ML20058L723
| ML20058L723 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/13/1993 |
| From: | Stollz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L729 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9312170162 | |
| Download: ML20058L723 (34) | |
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UNITED STATES 4 {h NUCLEAR REGULATORY COMMISSION k.....,/
WASHINGTON. D.C. 20555-0001 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATINC LICENSE Amendment No. 166 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated October 8, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the.
Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9312170162 931213 ADOCK0500g9 PDR P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate'the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be-implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISEION I
Jo n F. Stolz, Directo #
P ject Directorate I ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 13, 1993
n ATTACHMENT TO LICENSE AMENDMENT NO. 166 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert l
ii 11 iii iii 1.0-6 1.0-6 3.6-la 3.6-1 3.6-lb 3.6-2 3.6-2 3.6-3 3.6-3 3.6-4 3.6-4 3.6-5 3.6-5 3.6-6 3.6-6 3.6-7a 3.6-7b 3.6-8 3.6-9 3.6-10 3.14-1 3.14-1 3.15-1 3.15-1 3.15-2 3.15-2 3.15-3 3.15-3 3.15-4 3.15-5 3.15-6 3.15-7 3.15-8 4.6-1 4.6-1 4.6-2 4.6-2 4.6-3 4.6-4 4.6-5 4.6-6 4.6-7 4.6-8 4.6-9 4.6-10 4.14-1 4.14-1 4.15-1 4.15-1 4.15-2 4.15-2 4.15-3 4.15-4 4.15-5
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4.16-3 4.16-4 l
4.16-5 4.16-6 4.16-7 6-10 6-10 6-11 6-11 6-12 6-12 i
6-12a 6-12b 6-13 6-13 6-14 6-14 i
6-15 6-15 6-16 6-16 6-17 6-17 6-18 6-18 6-19 6-20 l
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TABLE OF CONTENTS (Cont'd)
Section 3 Limiting Conditions for Operation 3.0 Limiting Conditions for operation (General) 3.0-1 3,1 Protective Instrumentation 3.1-1 3.2 Reactivity control 3.2-1 3.3 Reactor Coolant 3.3-1 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1 3.6 Radioactive Effluents 3.6-1 3.7 Auxiliary Electrical Power 3.7-1 3.8 Isolation condenser 3.8-1 3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 3.12 Alternate Shutdown Monitoring Inctrumentation 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1 3.14 DELETED 3.14-1 3.15 Explosive Cas Monitoring Instrumentation 3.15-1 3.16 (Not Used) 3.17 Control Room Heating, Ventilating and Air Conditioning System 3.17-1 Section 4 Surveillance Requirements 4.1 Protective Instrumentation 4.1-1 4.2 Reactivity Control 4.2-1 4.3 Reactor Coolant 4.3-1 4.4 Emergency Cooling 4.4-1 4.5 Containment 4.5-1 4.6 Radioactive Effluents 4.6-1 4.7 Auxiliary Electrical Power 4.7-1 4.8 Isolation Condenser 4.8-1 4.9 Refueling 4.9-1 4.10 ECCs Related Core Limits 4.10-1 4.11 Sealed Source Contamination 4.11 I 4.12 Alternate Shutdown Monitoring Instrumentation 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 4.14 DELETED 4.14-1 4.15 Explosive Gas Monitoring Instrumentation 4.15-1 4.16 Radiological Environmental Surveillance (Deleted) 4.16-1 4.17 Control Room Heating, Ventilating and Air Conditioning System 4.17-1 I
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l OYSTER CREEK 11 Amendment No.: 64, 84, 97, 108, 115, 126, 16 L 166 i
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4 TABLE OF CONTENTS fcent*di section 5 Design Features 5.1 Site 5.1-1 5.2 containment 5.2-1 5.3 Auxiliary Equipment 5.3-1 Section 6 Administrative Controls 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications 6-2a 6.4 Training 6-3 6.5 Review and Audit 6-3 6-6 Reportable Event Action 6-9 6-7 Safety Limit Violation 6-9 6-8 Procedures and Programs 6-10 6-9 Reporting Requirements 6-13 6-10 Record Retention 6-17 6-11 Radiation Protection Program 6-18 6-12 (Deleted) 6-18 6-13 High Radiation Area 6-18 6-14 Environmental Qualification 6-19*
6-15 Integrity of Systems outside containment 6-19 6-16 Iodine Monitoring 6-19 6-17 Post Accident Sampling 6-20 6-18 Process Control Plan 6-20 6-19 Offsite Dose Calculation Manual 6-20
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6-20 DELETED 6-20 l
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- Issued by NRC Order dated 10-24-60 OYSTER CREEK 111 Amendment No.s94, 97, 98 108, 115, 134 166
~9 1.28 FRAC'" ION OF RATED PObTR fFPP)
The FRACTION OF RATED POWER is the ratio of core thermal power to rated thermal power.
1.29 TOP OF ACTIVE FUEL !TAF) - 353.3 inches above vessel zero.
4 1.30 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section i
50.73 to 10 CFR Part 50.
1.31 IDENTIFR D LEAKAGE IDENTIFIED LEAKAGE is that leakage which is collected in the primary containment equipment drain tank and eventually transferred to radwaste for processing.
1.32 UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE is all measured leakage that is other than identified leakage.
1.33 PROCESS CONTROL PLAN (PCP)
The PROCESS CONTROL PLAN shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1.34 AUGMENTED OFFGAS SYSTEM fAOG)
The AUGMENTED OFFGAS SYSTEM is a system designed and installed to holdup and/or process radioactive gases from the main condenser offgas system for the purpose of reducing the radioactive material content of the gaees before release to the environs.
1.35 MEMBER OF THE PUBLIC A MEMBER OF THE PUBLIC is a person who is not occupationally associated i
with GPU Nuclear and who does not normally frequent the Oyster Creek Nuclear Generating Station site.
The category does not include contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on the site, or for i
other purposes associated with plant functions.
l.36 OFFSITE DOSE CALCULATION HANUAL (ODCM)
The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive geseous and liquid effluent, in the calculation of gaseous 5
and liquid ef fluent monitoring Alarm / Trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 3.6 AND 3.15, respectively; and, (2) descriptions of the information that should be included in the Annual Radioactive Effluent Release Report AND Annual i
Radiological Environmental Operating Report required by Specifications 6.9.1.d and 6.9.1.e, respectively.
i OYSTER CREEK 1.0-6 Amendment No.: 14, 28, 29,75,84,108, 138. 166 Correction 10-10-78
3.6 Padioactive Effluents Aeolicability:
Applies to the radioactive effluents of the facility.
Obiective:
To assure that radioactive material is not released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released is kept as low as is reasonably achievable and, in any event, within the limits of 10 CFR part 20.106 and 40 CFR Part 190.10(a).
Specification 3.6.A.
Peactor Coolant Radioactivity The specific activity of the primary coolant except during REFUEL MODE shall be limited to: Less than or equal to 0.2 microcuries per gram DOSE EQUIVALENT (D.E.) I-131.
Limiting condition for Operation 1.
Whenever an isotopic analysis shows reactor coolant activity exceeds 0.2 uci/ gram DOSE EQUIVALENT (D.E.) I-131, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Additional analyses shall be done at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within its limit.
2.
If the reactor coolant activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram D.E.
I-131, be in at least SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.
Annual Reporting Requirement The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.6.A shall be reported on an annual basis.
The following information shall be included (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radioiodine activity is reduced to less than the limit; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after radiciodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radiciodine activity is reduced to i
less than the limit; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state levels and, (5) The time duration when specific activity of the primary coolant exceeded the radiciodine limit.
h If there are eensecutive thermal power changes by more than 15% per hour, take sample and analyze at least Eng sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change and at least once per four hours thereafter, until
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the specific activity of the primary coolant is restored to within limits.
OYSTER CREEK 3.6-1 Amundment No.: 48, 108, 126, 166 l
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4.
With the reactor mode switch in Run or Startup position, with:
1.
Thermal power changed by more than 15% of rated thermal power in one hour *, or 2.
The off-gas level, at the SJAE, increased by more than 10,000 microcuries per second in one hour during steady state operation at release rates less than 75,000 microcuries por second, or 3.
The off-gas level, at the SJAE, increased by more than 15% in one hour during steady state operation at release rates greater than 75,000 microcuries per
- second, take sample and analyze at least one sample, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change in thermal power or off-gas level and at least once per four hours thereafter, until the specific activity of the primary coolant is restored to within limits.
3.6.B Licuid Radwaste Treatment - RELOCATED TO THE ODCM 3.6.C Padioactive Licuid Storace Applicability: Applies at all times to specified outdoor tanks used to store radioactive liquids.
1.
The quantity of radioactive material, excluding tritium, noble gases, and radionuclides having half-lives shorter than three days, contained ir, any of the following outdoor tanks shall not exceed 10.0 curies:
a.
Waste Surge Tank, HP-T-3 b.
Condensate Storage Tank 2.
In the event the quantity of radioactive material in any of the tanks named exceeds 10.0 curies, b<Sgin treatment as soon as reasonably achievable, continue it until the total quantity of radioactive material in the tank is 10 curies or less, and describe the reason for exceeding the limit in the next Annual Effluent Release Report.
l 3.
Specifications 3.0. A and 3.0.B do not apply.
3.6.D Condenser Offcan Treatment - RELOCATED TO THE ODCM 3.6.E Main Condenser Offene Padioactivity 1.
The gross radioactivity in noble gases discharged from the main condenser air ejector shall not exceed 0.21/E Li/see after the holdup line where E is the average gamma asnergy (Mev per atomic transformation).
2.
In the event Specification 3.6.E.1 is exceeded, reduce the discharge rate below the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least SHUTDOWN CONDITION within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
OYSTER CREEK 3.6-2 Amendment No.: 48, 108, 126. 166
N 3.6.F Condenser Oftcas Hydrocen Concentra M 1.
The concentration of hydrogen in the Augmented Offgas System (AOG) downstream of the recombiner during AOG operation shall not exceed 4 percent by volume.
2.
In the ervent the hydrogen concentration downstream of a recorr.biner exceeds 4 percent by volume, the concentration shall be reduced to less than 4 percent within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
3.
In the event the hydrogen concentration is not reduced to 14 l
percent within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, bo in at least SHUTDOWN CONDITION or within the limit within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.G Not used.
3.6.H Not used.
3.6.I Rad ioact ivity C# eentration in Lieuid Effluent RELOCATED TO THE ODCM 3.6.J Limit on D7se Due to Licuid Effluent RELOCATED TO THE ODCM 3.6.K Dose Rate Due to Gaseous Effluent RELOCATED M THE ODCM 3.6.L Air Dose Due to Noble Gas in Gaeeous Effluent RELOCATED TO THE ODCM 3.6.M Dese Due to Radiciodine and Particulates in Gaseous Effluent RELOCATED TO THE ODCM 3.6.N Annual Total Dose Due to Radioactive Effluents RELOCATED TO THE ODCM OYSTER CREEK 3.6-3 Amendment No.: 49, 108, 126 166 I
9%,
Basist 3.6.A 10 CFR 100, as implemented by SRP Section 15.6.4, requires that the radiological consequences of failure of a main steam line outside containment be limited to small fractions of the exposure guidelines of 10 CFR 100.
During Systematic Evaluation Program (SEP) for Oyster Creek, an independent assessment of the radiological consequences of a main steam line failure outside containment *SEP Topic XV-18) was performed by the NRC staff.
The assessment determined that if the existing Oyster Creek Technical Specification limit for primary coolant iodine activity (8.0 uci total iodine per gram) is used, the potential offsite deses would exceed the applicable dose limit. The staff recommended that Oyster Creek maintain the primary coolant radiciodine activity within the General Electric Str adard Technical Specification (NUREG-0123) limit (0.2 uCi/ gram DOSE EQUIVALENT I-131), which would meet the acceptance criteria.
However, the Staff's analyses for Oyster Creek showed that small-line failures are more limiting than the main steam line failure.
10 CFR 100, as implemented by SRP Section 15.6.2, requires that the radiological consequences of failure of small lines carrying primary coolant outside containment be limited to small fractions of the exposure guidelines of 10 CFR 100.
During the evaluation of SEP Topic XV-16 " Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment" the Staff determined that Oyster Creek does not comply with current acceptance criteria. The Staff recommended that the General Electric Standard Technical Specification (NUREG-0323) limit (0.2 uCi/ gram DOSE EQUIVALENT I-131) for reactor coolant radiciodine activity be adopted in order to ensure that the radiological consequences to the environment from a failure of small lines are acceptably low.
The LCO statement permitting power operation to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 microcuries per gram DOSE EQUIVALENT I-131, accommodates possible iodine spiking 1
phenomenon which may occur following changes in thermal power.
The reporting of cumulative operating time with greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 will allow sufficient time for Commission to evaluate the circumstances.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analysis following power changes may be permissible if justified by the data obtained.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.
3.6.B RELOCATED TO THE ODCM l
OYSTER CREEK 3.6-4 Amendment No.: 49, 108, 126 166
4 3.6.C Restricting the quantity of radioactive material contained in che specific tanks provides assurance that in the event of an urcontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2 in the canal at the Route 9 bridge.
P Retaining radioactive liquids on-site in order to permit systematic and appropriate processing is consistent with maintaining radioactive discharges to the environment as low as practicable. Limiting the contents of each outside tank to 10 curies or less assures that even if the contents of a tank were released onto the ground and drained into the discharge canal, the potential dose to a member of the public is estimated to be less than 1 percant of the 500 mem/ year limit to the total body of a member of the public and only 1 percent of the corresponding 1500 mrem / year standard for a single organ.
In the highly unlikely event that every outside tank named in Specification 3.6.C were to contain 10 curies and the contents of all were to spill into the discharge canal, the potential dose to a member of the public is estimated to be only about 2 percent of the 500 mrem / year limit to the total body and about 6 percent of the corresponding 1500 mram/ year standard.
3.6.D RELOCATED TO THE ODCM 3.6 E Some radioactive materials are released from the plant under controlled conditions as part of the normal operation of the facility.
Other radioactive material not normally intended for release could be inadvertently released in the event of an accident.
Therefore, limits in 10 CFR Part 20 apply to releases during normal operation and limits in 10 CFR Part 100 apply to accidental releases.
Radioactive games from the reactor pass through the steam lines to the turbine and then to the main condenser where they are extracted by the air ejector, passed through holdup piping and released via the plant stack preferably after treatment in the Augmented Offgas System.
Radioactive materials release limits for the plant stack have been calculated using meteorological data from a 400 ft. tower at the plant site. The analysis of these on-site meteorological data shows that a release of radioactive gases after 30 minutes holdup in the offgas system of 0.3 C1/sec., would not result in a whole body radiation dose exceeding the 10 CFR 20 value of 0.5 rem per year.
]
The Holland plume rise model with no correction factor was used
)
in the calculation of the effect of momentum and buoyancy of a continuously emitted plume.
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OYSTER CREEK 3.6-5 Amendment No.: 49, 108, 12 6 166
1 Independent dose calculations for several locations offsite were made by the AEC staff from onsite meteorological data developed by the licensee and diffusion assumptions appropriate to the site.
The procedure followed is described in Section 7-5.2.5 of
" Meteorology and Atomic Energy - 1968," equation 7.63 being used.
The results of these calculations were equivalent to those generated by the licensee provided the average gamma energy per disintegration for the assumed noble gas mixture with a 30 minute holdup is 0.7 MeV per disintegration. Based on these calculations, a maximum release rate limit of gross activity, except for iodines and particulates with half lives longer than eight days, in the amount of 0.21/E curies per second will not result in off-wite annual _, doses in excess of the limits specified in 10 CFR Part 20.
The E 'Jetermination need consider only the average gamma energy per oisintegration since the controlling whole body dose is due to the cloud passage over the receptor and not cloud submersion, in which the beta dose could be additive.
A subsequent licensee calculation, using ODCM methodology and based on representative 1989 and 1990 air ejector of fgas - Noble gas concentrations, has established that a release rate of.34 Ci/see would be within 10 CFR 20 limits, assuming a maximum projected Ei of 0.93 Nov/ disintegration.
The above discussion does not take into consideration the reduction in release rate afforded by operation of the Augmented Offgas System.
3.6.F The purpose of Specification 3.6.F is to require that the concentration of potentially explosive gas mixtures in the Augmented Offgas system be maintained below the flammability limit of hydrogen in air, although the AOG is designed to withstand a hydrogen explosion.
Specification 3.6.F applies to the hydrogen concentration downstream of a recombiner during AOG operation.
The AOG has redundant recombiners so that the recombiner in use can be isolated and purged with air in the event hydrogen in it exceeds the specified limit.
3.6.G NOT USED 3.6.H NOT USED 3.6.I RELOCATED TO THE ODCM 3.6.J RELOCATED TO THE ODCM 3.6.K RELOCATED TO THE ODCM 3.6.L RELOCATED TO THE ODCM i
3.6.M RELOCATCD TO THE ODCM 3.6.N RELOCATED TO THE ODCM OYSTER CREEK 3.6-6 Amendment No.: 49, 108, 166
"I 3.14 Solid Radioactive Weste - DELETED T
b OYSTER CREEK 3.14-1 Amendment No.: 108, 166 t
3.15 Egolosive Gas Monitorine Instrumentation Obieetive: The explosive gas monitoring instrumentation channels shown in Table 3.15.2 shall be OPERABLE with Alarm / Trip setpoints set to ensure that the limits of Specification 3.6.F are not exceeded.
Arnlicability:
As shown in Table 3.15.2 Specification A.
Exelosive Gas Instrumentation 1.
With an explosive gas monitoring instrumentation channel Alarm / Trip setpoint less conservative than required by the Objective above declare the channel inoperable and take ACTION shown in Table 3.15.2.
2.
With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.15.2.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3.
3.
The provisions of Specifications 3.0 and 3.1 are not applicable.
Basis:
A.
The explosive gas monitoring instrumentation in Table 3.15.2 is provided for monitoring hydrogen below the explosive level in the Offgas System downstream from the recombiner. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR 50.
The offgas hydrogen monitor has an alarm which reports ir the reacter Control Room.
The offgas hydrogen monitor initiates.y typass of the Augmented Offgas System in the event the setpoint is exceeded.
1 OYSTER CREEK 3.15-1 Amendment No.: 108, 16f l
TABLE 3.15.2 O
EXPI/1SIVE MONITORING INSTRUMENTATION 4
et*
Minimum (a) g Channels Essential f,
Instrument Operable Function Applicability Action Q
1.
Main Condenser Offgas Treatment System 2(d)
Monitor hydrogen (c) 125 Recombiner Effluent Hydrogen Monitor concentration Y
0 l>
li I
a
=
?
m A
N
\\
l TABLE 3.15.2 NOTATIONS (a) Channels shall be OPERABLE and in service as indicated except that a channel may be taken out of service for the purpose of a check, calibration, test, maintenance or sample media change without declaring the channel to be inoperable.
(b) NOT USED (c) During Augmented Offgas Treatment System operation.
(d) One hydrogen and one temperature sensor.
ACTION 125 With one channel OPERABLE, operation of the main condenser offgas treatment system may continue provided a recombiner temperature sensing instrument is operable. When only one of the types of instruments, i.e.,
hydrogen monitor or temperature monitor, is operable, the offgas treatment system may be operated provided a gas gample is collected at least once per day and is analyzed for hydrogen within four i
hours.
In the event neither a hydrogen monitor nor a recombiner temperature sensing instrument is operable when required, the Offgas Treatment System may be operated provided a gas sample is collected at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l 1
lbb OYSTER CREEK 3.15-3 Amendment No.:
108+
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4.6 RADIOACTIVT EFFLUENT I
Aeolicability:
Applies to monitoring of gaseous and liquid radioactive effluents of the Station during release of effluents via the monitored pathway (s).
Each Surveillance Requirement applies whenever the corresponding Specification
)
is applicable unless otherwise stated in an individual Surveillance Requirement.
Surveillance Requirements do not have to be performed on inoperable equipment.
Obiectives To measure radioactive ef fluents adequately to verify that radioactive effluents are as low as is reasonable achievable and within the limit of 10 CFR Part 20.106.
i Snecification:
A.
Reactor Coolant Reactor coolant shall be sampled and analyzed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for DOSE EQUIVALENT I-131 during RUN MODE, STARTUP MODE (.nd SHUTDOWN CONDITION.
B.
NOT USED.
C.
Radioactive ticuid Storace 1.
Liquida contained in the following tanks shall be sampled and analyzed for radioactivity at least once per 7 days when radioactive liquid is being added to the tank:
a.
Waste Surgo Tank, HP-T-3, B.
Condensate Storage Tank.
D.
Mpin Condenser Offeas Treatment RELOCATED TO THE ODCM E.
Main Condenser Offcas kadioactivity 1.
The gross radioactivity in fission gases discharged from the main condenser air ejector shall be measured by sampling and analyzing the gases.
a.
at least once per month, and b.
When the reactor is operating at more than 40 percent of rated power, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an increase in the fission gas release via the air ejector of more than 50 percent, as indicated by the condenser Air Ejector Offgas Radioactivity Monitor after factoring out increase (s) due to change (s) in the thermal power level.
F.
Condenser Offcas Hydrocen Concentration The concentration of hydrogen in of fgases downstream of the I
recombiner in the Offgas System shall be monitored with hydrogen instrumentation as described in Table 3.15.2.
i G.
NOT USED.
H.
NOT USED.
OYSTER CREEK 4.6-1 Amendment No.: 108, 126, 166
)
dE I.
P a d ioa ct ivity Concentration in Licuid Effluent RELOCATED TO THE CDCM J.
Dose due to Licuid Effluent RELOCATED TO THE ODCM K.
Dose Rate Due to Gaseous Ef fluent RELOCATED TO THE ODCM L.
NOT USED.
M.
Dose Due to Radiciodine and Particulates in Gaseous Effluent RELOCATED TO THE ODCM N.
Annual Total Dose Due to Pr.dwaste Effluent RELOCATED TO THE ODCM.
Baeis:
1 A.
The reactor water sample will be used to assure that the limit of Specification 3.6. A is not exceeded. The total radioactive iodine activity would not be expec'.ed to change rapidly over a 1
period of several days.
In addition, the trend of the stack off-gr.s release re.te, which is continuously monitored, is a good indicator of the trend of the iodine activity in the reactor coolant.
RELOCATED TO THE ODCM.
166 OYSTER CREEK 4.6-2 Amendment No.: 108, 126
'N 4.14 solid Radioactive Waste - DELETED 1
OYSTER CREEK 4,14 1 Amendment No.:
108, 166
gg 4.15 Explosive Gas Monitorino Instrumentation Applicability: States surveillance requirements for OPERABILITY of explosive gas monitoring instrumentation.
Obiective To demonstrate the OPERABILITY of explosive gas monitoring instrumentation.
Specification:
Gaseous Effluent In st rument ation Each explosive gas effluent monitoring instrument channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.15.2.
4 l
I i
l OYSTER CREEK 4.15-1 Amendment No.: 10e, 166
O]
]
TABLE 4.15.2 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION (f) TEST REQUIRED (a)
- 1. Main Condenser D
N/A Q(g)
M (c).
Offgas Treatment System Hydrogen Monitor i
Lgcend D = once per 24 hrs; M = once per 31 days; Q = once per 92 days; N/A = Not Applicable.
l l
l TABLE 4.15.2 NOTATIONS (a)
Instrumentation shall be OPERABLE and in service except that a channel may i
be taken out of service for the purpose of a check, calibration, test or maintenance without declaring it to be inoperable.
(c) During main condenser offgas treatment system operation.
(f) The CHANNEL CALIBRATION shall be performed according to established station calibration procedures.
(g)
A CRANNEL CALIBRATION shall include the use of at least two standard gas samples, each containing a known volume percent hydrogen in the range of the instrument, balance nitrogen.
t h
s OYSTER CREEK 4.15-2 Amendment No.:
145, 155
M 4
4.16 Radiolocleal Environmer.tal Surveillance RELOCATED TO THE ODCM l
OYSTER CREEK 4.16-1 Amendment No.: 103 166
=-,
.- +
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the items referenced below a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33 as referenced in the CPU Nuclear operational Quality Assurance Program.
b.
Surveillance se$ test activities of equipment that affects nuclear safety and radioactive waste management equipment.
c.
Refueling Operations.
d.
Security Plan Implementation.
e.
Fire Protection Program Implementation.
f.
Emergency Plan Implementation.
g.
Process Control Plan Implementation.
h.
Offsite Dose Calculation Manual Implementation.
- i. Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 4.15, Revision 1.
j.
Plant Staff Overtime pursuant to Technical Specification 6.2.2.2(1), above.
I 6.8.2 Each procedure required by 6.8.1 above, and substantive changes thereto, shall be reviewed and approved as described in 6.5.1 prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1, above, may be made provided:
a.
The intent of the original procedure _is not altered; b.
The change is approved by two members of GPU Nuclear Management Staff qualified in accordance with 6.5.1.14 and knowledgeable in the area affected by the procedure. For changes which may affect the operational status of unit systems or equipment, at least one of these individuals shall be a member of unit management or supervision holding a Senior Reactor Operator's License on the unit.
c.
The change is documented, reviewed and approved as described in 6.5.1 within 14 days of implementation.
OYSTER CREEK 6-10 Amendment No.: 69, 78, 84, 108, 125, 134, 161, 166 1
~1 1
6.8.4 The following programs shall be established, implemented and maintained:
a.
Padioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a l
for the control of radioactive effluent and for maintaining l
the doses to MEMBERS OF THE PUBLIC from radioactive effluent as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1.
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including the surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2.
Limitations on the concentrations of radioactive material released in liquid effluent to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2.
3.
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluent in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCH.
4.
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to UNRESTRICTED AREAS conforming to Appendix I of 10 CFR 50, 5.
Determination of cumulative and projected dose contributions from radioactive affluent for the current calendar quarter and the current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6.
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in the 31 day period would exceed 2 percent of the i
guidelines for the annual dose or dose commitment I
conforming to Appendix I to 10 CFR 50, 7.
Limitations on the dose rate resulting from radioactive materials released in gaseous affluent to areas beyond the EXCLUSION AREA boundary conforming to doses associated with 10 CFR 20, Appendix B, Table II, Column 1,
8.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents beyond the EXCLUSION AREA boundary conforming to Appendix I of 10 CFR 50, OYSTER CREEK 6-11 Amendment No.: 69, 78, 84, 108, 125, 134, 166
j 1$-
l 4
- 9. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluent released beyond the EXCLUSION AREA boundary conforming to Appendix I of 10 CFR 50,
- 10. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from Uranium fuel cycle sources conforming to 40 CFR Part 190.
b.
Radiolocical Environmental Monitorine Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the
- ODCM, 2.
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3.
Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
CTSTER CREEK 6-12 Amendment No.: 69, 78, 84, 108, 166 j
125, 134 l
l
9 6.9 REPORTING REOUTREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Administrator of I
the NRC Region I office unless otherwise noted.
I 6.9.1 ROUTINE REPORTS a.
Startuo Report.
A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design of a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the i
operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specified details required in I
license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e.,
initial criticality, completion of startup test program, and resumptG..a or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
b.
Annual Exposure Data Reoort.
Routine exposure data reports covering the operation of the facility during the previous calendar year shall be submitted prior to March 1 of.each year.
Reports shall contain a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated man rem exposure according to work and job functions (this tabulation supplements the requirements of 10 CFR 20.407),
e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
c.
Monthly Operatino Reoort.
Routine reports of operating statistics and shutdown experience shall be submitted on a monthly: basis which will include a narrative of operating experience, to the Director, Office of Management and Program Control, U.S. Nuclear Regulatory Commission, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report.
OYSTER CREEK 6-13 Amendment No. 269, 16078, 84, 108, 125,
- 134,
d.
Annus) Padioactive Effluent Pelease Report The Annual Radioactive Effluent Release Report covering the operations of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1, each year.
The Report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit.
The material provided shall bas (1) consistent with the objectives outlined in the ODCH and PCP; and, (2) in conformance with 10 CFR 50.36(a) and Section IV.B.1 of Appendix I to 10 CFR Part 50.
e.
Annual Radiolocical Environmental Operatina Pecort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The Report shall include summaries, interpretations, and an analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined int (1) the ODCH; and, (2)
Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
f.
CORE OPERATING LIMITS REPORT (COLR) 1.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle for the followings a.
The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.10.A b.
The K, core flow adjustment factor for Specification 3.10.C.
c.
The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.10.C d.
The LOCAL LINEAR HEAT GENERATION RATE (LLHGR) for i
specification 3.10.B.
and shall be documented in the COLR.
2.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the i
following documents.
a.
GPU Nuclear (GPUN) Topical Report (TR) 020, Methods for the Analysis of Boiling Water Reactors Lattice i
Physics, (The approved revision at the time reload-analyses are performed shall be identified in the COLR.)
b.
GPUN TR 021, Methods for the Analysis of Boiling Water Reactors Steady State Physics, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
OYSTER CREEK 6-14 Amendment No.: j$6,108, 134, 147
N E
c.
GPUN TR 033, Methods for the Generation of Core Kinetics Data for RETRAN-02, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
d.
GPUN TR 040, steady-State and Quasi-Steady-State Methods Used in the Analysis of Accidents and Transients, (The approved revision at the time reload analyses are performed shall be identified in the CCLR.)
e.
GPUN TR 045, BWR-2 Transient Analysis Model Using the Retran Code, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
f.
NEDE-31462P and NEDE-31462, Oyster Creek Nuclear Generating Station SAFER /CORECOOL/GESTR-LOCA Loss-of-coolant Accident Analysis, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
g.
NEDE-24011, General Electric Standard Application for Reactor Fuel, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
h.
NEDE-24195, General Electric Reload Fuel Application for Oyster Creek, (The approved revision at the time reload analyses are performed shall be identified in the COLR.)
1.
XN-75-55-(A); XN-75-55, Supplement 1-(A); XN-75-55, Supplement 2-(A), Revision 2,
" Exxon Nuclear Company WREM-Based NJP-BWR ECCS Evaluation Model and Application to the Oyster Creek Plant," April 1977 j.
XN-75-36(NP)-(A); XN-75-36(NP), Supplement 1-(A),
" Spray Cooling Heat Transfer Phase Test Results, ENC
- 8x8 BWR Fuel 60 and 63 Active Rods, Inter im Report," October 1975 3.
The core operating limits shall be deta. mined such that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.
4.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector, o
Basies 6.9.1.e - RELOCATED TO THE ODCM 6.9.2 RFPORTABLE EVENTS The submittal of Licensee Event Reports shall be accomplished in accordance with the requirements set forth in 10 CFR 50.73.
OYSTER CREEK 6-15 Amsndment No. 147, 166
\\
1El l 6.9.3 UNIOUE REPORTING REOUIREMENTS Special reports shall be submitted to the Director of Regulatory Operations Regional Office within the time period specified for each l
report. These reports shall be submitted covering the activities I
identified below pursuant to the requirements of the applicable reference specification.
I Materials Radiation Surveillance Specimen Reports (4.3A) a.
b.
Integrated Primary Containment Leakage Tests (4.5) c.
Results of required leak tests performed on sealed sources if the tests reveal the presence of 0.005 microcuries or more of removable contamination.
d.
Core Spray Sparger Inservice Inspection (Table 4.3.1-9)
Prior to startup of each cycle, a special report presenting the results of the inservice inspection of the Core Spray Spargers during each refueling outage shall be submitted to the Commission for review.
i 1
e.-j.
Pursuant to the ODCM k.
Records of results of analyses required by the Radiological Environmental Monitoring Program.
1.
Failures and challenges to Relief and Safety Valves which do not constitute an LER will be the subject of a special report submitted to the Commission within 60 days of the i
occurrence. A challenge is defined as any automatic l
actuation (other than during surveillance or testing) of Safety or Relief Valves, ra. Plans for compliance with standby liquid control Specifications 3.2.C 3(b) and 3.2.C.3(e)(1) or plans to obtain enrichment test results per Specification 4.2.E.5.
n.
Inoperable high range radioactive noble gas effluent monitor (3.13H)
OYSTER CREEK 6-16 Amendment No.: 69, 78, 108, 124, 134, 137, 16L 166
't 6.10 RECORD PETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principle maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All Licensee Event Reports.
d.
Records of curveillance activities, inspections and calibrations required by these technical specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to operating procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating Licenses a.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant staff, h.
Records of inservice inspections performed pursuant to these technical specifications.
i.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
j.
Records of reviews by the Independent Onsite Safety Review Group.
OYSTER CREEK 6-17 Amendment No. 69, 108, 117, 134
- 166,
Y k.
Records of Environmental Qualification which are covered under the provisions for paragraph 6.14.
1.
Records of the service lives of all snubbers, including the date which the service life commences, and associated installation and maintenance records.
m.
Records of results of analyses required by the Radiological Environmental Monitoring Program.
n.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PLAN.
6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.
6.11 RADIATION PPOTECTION PROGRAM Procedures for persor.usi radiation protection shall be 7repared consistent with the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (Deleted) 6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1,000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
NOTE:
Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation i
protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.
An individual or group of individuals permitted to enter such areas shall be provided with one or more of the following a.
A radiation monitoring device which continuously indicates j
the radiation dose. ate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a pre-set integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have l
been made knowledgeable of them, c.
A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive sxposure control over the activities within the area and who will perform periodic radiation surveillance at the j
frequency in the RWP.
The surveillance frequency will be established by the Director responsible for radiological controls.
OYSTER CREEK 6-18 Amendment No.:69. 100, 108, 134, 166
6.13.2 Specification 6.13.1 shall also apply to each high radiation in which the intensity of radiation is greater than 1,000 area mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of operations and/or radiation protection supervision on duty.
6.14 ENVIRONMENTAL OUALIFICATION A.
By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions oft Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588
" Interim Staff Position of Environmental Qualification of Safety-Related Electrical Equipment," December 1979.
Copies of these documents are attached to order for Modification of License DPR-16 dated October 24, 1980.
B.
By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventative maintenance and periodic visual inspection requirements, and 2.
System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency of once every 24 months. The systems subject to this testing are (1) Core Spray, (2) Containment Spray, (3) Reactor Water Cleanup, (4) Isolation Condenser, and (5) Shutdown Cooling.
6.16 IODINE MONITORIEQ The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas
- under accident conditions. This program shall include the following:
a.
Training of personnel, b.
Procedures for monitoring, and Provisions for maintenance of sampling and analysis equipment.
c.
- Areas requiring personnel access for establishing hot shutdown condition.
OYSTER CREEK 6-19 Amendment No.: 69,108,134, 141, 166
~
6.17 POST-ACCIDENT SAMPLING j
The following program shall be established, implemented, and maintained.
A program has been established which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under i
accident conditions. The program shall include the following:
Training of personnel in sampling and analysis.
a.
b.
Procedures for sampling and analysis.
Provisions for verifying operability of the System.
c.
6.18 PPOCESS CONTPOL PLAN GPU Nuclear Corporation initiated changes to the PCP:
a.
1.
Shall be submitted to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made.
This submittal shall contains sufficiently detailed information to justify the changes a.
without benefit of additional or supplemental information; b.
a determination that the changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
documentation that the changes have been reviewed and approved pursuant uo Section 6.8.2.
2.
Shall become effective upon review and approval by GPU Nuclear Management.
6.19 OFFSITE DOSE CALCULATION MANUAL The ODCM shall be approved by the Commission prior to a.
implementation.
b.
GPU Nuclear Corporation initiated changes to the ODCM shall be submitted to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made.
This submittal shall contain:
1.
sufficiently detailed information to justify the changes without benefit of additional or supplemental information; 2.
a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determination;
- and, 3.
documentation that the changes have been reviewed and approved pursuant to Section 6.8.2.
c.
Change (s) shall become ef fective upon review and approval by GPU Nuclear Management.
6.20 KAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS DELETED.
OYSTER CREEK 6-20 Amendment No. 6gg 98, 108, 134