ML20101H514
| ML20101H514 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 06/24/1992 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20101H512 | List: |
| References | |
| NUDOCS 9206300006 | |
| Download: ML20101H514 (16) | |
Text
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W 9
b ATTACHMENT 1 REVISED TECF:NICAL SPECIFICATION PAGES 11 AND 1-7 E
4
' 's Tsc\92-029.001 9206300006 920624 PDR ADOCK 05000498
' ATTACHMENT I ST HL AE 90 *LS -
INDEX -PAGE- l 0F __3_ -
DEFINI1 IONS SECTION .PAGE 1.28 RE ACTOR TRIP SYSTEM RESPONSE 11ME . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.29 REPORTABLE EVENT... . .. .... .. ... ...... ...... .. ... 1-5 .
1.30 SHUTDOWN MARGIN.,. . ..................... ......... .,... 1-5 1.31 SITE BOUNDARY....... .... .............. ... .... .. ... 1-6 1.30 SLAVE RELAY TEST... ...... ...... ............................ 1-6
-1.33 SO LIO!H6AHOA . . . . . . . . . . .................. ........ ...... M SOURCE CHECK....... .. .. .. ............ .............. 1-6
- 1. 3)4 1.35 ST AGGERED. TEST BASIS. . . . .. . .. .. ... ....... ... .. 1-6
~
5-
,1.3$. THERHAL POWER. . ..... .. ......... ......... . . 1-6 6
1.3/ 1 RIP ACTUATING DEVICE OPERA 110NAL TEST. . . .. ....... .. 1-6
- 1. 3[7 -UN10EN11 FLED LEAKAGE. .. . . ... . ..........,,, . .. . . 1-6 1.3[ UFRESTRICTED AREA, . . . .,. ........ . 1 1. Ah VENTING. . . . . . .,. ., .. . ... .. .. 1-7 TABLE 1.1 FREQUENCY NOTATION. . .., . . ... .. . . 1-8 TABLE 1.2 OPERA 110NAL MODES. . .... . ... 1-9 s
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SOUlii IEXA5 - O'f1151 & 2 i
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DEL 11Lll10!!L UNRESTRICTED TREA 8
- 1. 3/ An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactiv'e materials, or any arsa within the SITE B0UNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. .
VENTING 39 1.A0 VEN11NG shall be the controlled process of discharging air or gas from a confinement to maintain temperature pressure, humidity, concentration, or other operating condition, in such a manne that replacement air or gas is not pro-vided or required during VENTING. Vei.t, used in system names, does not imply
- a VENTING process.
1 l
SOUTH TE uS - UNITS 1 & 2 1-7 l
. . = - . . . . _ - . . . . . .... . -.. .
t ATTACHMENT 2 REVISED ODCM PART A PAGES 29 AND 31
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-.Tsc\92 029,001
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- TABLE 3.3-13 '
RADIOACTIVE GASEOUS EFFLUENT MONIiORING INSTRUMENTATION .
I
. dof Use
[
- f. MINIMAL CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION M Condenser Evacuation System
- a. Condenser Air Removal System. Discharge Header Noble Gas Activity Monitor 1
- 49
- b. Flow Rate Monitor- 1
- 48
- c. Sampler Flow Rate Monitor
- 1 48 L
.3 [. Unit Vent ,
- a. Noble Gas Activity Monitor
- 1 49
- 53 P
- c. Particulate Monitor or Particulate Sampler 1
- 53
- d. Flow Rate Monitor 1
- 48
?
i
- e. Sample Flow Rate Monitor 1 *- 48
+
L T CD 3 .
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'S NL 89.0G7.01.R4 29 Rev. 4 1.f . '
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ATTACHMENT 3 TYPOGRAPHICAL MISTAKES CONTAINED IN THE ORIGIMAL PROPOSFD AMENDMENT l
l Tsc\92 029.001:
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' ' M' E pt11 muons MA51ER RELAY lEs1 ggm ST HL-AE 402.5
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1.17 PAGE _ 1 0F 9 A MA51ER RELAY 1EST shall be the energi:ation of each raster relay and ~
verification of OPERABILITY of each relay. The MA51ER RELAY TEST shall inc,lude a continuity che:L of each associated slave relay.
j t E_MBER(5) Of THE PUBL1C -
1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who u:,e portions of the site for recre- j ational, occupational, or other purposes not associated with the plant.
Of f 511E DOSE CALCULATION MANUAL yc4 b M M 1.19 The Off 511E DOSE CALCUL/,110N MANUAL (ODCM) shall contain the methodology and paramcters used in the calculation of of fsite doses 4ee-to- radioactive gaseous and liquid ef fluents, in the calculation of gaseous and liquid ef fluent monitoring Alarm / Trip setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. ,,
OPERABLE - OPERABillTY k - - - -
1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABill1Y when it is capable of performing its specified knction(s),
and when ail necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the syster::, subsystem, train, component, or device to perform its function (s) are also capable of perfort..ing their related support function (s).
OPERATIONAt MODE - MODE 1.21 An OPERA 110NAL MODE (i.e., MDDE) shall correspond to any one inclusive co.mbination of core reactivity condition, power level, and average reactor coolant temperature specified in Tabic L 2.
PHYSICS TESTS 1.22 -PHYSICS lESTS shall be those tests per formed to reasure the fundamental nuclear characteristics of the reactor core and related instrumentation:
(1) described 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 BOUbOARY LEAKAGE .
L 23 PRESSURE BOUNDARY LEAXAGE chall be leakage (except steam generator tube leata?)pip body, nrough a nonisolable fault in a Reactor Coolant System component well, or vessel vall.
SOUTH TEXA5 - UNITS 14 2 14
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- ATTACHMENT 3 ST-HL-AE W25 DEFINITIONS PAGE 7 0F 'l GASEOUS VASTE PROCESSING SYSTEM 1.7 A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed _to_ reduce radioactive gaseous effluents by-collecting Reactor Coolant System.offgases from the Reactor Coolant Sy tem and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBER (S) OF THE PUBLIC
~
1.8 MEMBER (S) OF THE PUBLIC chall include al1 persons who are not occupationally associated with the plant. This category does not include employees o' the licensee, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
O_FFSITE DOSE CALCULATION MANUAL 1.9 The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology cnd parameters used in the calculation of_offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the EavironmanLATOR451ological
~
Monitor!ng Program. The ODCM shall also contain (1) 't e Radioactive Effluent Controls and Radio p1 fical Enviror ental Monitoring Programa required by Section 6.8 g8Mnd /
(2) descriptions of the information tNat should be jncluded in the Annual Radiological Environmental hperating an'd' Semiannual Radioactive Effluent Release Reports redetred'byTechnical Spacifications 6.9.1.3 and 6.9.1.4.
OPERABLE - OPERABILITY 1.10 A system, subsystem, train, component or device shall be OPEEABLE or have OPERABIL'Tv when it is capable of performing its specified func*Im.(s), and when all necessary attendant inste mentatiun, controls, electrical power, cooling 'r seal water, tubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).'
OPERATIONAL MODE - MODE 1.11 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power IcVei, and average reactor coolant temperature specified in Table 1.2.
NL.89.087.01.R4 13 Rev. 4
- ATTACHMENT 3 ST HL AE you$
" __PAGE _7 _ 3F_ 9
' 3/4 LIMITING CONDITIONS FOR OPERATION' AND SURVEILLANCE "EQUIREMENTS
.3/4.0 APPLICABILITY m
CONTROLS Cookkinerk 3,0.1 Compliance with the Limiting conditions for Oper tion +ont-4eued in the succeeding controls is required during the'OERRyAlp'
~
HODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements-shall be met.
3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not roet within the specified time intervals. If the Control is restored prior to expiration of the specified +1me intervals, completion of the ACTION-requirements is not required.
3.0.3 When a control is not met, except as provided in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a HODE in which the Control does not apply by placing it, as applicable, in:
- a. At 1 cast 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 />,
- b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in i
accordance with the.specified time limits as measured from the time of failure to meet the Control. Exceptions to these
-requirements are stated in the individual controls.
This control is not applicable in MODE 5 or 6.
3.0.4 Entcy into an OPERATIONAL HODE or other specified condition l shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met _within a specified time. interval. Entry into an OPERATIONAL HODE or specified condition may be made in accordance with ACTION requirements when conformance to them l
t permits continued operation of the f acility for ar unlimited period of time. Thit provision shall not prevent-passage through or to OPERATIONAL HODES as required to comply with ACTIUN requirements. Exceptions to these requirements are stated in the-individual Controls.
/
NL.89.087.01.R4 19 Rev. 4
ATTACHMENT 3 ST-HL-AE-Val S PAGE._S OF 9' TABLE A3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANAIYSIS PROGRAM LOVER LIMIT MINIMUM OF DEfE ON LIQUID RELEASE SAhtLING ANALYSIS TYPE OF ACTIVITY (LLD)
TYPE' FREQUENCY FREQUENCY ANALYSIS .(uCi/ml) l..- Bitch Vaste 's P P Principaf33*** *
/ Release Eacli_ Batch Each Batch Ihit t e rs L xs N /
/~ IX10
-6
/ I-131 Y,_ /
- a. Vaste Monitor _3 Tanks P M Dissolved and lx10 One Batch /M Entrained Gases (Gamma Emitters)
- b. Laundry And Hot ,3 Shower P M H-3 lx10 Tank Each Batch Composite Gross Alpha lx10
- c. Vaste Eva-potator _3 Condensate P Q Sr-89, Sr-90 5x10
)
Tanks Each Batch Cc;mposite Fe-55 lx10
- d. Any other tanks which discharge liquid wastes past RT-8038 l
NL.89.087.01.R4 36 Rev. 4
, TABLE I4-1 PADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM .
MINIMUit LOWER LIMIT OF GASEOUS RELEASE- SAMPLING ANALYSIS TYPE OF'- DETECTION (LLD) -
TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)
- 1. Unit Vent M(3),(4) e Principal Gamma Emitters ( 1x10
_4 Grab Sample M H-3 (oxide) -6 1x10
- 2. Condenser Air [3 ,/ Principal Gamma Emitters (2) 1x10
-4 Remo al System Discharge Header Grab Sample M H-3 (oxide) -6 0
- 3. All Release I-131 Types as listed in Continuous (6) W(7) 1x10
-12
- 1. and 2. above Charcoal Sample I-133 -10 0 ,
Continuous (6) p(7) Principal Gamma Emitters ( 1x10~
Particulate
, Sample _
M Gross Alpha >
Continuous ( ) 0
-l1 Composite 'd"aM ,
Particulate Sample
- ho '
- m -
Continuous (6) Q Sr-89, Sr-90 -11 l c, M Composite 1x10 on pW Particulate O ,
Sample N L. 8 9. 0 8 7. 01. P2 46 Rev. 4 E t
L
ATTACHMENT 2L ST HL-AE4xts TABLE AS-2 PAGE - G-__. 0F 9 --
TABLE NOTATIONS (1)This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, togetLer vith those of the above nuclides shall-also be analy cd and' reporter. in the Annual Radiological
',Env 'al Operat inC Report pursuant - to Te chnical Specification
\
( 4elerld 6.9 ' d$. /
(2) Required-detiction capabilities for thermoluminescent dosimeteers used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4,13.
(3)The LLD is defined, for purposes of these epecifications, as the smalJest concentration of radioactive material in a sample that will yield a net count, above system. background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank obse rvat ion repreceits a "real" signal.
For a particular measuremeit system, which may include radiochemical separation:
- LLD =
E'* V a 2.22 x Y
- exp (-7(ot)
Where:
LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume),
s the standard deviation of the background counting rate or of the b= counting rate of a blank sa -ie as appropriate. (counts per i minute),
E= the counting efficiency (toonts per disintegration),
V= the sample size; (un it s rf mass or volume),
2.22 = the number of-disintegrations per minute per picocurie, Y= the fractional radioc'.emics1 yield, when applicable,
- 1L= the_{adioactive decay constant for the particular radionuclide (s ), and l
6t = the clapsed time.between environmental collection, or,end of the sample co11cetion period, and the time of counting (s).
p - %~O Typical values of E, V, Y, and 6t thould b. used in the calculation.
I -
NL.89.087.01.P2 70 Rev. 4
.._,m. ., . ,
.w ATTACHMENT 3 3/4.11 RADIOACTIVE nJFLUENTS ST HL PAGE ~7 AE-0F 4o15
- - 9 BASES 3/4.11.1.2 DOSE (Continued)
This Conteol applien to the release of radioactive materials in 11guld effluents from each unit at the site..
3/4.11.1.3 LIQUID WASTv PROCESSING SYSTEM The OPERABILITY of tSe Liquid Waste Processing System ensures that this system will be availabic for use whenever 11guld effluents require treatment prior to release to the environment. Th> requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10CFRSO 36a, General Design Criterion 60 of Appendix A to 10CFR Part 50 and the- design objective given in Section II.D of Appendix I to 10CFR Part 50.
The specified limits governing the use of appropriate portions of the Liquid Vaste' Processing System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effleunts.
.This Control applies to the release of radioactive materials in l' quid effluents from each unit.at the site.
, ~[Sh4.ll.1.4 LIQUID HOLDUP TANKS ~'
N The tanks covere -b this Control. include all those outdoor radv3ste tanks that are not surrounde sliners, dikes, or walls cap 3b -lf of holding the tank contents and that do not hav$'ltn overflows and,swfrounding area drair.s connected to-the Liquid Waste Process na s Sys&da.
Restricting the quantity ojf contained in the specified tanks provides assurance that loactive in themateris(of event a uncontrolled release of the tanks' entents, the resulting concentratinns wot be less than the limits f- R Part 20, Appendix B, Table II, Column 2 e nearest yocab e water supply and the nearest surface water supply in an '
- UNRESTRICTED ARBA.
NwC' . - - -
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE-This Control is provided to ensure that the dose at any time at and beyond the SITE EOUNDARY f rom gaseous ef fluents f rom all units on the site will be within the annual dose limits of 10CFR Part 20 to UNRESTRICTED AREAS.
The annual dose limits are the doses associated with the concentrations of
- , 10CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the S7.TE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of-NL 89.087.01.P3 82 Rev. 4
c;
- w-_ ATTACHMEND
/p-ST-HL-AE-WoM "
y x PAGE _2- - 0F 9 x .- _
ADMINISTRATIVE CONTROLS N AwanL RADtocosicAL GWAoNMENML cPEMTM REPDET' ,
$EtiIANNUAL RADIOACTIV PEEFLUENT-RELEASEitEPORT
- i
\ )
\ 6. 9.1 - 3 Routine Annual Radiological Environmental Operat'ing Reports
\ covering'the opera 61on of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior t 7 May- L R the year following initialJ riticaN ty and shall include copies of reports oTtTo preoperatioriil'Iidiological Environmental Monitoring Program of the '_ nit for at least two years prior to initial criticality.
The annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological env /oncental surveillance activities for the report perl(d.
including a comporison wJ preoperational studies and with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plan + operation oc the envircr; ment. The reports shall also include the results o. thn Land Use Census required by Control 3.12.2.
The Annual Radiological Environmental Opereting Reports shall include the results of analysis of all radiological enviror. men tal samples and cf all environmental radiation measurements taken durine ne pericd pursuant to the locations specified in the table and figures la the Offsite Dose Calt.ulation Manual as well as summarized and tabulated results of these analyres cad measurements in the format of the table in the Radiological Assesscent Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the misting results.
The missing data shall-be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and t he corrective action taken if the specified program is not being performed as required by l
Control 3.12.3; reasots for not conducting the Radiologien1 Environmental Monitoring Program as required by Control 3.12.1, and discussion of all l -devintions-froru the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pursusat to ACTION b. of Control 3.12.;; and discussion of all analyses in shich the LLD required by l Tal'le_4.12-1 was_not - achinvable. ,
)
- A single submittal may be made for a multiple unit sterion.
- One map shall cover -t ations near the SITE BOUNDARY: a second shall include the more distant Ma* tons.
NL.89.087,01.P3 96 Bev. 4
ATTACHMENT 3 ST HL-AEWoA G PAGE 9 0F 9 ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report'shall begin wit the date of initial criticality.
The Semiannual Radioactive Effluent Release Repo ts shall include a summary of the quantities of radic 'ive IIquid and gaseous effluent 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 Radioactive Materials in Liquid and Gaseous Ef fluents f rom Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories class of solid wastes (as defined by 10CFR Part 61),
type of container (e.g., LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).
The Semiannual hadioactive Effluent Release F9 port to be submitted within 60 days af ter 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 the form of an hour-by-hour listing on magnetic tape of wino speed, wind direction, atmosp p ies. stability, and precipitation (if
~
measured), or in the form of joint, frequency d}rtribut ions of wind speed, vind direction, and atmospheric stabtr'+.y.*V This name report shall include an assessment of the radiation dog'es due to tho'kadioactive liquid and gaseous effluents released from the unfL sor_ station during the previous calendar year.
This same report shall-als<. 2, 1ude an assessment of the radiation doses from radioactive liquid and gasec.s ef fluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure (5.1-3]) during the report' period.
All assumptions used in making these assessments, i.e., specitic activity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling- f requency and measurement, shall be used for determining the gasecus pathway doses. The <
. assessment of radiation doses'shall be performed in accorcance with the methodology and parameters in this document.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. _
- In lieu of submission with the Semiannual Radioactive Effluent Felease Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
NL.89.087.01.P3 97 Rev. 4
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