ML20086A425
| ML20086A425 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/29/1991 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086A428 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9111190120 | |
| Download: ML20086A425 (32) | |
Text
-
[fec%(o UNITED STATES g
NUCLEAR REGULATORY COMMISSION y'
g
.E WASHINGTON. D. C. 20555
%...../
SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT il0. 1 AMENDMENT TO FACILITY OPERATING LICENSE, Amendment No. b 2 License No. NP 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated June 3,1991, 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; 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 conducted in compliance with the Comission's regulations; 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:
9111190120 911029 PDR ADOCK 05000395 P
s nd (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. -104, and the Envirnnmental 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 Elinor G. Adensam, Director Proiect Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date'of Issuance:
October 29, 1991 1
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ATTACHMENT 1T) LICENSE ANENDMENT NO.104 TO FACILITY OPERATING LICENSE NO. P!PF-17 DOCKET NO. 50-395 Replace the following pages o' the Appendix A Technical Specifications with the enclosed pages. -The revised pages are indicated by marginal'1ines.
Remove Pages Insert Pages I.
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'XI XI XVI XVI 1-4 1-4 1-5 1-5 3/4 3-67
'3/4 3-67 3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-69 3/4 3-70 3/4 3-70 3/4.3-71 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 3/4 3-76 3/4 3-77 3/4 3-78 3/4 3-79 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-?
3/4 11-3 3/4 11-3 i.-
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3/4 11-4 3/4 11-5 3/4 11-5 3/4 11-6.
i 3/4 11-10 3/4 11-11
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3/4 11-13 3/4 11-14 j.
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B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 I
B 3/4 11-6 B 3/4 12-1 B 3/4 12-2 6-12 6-12 6-12a 6-12a 6-12b 6-12b 6-14 6-14 6-15 6-15 6-16 6-16 6-18 6-18 6-19 6-19 6-20 6-20 6-21 l
t 4
DEFINITIONS SECTION PAGE
-1.0 DEFINITIONS 1.1 ACTION.................................................
1-1
- 1. 2 ACTUATION LOGIC TEST....................................
1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST.........................
1-1
- 1. 4 AXI AL F LUX DIFFERENCE...................................
1 1.5 CHANNEL CALIBRATION....................................
1-1 1.6 CHANNEL CHECK..........................................
1 1.7 CONTAINMENT INTEGRITY..................................
1-2 1.8 CONTROLLED LEAKAGE.....................................
1-2 1.9 CORE ALTERATION.........................................
1-2 1.9a CORE OPERATING LIMITS REPORT............................
1-2 1.10 DOSE EQUIVALENT I-131...................................
1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY.........................
1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME................
1-3 1.13 FREQUENCY NOTATION......................................
1-3 1.14 GASE0US RADWASTE TREATMENT SYSTEM.......................
1-3 1.15 IDENTIFIED LEAKAGE......................................
1-3 1.16 MASTER RELAY TEST.......................................
1-3 1.17 0FFSITE DOSE CALCULATION MANUAL (ODCM)..................
1-4 1.18 OPERABLE - 0PERABILITY................................
1-4 1.19 OPERATIONAL MODE - MODE................................
1-4 1.20 PHYSICS TESTS...........................................
1-4 1.21 PRESSURE B0UNDARY LEAKAGE...............................
1-4 1.22 PROCESS CONTROL PROGRAM (PCP)..........................
1-4 1.23 PURGE-PURGING...........................................
1-4 1.24 QUADRANT POWER TILT RATIO..............................
1-5 1.25 RATED THERMAL POWER...................................
1-5
- 1. 26 REACTOR TRIP SYSTEM RESPONSE -TIME.....................
1-5 1.27 REPORTABLE EVENT.....................................
1-5 1.28 SHUTDOWN MARGIN........................................
1-5 1.29 CLAVE RELAY TEST........................................
1-5
- 1. 3 0 0:h.iTE.....................
I 1
1.31 S0JRCE CHECK...........................................
1-5 1.32 STAGGERED TEST BASIS...................................
1-6 1.33 THERMAL POWER..........................................
1-6 1.34 TRIP ACTUATING DEVICE OPERATIONAL TEST..................
1-6 1.35 UNIDENTIFIED LEAKAGE....................................
1-6 1.36 VENTILATION EXHAUST TREATMENT SYSTEM....................
1-6 1.37 VENTING....................
1-6 TABLE 1.1 OPERATIONAL MODES................................
1-7 TA8LE 1.2 FREQUENCY NOTATION 1-8 SUMMER - UNIT 1 I
Amendment No.
35, SS, 104
INDEX LIMITING CONDITIONS FOR OPERATIpri AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS-3/4.2.1 AXIAL FLUX DIFFERENCE....................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R.............................
3/4 2-4 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.........................................
3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO..........
3/4 2-12 3/4 2.5 DNB PARAMETERS..............
3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1' ' REACTOR TRIP SYSTEM INSTRUMENTATION.....................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATIOM SYSTEM INSTRUMENTATION........................................
3/4 3-15
- 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring...................................
3/4 3-41 Movable Incore Detectors...............................
3/4 3-46 Seismic Instrumentation.................................
3/4 3-47 Meteorological Instrumentation..........................
3/4 3-50 Remote Shutdown Instrumentation..........................
3/4 3-53 Accident Monitoring Instrumentation.....................
3/4 3-56 l
Explosive Gas Monitoring Instrumentation.................
3/4 3-73 Loose-Part Detection Instrumentation....................
3/4 3-80 SUMMER - UNIT 1 IV Amendment No.
79, 104 J
e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks.....................................
3/4 11-7 Settling Pond...............
3/4 11-8 3/4.11.2 GASE0US EFFLUENTS Explosive Gas Mixture...................................
3/4 11-17 Gas Storage Tanks.................
3/4 11-18 SUMMER - UNIT 1 XI Amendment No. 104
INDEX BASFS SECliON PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.......................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS......................................
B 3/4 11-3 A
SUMMER - UNIT 1 XVI Amendment No. 104
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.17 The OFFSITE DOSE CALCULATION PJ.NUAL (0DCM) shall contain the methodology and parameters used in the calculation f offsite doses resulting from radioactive gaseous and liquid effluen;., in the calculation of gaseous and liquid effluents monitoring Alarm / Trip Setpoints and in the conduct of the Environmental Radiological Monitoring Program, iheODCMshallalsocontain (1) the Radioactive Effluent Controls and Radiological Environmental 7'
Monitoring Programs recuired by Section 6.8.4 and (2) descriptions of the
??
information that shoulc be included in the Annual Radiological Environmental
?
Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.8.
OPERABLE - OPERtBILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s)arealsocapableofperformingtheirrelatedsupportfunction(s).
3 OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1 PHYSICS TESTS 1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) descritied in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
PRESSURE B0UNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, 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 compl1 'ce with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requi ements, and other requirements governing the disposal of solid radioactive vaste,
, PURGE - PURGING 1.23 PURGE or PURCING is the controlled p. ~ess of discharging air or gas from a confinement to maintain temperaturr, pressure, humidity, concentration or other operati e condition, in such a manner that replacement air or gas is required to purit, the confinement.
SUMMER - UNIT 1 1-4 Amendment No.
104
^
QOADRANTPOWERTILTRATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
With one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2775 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sr..isor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would De suberitical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawr..
SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shall be the ener verification of OPERABILITY of each refay.gization of each slave relay and The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
1.30 Not Used SOURCE CHECK 1.31 A' SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
l SUMMER - UNIT 1 1-5 Amendment No. 35,104
IN'TRUMENTATION S
EXPLOSIVE GAS MONITORING INSTRUMENTATION
, LIMITING CONDITION FOR OPERATION 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table l
3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.
APPLICABILITY:
As shown in Table 3.3-13 ACTION:
With a explosive gas monitoring instrumentation channel alarm / trip a.
setpoint less conservative than recuired by the above Specification, declare the channel inoperable, anc take ACTION shown in Table 3.3-13.
l b.
With less than the minimum number of ex)losive gas effluent I
monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to operable status within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.
Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report explain why this inoperability was not corrected in a timely manner,.
c.
The provisions of Specifications 6.9.1.12.b, 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.'3.3.9 Each ex,losive gas monitoring instrumentation channel shall be demonstratedOPEIRABLEbyperformanceoftheCHANNELCHECK,SOURCECHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.
SUMMER - UNIT 1 3/4 3-67 Amendment No. 35, 104
w TABLE 3.3-13 v,
EXPLOSIVE GAS MONITORING INSTRUMENTATION c:
MINIMUM CHANNELS
${
INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS l
MONITORING SYSTEM a.
Oxygen Monitor 2
44 b.
Hydrogen Monitor 1
42 li
!h O
TABLE 3.3-13 (Continued)
TABLE NOTATION
- During waste gas holdup system operation (treatment for primary system offgases).
ACTION 38 -
(Not used)
ACTION 39 -
(Not used)
ACTION 40 -
(Not used)
ACTION 41 -
(Not used)
ACTION 42 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirer.ent, suspend oxygen supply to the recombiner.
ACTION 43 -
(Not used)
ACTION 44 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With both the channels inoperable, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other opera-tions.
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SUMMER - UNIT 1 3/4 3-69 Amendment No. 104
TABLE 4.3-9 c,
C-hk EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
gg ANALOG chi.JNEL MODES IN WHICH
- q CHANNEL CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 1.
WASTE GAS HOLDUP SYSTEM EXPLOSIVE' GAS MONITORING SYSTEM i
- a. Hydrogen Monitor D
Q(4)-
M
- b. Oxygen Monitor D
Q(5)
M R
u M
a n.
2"+
2?
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I INSTRUMENTATION I
TABLE 4.3-9 (Continued)
TABLE NOTATION During waste gas holdup system operation (treatment for primary system offgases).
(1) The CHANNEL CALIBRATION shall include the use of standard gas samples
(
containing a nominal:
1.
1500 1 30 ppm hydrogen, balance nitrogen, for the outlet hydrogen monitor and 2.
4 1 0.1 volume percent hydrogen, balance nitrogen, for the inlet hydrogen monitor.
(2) The CHANNEL CALIBRATION shall include the use of standard gas samples l
containing a nominal:
1.
75 i 1.5 ppm oxygen, balance nitrogen, for the outlet oxygen monitor and 2.
3.5 1 0.1 volume percent oxygen, balance nitrogen, for the inlet oxygen monitor.
SUMMER - UNIT 1 3/4 3-71 Amendment No. 20. 56, 104
4 RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION l
3.11.1.4 The quantity 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:
At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions or 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 tank contents to within the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 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.
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l SUMMER - UNIT 1 3/4 11-1 Amendment No. 104 Y -,
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l RADI0 ACTIVE EFFLUENTS SETTLING POND LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each settling pond i
shall be limited by the following expression:
264 *
< 1. 0 excluding tritium and dissolved or entrained noble gases, where, Aj = Pond inventory limit for single radionuclide "j", in curie.
C j = 10 CFR 20, App'j" dix B, Table II, column 2, concentration for single en radionuclide
, microcuries/ml.
V = design volume of liquid and slurry in the pond, in gallons.
264 = Conversion unit, microcuries/ curie per milliliter / gallon.
APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material in the settling pond exceeding the above limit, immediately suspend all additions 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.
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 the settling ponds shall be limited by the expression:
I
< 0.6 j
SUMMER - UNIT 1 3/4 11-2 Amendment No. 104
~
RADIOACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) where O = concentration of radioactive materials in wet, drained slurry (used j
powdex resin) for radionuclide "j" excluding tritium, dissolved or entrained noble gas and radionuclides with less than 8 day half-life 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.
Cj = 10 CFR 20, Apgendix B, Table II column 2 concentration for single radionuclide j", in microcuries/ milliliter.
SUMMER - UNIT 1 3/4 11-3 Amendment No. 104
R DI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 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 i
exceeds 4% by volume.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to 4% 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 conccntration of oxygen in the waste gas holdup system greater than 4% by volume, immediately suspend all acditions 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 />.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and oxygen monitors required 'PERABLE by Table 3.3-13 of Specification 3.3.3.9.
SUMMER - UNIT 1 3/4 11-4 Amendment No.
104
RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 160,000 curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
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 tank contents to within the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials arc being added to the tank.
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SUMMER - UNIT 1 3/4 11-5 Amendment No. 104 l
1 i
INSTRUMENTATION BASES 3/4.3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This~ instrumentation includes provisions for monitoring and controlling the concentrations of potentially explosive gas m : tares in the waste gas holdup system.
The OPERABILITY and use of this inn rumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors,"
.y 1981.
SUMMER - UNIT 1 B 3/4 3-4 Amendment No. 104 r
_ _ i___ _
RADIDACTIVE EFFLUENTS v.
BASES 3/4.11.1.3 Not Used 3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of' radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concent.aations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water 4.
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 i
pond is located in an uncontrolled area as defined in 10 CFR 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR 20 applies.
~
The batch limits of slurry to the chemical treatment ponds assure that radioactive-material in the slurry transferred to the SP are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a.
The expression in Specification 4.11.1.5 assures no batch of slurry will be transferred ~to the SP.unless the sum of the ratios of the activity of the radionuclides
-to their respective concentration limitation is less than the ratio of the 10'CFR 50, Appendix I,Section II.A, total body level to the 10 CFR 20, 105(a),
whole' body Gose limitation, or that:
1 3 mrem /yr
= 0.006 j j 500 mrem /yr where
.c. = radioactive slurry concentration for radionuclide "j" entering the J
unrestricted area SP, in microcuries/ milliliter en Column 2, concentration for single C. = 10 CFR 20, App'j" dix B, Table II,/ milliliter.
J radionuclide.
in microcuries
.For the design of filter /demineralizers using powder resin, the slurry wash volume and the weight of resin used per batch is fixed by the cell surface area
- i and the slurry volume to resin weight ratio is constant at 100 milliliters / gram of wet, drained resin with a moisture content of approximately 55 to 60% (bulk
. density-of about 58 pounds per cubic feet).
The wet drained slurry density is p
SUMMER-- UNIT 1 B 3/4 11-1 Amendment No. 104
. = -
iw.,om...
- ,,..,.,,m..,.me,,,
.m.., _, _,, _,,..,.,
..-cm,,
m-y.,,,m,.,,,,-
< _,,.y.,
y
_,m3
~.-.
=--
RADI0 ACTIVE EFFLUENTS BASES 3/4 11.1.5 SETTLING PONOS (Continued) approximately I gr/mi and the absorption characteristic for gamma radiation is essentially that of water.
Therefore, C) 0' ml/gm) < 0.006, and i & <.e a Where the terms are defined in Specification 4.11.1.5.
The batch limits provide assurance that activity input to the SP will be minimized, and a means of identifying radioactive material in the inventory limitation of Specification 3.11.1.5.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.
Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen to.
- ce the concentration below the flammability limits.
Maintaining the
- v. m v. ration of hydrogen and oxygen below their flammability limits provides v we.nce that the releases of radioactive materials will be controlled in
. e emance with the requirements of General Design Criterion 60 of Appendix A o 1J 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 nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".
i.
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l SUMMER - UNIT 1 B 3/4 11-2 Amendment No. 104 i
-~. _ ____.._.-_-_._ _ _
ADMINISTRATIVE CONTROLS c.
Secondary Water Chemistry A program for monitoring.of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
(i) Identification of a sampling schedule for the critical variables
_and control points for these variables, (ii) Identification of the procedures used to measure the values of-the critical variables, (iii) Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser.
in-leakage.
(iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions,
-(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and_ timing of administrative events required to initiate corrective action.
d.
Postaccident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines end particulates in plant gaseous effluents, and containment atmosphere samples under accident cond:tions. The program shall include the following:
(i) Training personnel, (ii) Procedures:for sampling and analysis, (iii) Provisions for maintenance of sampling'and analysis equipment.
e.
Radioactive Effluent Controls Program A program shall be-provided conforming with 10 CFR 50.36a for the
- control-of radioactive effluents and for maintaining the doses to members of.the public from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in 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-f monitoring instrumentation including surveillance tests and setpoint determinations in accordance with the methodology in the ODCM, 2)-
Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming 10 CFR Part 20, Appendix B, Table II, Column 2; SUMMER - UNIT 1 6-12 Amendment No. 35. 57-79, 104 m,
.-~,
m
\\o ADMlNISTRATIVE CONTROLS Radioactive Effluent Controls Program (Continued) e.
3)
Monitoring,luents in accordance with 10 CFR 20.106 and with the sampling, and analysis of radioactive liquid and gaseous eff 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 effluents released to unrestricted areas conforming to Appendix I to 10 CFR Part 50.
5)
Determinationofcumulativet.ndarojecteddosecontributions from radioactive effluents for t1e current calendar quarter and 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 or radioactivitywhentheprojecteddosesina31-dayperiodwould exceed 2 percent of the guidelines for the annual or dose commitment conforming to Appendix I to 10 CFR Part 50; 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1; 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50; 9)
Limitations on the annual and quarterly doses 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 effluents 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.
f.
Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.
The program shall arovide (1) representative measurements or radioactivity in the lighest 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 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; SUMMER - UNIT 1 6-12a Amendment No. 104
ADMINISTRATIVE CONTROLS f.
Radioactive Effluent Controls Program (Continued) 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 the census; and s.
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 aae performed as part of the quality assurance program for environmental monitoring.
SUMMER - UNIT 1 6-12b Amendment No.
104 l
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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 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; (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 3
after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine 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; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in 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 with 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.
6.9.1.7 Not used.
l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 6. 9.1. 8 Semiannual radioactive effluent release report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
SUMMER - UNIT 1 6-14 Amendment No. 79, 104
A6MINISTRATIVECONTROLS The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provi-ded shall be (1) consistent with the objectives outlined in the ODCM and PCP 3
and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
)
2 SUMMER - UNIT 1 6-15 Amendment No-64, 79 104
AdMINISTRATIVECONTROLS 6.9.1.9 Not used.
MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCCLATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above.
CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
a.
Moderator Temperature Coefficient BOL and E0L Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, b.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, c.
Control Bank Insertion Limits for Specification 3/4.1.3.6, ND d.
Axial Flux Difference Limits, target band, and APL for Specification 3/4.2.1, TP ND e.
Heat Flux Hot Channel Factor, F
, K(Z), W(Z), APL and W(Z)BL for Specification 3/4.2.2, f.
Nuclear Enthalpy Rise Hot Channel Factor, F and Pcwer Factor l
Multiplier, PFAH, limits for Specification 3/4.2.3.
l 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 following documents:
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",
a.
l July 1985 (W Proprietary).
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SUMMER - UNIT 1 6-16 Amendment No.
7g, gg, 104 l
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l ADMINISTRATIVE CONTROLS Records of transient or operational cycles for those unit components e.
identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities as 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 equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
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.
n.
Records of analysis required by the radiological environmental monitoring program, o.
Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 4
6.12.1 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 1000 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).* Any individual or group of individuals 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 radiation dose rate in the area.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.
SUMMER - UNIT 1 6-18 Amendment No. 35. J7, 75, 77.
104
ADMINISTRATIVE CONTROLS b.
A radiation monitoring device which continuously integrates the radtation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may ae made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, c.
A health physics qualified individual (i.e., qualified in radiation prote: tion procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activit1e> within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the admin-istrative control of the Shift Foreman on duty and/or health physics supervision.
Doers shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area.
The maximum allowable stay time for individuals in that area shall be established prior to entry.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP direct or remote (such as use of closed circuit TV cameras) continuous surveillance shall be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
G.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s);
and 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PSRC and approval of the General Manager, Nuclear Plant Operations.
" Measurement made at 18" from source of radioactivity.
SUMMER - UNIT 1 6-19 Amendment No.
- 35. 79 104
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ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
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 shall contain:
1)
Sufficient information to support the change together with appropriate analyses or evaluations justifying the change (s);
and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations, b.
Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Nuclear Plant Operations.
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 Semiannual Radioactive Effluent Release Report for the period of the report in wnich any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
SUMMER - UNIT 1 6-20 Amendment No. 47. 79, 104 l
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