ML20058E278
| ML20058E278 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/23/1982 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8207280131 | |
| Download: ML20058E278 (7) | |
Text
.
SOUTH CAROLINA ELECTRIC Sc GAS COMPANY eas t tw e se n aan,se y
Cotuuma. south C AROUNA 29218 O. W. DimoN. Ja.
vice Pace.oc%r July 23, 1982 suc a.. o....,,o~s Mr. Harold R. Dmtcn, Director Office of Nuclear Peactor regulaticn U. S. Nuclear Regulatory Conmissicn Washingtrn, DC 20555
Subject:
Virgil C. Sumner Nuclear Staticn Docket No. 50/395 Technical Specifications
Dear Mr. Dmtcn:
Ehclosed are Iroposed miscellaneous changes to the Proof and Review copf of the '1bchnical Specificaticns for the Virgil C. Sunmer Nuclear Staticn.
'Ihe following is a brief explanaticn of the reascms for the requested changes:
Page Explanaticn 3/4 3-79
'Ihe waste gas holdup systs includes two redundant hydrogm reembiners, cne of which is aligned for systs op3raticn. Since each recombiner has its own hydrogcn and oxygm imnitors and ccntrols, the APPLICABILITY has bem changed to clarify that the mmitors required to be OPERABLE are the cnes associated with the recombiner that is in operaticn. Except for the inlet oxygcn monitor, the ccnccntraticn of the standard gas samples have bem changed to the manufacturer's reccmmndaticn for calibraticn. 'Ihe manufacturer reccmnmds j
using air to calibrate the inlet oxygcn S09' ntnitor,but we have elected to use a 3.5%
V oxygm sample gas because this mcnitor is used to autmatically isolate the oxygm supply to the recombiner at 3.5%.
3/4 6-21
'Ihe nunufacturer reconTnmds that these hydrogm rxnitors be calibrated with a sample gas ccntaining slightly less than the maxanum instrurmnt spen of 20% hydrogcn.
3/4 11-17 Error correcticn.
8207280131 820723 PDR ADOCK 05000395 A
pop
F Mr. H. R. Dtntm July 23, 1982 Page 2 B3/4 11-5 1he bases in the Standard Technical Spci-ficaticns require that autmatic ccntrols to gevcnt the hydrogm md oxygm ocncm-traticns frm reaching flanmability limits include cne of the following three features:
- 1) isolaticn of the source of hydrogcn and/or oxygm, 2) automatic diversicn to recombiners, or 3) injecticn of dilutants. Our waste gas holdup system has autonatic ocntrols that include the first of the above features, but the cmtrols do not Irovide for automatic diversicn to reconbiners or injecticn of dilutants.
6-17 Our OFFSITE DOSE CAICULATION MANUAL (ODCM) uses an annual average of the historical meteorological ccnditims to assess the gaseous pathway doses. The requested change is needed to avoid ccnflicting requiremcnts in the last two scntcnces of this paragralt.
If you have any questicns, please let us kncv.
V truly s
/
t t'
O. W. Dixm, Jr.
LDS/vtw Ehclosure cc:
V. C. Sunmer R. B. Clary G. H. Fischer O. S. Bradham H. N. Cyrus L. D. Shcaly T. C. Nichols, Jr.
A. R. Kocn O. W. Dixcn, Jr.
M. N. Browne M. B. Trhitaker, Jr.
G. J. Braddick J. P. O'Reilly M. J. Virgilio H. T. Babb J. L. Skolds D. A. Nauman B. A. Bursey C. L. Ligcn (NSRC)
NPCF W. A. Williams, Jr.
File a
o r.
INSTRUMENTATION g;,
TABLE 4.3-9 (Continued)
TABLE NOTATION bi
P '/'#"
l
- At all times.
NE During waste gas Mup'7"yster.per:tien (treatment for pc4 mary jyster s
-ef-fgases-),
(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciatior. occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of Power (alarm only).
3.
Instrument indicates a downscale failure (alarm only).
4.
Instrument controls not set in operate mode.
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Loss of Power.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have beeri obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
RHeen L ~h e4' ppn 1.
-One !clu e percent hydrogen, balance nitrogen, for the outlet hydrogen monitor and E.34 f-2.
h volume percent hydrogen, balance nitrogen for the inlet hydrogen monitor.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
.teverdy Cue pp m 1.
Orc ;cle=0 percet oxygen, balance nitrogen, for the outlet oxygen h,".e [8be AalE
.b 2.
t-eur volume percent oxygen, balance nitrogen for the inlet oxygen monitor.
BR 0 31982 SUMMEP - UNIT 1 3/4 3-79 YAR j 332
P" c0NTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent containment hydrogen monitors shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.6.5.1 Each hydrogen monitor shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gaser containingl
/9. F Gns volume percent hydrogen, balance nitrogen.
L.
Iour volume = percent-hydrogenAa4ance nitrogen s_
APR 151992 SUMMER - UNIT 1 3/4 6-21
p-RADI0 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 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 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 concentration of oxygen in the waste gas holdup system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within one hour 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 of Specifications 6.9.1.12.b, 3.0.3 and 3.0.4 are not
{(j')
c.
applicable.
SURVEILLANCE REOUIREMENTS 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 9
and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.44P.
)
1 MAR 0 31992
.)
SUMMER - UNIT 1 3/4 Il-17 c.
x J
f RADIOACTIVE EFFLUENTS q.:
BASES to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi ti ons. The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which j
were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consump-tion of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available
~
for use whenever gaseous effluents require treatment prior to release to the
[Q environment.
The requirement that the appropriate portions of these systems te used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reason-ably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
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 ar.d oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen,-
and cutemat.-ie-d, crsion to rccamW to reduce the concentration below the flammability limits.
Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radio-active materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
MAR 0 3 Iggi s-
=;
SUMMER - UNIT 1 B 3/4 11-5
F C
ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a' summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring,
' Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear. Power Plants," Revision 1, June 1974, with data summarized on a t
quarterly basis following the format of Appendix B thereof.
p A
The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in s
the form of an hour-by-hour listing of wind speed, wind direction, and atmos-c pheric stability, and precipitation (if measured) on magnetic tape, or in the
[w form of joint frequency distributions of wind speed, wind direction, and e0 d
atmospheric stability.
This same report shall include an assessment of the Q
radiation doses due to the radioactive liquid and gaseous effluents released N
from the unit or station during the previous calendar year.
This same report
$4 shall also include an assessment of the radiation doses from radioactive
{[
liquid and gaseous effluents to members of the public due to their activities
-4 S
.$ f inside the site boundary (Figures 5.1-3 and 5.1-4) during the report.
All assumptions used in making these assessments (i.e., specific activity, exposure 4 E time and location) shall be included in these reports. @ meteorological' conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public form reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show' conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribu-tion from liquid and gaseous ef fluents are given in Regulatory Guide 1.109, Rev. 1.
The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:
a.
Container volume, b.
Total curie quantity (specify whether determined by measurement or estimate),
Principal radionuclides (specify whether determined by measurement c.
or estimate),
Type of waste (e.g., spent resin, compacted dry we,te, evaporator d.
bottoms),
tf p
. m.
ut MAR 0 31982 SUMMER - UNIT 1 6-17