commitment to (1) meet the quarterly and yearly dose limitations for liquid affluents, per Section II.A of Appendix I, 10CFR50; (2) restrict the air doses for beta and gamma radiation frca the site to areas at and beyond the' site boundary as specified in 10CFR50, Appendix I,Section II.B; (3) maintain the dose level at and beyond the site boundary from release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days within the design objectives of 10CFR50, Appendix 2,Section II.C; and (4)
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limit the annual dose frcm the plant -to any member of the public to within the requirements of 40CFR190. In each pertinent section, the Licensee has made a commitment to perform dose calculations in accordance with methods given in the 00CM. This satisfies the intent of NUREG-0473.
I 3.2.4 Effluent Treatment 4
The objectives of the RETS with regard to effluent treatment are to ensure that wastes are treated to keep releases ALARA and to satisfy the provisions of technical specifications governing the maintenance and use of radweste treatment equipment.
In the proposed Specifications 3.6.B and 3.6.D, the Licensee has made a commitment to use the liquid and gaseous radwaste treatment systems to reduce the radioactive materials in liquid and gaseous wastes prior to their discharge. The commitment includes:
a.
Liquid radwaste treatment system. Se Licensee proposes to treat the l
liquid affluents whenever the radioactivity, exclusive of tritium and l
disoolved noble gas, in the batch exceeds 0.001 uC1/ml.
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TER-C5506-106 b.
Gaseous radwaste treatment system. The Licensee proposes to treat the gaseous effluents by operating the condenser offgas treatment syst y as necessary to meet the proposed Specification 3.6.D.
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Licensee has also made a casunitment to verify the operation of the offgas system charcoal adsorbers by verifying that the AOG system bypass valve alignment or alignment indication closes at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the main condenser air ejector is operating.
It was determined [25] that the Licensee's proposal on the radwaste treatment system meets the intent of NUREG-0473.
3.2.5 Radioactivity Inventory Limits The objective of the RETS with regard to the liquid tank inventory limits is to ensure that the rupture of a radweste tank would not cause offsite doses greater than the limits set in 10CFR20 for monoccupational exposure. The Licensee has provided a limit of 10 curies for outdoor liquid holdup tanks.
For radioactivity releases at the main condenser air ejector discharges, a release rate limit of 0.21I ci/see after the holdup line (E is the average gamma energy in MeV per atomic transformation) has been set for noble gases.
It was determined [25] that the Licensee's coenitment to comply with these radioactivity inventory and release rate limits satisfies the intent of NUREG-0473.
I 3.2.6 Explosive Gas Mixtures i
The objective of the RETS with regard to explosive gas mixtures is to prevent hydrogen explosions in waste gas systems. The Licensee stated that the waste gas holdup system is designed to withstand a hydrogen / oxygen explosion.
In Specification 4.6.F of the Licensee's submittal, a ecouaitment is made to monitor the concentration of hydrogen in the offgas downstream of the roccabiner of the main condenser offges treatment system. The Licensee uses one hydrogen monitor and one temperature sensor to verify and control the hycrogen concentration at the roccabiner.
I TER-C5506-106 As in the previous reviews of other plants, it is determined that the Licensee meets the intent of NUREG-0473 in the interim until the NRC completes f
its study of the explosive gas problem.
3.2.7 Solid Radwaste System he objective of the REFS with regard to the solid radwaste system is to ensure that radwaste will be properly processed and packaged,before it is shipped to the burial site. Specification 3.11.3 of NUREG-0473 provides for the establishment of a PCP to show compliance with this objective. The Licensee has made a comunitment to implement such a program in accordance with a PCP and to thus ensure that radwaste is properly processed and packaged before it is shipped to the burial site. This meets the intent of NUREG-0473.
3.2.8 Radiological Environmental Monitoring Program The objectives of the RETS with regard to environmental monitoring are to ensure that an adequate and full-area-coverage monitoring program exists and that the 10CFR50, Appendik I requirements for technical specifications on environmental monitoring are satisfied.
In all cases, the Licensee has followed NUREG-0473 guidelines, including the Branch Technical Position dated November 1979 [32], and has provided an adequate number (32) of thermo-luminescent dosimeter (tim) sample locations cuitting water sectors not applicable to land pathways. S e Licensee's methods of analysis and maintenance of yearly records satisfy the NRC guidelines and, meet the intent of 10CFR50, Appendix 1.
he Licensee has also made a cessaitment to document the environmental monitoring sample locations in the CDCM, which meets the intent of NUREG-0473. The specification for the land use census satisfies the provisions of Section 3.12.2 of NUREG-0473 by providing for 'an annual census in the specified areas. Se Licensee participates in an interlaboratory ocuparison program approved by the NRC and reports the results in the Annual Radiological Enviremmental Operating Report, which also meets the intent of NUREG-0473.
It is therefore concluded that the radiological environmental monitoring program as proposed by the Licensee meets the intent of NUREG-0473..
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O TER-C5506-106 3.2.9 Audits and Reviews The obje(tive of the RETS with regard to audits and reviews is to ensure that audits and reviews of the radwaste and environmental monitoring programs are properly conducted. The Licensee's administrative structure designates the Vice President of each division within the GPU Nuclear Corporation to be responsible ~for review of the proposed changes to the Technical Specifications which include the PCP and the ODCM. Audits are performed under the cognizance of the Vice President of Nuclear Assurance; these audits encompass the radiological environmental monitoring program, the ODCM, and the PCP. It is determined that the Licensee-proposed a kinistrative structure satisfactorily meets the intent of NUREG-0473.
3.2.10 Procedures and Records The objective of the RETS with regard to procedures is to satisfy the provisions for written procedures specified in NUREG-0473 for laplementing the CDCM, the PCP, and the quality assurance (QA) program. It is also an objective of RETs to properly retain the documented records related to the environmental monitoring program and certain QA procedures. The Licensee has made a comanit-ment to establish, implement, and maintain written procedures for the PCP, the CDCM, and the quality control program using the guidance in Regulatory Guide 1.33-1972. It was considered [25] that the Licensee thus meets the intent of WUREG-0473. The Licensee intends to retain the records of analyses required by the radiological environmental monitoring program for'the duration of the facility operating license. It is thus determined that the Licensee meets the intent of MUREG-0473.
3.2.11 Reports I
In addition to the reporting requirements of Title 10, Code of Federal Regulations (10CFR), the objective of the 3tETS with rega'rd to administrative l
controls is to ensure that appropriate periodic and special reports are submitted to the N3lc.
The Licensee made a commitment to follow applicable reporting l
requirements stipulated by 10CFR regulations and also the following reports specified by NUREG-0473: l
TER-C5506-106 1
1.
Annual radiological environmental operating report. In Section 6.9.1.,e of the Licensee's submittal, a commitment was made to provide an annual radiological environmental surveillance report that includes f
summadies and analysis of the results of the environmental surveillance activities. The report also includes the results of land use censuses, and participation in an interlaboratory comparison program specified by Specification 4.16.3 of the submittal.
2.
sealannual radioactive release reports. In Section 6.9.1.6 of the Licensee's submittal, a ccmunitment was made to provide semiannual effluent release reports which include a susmary of radioactive liquid and gaseous effluents and solid waste released. Any changes to the 0D08 and PCP are also included in the report.
j 3.
special report. The Licensee has made a commitment to file a 30-day special report to the NRC under the following conditions as prescribed by the proposed specifications o Exceeding radioactive liquid effluent limits according to Dose, specification 3.6.J.1 Liquid Waste Treatment, specification 3.6.B.1 o Exceeding radioactive gaseous affluent limits according to Dose, specifications 3.6.L.1 and 3.6.M.1 l
Offgas Treatment system, specification 3.6.3.1 o Exceeding radioactive affluent limits according tot i
Annual total dose, Specification 3.6.N.1 i
These reporting commitments have satisfied the provisions of NUREG-0473.
3.2.12 Implementstion of Maior Programs one objective of the administrative controls is to ensure that implementation of major programs such as the CDCM, PCP, and major changes to the radioactive weste treatment system follow appropriate administrative procedures. Se Licensee has made a commitment to review, report, and implemen't major programs such as the CDCM and PCP, and to document and report major changes to the radioactive waste treatment system. Rose commitments meet the intent of MUREG-0473.
TER-C5506-106 3.3 OFFSITE DOSE CALCULATION MANUAL (ODCM)
As specilled in NUREG-0473, the ODCM is to be developed by the Licensee to document the methodology and approaches used to criculate offsite doses and maintain the operability of the effluent systems. As a minimum, the ODCM should provide equations and methodology for the following topics:
o alarm and trip setpoint on affluent instrumentation o liquid effluent concentration in unrestricted areas gaseous effluent dose rate at or beyond the site boundary o
l o liquid and gaseous effluent dose contributions liquid and gaseous effluent dose projections.
o In addition, the ODCM should contain flow diagrams, consistent with the systems being used at the station, defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems. A description and location of samples in support of the environmental monitoring program are also needed in the ODCH.
3.3.1 Evaluation The Licensee has followed the methodology of NUREG-0133 [9] to determine the alarm and trip setpoints for the liquid effluent monitors, which ensures that the maximum permissible concentrations, as specified l'n 10CFR20, will not be exceeded by discharges from various liquid or gaseous release points.
The Licensee demonstrated the method of calculating the radioactive liquid concentration by describing in the ODCM the means of collecting and analysing representative samples prior to and after releasing liquid affluents into the circulating water discharge.
Methods are also included for showing that dose rates released to unrestricted areas due to noble gases, radiciodine, and particulates with half-lives greater than 8 days are in compliance with 10CFR20. In this calculation, the Licensee has considered effluent releases from the plant stack; those releases are being treated as elevated level. The Licensee -..
TER-C5506-106 intends to use.the maximally exposed individual and the critical organ as the reference recejtor. The Licensee has demonstrated that the described methods and relevant parameters have followed the conservative approaches provided by NUREG-0133 and Regulatory Guide 1.109.
Evaluation of the cumulative dose is to ensure that the quarterly and annual dose design objectives specified in RETS are not exceeded.
For liquid releases, the Licenses has identified fish ingestion and potable water consumption as the viable pathways. In the calculation, the Licensee has used the suggested methodology given in Regulatory Guide 1.109.
The Licer.see has used the maximally exposed individual as the reference i
receptor. To correctly assess the cumulative dose, the Licensee intends to I
estimate the dose once per 31 days.
Evaluation of the cumulative dose from noble gas releases includes both beta and gamma and air doses at and beyond the site boundary. The critical organs under consideration are the total body and skin for gamma and beta radiation, respectively. Again, the'Licent.ee has followed the methodology of NUREG-0133 and Regulatory Guide 1.109.
For iodine-131, iodine-133, tritium, and particulates with half-lives greater than 8 days, the Licensee has provided a method to demonstrate that l
cumulative doses calculated from the release meet both quarterly and annual I
design objectives.
I The Licensee has provided a brief description of sampling locations in Section 6 of the ODCM.
The Licensee has assessed the total dose (40CFR190 requirement) including the direct radiation, which satisfies the total dose provision of NUREG-0473.
In summary, the Licensee's CDCX uses documented and approved methods that l
are generally consistent with the methodology and guidance in NUREG-0133, and therefore the CDCM is an acceptable reference.
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TER-c5506-106 4.
CONCIESIONS
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Table 1 s,ummarizes the results of the final review and evaluation of the submittal for the oyster Creek Nuclear Generating Station proposed Radio-logical Effluent Technical Specifications (RETS). The following conclusions have been reached:
1.
The Licensee's proposed Radiological Effluent Technical Specifications (RETS) submitted October 22, 1984 [23] meet the intent of NURSG-0473, " Radiological Effluent Technical specifications."
2.
'the Licensee?s offsite Dose Calculation Manual (DDCM) submitted October 1, 1983 [20] uses documented and approved methods that are f
generally consistent with the criteria of NUREG-0133 and applicable to Oyster Creek Nuclear Generating Station. It is thus an acceptable reference.
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TER-C5506-106 Table 1.
Evaluation of Proposed Radiological Effluent Technical specifications
.(RETS), Cyster Creek Nuclear Generating station i
Technical specifications Replaces NRC staff or Updates std. RETS Licensee Existing NUREG-0473 Proposal Tech. Specs.
(section)*
(section)
(Section)
Evaluation Effluent 3/4.3.3.3.10 3.15.A To be added Meets the intent Instrumentation 3/4.3.3.3.11 3.15.B to Appendix A of NRC criteria Radioactive 3/4.11.1.1 3.6.I 3.6 Meets the intent Effluent 3/4.11.2.1 3.6.K Appendix A of NRC criteria Concentrations Offsite Doses 3/4.11.1.2, 3.6.3 3.6 Meets the intent 3/4.11.2.2, 3.6.L Appendix A of NRC criteria 3/4.11.2.3, 3.6.M 3/4.11.4 3.6.N Effluent 3/4.11.1.3 3.6.B To be added Meets the intent Treatment 3/4.11.2.4 3.6.E to Appendix A of NRC criteria Radioactivity 3/4.11.1.4 3.6.C To be added Meets the intent Inventory Limits 3/4.11.2.6 3.6.D to Appendix A of NRC criteria Explosive Gas 3/4.11.2.5B 3.6.F To be added Meets the intent Mixtures to Appendix A of NRC criteria in the interim solid Radioactive 3/4.11.3 3.14 To be added
. Meets the intent taste to Appendix A of NRC criteria l
Environmental 3/4.12.1 4.16 2.0 Meets the intent l
Monitoring Appendix B of NRC criteria Audits and 6.5.1, 6.5.2 6.5.3 6.5 Meets the intent Reviews Appendix A of NRC criteria Procedures and 6.8, 6.10 6.8, 6.10 6.0, 6.10 Meets the intent Records Appendix A of NRC criteria f
Reports 6.9 6.9 6.9 Meets the intent Appendix A of NRC criteria Implementation of 6.13, 6.14, 6.17, 6.18, To be added Meets the intent Major Programs 6.15 6.19 to Appendix A of NRC criteria
- section number sequence is according to NUREG-0473, Rev. 3, Draft 7" [12)..
I TER-C5506-106 5.
REFERENCES J
E 1.
"Radiolo(ical Effluent Technical Specifications for Boiling Water Reactors," Rev. 2 NRC, July 1979 NUREG-0473 2.
Title 10, Code of Federal Regulations, Part 50, Appendix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the criterion, 'As Low As Is Reasonably Achievable,' for Radioactive Material in Light-Water-Coolud Nuclear Power Reactor Effluents" j
3.
Title 10, Code of Federal Regulations, Part 50, Appendix I,Section V,
" Effective Dates" 4.
Title 10, Code of Federal Regulations, art 20, " Standards for Protection Against Radiation"
- 5.
- Title 40, Code of Federal Regulations, Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operations" 6.
Title 10, Code of Federal Regulations, Part 50, Appendix A, " General Design criteria for Nuclear Power Plants" 7.
Title 10, Code of Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" "RadiologicalEf[1uentTechnicalSpecificationsforPressurisedWater 8.
Reactors," Rev. 2 NRC, July 1979 NUREG-0472 x
9.
" Preparation of Radiological Effluent Nachnical Specifications for l
Muclear Power Plants, A Guidance ManuaE for Users of Standard Technical l
Specifications" NBC, October 1978 NUREG-0133 1
I 10.
C. Willis and F. Congel (NRC)
'Susmary of Draft Contractor Guidance of RETS" Presented at the AIF Environmental Subccanittee Meeting, Washington, DC May 19, 1982 11.
F. Congol (NRC)
Memo to RAB Staff (NRC)
Subject:
Interim Changes in the Model Radiological Effluent Technical l
Specifications (RETS) j August 9,1982... _. _
4
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e TER-C5506-106 4
12.
N. Meinke (NRC) h ao to N.. Strum (Yankee Atostic Electric Company) subjects fSpecific Osanges for NUREG-0472/3, Rev. 3
?
september 20, 1982 l
13.
" Radiological Effluent Technical Specifications for Boiling Mater Weactors," Rev. 3, Draft 7",-intended for contractor guidance in reviewing METS proposals for' operating reactors WRC, December 1983 NUREG-0473 l
2 1
14.
Oyster Creek Nuclear Generating Station Radiological Effluent Technical specifications l
General Public Utility Nuclear Corporation, 1979 NRC Docket No. 50-219 15.
Dyster Creek Nuclear Generating Station Offsite Dose Calculation Manual General Public Utility Nuclear Corporation, 1979 NRC Docket No. 50-219 16.
" Comparison of Specification NUREG-0473, Radiological Effluent Technical i
specifications for EWRs, vs. Licensee Substittal of Radiological Effluent Technical Specifications for' Oyster Creek Nuclear Generating Station" (Draft)
Franklin Wesearch Center, January 27, 1982 i
- 17. Technical Review of Offsite Dose Calculation Manual for Oyster Creek l
Nuclear Generating Station (Draft)
Franklin Research Center, January 26, 1982 18.
Franklin Research Center Letter of Transmittal to MN:.
Subject:
Trip report on site visit to Oyster Creek Nuclear Generating Station February 4, 1982 19.
OysterCreekMuclearGeneratIngStationRadiologicalEffluentTechnical Specifications (RETS), Draft.
GPU Nuclear Corporation September 26, 1983 NRC Docket No. 50-219 20.
Oyster Creek Nuclear Generating Station Offsite Dose Calculation Manual, (ODCN)
GPU Nuclear Corporation October 1, 1983 i
NRC Docket No. 50-219 i
I l
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6 s
TER-C5506-106 21.
S.Pandey[S.Chen(FRC)
Memo to W. Meinke (NRC)
Subject FRC's Comments on Oyster Creek Draft RETS Submittal f
January
, 1984 22.
S. Pandey/S. Chen (FRC)
Memo to W. Meinke (NE)
Subject:
FRC's Comments on Oyster Creek Draft CDCM Submittal i
April 20, 1984 23.
P. B. Fiedler (CPU)
Letter to W. A. Paulson (NE)
Subject:
Proposed Radiological Effluent Technical Specifications for Oyster Creek Nuclear Generating Station October 22, 1984~
NRC Docket No. 50-219 24.
" Comparison of Specification NUREG-0473, Radiological Effluent Technical Specifications for SWRs, vs. Licensee Final Submittal, dated October 22, 1984, of Radiological Effluent Technical Specifications for Oyster Creek Muclear Generating Station" Franklin Research Center, June 1985 l
25.
W. Meinke (NRC) i Memo to S. Pandey (FRC)
Subject:
Comments on Oyster Creek's RETS submittal i
June 6, 1985 l
26.
C. Willis (NRC)
Letter to Dr. S. Pandey (FE)
Subject:
Changes to RETS requirements following meeting with Atomic Industrial Forum (AIF)
November 20, 1981 a
27.
C. Willis (NE)
Letter to Dr. S. Pandey (FRC)
Subject:
Control of explosive gas mixture in PWRs December 18, 1981 28.
C. Willis and F. Congel (NE)
" Status of NRC Radiological Effluent Technical Specification Activities" Presented at the AIF Conference on NEPA and Nuclear Angulations, Washington, D.C.
October 4-7, 1981 29.
C. Willis (wRC)
Memo to P. C. Wagner (NRC)
" Plan for Implementation of RETS for Operating Reactors" November 4,1981..
/
TER-C5506-106 30.
W. P. Gaamaill (NRC)
Memo to P4 C. Wagner (NRC)
" Current Fositi n on Radiological Effluent Technical specifications (RETS) Including Explosive Gas Controls" October 7, 1981 31.
"An Acceptable Radiological Environmental Monitoring Program" Radiological Assessment Branch Technical Posjtion, Revision 1 November 1979 32.
W. P. c===111/P. J. Congel (NRC)
Memo to ETSB/RAB (N3C)
" Radiological Effluent Technical specifications (RETS) Provisions for 1-133" November 29, 1982
NRC, February 1980 NUREG-0543 34.
" General contents of the offsite Dose Calculation Manual," Revision 1 Branch Technical Position, Radiological Assessment Branch February 8,1979 35.
Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I NRC, October 1977 Regulatory Guide 1.109, Revision 1 l
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