ML20095L165
| ML20095L165 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/28/1995 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095L168 | List: |
| References | |
| NUDOCS 9601020108 | |
| Download: ML20095L165 (18) | |
Text
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l C Mtv 0-t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION o,
WASHINGTON, D.C. 20066 4001
..u.*
SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for ameadment by South Carolina Electric & Gas Company (the licensee), dated February 21, 1995, as supplemented on August 31, 1995, And December 4, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 1
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 i
conducted in compliance with the Comission's regulations; i
D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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.
NPF-12 is hereby amended to read as follows:
4 9601020108 951228 PDR ADOCK 05000395 P
o (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 130, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,s2 Frederick J. Heb on, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1995 4
4
ATTACHMENT TO LICENSE AMENDMENT NO. 130 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revisions are indicated by marginal lines.
t Remove Paae Insert Paae 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 j
3/4 11-4 3/4 11-4 B 3/4 11-1 B 3/4 11-1 8 3/4 11-2 B 3/4 11-2 6-11 6-11 6-12 6-12 6-12a 6-12a 6-12b 6-12b 6-13 6-13 6-14 6-14 6-18 6-18 6-19 6-19 6-20 6-20 4
i 1
3/4.11 RADIOACTIVE EFFLUENTS l
3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 Deleted b Amendment 104.
3.11.1.2 Deletedb Amendment 104.
3.11.1.3 Deletedb Amendment 104.
3.11.1.4 The q uantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
a.
Condensate Storage Tank b.
Outside Temporary Storage Tank APPLICABILITY: Atalltimes.
ACTIOM a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the l
tank contents to within the limit.
j b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1 Deletedb Amendment 104.
4.11.1.2 Deleted b Amendment 104.
4.11.1.3 Deleted b Amendment 104.
4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
- SUMMER - UNIT 1 3/4111 Amendment No.104,130 i
.l RADIOACTIVE EFFLUENTS i
SETTLING POND LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each settling pond shall be limited by the following expression:
264 5
Ay
\\
V j
Cj excluding tritium and dissolved or entrained noble gases, where, Aj = Pond inventory limit for single radionuclide "j ",in curies.
l Cj = 10 CFR 20, Ap "endix B, Table 2, column 2, concentration for single l
radionuclide
, microcuries/ml.
V = design volume ofliquid and slurryin the pond,in gallons.
264
= Conversion unit, microcuries/ curie per milliliter / gallon.
APPLICABILITY: Atalltimes.
ACTION:
With the quantity of radioactive material in the settiing pond a.
exceeding the above limit, immediately suspend all adc itions of radioactive material to the pond and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the pond contents to within the limit, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
4 SURVEILLANCE REQUIREMENTS 4.11.1.5 The quantity of radioactive material contained in each batch of slurry (used powdex resin) to be transferred to the settling ponds shall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to tae settling ponds shall be limited by the expression:
f b
< 1.0 i
J Gj d
SUMMER-UNIT 1 3/4 11-2 Amendment No.104,130 i
r,
.-=
= -
4 RADIOACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) where Qj = concentration of radioactive materials in wet, drained slurry (d or used powdex resin) for radionuclide "j " excludin ; tritium, dissolve entrained noble gas and radionuclides with(..ess than 8 day half life, l
in microcuries per gram. The analysis shall include at least Ce-144, Cs-134, Cs-137, Sr 89, Sr-90, Co-58 and Co-60. Estimates of Sr-89, Sr-90, batch concentrations shall be based on the most recently available quarterly composite analyses.
Oj = 10 CFR 20, Ap "endix B, Table 2, column 2, concentration for single l
radionuclide
,in microcuries/ milliliter.
i f
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l SUMMER - UNIT 1 3/4 11-3 Amendment No.104,130
1 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 Deleted b Amendment 104.
3.11.2.2 Deletedb Amendment 104.
3.11.2.3 Deleted b Amendment 104.
3.11.2.4 Deleted b Amendment 104.
3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABILITY: At all times.
ACTION:
With the concentration of oxygen in the waste gas holdup system a.
greater than 2% by volume but less than or equal te 1% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of oxygen in the waste gas holdu;) system greater than 4% by volume, immediately suspend all addtions of waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and less than or equal to 2%
by volume within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, The provisions ofSpecifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.11.2.1 Deleted b Amendment 104.
4.11.2.2 Deletedb Amendment 104.
4.11.2.3 Deleted b Amendment 104.
4.11.2.4 Deleted b Amendment 104.
4.11.2.5 The concentration ofhydrogen and oxygen in the waste gas holdup 3
system shall be determined to be wit 2in the above limits by continuously monitoring the waste gases in the waste gas holdu > system with the hydrogen a
and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.9.
l I
SUMMER -UNIT 1 3/4 11-4 Amendment No.104,130
3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Deleted b Amendment 104.
3/4.11.1.2 Deletedb Amendment 104.
3/4.11.1.3 Deleted b Amendment 104.
3/4.11.1.4 LIQUID HOLDUP TANKS l
Restricting the quantity of radioactive material contained in the s >ecified i
tanks tanks'provides assurance that in the event of an uncontrolled release of t ie contents, the resulti: P concentrations would be less than the limits of l
10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water i
supply and the nearest surface water supply in an unrestricted area.
3/4.11.1.5 SETTLING PONDS The inventory limits of the settling ponds (SP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in Specification 3.11.1.5 assumes the pond inventory is uniformly mixed, that the pond is located in an unrestricted area as defined in 10 CFR 20, and that the concentration limit in Note 4 to Appendix B of10 CFR 20 applies.
The density of wet, drained resin is approximately the same as water (bulk density of about 58 pounds per cubic foot); and the absorption characteristics for gamma radiation I
are essentially that of water. Therefore, direct comparison ofradionuclic,e specific activity in wet, drained resin to the appropriate concentration in 10 CFR 20, Appendix B, Table 2, i
Column 2, ensures that the limit of Specification 3.11.1.5 will not be exceeded.
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SUMMER - UNIT 1 B 3/411-1 Amendment No.104,130 i
4 RADIOACTIVE EFFLUENTS BASES I
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Deleted b Amendment 104.
3/4.11.2.2 Deleted b Amendment 104.
3/4.11.2.3 Deleted b Amendment 104.
3/4.11.2.4 Deleted b Amendment 104.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is providod to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdu maintained below the flammability limits of hydrogen anc oxygen. p system is Automatic control features are included in the system to arevent the hydrogen and oxygen concentrations from reaching these flammabi..ity limits. These automatic control features include isolation of the source of h drogen and/or oxygen to reduce the concentration below the flammabilit limits. Maintaining the concentration of hydrogen and oxygen below their ammabilitylimits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50, 3/4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the i
nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".
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SUMMER UNIT 1 B 3/4112 Amendment No.104,130 i
4 m
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ADMINISTRATIVE CONTROLS d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDUR$S AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The ap?licable procedures recommended in Appendix "A" of Regulatory Guide L.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
'd.
Security Plan.
e.
f.
g.
h.
OFFSITE DOSE CALCULATION MANUAL.
i.
Efnuent and environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed
]
prior to implementation as set forth in 6.5 above.
6.8.3 NOT USED.
i 6.8.4 The following programs shall be established, implemented and maintained:
I a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside contamment that could contain highly radioactive fluids during a i
serious transient or accident to as..ow as practical levels. The systems include the chemical and volume control, letdown, safety mjection, residual heat removal, nuclear sampling.
t handling, gas radwaste handling and reactor buildm, liquid radwaste l
g spray system.
The program shall include the following:
1)
Preventive maintenance and periodic visual inspection requirements, and Integrated leak test re 2) cycle intervals or less.quirements for each system at refueling b.
In-Plant Radiation Monitoring 1)
Training of prsonnel, 2)
Procedures tor monitoring, and 3)
Providons for maintenance of sa npling and analysis equipment.
1 i
. SUMMER - UNIT 1 6-11 Amendment No.18,49,72,79, 117, 130
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ADMINISTRATIVE CONTROLS This report shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of specification 3.4.8. The following information shall be included: (1) Reactor power history; tarting -
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; (2) Results of the last isotopic anal,ysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time ofsampling and the radioiodine concentrations; (3) Clean up system flow history startmg 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 hmit was exceeded; (4) Graph of the I 131 concentration and one other radioiodine isotope concentration m microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The annual radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, 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 wit2 the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
i 3
a 6.9.1.7 Not used.
j l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Annual radioactive effluent release report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of I
l each year.
l The report shall include a summary of the quantities of radioactive liquid 3
- and gaseous effluents and solid waste released from the unit. The material
)
1 provided shall be (1) consistent with the objectives outlined in the ODCM i
3 and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of I
Appendix I to 10 CFR Part 50.
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SUMMER -UNIT 1 6-14 Amendment No. 79,104, 117, 130
ADMINISTRATIVE CONTROLS e.
Records of transient or operational cycles for those unit components identified in Table 5.71.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit
- staff, h.
Records ofin service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities a.5 specified in the NRC's approved SCE&G position on Regulatory Guide 1.88, Rev. 2, October 1976.
j.
Records of reviews performed for changes made to procedures or ui ment or reviews of tests and experiments pursuant to 10 CFR k.
Records of meetings of the PSRC and the NSRC.
1.
Records of the service lives of all hydraulic and mechanical snubbers defined in Section 3.7.7 including the date at which the service life commences and associated installation and maintenance records.
m.
Records of secondary water sampling and water quality.
l n.
Records of analysis required by the radiological environmental monitoring program.
j.
o.
Records of reviews performed for changes made to the Offsite Dose l
Calculation Manual and the Process Control Program.
a 5
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with th a requirements of10 CFR Part 20 and shall be agroved, mi.i..tained and adhered to for all operations involving personnel r iation e>
aure.
l j
6.12 HIGH RADIATION AREAS t
6.12.1 In lieu of the " control device" or " alarm signal" rec uired by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in whicL2 the intensity of l
radiation is greater than 100 mrem /hr* but less than 1000 mrem /hr* shall be barri.:aded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Health Physics personnel or individuals escorted by Health Physics l
personnel shall be exempt from the RWP issuance requirement during the l
performance of their assigned duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.
Any individual or group ofindividuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the l
radiation dose rate in the area.
i Measurement made at 30 cm (12 in.) from the radiation source or from any surface penetrated by the radiation.
SUMMER' UNIT 1 6-18 Amendment No. 35,49,75, L
79,104, 130 p
,m...m..-..u m
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ADMINISTRATIVE CONTROLS '
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset intepa,ted
~ dose is received. Entry into such areas with this monitoring c evice may be made after the dose rate levelin the area has been established and personnel havs been made knowledgeable of them, A health physics qualified individual (i.e., qualified in radiation s
c.
protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiatioa surveillance at i
the frequency specified by the RWP.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiatic n levels greater than 1000 mrem /hr* but less than 500 rads /hr**
and the keys shall be provided with locked doors to prevent unauthorized entry,hift S'upervisor shall be main tained under the administrative control of the duty S and/or health physics supervision. Doors shall remain locked except during periods of access )y personnel under an approved RWP which shall snecify the dose rate levels in the immediate work area. The maximum allowable stay j
time for individuals in that area shall be established prior to entry. In lieu of the stay time specification of the RWP, direct or remote continuous surveillance (such as closed circuit TV cameras) shall be made by personnel qualified in j
radiation protection Nocedures to provide positive exposure control. er the activities within the a:ea.
For individual areas accessible to personnel with radiation levels greater than j
1000 mrem /hr* but less than 500 rads /hr** that are located withm larger areas j
(such as PWR containment) where no enclosure can be reasonably constructed i
around the individual areas, then those areas shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
j ll 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
1
(
6.13.2 Changes to the PCP:
a.
Shall be documented and recordyneviews performed shall be retained as required by Specific @at 6.10.2.o. This documentation i
shallcontain.
1)
Sufficient information to support the change together with the appropriate analyses or eva.uationsjustifymg the change (s);
and 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing
.equirements of Federal, State, or other applicable regulations.
l 1
b.
Shall become effective after review and acceptance by the PSRC and approval of the General Manager, Nuclear Plant Operations.
l Measurement made at 30 cm (12 in.) from the radiation source or from any j
surface penetrated by the radiation.
Measurement made at 1 meter from the radiation source or from any surface penetrated by the radiation.
SUMMER -UNIT 1 6-19 Amendment No. 35,79, 104,130
. _.. - - _. ~ _
ADMINISTRATIVE CONTROLS l
c.
Secondary Water Chemistrv A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
1)
Identification of a sampling schedule for the critical variables i
and control points for these variables, 2)
Identification of the procedures used to measure the values of the criticalvariables, 3)
Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser i
in-leakage, 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective actions for all off-control point chemistry conditions, l
6)
A procedure identifying (a) the authority responsible for the j
interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
l d.
Postaccident Samoling A program which'will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous emuents, and containment atmosphere samples under accident conditions. The program shall include the following:
4 1)
Training personnel, i-2)
Procedures for sampling and analysis, 3)
Provisions for maintenance of sampling and analysis equipment.
e.
Radioactive Emuent Controls Program l
A program shall be provided conforming with 10 CFR 50.36a for the
~
control of radioactive emue ats and for maintaining the doses to members of the public from radioactive emuents as low as reasonably 1
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 j
program shall include the following elements:
~
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation meluding surveillance tests and j
setpoint determinations in accordance with the methodology in the ODCM; l
2)
Limitations on the concentration ofradioactive material released in liquid emuents to unrestricted areas conforming to 10 times the concentration values in 10 CFR Part 20, Appendix B, Table 2, Column 2; SUMMER -UNIT 1 6-12 Amendment No. 35,57, 79,104,117,130
{
ADMINISTRATIVE CONTROLS e.
Radioactive Emuent Controls Program (Continued) 3)
Monitoring, sampling, and analysis of radioactive liquid knd gaseous emuents m accordance with 10 CFR 20.1302 and with l
the methodology and parameters in the ODCM; 4)
Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid emuents released to unrestricted areas conforming to Appendix 4
Ito 10 CFR Part 50; 5)
Determination of cumulative ar d projected dose contributions from radioactive emuents for the current calendar quarte'r and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days; i
i i
6)
Limitations on the operability and use of the liquid and gaseous emuent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases or radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual or dose i
commitment conforming to Appendix I to 10 CFR Part 50; 7)
Limitations on the dose rate resulting from radioactive material released in gaseous emuents from the site to areas at or beyond the site boundary shall be limited to the following:
1 (a)
For noble gases: Less than or equal to a dose rate of i
500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin; and i
(b)
For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate j
of1500 mrem /yr to any organ;
~
8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous emuents to areas beyond tlie site boundary conforming to Appendix I to 10 CFR Part 50; 9)
Limitations on the annual and quarterly dosea to a member of the,public from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate from with half lives greater than 8 days in gaseous emuents released to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 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.
SUMMER-UNIT 1 6-12a An ndment No.104,117,130
=
ADMINISTRATIVE CONTROLS i
f.
Radiolorical Environmental Monitoring Prorram A program shall be provided to monitor the radiation and radionuclides m the environs of the plant. The program shall provide (1) representative measures of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling ofenvironmental 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, sampl,ing, analysis, and reporting of radiation and radionuclides m the environment in accordance with the methodology and parameters in the ODCM; 2)
A Land Use Census to ensure that chan es in the use of areas at and beyond the site boundary are ide tified and that modifications to the monitoring program are made if required by the results of the census; and 3)
Participation in an Inter laboratory Comparison Program to ensure that independent checks on the precision and accuracy of measurements of radioactive materials in environmental sample matrices are performed as part of the quality amurance program for environmental monitoring.
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t SUMMER-UNIT 1 6-12b Amendment No.104,117,130 i
i ADMINISTRATIVE CONTROLS i
6.9 REPORTING REQUIREMENTS s
ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code 4
i of Federal Regulations, the following reports shall be submitted to the Regional Administrator Office ofInspection and Enforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary, report of plant startup and power escalation testing shall be submitted following (lanned increase in power level, (3) installation of1) rece l
the license involving a p fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, l
thermal, or hydraulic performance of the plant.
j 6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values 1
of the operating conditions or characteristics obtained during the test program l
and a comparison of these values with design predictions ano specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions i
based on other commitments shall be included in this report.
1 6.9.1.3 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 resumption or commencement of commercial operation) sup >lementary reports shall be l
submitted at least every three months until all t tree events have been completed.
ANNUAL REPORT 6.9.1.4 Annual re > orts covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 31 of each year.
The initial report shall be submitted prior to March 31 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated collective deep dose equivalent (reported in person-rem) according to work and job l
functions, if e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assi;J, or film badge measurements. Small exposures to piments to various duty functions may be estimated based on pocket dosimeter,TL less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
y This tabulation supplements the requirements of120.2206 of10 CFR Part 20.
l SUMMER-UNIT 1 6-13 Amendment No. 79,130
ADMINISTRATIVE CONTROLS 6.140FFSITE DOSE CALCULATION MANUAL (ODCM) 6.141 The ODCM shall be approved by the Commission prior to implementation.
l 6.14.2 Changes to the ODCM-a.
' Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o. This documentation
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shallcontain:
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1)
Sufficient information to support the change together with appropriate analyses or eva. uations justifying the change (s);
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1 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR l
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Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and i
not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
i b.
Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Nuclear Plant Operations.
I c.
Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Re port for the period of the report in which any change to the ODCIW was made. Each change shall be identified by markings in tne margin of the affected ages, clearly indicating the area of the page that was chang, and shall indicate the date (e.g., month / year) the change was imp emented.
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SUMMER-UNIT 1 6-20 Amendment No.16,35, 41,79,104,117.130
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