ML18022A897

Proposed Radiological Effluent Ts,Per Generic Ltr 89-01, Deleting Section 1.34 Re Solidification & Table 3.3.12 Re Radioactive Liquid Effluent Monitoring Instrumentation

ML18022A897
Person / Time
Site:	Harris
Issue date:	07/21/1992
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18010A700	List: ML18010A699 ML18022A897
References
GL-89-01, GL-89-1, NLS-92-132, NUDOCS 9207290107
Download: ML18022A897 (236)

Text

ENCLOSURE TO SERIAL: NLS-92-132 ENCLOSURE 5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (GENERIC LETTER 89-01) 9207290i07 920721 PDR ADOCN 05000400 P PDR TECHNICAL SPECIFICATION PAGES

i

'H P ~ "<<d

/

EHOEX DEFINITIONS SECTION PAGE

1. 32 SITE BOUNDARY............................................ ~ ~ .. 1-5

l. 33 SLAVE RELAY TESTo ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-6

l. 34 ~ ~ ~ ~ ~ ~ ~ ~

(OEQ7E'~) ~ O ~ ~ o ~ ~ ~ ~ o ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1. 35 Qt'~

Ql 5 QURCas P CHECKo 1-5

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1. 36 STAGGERED TEST BASISo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ 1-6

1. 37 TH ERNL POWER o ~ ~ ~ o ~ ~ ~ ~ ~ op .o ~ ~ ~ .go o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.38 .TRIP ACTUATING DEVICE OPERATIONAL TEST....................... 1-6

1. 39 UNIDENTIFIED LEAKAGE......:...... 1-6

1. 40 UNRESTRICTED AREAo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ 1-6 VENTILATION EXHAUST'TREATMENT SYSTBI.......................... 1-7 42 I VENT NG o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

I

~ ~ ~ ~ ~ ~ ~ 1-7

'ABLE FREQUENCY NOTATION...... 1 TABLE 1. 2 OPERATIONAL MODES.................. 1" 9 SHEARON HARRIS - UNIT 1

INDEX LIHITIHC CONDITIONS FOR OPERATION AND SURVEILLANCE RK UIREMEHTS SECTION PACK TABLE 3-3-6 RADIATIOH OPERATIONS' MOHITORIHC INSTRUMENTATION FOR PLANT . ~ ........................,...,...,. 3/4 3-51

,TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLAhT OPERATIONS SURVEILLANCE REQUIREMENTS.............,,..., .. 3/4 3-54 HovabLe Incore Detectors.........................,....... 3/4 3-56 Seismic Instrumentation.....,...,.....,....,...,...,...,, 3/4 3"57 TABLE 3 ~ 3 7 SEISMIC MOHITORIHC INSTRUMENTATION~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-58 TABLE 4.3-4 SEISMIC HONITORINC INSTRUHENTATIOH SURVKILLAHCK I

REQU REHEHTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-59 MeteoroLogicaL Instrumentation.................,......,., 3/4 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORIHC INSTRUMENTATION.......,,.... 3/4'-61 TABLE 4.3-5 METEOROLOGICAL MONITORINC INSTRUHENTATIOH SURVEILLANCK I

REQU REMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ + ~ 3/4 3-62 Remote Shutdown System................................... 3/4 3"63 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM..............................:. 3/4 3-64 TABLE 4.3-6 REMOTE SHUTDOWN HOHITORIHC INSTRUMENTATION SURVEILLANCE REQUIREMENTSe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ os ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-65 Accident Monitoring Instrumentation..... ~ .........,...... 3/4 3-66 TABLE 3.3" 10 ACCIDENT MONITORINC INSTRUHEHTATION.................. 3/4 3-68 TABLE 4.3-7 ACCIDEHT HONITORIHC INSTRUMENTATIOH SURVEILLAHCE REQUIREMEHTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ e ~ ~ ~ ~ s ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-70 TABLE 3.3"11 (DELETED) ~ ....... ................ ... ....o.o..o...

~ ~ ~ ~ 3/4 3"73 MetaL Impact Monitoring System........................... 3/4 3-74 3/4 3>>75 INSTRUMENTATION'

~i &s 0~< Honitoring Instrumentation.. 3/4 3-82 TABLE 3.3-13 MONITORINC

.. ~ .~.~ ... ~ . .. ~ . ~ .. ~ . ~ ..... ~ . ~ .. ~ .. ..

~ ~ . 3/4 3-83 TABLE 4+3-9 MONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-86 3/4 '.4 TURBINE OVERSPEED PROTECTION. ~ o. ~ o ~ eo ~ .~o ~ o ~ e ~ ~ ~ ~ ~ oooooo ~ o 3/4 3-89 SHEARON HARRIS - UNIT 1 Vl Amendment No. PO

INDEX LIMITING CONOIT:ONS FOR OPERATION ANO SURVEILLANCE REQUIREMENTS SiCTIQN PAGE 3/4o 11 RADIOACTIVE EFFLUENTS Qoa~r~og 3/4. 11. 1 LIQUID EFFLUEHTS oncent at>on............................................ 3/4 11-1 BL". 4o -1 IOA E LI)UI WASTE S PL1NG ANO ALYSIS P ROG ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ /4 11-2 O OS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3/4 11-5 L'quid tm ent stele ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ 3/4 11r6 L'quid Holdup Tanks............... .. -.- ..-. ~ ~ ~ ~ - ~ ~ ~ ~ -- ~ ~- 3/4 U.-7 3/4. 11. 2 GASEOUS EFFLUEHTS (QQAXfEQD O0 Rat ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 U.-B T BLE .1 2 RA OACTIVE GAS S WASTE S PLING ANO A LYSIS PR OG ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4' ~ ~ ~ ~ 3/4 U,-9 0 o e8 Notll 6 G es ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 11-ose - Iodi -131, Iodi -133, Triti, and Radioac ive.

Material i Particulat Form....... 3/4 -13 Gaseous adwaste T trent System ............. ......-.. 3 4 U.-14 Cg-'as

..or<>

3 /4. U,. 3 Explosive Gas Mixture...........;.....................

L Stol age Tanks*

I E

~ ~ ~ ~ ~ e ~

5

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ re e e e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ e o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e e ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~

3/4 U.-15 3/4 11-16 3/4 11-17 3/4. 11. 0 ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 11-19 12 RADIOLOGICAL ENVIRONMENTAL MON ITORENG gglgfcd)'/4. 3/4 ~ MON ORING ROGRAH e ~ o ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 12-1 T LE 3.12- RAOI GICAL VIRONM AL MONITOR NG PROGRAM....... 3/ 12 3 ABLE 3. 12 RE RTZNG ELS FOR IOACTIV CQNCEHTRA ONS N EHV RONM AL SAHP 3/4 12-TABLE 4. -I. CTI CAPABIL IES FOR IRONMEHTAL. PLE ANALY Se ~ ~ ~ ~ ~ ~ ~ ee ~ ~ ~ e ~ ~ eo ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 -10 3/4.. 2 O US CEHSUS.............. 3/ 12-13 3/4 12.3 NTER BORATORY OMPARISON OGRAM..... /4 12r14 SHEARON HARRIS - UNIT 1 xii

INOEX 8ASES SECTION PAGE 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4.10. 1 SHUTOOWN MARGIN...............;;.......................... '8 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, ANO POWER OISTRIBUTIQN LIMITS.... 8 3/4 10-1 3/4.10.3 PHYSICS TESiS................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ 0 ~ ~ ~ ~ 8 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 10-1 3/4.10.5 POSITION INQICATION SYSTEH " S HUTQ OWN o . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 10-1 3/4. 11 RAO IOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUEN i S......;...... 8 3/4 11-1 3/4. 11. 2 GASEOUS EFFLUENTS........... 8 3/4 11-2 3 4.11 SOLI RAQIOA IVE W i S............................. 3/4 3/4. 1. 4 T AL OOS .........,........ .................. ......... 8 3/ 11-5 3/4. 12 RAOIOLOGICAL ENVIRONMENTAL i&NITORING 3 .12 1 I PR RAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ o o ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 12-l

/4.. 2 USE C SUS............. 3/4

/ .12.3 TERLAB TORY QHPARISO PROGRAM. 834 (i>z~ersO)

SHEARON HARRIS - UNIT 1 XV1

INOEX AOMINISTRATIVE CONTROLS SECTION PAGE 6.14 OFFSITE.'OOSE CALCULATION MANUAL OOCM ... ~...... ~ ~ ~ .. - ~ ~ ~ ~ ~ 6-27 6.15 HA R C NGE TO UI EOUS ANO SO QW E EATH ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t~~~~~ ~ 6-28 (DEcfTf Dg'HEARON HARRIS - UNIT 1

DEFINITIONS MASTER RELAY TEST

1. 18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER S OF THE PUBLIC

1. 19 MEMBER(S) OF 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 use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL pgsvlfjeg Aem 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contai the methodology parameters used in the calculation of offsite doses radioactive 'nd I

gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.

OPERABLE - OPERABILITY Sasa T'1 it is train, 1.21 A system, subsystem, component or device shall be OPERABLE or have OPERABILITY. when 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) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE 1.22 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 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure 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 BOUNDARY LEAKAGE.

1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

SHEARON HARRIS - UNIT 1 1-4

INSERT 1 (on Page 1-4)

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4

'nd (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.

DEFINITIONS PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tes li 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 wa as to assure compliance with 10 CFR Parts 20, 61, and 71 and State regul ati ons, bur i al ground requi rements, and other requi r e-men s governing the disposal of radioactive waste.

PURGE - PURGING solid 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

VAGRANT POWER TILT RATIO 1.27 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 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2775 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored paraaeter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which

.the reactor is subcritical or would be subcritical from its present condition assuming all 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 withdrawn.

SITE BOUNDARY 1.32 For these Specifications, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SHEARON HARRIS - UNIT 1 1-5

DEFINITIONS SLAVE RELAY TEST 1.33 A SLAVE RLLAY TEST shall be the ener gization of each slave relay and veri fication of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION

~

&srjib /worn Tpc'4a'Iced, SpzcIFi'cappy~

>~~ ~</ ~rrZ r. eh'Cp.

SOURCE CHECK 1.35 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGEREO TEST BASIS 1.36 A STAGGEREO TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or ather designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing af one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.37 THERHAL POSER shall be the total reactor core heat transfer rate ta the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Ac.uating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED l&KAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.40 An UNRESTRICTED NEA shall be any area at or beyond the SITE BOUNDARY access to wbich is not controlled by the licensee for purposes of protec i<< o individuals from exposure ta radiation and radioactive materials, or any <<<<

within the SITE BOUNDARY used for residential quarters or for industrial, coaeercial, institutional, and/or recreational purposes.

SHEARON HARRIS - UNIT 1 1-6

INSTRUMENTATION PyP gPSygys RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMLNTATION MITING CONDITION FOR OPERATION 3.3.3. 0 The radioactive liquid effluent monitoring instrumentation ch nels shown i Table 3.3-12 shall be OPERABLE with their Alarm/Trip Setpoin set to ensure tha the limits of Specification 3.U,.3..1 are not exceeded. he Alarm/

Trip Setpoin of these'channels shall be determined and adjusted n accordance with the metho logy and parameters in the OFFSITE DOSE CALCULA ON MANUAL (ODCM).

APPLICABILITY:. At a times.

ACTION:

ao With a radioactive 'quid effluent mon'ring instrumentation channel Arlarm/Trip Setpoint 1 s conservativ than required by the above specification, immediat (1) sus nd the release of radioactive liquid effluents monitore by th affected channel or (2) declare the channel inoperable and take C ON as directed by b. below.

b. With less than the minimu numbe of radioactive liquid effluent monitoring instrumentat' channel OPERABLE, take the ACTION shown in Table 3.3-X2. Exe best effort return the instrument to OPERABLE status wit n 30 days and, if nsuccessful, explain in the next Semiannual R ioactive Effluent Rel se Report pursuant to Specification 6 .1.4 why this inoperabili was not corrected in a timely mann

c. The provi ions of Specifications 3.0.3 and 3.0.4, re not applicable.

SURVEILLANCE E UIREMENTS 4.3.3.1 Each radioactive liquid effluent monitoring instrumentation annel shall e demonstrated OPERABLE by performance of the CHANNEL CHECK, SOUR CH, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the fre encies shown in Table 4.3-8.

SPfctFinfjoais I/, 8.~ gO Aaa ~~7 q~ oE 4g 3.g~ hAvs grew ~g~g~g Szo~ fi+Huis/ Spsaf/'otfiws'ed'ave 8<su RcZoufia /y fh OKRA ~

I Pcs Jk Q-N fh~ooJg ~/5'" g hour 6'EN &&PFZ.

SHEARON HARRIS - UNIT 1 .

3/4 3-75

TABLE 3.3-12 Pl 2 RADIOACTIVE LI UID EFFLUENT HONITORING lttSTRUHEttTATION C)

Hl tt IHUti CttAHHELS It tSTRUHEttT OPERABLE ACTI OII g l. Radioactivity t1o tors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Ef ent Lines

1) Treated Laundry and t Shower Tanks Discharge Honit 35

2) Maste tionitor Tanks and te Evaporator Condemn te Tanks Discharge Honitor

.3) Secondary Maste Sample Tank Discli e itor 35, 36"

b. Turbine Building Floor Drains Effluent ne 36

c. Outdoor Tank Area Drain Transfer P p Honitor 37

2. Radioactivity Honitors Providing arm But ttot Providing Au ati c Termination of Release

a. Normal Service Mater stem Return From Maste Processing 39 Building to the Ci ulating Mater System

b. Normal Servi Mater System Return From the Reactor Auxiliary 39 Building t tl>e Circulating. Mater System

3. Flow Rate asurement Devices a, >quid Radwaste Effluent Lines

1) Treated Laundry and llot Shower Tanks Disci)arge O

2) Maste Honitor Tanks and Maste Evaporator Condensate Tanks Discharge

ThOLE. 3. 3-12 Continued)

RnDIOACTIVE LI uID EFFLUENT HONITORING INSTRUHENTnTION HINI HUH CNANNELS INSTRUHEN OPERABLE ACTION

3. Flow Rate surement Devices (Continued)

3) Secon Maste Sample Tank

b. Cooling Tower Blo own "Mhen the Secondary Maste System is being ed in the cont'ous release;mode, Action 36 shall be taken when the monitor is inoperable. In the bate release de, hction 35 is applicable.

I

TABLE 3. 3-12 Continued ACTION STAT""MENTS ACTION With the number of channels OPERABLE less than required the Minimum Channels OPERABLE requirement, effluent releas via this pathway may continue provided that prior to init ting a release:

a. At least twa independent samples are analyze in accardance with Specification 4.11.1.1.1, and

b. At least two technically qualified membe s of the facility taff independently verify the release ate calculations a d discharge line valving. I~

Otherwis suspend release of radioac.i effluents via this pathway.

ACTION 36- With he n r of channels OPERABL" less than required by the Minimum Channe s OPERABLE requir nt, diffluent releases via this path~ay ma continue pravid grab samples are analyied for radioactivity at lower limit f detection of no mare than 10-r microCurie/ml

a. At least once p 12 urs when the specific activity of

~

the secondary coo an OOSE E/UIVALENT I-, is greater than 0.01 microCurie/gram or

b. At least once pe 24 ours when the specifi.c activity of the secondary c olant less than or equal to

0. 01 micraCur /gram 00 EgUV/ALIT I-131 ACTION 37- With the number f channels OP BLE less than required by the Minimum Channe OPERABLE requfr ent, effluent releases via this pathway ay continue provided that, at least ance per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, gr samples are collecte and analyzed for radio-activity a a lower limit of detecti of no more than 10-r mf c Curie/ml.

ACTION 38- With e number of channels OPERABLE Ies than required by the Mini Channels OPERABl i- ~ufrement, ef uent releases via thf pathway may continue provided the flaw ate is estimated at east once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual rele es. Pump perform-ce curves generated in place may be used ta tfmate flow.

ACTION 39- With the number of channels OPERABLE less than re uired by the Minimum Channels OPERABLE requirement, effluents r leases via this pathway may continue provided the weekly Cooli Tower Blaw-down weir surveillance fs performed as required by S cifica-tian 4.U..1.1.1. Otherwise follow the ACTION specific in ACTION 37 above.

SHEARON HARRIS - UNIT 1 3/4 3-78

TABLE 4.3-8 RADIOACTIVE LI UID EFFLUENT HONITORINC INSTRUHENTATION SURVEILLANCE RE UIREHENTS DI CITAL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUHENT CHECK CHECK CALIBR ON TEST

1. Radioactivity Ho tors Providing Alarm and Automatic Terms tion of Release

a. Liquid Radwaste Eff nt Lines

1) Treated Laundry and t Shower R(3) q(1)

Tanks Discharge Honitor

2) Maste Honitor Tanks and R(3) q(I)

Waste Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tan P, X(S) R(3) q(I)

Discharge Honitor

b. Turbine Building Floor ains R(3) q(l)

Effluent Line

c. Outdoor Tank a Drain Transfer R(3) q(I)

Pump Honit

2. Radioactiv y Honitors Providing Alarm But No roviding Automatic Termination of ease

a. Normal Service Mater System Return From the Waste Processing Building to the. Circulating Mater System R(3) q(2

RADlOACTlVE Ll UlD EFFlUENT HONlTORlNG lNSTRUHENTATION SURVElLLANCE RE UIREHENTS t"

C) Dl AL ANNEL CINNHEL SOURCE CIIANNEL ERAT lONAL lNSTRUHEHT CIIECK CIIECK CALl0RATlON TEST

~

2. Radioactivity itors Providing A)are Q But Not, Providing toaatic Teraination of Release (Continue

b. Normal Service Mater stea Return R(3) - Q(2)

Froa the Reactor Auxilia Building to the Circulating Mater Sy ew

3. Flow Rate Heasuresent Devices 4J a. Liquid Radwaste Effluent Lines 4l I

l) Treated Laundry and Ilot Shower N.A. N.A.

CO Tanks Discharge Cl

2) Maste Honltor Tanks an aste p($ ) N.A. N.A.

Evaporator Condensa Tanks Discharge

3) Secondary ste Saaple Tank D(4) N.A. N.A.

b. Cooling T er Blowdown O(~) N.A. N.A.

. TABLE 4.3-8 (Continued)

'TABLE NOTATIONS (1) e DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that aut atic is lation of this pathway and control room alarm annunciation occur >f any f the following conditions exists:

a. I trument indicates measured levels above the Alarm/Trip etpoint, or

b. Circus failure (monitor loss of communications (alar only), detec or loss o counts (Alarm only) or monitor loss of power , or

c. Detector c eck source test failure (alarm only),

d. Detector chan el out 'of service (alarm only), o

e. Monitor loss of ample flow (alarm only).

(2) The DIGITAL CHANNEL OPE TIONAL TEST shall als demonstrate that control room alarm annunciation o curs if any of the ollowing conditions exists:

a. Instrument indicates me sured levels ove the Alarm Setpoint, or

b. Circuit failure (monitor ss of c munications (alarm only), detector loss of counts, or monitor ss o power), or

c. Detector check source test fai re, or

d. Detector channel out of ser ce,

e. Monitor loss of sample fl w.

(3) The initial CHANNEL CALIBRA ON shall be pe ormed using one or more of the reference standards c tified by the Nati al Bureau of Standards (NBS) or using standards hat have been obtaine from suppliers that participate in measure nt assurance activities ith NBS. These standards shall permit calibrat' the system over its inte ed range of energy and measurement range. or subsequent CHANNEL CALIBRA ON, sources that have been related to th initial calibration shall be use (4) CHANNEL CHECK sh 1 consist of verifying indication of ow during periods of release. C NNEL CHECK shall be made at least once pe 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which cont'ous, periodic, or batch releases are made.

(5) Men the S ondary Waste System is being used in the batch re ease mode, the sourc check shall be prior to release. When the system i being used in the ntinuous release mode, the source check shall be monthl .

EARON HARRIS - UNIT 1 3/4 3-81 Amendment No.

INSTRUMENTATION

<<pkosiv GA EBS-4 EHT MONITORING INSTRUMENTATION

~~ ~SKI Z LIMITING CONOITION FOR OPERATION 3.3.3. 11 The gas monitoring instrumentation channels l shown fn Table .3-13 shall be OPERABLE w th thefr larm/Trip Setpofnts set to ensure that the limits of Specfficatfo 3. 1 . . an 3. 11.2.5 are not exceeded. e A a rp e n s o hese anne mee g Speci >cation shall e det fned d adieu ed in accor ance wi the m thodolo d pa te fn th OOCN.

APPLICABILITY: As shown fn Table 3.3-U ACTION:

gv s~>asm>>

a. With'~ gaslgig effluent monitoring fnstrumentatfon channel arm/Tr p Set oint less conservative than required b the f

above speci fcatf on mme a e s spen he r ease ra i ve seo f ents onit ed b th af ected ch n or dso are r s o.nannsl nooeraois and take AGTI0N d r c e b SAOIdrP( du 7i biz 84-13.

aurora t~ Wfth the number of OPERABLE t monitoring g~yp>>rtw h R instrumentation channels less than the Hfnfmum Channe s OPERABLE, fu&jccrpaF&47i~ take the ACTION shown fn Table 3.3-13.

s to OPERABLE status within 30 days.. f unsuccessful, PjyPPR g ANCku5rdl/7 pursuant to Speci ffcatfon why this fnope ilfty was not g $ OZurtg /PrPOW7 A corrected fn a timely manner. g Adrs/

<g4 m spCoiu

'Af Ce~>SSdrddsd c The provisions of Specfffcat ons .. ana a.u.4 are not applicable.

SURVEILLANCE RE UIREMENTS FxpLrwv>>

4.3.3.11 Each g monitoring instrumentation channel shall be demonstrated OPERABLE b erformance of the CHANNE CHECK CHANNEL CALIBRATION and A N 0 ON NALOG NNEL OPERATIONAL TEST at the requencfes s own in able 4.3-9.

SHEARON HARRIS - UNIT 1 3/4 3-82

TABLE 3.3-13 ExPCOglVE GA S F E l l HON TOR NG I NSl RUHENTATION HINIHUH CINNNELS INSTRlNENT OPERABLE APPLICABILITY hCTIOH

l. GASEOUS MASTE PROCESSING SYSTEH HYDROGEN AND OXYGEN ANALY2ERS

a. Recoablner Outlet Hydrogen Honitor 1/recoabiner 50

b. Recoabiner Outlet Oxygen Honitor 1/recoabiner

c. Coapressor Discharge Oxygen Honitor . 1 48 TURBINE BUILDING VENT STACK

a. ble Gas Activity Honitor 47

b. Iodine le r 49

c. Particulate Saip 49

d. Flow Rate Honitor

e. Saapler flow Rate Honitor 46

3. PLANT VENT STACK aO Noble Gas Activity Honitor 47

b. Iodine Saapler 49 C. Particulat aapler

d. f Rate Honitor 46

e. Sampler flow Rate Honitor

TABLE 3. 3-13 Continued}

RAOIOACTlVE GASFOUS EFFLUENT HONITORlNG INSTRWENTATION HINIHUH CHANNELS INSTR T OPERABLE APPLICABILITY CT ION WASTE PROCESSING ILOING VENT STACK 5 a.I Noble Gas hctivi Honitor (PIG) 45, 51 a.2 Noble Gas Activity Mon or (WRGH) HOD I, 2, 3 52

b. Iodine Saapler

c. .Particulate Sampler

d. Flow Rate Honitor 46

e. Sampler Flow Rate Monitor

5. WASTE PROCESSING BUILDING STACK 5A

a. Noble Gas Activity Honitor 47

b. Iodine Saapler

c. Particulate Saapl 49

d. Flow Rate tor 46

e. Sampl Flow Rate Honltor

TABLE 3.3"13 Continued TABLE'OTATIONS t 1 t" es.

Ouring GASEOUS RAOWASTE TREATMENT operation ACTION STATBIENTS ACTION 45- the number of channels OPERABLE less than required by inim annels OPERABLE requirement, the contents of wast gas decay s) may be released to the environ provided (moy usso) that prior to ins 'ing the release:

At least two indepe t sampl the tank's contents gr analyzed, and At least two techn y qualif> embers af the facility staff indeperi ly verify the release te calculatians and dis e valve lineup.

the e, suspend release of radioactive eff1uents via s ACTION 46- er of channe s OP RABI less than're inimum Channels r en releases vsa

( is pat&ay ma avzde is estimated ACTION 47- er o c anne s ess an require inimum Channe requirement, e eases via (r-r us~op his pathway may continue samples are taken at least once and these samples ed for ACTION 48- With the number of channnels OPERABLE less than the Minimum Channels OPERABLE requirement, 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 aperations and at least ance per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> du>

ing other operations.

ACTION 49- ber of channels OP RA ess than requ~r inimum Channe requi~ement. e e eases via the (hog USSO) affected pathway may canti samples are continuously ol1 ected wi 'amp1 ing equi pme uired in ACTION SO- With the number of channels OPERABLE ane less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply

(~yP VSt'Dg to the recombiner.

ACTION 51- umber o channe s OP RABL less than re ui e Minimum Channe E requirement f e PIG and WRGM, effluent releases via this continue provided grab samples are east once per IZ hou ese samples.

(eO~ uSZO) ed for radiaactivit withi 4 ho r ACTION 52-SHEARON HARRIS - UNIT 1 3/4 3-85

E~iVIE'ABLE 4.3-9 NlTORlNG INSTRUHI.NTAflOH SURVElLLANCE RE UlREHENTS AN440E" I L HODES FOR WlllCII CIIANNEL CIIANNEL OPERATIONAL SURVE1L LANCE IRSTllUREDT CIIECK CALlBRAT ION TEST ~IS RE lllllED l; GASEOUS WASTE PROCESSlNG SYSTEH--

IIYOROGEN AND OXYGEN ANALYZERS Recoab incr Outlet Ilydrogen Q(4)

Honi tor j Recoabiner Outlet Oxygen Honitor

'gp Q(S)

C. Coapressor Discharge Oxygen Q(5)

Honi tor

2. TURBINE BUlLDlNG VENT STACK a0 e Gas Activity R(3) Q(2)

b. iodine ler H.h. N.A. N.A. N.A C. Particulate Sa r H.h. H.h. N.A. N.A.

Flow Rate Honitor D N.h. Q

e. Saapler flow Rate Honitor D -

N.h. 9

3. PLAN VENT STACK

a. Noble Gas Activity Honitor R(3) Q(2)

b. iodine Saapler N.h. N.A. A. N.h.

C. Particulate Salpler H.h. N.h. N.A. N.A.

Flow Rate H or N.A. R SaITp Flow Rate Honitor N.A. -R

TABLE 4. 3-9 Continueil RAOIOACTlVE GASEOUS EFFLUENT HONlTORlNG 1NSTRUHENTATlON SURVElLLANCE RE UlREHENTS DIGITAL CIIAIINEL HOOES FOR CII CHANNEL SOURCE CIIANNEL OPERATlONAL SURVEIL CE 1HSTRUHEHT CIIECK CIIECK CAL IBII~AII0 TEST 1S UIREO tll r c I. WASTE PROCESSlNG BUlLO G VENT STACK 5

a. 1 Noble Gas Activity Honito PlG) D R(3}

a.2 Noble Gas Activity Honitor (WRGH) R(3) Il(2)

b. iodine SaILpler N.A.

N.A. N.A.

c. Particulate Saapler N.A. N. N. A. N.A.

Kal

d. Flow Rate Honitor I

'4 CKA

e. Sampler Flow Rate Honitor N.A.

5. MASTE PROCESSlHG BUlLOlHG VENT STACK 5A

a. Noble Gas Activity Ho or R(3)

b. iodine Saapler H.A. N.A. N.A. N.A.

c. Particula Sampler H.A. N.h. H.h. H.A.

d. Flo ate Honitor D N.h.

e. Sampler Flow Rate Honitor H.A.

TABLE 4.3-9 Continued TABLE NOTATIONS a s.

P'Ouring GASEOUS RAGWASTE TREATMENT SYSTEW operation.

~AN G NP8. 0 T (i) IGITAL CHANNEL OPERATIONAL TEST shall also danonstrate that au c isolat f this pathway and control room alarm annunciation if any of the follow'onditions exists:

( Aug'USFOJ

a. Instrument indica measured levels above larm/Trip Setpoint, or

b. Circuit failure {monitor Ios unications - {alarm only)', detec tor loss of counts (al only) orE mon loss of power), or

c. Oetec.or chec rce test failure (alarm only ,

d. Oete channel out of service (alarm only), or onitor loss of s Ie flow (alarm onl (2) GI AL CHANNEL OPERATIONAL TEST shall also demonstrate that con room ala nunciation occurs if any of the following condit'xists:

Er USE'Og a0 Instrument in measured levels above th rm Setpoint, or Circuit farlure (monitor of co cations (alarm only), detec-tor loss of counts, or mani of power), or c Oetector check so est failure, or Oetecto nnel out, of se~ice, or

e. nitor loss of s Ie flow.

(3) al CHANNEL CALIBRA ON sha I be performed using one or mo the reference rds certified by the National Bureau ards (NBS) or using standa ave been obtai suppliers that

(~TfI C/5~0$ articipate in measurement assuran 'rties with "NBS. These standards shall permit calibratin stan over its range of energy and asurement r . or subsequent CHANNEL CALIBRATION, that have e ed to the initial caIrbratron shall be used.

(<) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

SHEARON HARRIS - UNIT 1 3/4 3-88

3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUENTS ONCENTRATION LIMITI CONDITION FOR OPERATION 3.11.1.1 The ncentration of radioactive material released in >quid effluents to UNRESTRICTED EAS (see Figure 5.1-3) shall be limited to e concentrations specified in 10 CF art 20, Appendix B, Table II, Column for radionuclides other than dissolved entrained noble gases. For dis ved or entrained noble gases, the concent tion shall be limited to 2 10-~ microCurie/ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioact e mate 1 released in liquid,effluents to UNRESTRICTED AREAS exceeding the bove limits, immediately restore the concen-tration to within the above 1'ts.

SURVEILLANCE REOUIREM S 4.11.1.1. 1 Ra active liquid wastes shall be sampled and ana ed according to the sampl g and analysis program of Table 4.11-1.

4. 11.1. .2 The results of the radioactivity analyses shall be used in cordance with e methodology and parameters in the ODCM to assure that the concen ations he point of release are maintained within the limits of Specification

.11.1.1.

A, +J 2 J

~ p p+ Jl ~ 4 Q/VCg ///

1+~ ~ +PEc'PF oe7]4k' gl ~Q~f g pg gg~~

SHEARON HARRIS - UNIT 1 3/4 11-1

TABLE 4.11-1 RAOIOACTIYE LIQUID WASTE SAMPLING 'AND ANALYSIS PROGRAM LOW LIMIT MINIMUM OF ETECTION LIQUIO LEASE SAMPLING FREQUENCY ANALYSIS FREQUENCY TYPE OF ACTIYITY ANALYSIS

~)(l)

TYPE (pCi/ml )

1. Batch Was e p P principa(,Gam Release Each Hatch Each Hatch Emitters Sxl0-7 Tanks I-131 lxl0-6

a. Waste Monitor p Oissol ed and lx10-s Tanks 0 Batch/M Entr ned Gases

b. Waste (Ga a Emitters)

Evaporator p M lx10-s Condensate Tank Each Ba h Composite 4 Gross Alpha lx10-7

c. Secondary Waste 5xl0-s p Q Sr-a9, Sr 90 Sample )

Each Batch mposit Tank (')

Fe-55 lxl0-6

d. Treated Laundry and Hot Shower Tanks Z. W p1"lncipaf~ljamma 5yjO-7 Continuo'~

Releases Continuou Composite Emi tters

a. Cool i ng . M(7 M(7) D ssolved and ~wl0-s Tower Weir Grail ample En ained Gases (G a Emitters)

b. Secondary I-131 lx10-6 Waste Sample M

6 7 H-3 lxl Tank Continuous Composite -'x10-7 Gross Alpha Sr 89, Sr 90 5x10 s 6 7 Continuous Composite Fe-55 10 6 SHEARON HARRIS " UNiT 1 3/4 11-2 Amendment i

TABLE 4. il-1 Continued)

TABLE NOTATIONS Th LLQ is defined, for purposes of these specifica ions, as the small st can ntration of radioactive material in a sample that will yield a t count, above system background, that will he detected with 45~ prob ility with o y 5" probability of falsely concluding that a blank observ tion represen s a "real" signal.

For a parti ular measurement system, which may include radioc ical separation:

4e66 sb E

~

22 x LOe ~ Y- exp (-A4t)

Where:

LLQ = the "a priori'ower limit of detec on (microCurie per unit mass or volume),

sb = the standard deviat on of the ba ground counting rate or of the counting rate of a'la sample as appropriate (counts per minute),

E = the counting efficiency (c nts per disintegration),

V = the sample size (units mas or volume},

2.22 x 10e -" the number o disintegr tions per minute per microCurie, Y = the fractional ra ochemical yield, when applicable, A -"the radioactive decay constant for th particular radionuclide (sec-~), and 4t = the claps d time between the midpoint of le collection and the time of unting (sec).

Typical v ues of E, V, Y, and At should be used i the calculation.

lt should b recognized that the LLQ is defined as an a r ri (before the fact) mit representing the capability of a measuremen system- and not as a posterial S (after the fate) 'limit for a partioula measurement.

A bat release is the discharge of liquid ~astes of a discrete lume.

Pri to'sampling for analyses, each batch shall be isolated, and hen th ughly mixed by a method described in the OQCN to assure presentative sampling.

SHEARON HARRIS - UNIT 1 3/4 U;3

TABLE 4.11-1 (Continued)

TABLE NOTATIONS Continued T principal gamma emmiters for which the LLO specification applies in ude the following radionuclides: Mn"54, Fe-59, Co-58, Co-60, -65, Ho-9 Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured ut with a LLD f 5 x 10-s. This list does not mean that only these nuc des are to be c nsidered. Other gamma peaks that are identifiable, to ether with those of he above nuclides, shall also be analyzed and repor ed in the Semiannua Radioactive Effluent Release Report pursuant to ecifica-tion 6.9. 1. in the format outlined in Regulatory Guide l. , Appendix B, Revision 1, ne 1974.

(4) A composite samp e is one in which the quantity of li id sampled is proportional to t quantity of liquid waste dischar ed and in which the method of sampling mployed results in a specimen at is representative of the liquids relea d.

(5) A continuous release is he discharge of liqu'astes of a nondiscrete volume, e.g., from a volu e of a system that as an input flow during the continuous release.

(6) To be representative of the qu tities d concentrations of radioactive materials in liquid effluents, mples shall be collected continuously in proportion to the rate of flow o th effluent stream. Prior to analyses, all samples taken for the composit shall be thoroughly mixed in order for the composite sample~ to be re e entative of the effluent release.

I (7) These points monitor potential release thways only and not actual release pathways. The poten al contami tion points are in the Normal Service Mater (NSM) and Sec dary Maste (S Systems. Action under this specification is as folio~  :

a) . If the applica e (NSW or SM) monitor in Table 3.3-12 are OPERABLE agd ot in alarm, then no ana sis under this specifica-tion is req red but weekly composites w ll be collected.

b) If the a licable monitor is out of service then the weekly analysi for principal gamma emitters will b performed.

c) If t applicable monitor is in alarm or if the rincipal gamma emi ter analysis indicates the presence of radio tivity as de-f ed in the ODCM, then all other analyses of this specification all be performed at the indicated frequency as lo as, the initiating conditions exist.

(s) The econdary Maste System releases can be either batch or contin us.

The type of sample required is determined by the mode of operation b ng used.

HEARON HARRIS - UNIT 1 3/4 11" 4 Amendment No.

RAOIOACTIVE EFFLUENTS OOSE LI TING CONOITION FOR OPERATION 3.11.1. The dose or dose commitment to a MB1BER OF THE PUBLIC fram ra oactive material in liquid effluents released to UNRESTRICTEO AREAS (see Fig e 5.1-3) shall be imi ted:

Ou ing any calendar quarter ta less than or equal to 1. mrems to the hole body and ta less than or equal to 5 mrems to any organ, and Ouring y calendar year ta less than or equal to mrems to the whole bo and to less than or equal to 10 mrems any organ.

APPLICABILITY: At all times.

ACTEON:

With the calculat dose rom the relea of radiaac ive materials in liquid effluent exceeding any of t e above limits, prepare and submit to the Ca ission within days, pursuant ta Specification 6.9.2, a Special Repo that identi ies the cause(s) far exceeding the limit(s) and define the car ive actions that have been taken to reduce the releases a the p posed corrective actions ta be taken to assure that subs uen releases will be in compliance with the above limits.

b. The provisions of Specific i s 3.0.3 and 3.0.4 are not applicable.

SURVEIlLANCE RE UIREHENTS 4.11.1.2 Cumulative dose co ributions fram li id effluents for the current calendar quarter and the c rent calendar year s Il be determined in accordance with the methodology and rameters in the OOCN at least once per 31 days.

HEARON HARRIS.- UNIT 1 3(4 Q-5

RAOIOACTIVE EFFLUENTS IOUIO RAOMASTE TREATMENT SYSTEM LIMI NG CQNOITION FOR OPERATION 3.11.1. The Liquid Radwaste Treatment System shall be OPERABLE and prapr iate portions f the system shall be used to reduce releases of radioacti ity when the projec d doses due to the liquid effluent, to UNRESTRICTEQ AR S (see Figure 5. 1-3 would exceed 0.06 irem to the whole body or 0.2 m to any organ in a 31-day p iod.

APPLICABILITY: t all times.

ACTION:

With radioa ive liquid waste being discharge without treatment and in excess of e above limits and any porti of the Liquid Radwaste Treatment Syst not..in operation, prepare nd submit to the Commis-sion within 30 s, pursuant to Specifi tion 6.9.2, a Special Report that includes the ollowing information.

1. Explanation of y liquid radwa was being discharged without treatment, ident ication of a inoperable qquipment or subsystems, and th reason f the inoperability,

2. Action(s) taken to to the inoperable equipment to OPERABLE status, and 1

3. Summary description of a ion(s) taken to prevent a recurrence.

b. The provisions of Specif cations .0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11. 1. 3. 1 Oases due to 1'quid releases to UNRE ICTED AREAS shall be projected at least once per 31 day in accordance with the me odology and parameters in the OOCM when Liquid Ra t aste Treatment Systems are n being fully utilized.

4.11.1.3.2 The ins led Liquid Radwaste Treatment Sys shall be considered OPERAB by meeting Specificatians 3.U..1. 1 an 3.11.1.2.

HEARON HARRIS - UNIT 1 3/4 Q-6

RAOIOACTIVE EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS OOSE RATE LIMI HG CONOITION FOR OPERATION

3. 11.2. 1 e dose rate due to radioactive materials released in seous effluents fr the site to areas at and beyond the SITE BOUNOARY (see Figure

5. 1-1) shall b limited to the following:

a. For nobl gases: Less than or equal to 500 mre /yr to the whole body and l s than or equal to 3000 mrems/yr the skin, and

b. For Iodine-131, for Iodine-133, for triti, and for all radio-nuclides in parts ulate form with half- ves greater than 8 days:

Less than or equal 1500 mrems/yr t any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding th above imits, immediately restore the release rate to within the above imit(s).

SURVEILLANCE RE UIREMENTS 4.11.2.1.1 to noble gases in gaseous ffluents shall determined to be The dose w'natethedueabove limits in accordance wi the methodology be and parameters i the OOQI.

4. 11.2. 1.2 . e dose rate due to Iodine-131, Iodine-133, triti , and all radionucli s in particulate form with half-lives greater than 8 s in gaseous fluents shall be determined to be within the above limits ce with the methodology'nd parameters in the OOCM by obtainin 'cco repr sentative samples and performing analyses in accordance with the s ling a analysis program specified in Table 4. 11-2.

Sp/+IJ>~7/w&$ ~/q.lJ. 2.4~ /e,Jg. B. 2 ~ %~.gg g.9 >~4 A, ZA'g.g g~v~

+<~+i~~ +p~afl&b~A$ A4d /fag uf+ 7 NE'D C

@~pa'l<D'-P W8~yA'per'-JYA~vs 8a~dr(ds(.

SHEARON HARRIS - UNIT 1 3/4 11-8

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAH HINIHUH LO LIHIT Of 1 SAMPLING ANALYSIS D CTION (LLD)~

GASEOUS LEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pciiml)

1. Waste Ga Storage P P Tank Each Tank Each Tank Principal Gamma Emi rs (2) lxlO-+

Grab Sam le onta nment Purge P or Vent Each PURGE Each PURGE Principal G a Emitters (2) lxlO-+

b Sample 1xlO-H-3 oxide

3. a. Plant Vent H3,, 5 Pr cipal Gamma Emitters 2) lxlO-Stack Grab Sample N-3 oxide 1xlO-e

b. Turbine Bldg H Principal Gamma Emitters (2) lxlO-+

Veldt Stack, Grab Sample Waste Pro- II-3 oxide Turb ne Bldg. lxlO-cessing Bldg Vent Stack)

Vent Stacks 555h

4. All. Release Types Conti ous W I-131 lxlO-'~

as l)sted in l., 2.,

and 3. above Charcoal Sample I-133 lxIO-~o Continuous 7 Principal Gamma Emitt s 2

lxlo->>

Particulate Sam le Continuous H Gross Alpha lxlO->>

Composite Par-ticulate Sam le Continuous (6 Sr-09, Sr-90 lxlO-Composite par-ticulate Sample

TASLE 4. 11-2 Continued TAHLE NOTATIONS The LLO is defined, for purposes of these specifications, as. the small ncentration of radioactive material in a sample that will yield a n t c nt, above system background, that will be detected with 95" prob ility wit only 5~ probability of falsely concluding that a blank observ tion rep ents a "real" signal.

For a p ticular measurement +stem, which may include radioc ical separati 4.66 sb E ~ ~

2.22 x 10' Y.. exp (-Qt)

Where:

LLO "- the "a pr ri" lower limit of detec i n (microCurie per unit mass or volume),

sb = the standard d iation of the bac round counting rate or of the counting rate of a blank sample appropr iate (counts per minute),

E = the counting efficien (cou per disintegration),

V = the sample size (units o ss or volume),

2.22 x 10e -"the number of isi egrations per minute per microCurie, Y = the fractional radi hemical y old, when applicable, A. ~ the radioactive ay constant fo the particular radionuclfde (sec-i), and At = the elapse time between the midpoiret of sample collec ',on and the time of co ting (sec).

Typical val s of E, V, Y, and ht should be us in the calculation.

It should ba cognited that she Ltg is defined as an oriori (beiore the fact) 1i t representing the capability or a aeasu nrsyste.n and not as an gostatiori (sitar tha fact) liait ror a part ular aaasureaent.

EARON HARRIS -. UNIT 1 3/4 11 10

TABLE 4. 11-2 Continued TABLE NOTATIONS Continued) e princ',pal gamma. emit.ers for which the LLO specificatio6 apolies i lude the follawing radionuclides: Kr 87, Kr 88, Xe-133, Xe-133m Xe- 5, and Xe-138 in nable gas releases and Hn-54, Fe-59, Co-58, -60, Zn-6 Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in Iodine nd partic late releases. This list does not mean that only these n lides are ta be c sidered. Other gamma peaks that are identifiable, to ether with those of e above nuclides, shall"also be analyzed and repat ed in the Semiannual adioactive Effluent Release Report pursuant to ecificaticn 6.9.1.4 in e format outlined in Regulatory Guide 1.21, pendix B, Revision 1, J e 1974.

Sampling and ana sis shall also be performed follawi g shutdown, startup, or a THERMAL POWER change exceeding 15K of RATED TH . MAL POWER within a 1-hour period.

Tritium grab samples sh Il be taken at least o e per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flood

'"'Tritium grab samples shall b taken at Ie - once per 7 days frcm the ventilation exhaust from the ent fuel ol area, whenever spent fuel is in the spent fuel pool.

( )The ratio of the sample flow rate the sampled stream flaw rate shall be known for the time period covered each dose or dose rate calculation made in accordance with Specific ion 3.11.2.1, 3.U..2.2, and 3.U..2.3.

Samples shall be changed at I ast once p 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af er changing, r after removal fram sampler.

Sampling shall also be per rmed at least o e per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shu down, startup, or ERMAL POWER change exceeding 15K of RATED THERMAL PO R within a 1-hour per'ad and analyses shall be completed within 48 ha s cf changing. When s les collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are anaIyzed, the co sponding LLQs may be incre sed by a factor of 10.

This requirement do not apply if: (1) analysis ows that the OOSE EQUIVALENT 1-131 c ncentratian in the reactor coola has nest increased more than a fac of 3; and (2) the nable gas monito shaws that effluent activi has not increased more than a factor f 3.

EARON HARRES. - ONIT 1 3/4 11-11

RAO QACTIVE EFFLUENTS OSE - NOBLE GASES LIi'i. ENG CONDITION FQR QP RATION 3.U.2. The air dose due to noble gases released in gaseous ef Iuents to areas at nd beyond the SITE BOUNOARY (see Figure 5.1-3) shall be limi d to the folio ng:

a. Ou ng any calendar quarter: I.ess than or equal to 5 mr ds for gamm radiation and less than or equal to 10 mrads for eta radiation, and

b. Ouring a calendar year: Less than or equal to 1 mrads for gamma.

radiation nd less than or equal to 20 mrads for eta radiation.

APPLICABILITY: At all times.

ACTION With the calculate air dose from radioa ive noble gases in gaseous effluents exceeding any of the above the Commission withi 30 days, pursua I'ts, prepare and submit to to Specification 6.9.2, a Special Report that i ntifies the use(s) for exceeding the limi (s) and defines the correct ve actions hat have been taken to reduce the releases and the pro sed cor ective actions to be taken to assure that subsequent rel ases ill be in compliance with the above limits.

The provisions of Specific io s 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREHENTS

4. 11.2.2 Cumulative dose con ributions for the urrent calendar quarter and current calendar year for n le gases shall be de ermined in accordance with the methodology and parame ers in the GOD at leas once per 31 days.

EARON HARRIS - UNIT 1 3/4 Q-12

RADIOACTIVE gFFLUENTS 0 SE - IOOINE-131 IODINE 133 TRITIUM. ANO RAQIQACTIVE HATER AL IN A SCULP > e. ORB LIMITI CONDITION FOR OPERATION 3.11.2.3 e dose to a HEHBER QF THE PUBLIC from Iodine-U1, Iodine- 3, tritium, an all radfonuclides in particulate form with half-lives g ater than 8 days i gaseous effluents re3eased to areas at and beyond th SITE BOUNDARY (sae gure 5.1-3) shall be lfmited to the following:

a. During y calendar quar wr: Less than or equal to 7.5 mrems to any organ an

b. During any lendar year: Less than or equal to mrems to any organ.

APPLICABILITY: At all tim s.

ACTION:

a. fifth the calculated d e, rom the rel ase of Iodine-13L, Iodine-133, tritium, and radfonucl> es in partic ata form with half-lives greater than 8 days, in seous eff ents exceeding any of the above limits, prepare and submi the th Commission within 30 days, pursuant to Specification 6. 9.2, a ecia Report that identifies the cause(s) for exceeding the limit(s) efines the corrective actions that have been taken to reduce the rele es and the proposed corrective actions to be taken to assure that s s quent, releases will be in compliance with the above limits.

b. The provisions of'Specif cations 3. 3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIR&ENTS 4.LL.2.3 Cumulative dose ontrfbutions for the curre t calendar quarter and current calendar year fo Iodfne-L3L, Iodine-H3, trit and radionuclides in particulate form wi hal f-lives greater than 8 days hall be determined fn accordance with th methodology and parameters in the Qf at least once per 3L days.

, HEARON HARRIS - UNIT 1 3/4 LL-L3

RAQIGACTIVE -"FFLUENTS GASEOUS RABIAST"" TREATMENT SYSTPI LI ~TI."IG CONOITICN FOR OPERATION 3.".2.4 The VENTILATION EXHAUST.TRHTHENT SYSTBf and the GASEOUS RA ASTE TREATISE. SYSTcH shall be OPERABLE and approoriate portions of these systems shall be sed to reduce releases of radioactivity when the project doses in 3l days du to gaseous effluent releases to areas at and beyond e SITE BOUN-QARY (see F> ure 5.1-3) would exceed:

a. 0.2 ad to air from gamma radiation, or

b. 0.4 mra to air from beta radiation, or

c. 0.3 mrem any organ of a HBSH OF THE PUBL i.

APPLICABILITY: At al 1 mes.

ACTjON:

a. Wi h radioactive ga eous waste being ischarged without treatment and in excess of the bove limits, repare and submit to the Commission within 30 s, pursua to Specification 6.9.2, a Special Report that inc des the following information:

l. Identification of any in erable equipment or subsystems, and the reason for the ino rability,

2. Action(s} taken to sto the inoperable equipment to OPERABI ~

status, and

3. Suaaary descrip on of action ) taken to prevent a recurrence.

The provisions of pecifications 3.0. and 3.0.4 are not applicable.

SURVEILLANCE REOUIREME 4.U..Z.4.l Goses d to gaseous releases to areas at beyond the SITE BOUNOARY shall be jected at least once per 31 days in cordance with the methodology and p ameters in the ODN when the GASEOUS TREATHENT SY~ is not b ng fully utilized.

4; XZ.2.4.2 e installed VENTILATION EXHAUST TREATMENT SYSTEM nd GASEOUS RAOMASTE TR THENT SYSTEM shall be considered OPERABLE by meetin Specifica-tions 3. 2.1 and 3.i1.2.2 or 3. D.2.3.

SHEARON HARR!S UNIT I 3l4 XX-X4

RAOIQACTIVE EFFr UENTS 3/4. 1L. 3 SOLID RADIOACTIVE WASTES CONDITION FOR OPERATION

'IMITING 3.1 3 Radioactive wastes shall be solidified or dawatarad in accordance w h the P CESS CONTROL PROGRAH to meet shipping and transportation raquirama s during ansit, and disposal site requirements when received at the dis sal sita.

APPLICABILITY: At al 1 times.

ACTION:

With SOLIDI CATION or dawataring not meeting 'osal site and shipping and ansportation requirements, sus end shipment of the inadequately p essed wastes and correct e PROCESS CONTROL PROGRN, the procedures, a or the Solid Waste S ~am as necessary to prevent recurrence.

With SOLIDIFICATION or'atering performed in accordance with the PROCESS CONTROL PROG, tas e improperly processed waste in each container to ensure th t 'eets burial ground and shipping requirements and take approp 'ata administrative action to prevent racurranca.

C. The provisions of Spec ications 3. .3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIRBIENTS 4.D.3 SOLIOIFICATIQ of at least one representative t specimen from at least every tenth b h,of each type of wet radioactive tes (e.g., filter s'ludges, spent re ns, evaporator bottoms, boric acid solut ns, and sodium sulfate solutio ) shall be verified in accordance with the . CESS CONTROL PROGRAM:

a. f any test specimen fails to verify SOLIDIFICATION, the OLIOIFICATIQN of the batch under test shall be suspended until such time s additiona test specimens can be obtained, alternative SOLIDIFICATION p ametars can be determined in accordance with the PROCESS CONTROL PROG and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION o the batch may then be resumed using the alternative SOLIDIFICATION pararreters determined by the PROCESS CONTROL PRQQRAH; ra+, p~~~ ~s ~

pelocefrg fo fib gap pape 3/e l4-18 Ae~ 8<znr dzlWz4 SHEARON HARRIS - UNIT 1 3/4 Q-17

RADIOACTIVE EFFLUENTS OLID RADIOACTIVE MASTES SUR'LLANCE REQUIREMENTS Continued 4.LL.3 Continued)

b. f the initial test specimen from a batch of waste fails verify S IDIFICATION, the PROCESS CONTRQI. PROGRAM shall provi for the col ection and testing of representative test specimen from each cons utive batch of the same type of wet waste until at least three consec tive initial tes- specimens demonstrate SOLI FICAiiON. The PROCESS ONTROL PROGRAM shall be modified as requi ed, as provided in Speci 'cation S.L3, to assure SOLIDIFICATION subsequent batches of waste; d C. With the inst lied equipment incapable of me ing Specification 3.11.3'or decl ed inoperable, restore the uipment to OPERABLK status or provi for cbntract capability process wastes as necessary to sati fy all applicable tran ortation and disposal requirements.

RQN HARRIS UNIT 1 3/4 Ll-LB

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3/<. 2 RAO QLQGICAL NVIRONMENTAL bONITQR.NG 3/4. 2. 1 KiNcTGR!NG PROGRAM LIMz. ~NG C"NO!7".QN FQR OPERATION 3.12.1 Radiological Environmental Monitaring Program shall he con c ed as specific in Table 3.12-1.

APPLICAB ILITY: t al I imes.

ACiION:

With the Rad logical Environmental Monitoring agram not being conducted as s cified in Table 3.12-1, prepa and submit ta the Commission, the Annual Radial agical viranmental Operating Report required by ecification B.9.1.3, description of the reasons for nat canducting program as requi d and the plans far preventing b.

a recurrence.

an enviranmental sampling me the reporting levels of Table

't With the level of radioac.'ty a the result af plant effluents in a specified location exceeding 12-Z when averaged over any calendar quarter, prepare and submit o t Commission wi thin 30 days, pursuant to Specification 6.9.2, a ecial eport that identifies the cause(s) for exceeding the limit and defin s the corrective actions ta be taken to reduce radioa ive effluents o that the potential annual dose" ta a MEMBER OF E PUBLIC is less an the calendar year limits of Specifications .11.1. 2, 3.11.2.2, or 11.2.3. When more than one of the radio clides in Table 3.12-2 a detected in the sampling medium, this r ort shall be submitted if:

canc tration 1 concentration 2 rep cng eve reporting eve When dionuclides other than those in Table 3.12-2 are etected and are he result of plant effluents, this report shall be s mitted if t patential annual dase" to a MBIBER OF THE PUBLIC from a 1 radio-uclides is equal to or greater than the calendar year limit of Specificatian 3.11.1.2, 3. 11.2.2, ar 3.U,.2.3. This report is ot, required if the measured level of radioactivity was not the resu of plant effluints; hawever, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.3.

SPtcII IGIQth~ //+4~ 4 p hrfo7 P pale/ ~fg, jp,J /jppt /gal~ gz4 f' g s~~~+lmgjd~g~cf M4~zcP Wo 1"4 OUCH.

~fg /cd g Th<uogg 9/+ gcR -$ 51 g~>< g< ~gF/Z4 ~

e meth o ogy an arameter use o mate t po en s annua se ta a MB% OF THE P LIC shall e indic ed in th report.

SHEARON HARRIS - UNI7 1 3/4 12-1

RAOIOLOGECAL ENVIRONMENTAL HONITORENG iTORiNG PROGRAM L~4IT. MG CONP <T jON FOR OPERATION ACTiON ontinued):

c h milk or fresh leafy vegetation samples unavailable om one or mor of the sample locations required by Table 3. I2-L, dentify spec ic locations for obtaining replacement samples d add them withi 30 days to the Radiological Environmental Mon'toring Program given i the OOCN. The specific locations from wh' samples were unavail le may then be deleted from the moni ori g program. Pursuant to Specifs ation 6.14, submit in the next Semia ual Radioactive Effluent Re ease Report documentation for a ch nge in the OOC'8 t'h including a vised figure(s) and table for e OOCN reflecting e new location(s with supporting information dentifying the cause of the unavailabil'ty of samples and justifyi g the selection of the new location(s) r obtaining samples.

d. The provisions of S ecifications 3.0. and 3.0.4 are not applicable.

SURVEILLANCE RE UERBIENTS 4.12;1 The radiological environment nitoring samples shall be collected pursuant to Table 3. LZ-1 from the spec'c locations given in the table and figure(s) in the OCCAM, and shall be a zed pursuant to the requirements of Table 3.~U-1 and the detection cap lit> s required by Table 4.XZ-1..

SHEARON HARRIS

- UNO'. 3/4 12-2

TABLE 3.12-1 RADIOLOGICAL ENVIROHHEHTAL MONITORING PROGRAN" HNSER OF REPRESENTATIVE EXPOSURE Tl WAY SANPLES AHD SAMPL IHG AHD TYPE AHD F qUENCY AND/OR SAN SAHPLE LOCATIONS II<< I FUIIIUEII Y OF A YSIS

1. Direct Radiat Forty routine monitoring stations quarterly. G a dose quarterly.

either arith two or more dosimeters or arith one instrument for surtng and recording dose rat continuously, placed as foi los An inner ri of stations, one in each meteorolo cal sector in the general area of t SITE BOUNDARY; An outer ring of stati , one in each meteorological secto in the 6- to 8-km range from t site; and The balance of the sta ons to be placed in spe al interest areas such as po ation centers, nearby residen , schools, and in one or t areas to serve as control ations.

TABLE 3. 12-1 Continued RADIOLOGICAL EHVIRONHEHTAL HOHITORIHG PROGRN NlNOCR OF REPRESENTATIVE EXPOSURE PAT Y SAHPLES AND - SAHPLIHG AND TYP5 AND EQVEHCY

~- COLI.ECTIOH FRE UEHCY bF ALYSIS AND/OR SAHPLE SANPLE LOCATIONS(

2. Airborne Samp>es from five locations: Continuous sampler oper- dlolodine Cannl stet".

Radioiodine and ation with sample collec- ana ys s wee ly.

Particulates tion weekly or more Thre ampies from close frequently )f require y to the ee SITE BOUNDARY dust loading. Particulate Sa ler:

locations;- n different ross e a ra oactivity .

sectors, .of t highest analysis fo I lowing calculated annua average ground- level 0/g; filter change; (3) and gawaa isotopic analysis of composite (by One sample from the location) quarterly.

vicinity of a community having the highest calcu-lated annual average grou level 0/Q; and One sample from a control location, as f example 15 to 30 km dista and ln the least prevalen ind direction.

3. Haterborne

a. Surface One sample upstream. Composite sample over asiia isotopic analysis period.( ~ thly. Cbmposite for One sample downstream. 1-month trit analys l s quarterly.

b. Gr d Samples from one or two sources guar ter ly. Ganesa iso lc and only lf likely to be tritium anal s quarterly.

affected( ~.

TABLE 3.12-1 Continued BAOIOLOGICAL ENVIRONHENTAL HONI TORING PROGRAH NVHDER OF REPRESENTATIVE EXPOSURE TIIWAY SAHPLES AN SAHPLING AN TYPE AN BE(}UENCY AND/OR SAH SAHPLE LOCATIONS COLLECTION FRE UENCY 0 NALYSIS

3. Materborne nt)nued)

c. Or) nk ing One sample in the vicin) ty Composite sample over I-131 analysis on each the nearest downstream 2-week period (6) whe composite when the dose wu )pal water supply intake I-131 analysis is calculated for the con-frotl e Cape Fear River.

formed; monthly ow- sumption of the water posite othe se. is greater than 1 wrew One sample ow a control per year (8) . Composite location. for gross beta and gama isotopic analyses (4) wonthly. Compos I te for tritiutl analysis quarterly.

d. Sed)went One sample in the vicinity Semiannually. Gasea isotopic analysis from the cooling tower blowdo sew)annually.

Shoreline discharge in an area h exist)ng or potent recreational value.

4. Inges t ion

a. Hi lk Samp from w)lk)ng animals Sew)wbnthly when Gaeaa isotopic . and i hree locations within 5 kw anima)s are on pastur I-131 analysis sewi-stance having the highest dose month)y at other tiwes. aonth)y when an)mals potential. If there are none, are on. pasture; aonthly then one sample frow wi)k)ng at othe')wes.

animals in each of three areas between 5 to 0 kw distant where doses are calculate(g)o be greater

.than 1 wrew per yr e One sample frow wi )king animals at a control location 15 to 30 km distant and in the least prevaient. wind <))rect)on.

TABLE 3. 12-1 Continue RADIOLOGICAl. EHVIRONHEHTAL MOHI TORIHG PROGRN NNAER OF REPRESENTATIVE EXPOSURE PA AY SAMPLES AND SANPLIHG AHO TYPE A FREqUENCY AND/OR SAHPL SAMPLE LOCATIOHS COLLKCTIOH FRE UEHCY ANALYSIS

4. Ingestion (Cont ed)

b. Fish and sample of Sunfish, Cat- Sample in season, or Gaaea isotopic analysis (i)

Inverte- fls , and large-Mouth Bass semiannually lf the on edible portions.

brates species n vicinity of plant are not seasonal.

discharge ea.

One sample of me species ln areas not influen d by plant dl scharge.

c. Food Samples of three differen onthly during -Gaaaaa I~otopic and 1-13I Products kinds of broad leaf vegeta- growing season. ana lys ls.

tion gro~n nearest each. of two different offslte 'lo tions of highest predl ed annual average grou level D/q if milk samp ng is not performed.

One sam of each of the Monthly during Gaena isotopic~ ~

and 1-131 sfmi I broad leaf vegeta- growing season. analys I s.

ti gro~n 15 to 30 kta dis-ant in the le'ast prevalent wind direction if silk sam-pling is not performed.

TABLE 3.i~-L Continued TABLE NOTATIONS Specific parameters of dis:ance and direction sec or from the center,ne f one reactor, and additional description where pertinent, shall b pro-v ed for each and every sample loca ian in Table 3. U-L in a tab and fi re(s) in the 00C4l. Refer to NUREG-0133, "Preparation cf Rad'olcgical Effl nt Technical Specifications for Nuclear Power Plants," 0 ober L978, and Radiological Assessment Branch Technical Position, Rev ion L,

'ovembe L979. Geviaticns are permit.ed fram the required s ling schedule f specimens are unobtainable due ta circumstance such as hazardous anditians, seasonal unavailability, and malfun ian af auto-matic sampl g equipment. If specimens are unobtainabl due to sampling equipment ma unc ion, effort shall be made to complet corrective actiaa prior to the e of the next sampling period. All d iations fram the sampling schedu shall be documented in the Annual adiolcgical Environ-mental Operating eport pursuant to Specification .8. L.3. It is recog-nized that, at tim , it may not be possible or racticable to continue to obtain samales of -..; media of choice at the m t desired Iocatian ar time.

In these instances su table 'alternative media and locations may be chosen for the particular pat ay in question and propriate subs itutions made within 30 days in he Ra iological Environ ntal Monitoring Program. Pur suant ta Speci icaticn 6. , submit in t next Semiannual Radioactive Effluent Release Report do mentation f a change in the ODA including a revised figure(s) and tabl for the CM reflecting the new location(s) with supporting information i ntify g the cause of the unavailability of samples for that pathway an 'us ifying the selection of the new loca-tion(s) for obtaining samples.

(2) One or more instruments, such a ssurized ian chamber, for measuring and recording dose rate canti ously y be used in place of, or in addi-tion ta, integrating dosime rs. For e purposes of this table, a thermaluminescent dosimate (TLQ) is co idered ta be ane phosphor; twa or more phosphors in a p ket are canside as twa or mare dosimeters.

Film badges shall not b used as dosimete for measuring direct radiation.

(The 40 stations is no an absolute number. 'he number of direct radiation geographical limitations; monitoring stations e.g., at an ocean s', y be reduced according some sectors will be o r water so t>>at the number of dasimeters may e reduced accordingly. The quency of analysis or readout for TLD stems will. depend upon the char ristics of the speci-fic system use and should be selected to obtain a imum dose information

~ithin minima fading.)

(3) Airborne p iculate sample filters shall be analyzed r gross beta

-radioacti ity 24 haurs. ar mare after sampling to aIlaw radon and thoran ughter decay. If gross beta activity in air pa culate samples is gre ter than 10 times the yearly mean of control samples gamma isot ic analysis shall be performed on the individual sampl (4) 6 isotopic analysis means the identification and quantifica ion of am'-emitting radionuclides that may be attributable to the eff ents fram the facility.

SHEARON HARRIS - UNIT L 3/4 L2-7

TABL- 3.12-1 Continued TABL= NOTATIQNS Continued (5) he "upstream sample" shall be taken at a dis.ance beyond signi icant i luence of the discharge. The ."downstream" sample shall be taken n an are beyond but near the mixing zone. "Upstream" samples in an es ary must e taken far enough upstream to be beyond the plant influen . Salt

~ater hall be sampled only when the receiving ~ater is utilize for recreat'onal ac.ivities.

(5) composit sample is one in which the quantity {aliquot) o liquid sampled A

is proporti al to he quanti y of flowing liquid and in 'ch the method of sampling ployed results in a specimen that is repre antative of the liquid f1ow. this program composite sample aliquot shall be collected at time intarva that ar very short (a. g., hourly) lative to the ccmpositing perio (e.g., monthly) in order to assur obtaining a representative s le.

(7) Groundwater samples s all be taken when this so ca is tapped for drinking or irrigation purposes n areas where the hydr ulic gradient or recharge properties are sui'table or contamination.

(8) The dose shall be calculate for the maxi m organ and age group, using the methodology and paramete s in the 00 SHEAaON HARRrS - uNV' 3/4 ?2-8

TABLE 3.12" 2 REPORTIHG LEVELS fOR RADIOACTIVITY CONCENTRATIONS IN ENVIROHNENTAL SlNPLES HATER AIRBORNE PARTICULATE F ISii BILK FOOD PRODUCTS AHALVSIS (pCi/l) OR GASES (pCi/os) (pCi/kg, wet) (pCi/l) (pCf/kg, wet)

II-3 2 o 00~

Hn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10, Zn-65 300 20,000 ir-Hb-95 400 I-131 2@A 0.9 100 Cs-134 30 10 eo 1,000 Cs-137 50 2,000 70 2 >000 Da-La-140 200 "For drinking water s les. This is 40 CFR Part 141 value. If no drinking wat atlway exists, a value of 30,000 pCi/I e e used.

""Ilf no drinkin ater pathway exists, a value of 20 pCi/I say be used.

TNLE 4.12-1 rn OETKCT ION CAPABILITIES FOR KNVIROHHENTAL SAMPLE ANALYSIS C7 LOMER LINIT OF OETECTION LLO .

aA F I Sll

~

MA AIRBORNE PARTICULATE HILK FOOD P UCTS SKOINENT

. AHALYSiS (pCi OR GASES (pCI/es) (pCi/kg, wet). (pCi/I) (pC g, set) (pCI/kg, dry)

Gross Beta O. 01 ll-3 2000" Hn-54 15 130 Fe-59 30 260 Co-58,60 130 Zn-65 30 60 I

Zr-Hb-95 15 C7 1-131 .07 60 Cs-134 15 0.05 130 15 150 Cs"137 18 O. 06 150 18 80 180 Oa- La-140 "If no dri ng eater patlway exists, a value of 3000 pCi/1 cay be.used.

• "If n rinking water pathway exists, a value of 15 pCi/l cay be used.

TA8LE 4. 12-1 Continued TA8L= NOTATIONS

{1 his lis does not mean that only these nuclides are to be con@dered.

her peaks tha. are iden ifiable, together with those of the above nu lides, shall also be analyzed and reported in the Annual Radiologi al Env> onmental Operating Report pursuant to Specification 6.9.L.3.

{2)Requir detection capabilities for thermoluminescent dosimeters sed for envs onmental measurements shall be in accordance with the commenda-tions of egulatory Guide 4. 13-.

(3)The LLG is fined, for purposes of Nese specifications, a the smallest concentration of radioactive material in a sample that wiI yield a net count, above s tern background, that will be detec.ed wi . 9~~ probabili y with only ~" pro ability of falsely concluding that a b ank observation represents a "rea " signal.

For a particular mea urement system, which may incl de radiochemical separation:

4.66 sb LLG =

E ~

V ~

22 ~ Y . exp(- t)

'Where:

LLG -"the "a priori" lower 'mit of tection {picoCuries per unit mass or volume),

sb = the standard deviation of e background counting rate or of the counting rate of a blank Ie as appropriate (counts per minute),

E ~ the counting efficien {coun per disintegration);

V = the sample size (un of mass o volume),

2; 22 = the number of di ntegrations per m'nute per picoCurie, Y = the fractional radiochemical yield, w n applicable,

= the radioa ive decay constant for the p icular radionuclide

{sec-~), d bt ~ the el sed time between enviroe&ntal coll ion, or end of the s le collection period, and time of coun ing (sec).

Typical v ues of E, V, Y, and 4t shouId be used in the alculation.

EARON HARRIS - UNIT L 3/4 L2-LL

TABLE 4. 12-'ontinued TABLE NOTATIONS Continued t shnuld be recngnized that the LB is detined as an a ~riant (acier .e ct) limit representing the capability of a measurement system and no as an a oosteriori (after the fact) limit for a particular measurement.

Ana ses snaSS be gerfermed in such a manner that the stated LU)s u' be achie ed under routine conditions. Occasionally background fluctu tions, unavoi ble small sample sizes, the presence of interfering nucli es, or

,. other u ontrollable circumstances may render these LLDs unachi able.

In such c es, the contributing factors shall be identified a described in the Ann 1 Radiological Environmental Operating Report pu uant 'to Speci ficati o 6.9.1.3.

EARON HARRIS

- UNIT 1 3/4 I2-I2

RADIOLOGICAL ENVIRONMENTAL MONITORING 4.i2.2 LANO USE CENSUS L MIi NG CQNOITIQN FOR OP RAT ON 3 '2.2 Land Use Census shall be conducted and shall identify withi a distance 8 km (5 miles) the Iocatian in each of the 16 meteorala cal sectors of e nearest milk animal, the nearest residence, and the earest garden" of g ater than 50 aP (5QQ ft~) producing broad leaf veg ation.

APPLICA8ILITY: t all times.

ACTiON:

arith a Land Use Census identifying a location( that yields a calculated d e or dose commitment greater th the values currently being calculat d in Specification 4. 11. 2.3, ursuant to Specifica-tion 6. 9. 1.4, i ntify the new location(s) n the next Semiannual Radioactive Effl nt Release Report.

b. '>lith a Land Use Cen us identifying a Ia ation(s) that yields a calcu-lated dose or dase c itment (via th same exposure pathway) 20~

greater than at a loc ion from whic samples are currently being obtained in accordance ith Specifi ation 3. 12.1, add the new laca-tian(s) within 3Q days. the Rad'ogical Environmental Monitoring Program given in the OOQl. The ampling location(s), excluding the control station location, h vi the lowest calculated dose or dose cammitment(s), via the same osure pathway, may be deleted fram this monitoring pragram aft ctober 31 of the year in which this Land Use Census was candu d. ursuant to Specification 6.9. 1.4, submit in the next Semian ual Ra aactive Effluent Release Report documentation for a ch e in the N including a revised figure(s) and table(s) for the O reflectin the new location(s) with informa-tion supporting the ange in samplin locations.

C. The provisions of ecificatians 3.0.3 d 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENT

4. 12. 2 The Land Use ensus shall be conducted during the rowing season at least once per 12 ths using that information that will vide the best results, such as b a door ta-door survey, aerial survey, o by consulting local agriculture authorities. The results of the Land Use sus shall be included in the nnual Radiological Environmental Operating Re rt pursuant, to Specification .9.1.3.

"Broad leaf egetatian sampling of at least three different kinds o tion vegetation may be pe ormed at the SITE BOUNOARY in each of two different dire sectors ith the highest predicted 0/qs in lieu of the garden census.4.c Speci-in Table 3.12-1, Part , shall ficati s for broad leaf vegetation sampling'samples.

be fo owed, including analysis of control EARON HARRIS

- UNIT 1 3/4 12-13

RAOIOLQGICAL ENVIRONMENTAL MONITORING

/<.'2.3 IN ERLABGRATORY COMPARISON PROGRAM LIM NG CONQITIGN FOR OP RATION 3.12.3 nalyses shall be performed on all radioactive materials, suppl as part of a Interlaboratory Comparison Program that has been approved b the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILI At all times.

ACTION:

a. With ana ses not being performed as required abov, report the correc ive actions taken to prevent a recurrence o the Commission in the Annu I Radiological Environmental Opera ng Repor. pursuant to Specifica on &.9.1. 3.

The provisions Specifications 3.0.3 and .0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.12.3 The Interlaboratory Compa ison Progr shall be described in the OOCM.

A summary of the r suits obtained part o the above required Interlaboratory Comparison Program shall be include in t Annual Radiological Environmental Operating Report pursuant to Specific ti n &.9.1.3.

HEARON HARRIS

- UNIT 1 3/4 12-14

INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM (Continued)

This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

'/4.3 o 3.6 ACCIDENT MOHITORINC IHSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that suffi-cient infoc'mation is available on sel.ected plant pacemeters to monitor and assess these variabLes following an accidents This capability is consistent, with the recommendations of Regulatory Cuide 1.97, Revision 3, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Ducing and Folloving an Accident," May 1983 and NUREG-0737, "CLacification of TMI Action Plan Requirements," November 1980.

3/4.3.3.7 DELETED 3/4.3.3.8 DELETED 3/4.3.3.9 METAL IMPACT MONITORIHG SYSTEM The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metalLic parts in the Reactor System and avoid oc'itigate damage to Reactoc System components. The al.lovable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Cuide 1. 133, "Loose"Part Detection Program for the Primary System of Light-Mater-CooLed Reactors," Mey 1981.

3/4.3.3. 1 DIOA IVE LI UID FFLUEHT M NITORINC NSTRUMENTAT N The r dioactive quid efflu t instru ntation i provided t monitor and on-trol as applic Le, the re eases of c dioactive materials i Liquid effl ents dur'ng actuaL potential celeases o l.iquid fluents. T e Alarm/Trip Set" po'nts for th e instrume ts shall b calculet d and adjus ed in accor nce v'th the met dology and parameters in the OD M to ensure that the al rm/trip aLL occur ior to exc ding the imits of 0 CFR Part 0. The OP BILITY nd use of his instr ntation i consiste t, with the equiremen of Ceneral Design Cri erie 60, 6 , and 64 of Appendix A to 10 CF Part 50.

SHEAROH HARRIS - UNIT 1 B 3/4 3-5 Amendment No. $6

INSTRUMENTATION BASES FxP(cavd 3/4. 3. 3. 11 GA MONITORING INSTRUMENTATION The r ioactive g seous e u ins r umen tion is p vided to m itor and cant ol, as appl cable, the leases of r dioactive m terfals in aseous efflu-ent during ac al or poten al release of gaseous ffluents. he Alarm/Trip S points for ese inst nts shall calculate and ad)us fn accordance th the met dolagy and arameters i the 00C4l fll occur ior to exce din th tl an pravi r

'ts of CF ensure tha the alarm/trip Part 20 cantrallin s ins rumen cancentratians monitoring an the of potentia y explosive gas < tures in the SEQUS RAQMAST REATMENT SYSTBI.

The OPERABILITY and use of this instrumentatfan is consistent with the requiv'e-ments of General Oesi n Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

e ensit ity of ny na ac ivi y m i rs u e o s ow camp i gaseo efflu t, rele se requi ements Specff cation .11.2. shall e s h tha cancen ations as low . 1 x 10 pCi/mI are me urable.

3/4. 3. 4 TURBINE OVERSPE=O PROTECTION This specification is provided ta ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will pro-tect the turbine from excessive overspeed. Protection from turbine excessive averspeed is required since excessive overspeed of the turbine cauld generate potentially damaging missiles ~hich could impact and damage safety-related com-ponents, equipment or structures.

SHEARON HARRIS - UNIT 1 S 3/4 3-6

3/<. i'AOIOACTIYE EFFLUENTS BASES 3/<. 1'.'IOUIO EFFLUENTS 3/4. 11. i. 1 N mate than ie

's

's specification is provided to ensure. that the conc ntratian of radiaac.ive released in liquid waste effluents to UNRESTRICTEO AREAS will be ncentratian levels specified in 10 CFR Part 20, Appendix B, s

e II,

'imitation provides additional assur ance'at the I s

's Column Z.

mate. in bodies of water in UNRESTRICTEO AREAS 'esul. af'adioac.ive in exposures within: the Section II.A design objectives o ppendix I, '0 CFR Part 50, to a MBIBER OF PUBLIC, and (2) the limits 0 CFR Part 20.106(e) ta the population. The conc ration .limit for dis ved or entrained noble gases is based upon the assumpti that Xe-135 i he controlling radioisotcpe and i s MPC in air (submersion) was vert o an equivalent concentration in water using the methods described'n Int ational Commission on Radiological Protec ion (ICRP) Publication Z.

]I The required detection caoab ies 'or radicac.ive tarials in liquid was:e samples are tabulated in rms of the lower limits of d ction (LLOs). Oetailed discussicn of the L and other detection limits can be fa in HASL Pracedures Manual, HASL-300 evised annually), Currie, L. A., "Limits for alitative Oetec ion an antitative Oetermination - Applicaticn to Radiochem Anal. Ch . 40, 586-93 (1968), and Hartwell, J. K., "Oetectian Limits Radio-ana a ounting Techniques," Atlantic Richffe1d Hanford Company Report A A-215 (June 1975).

's specification is provided to implement the requireaaots of Sections II.A III. and IY.A of Appendix I, 10 CFR Part 50. The Limftfng Condition for Operatic 'mplements the guides set forth in Sectian II.A of Appendix . The ACTION stat ts provide the required operating flexibility and ie same time implement t, uides set farci in Section IY.A of Append to assure that the releases o dicactive material in liquid efflu to UNRESTRICTEO AREAS will be kept "as I as is reasonably achievabl . The dose calculat'an methodology and parameters i ie OOQI implement requirements in Sec-tion III.A of Appendix I that, con . ance wit e guides of Appendix I be shown by calculatianal procedures based cn. e and data, such that the actual exposure of a MEMBER OF THE PUBLIC th g prapriate pat!iways is unlikely .o be substantially underestimated. e aquatic specified in the OOQI for cal-culating the doses due tc th ual release rate f radioactive materials in liquid effluents are cons '

ent with the methodology r vided ' in Regulatory Guide 1. 109, -"Calcul of Annual Oases ta Man from Rou Releases of Reac-tor Effluents for , e Purpose of Evaluating Compliance with FR Part 50, Appendix I," isicn 1, October 1977 and Regulatory Guide 1.113, 'tfmating ersian of Effluents from Accidental and Routine Reactor ases Aquatic for Purpose of Implementing Appendix I," April 1977.

SHEARON HARRIS - UNIT 1 B 3/4 11-1

RAOIOACT~V EFF'ENTS BASES 3/4.11.1. 3 U> RA A T A i T will be a 'e RABILITY of the release to the en Liquid Radwaste Treatment System ensures that this for use whenever liquid effluents require '

ment. The requirement that the appr treatm rior portions of to iem this system be used when ified provides assuran t the releases of radioactive materials in liqui ents wi 1 ept "as low as is reasonably achievable." This specification impl the requirements

" Part 50 and of 0 CFR 50.36a, General Design Criterion 60 of ndix A to the design objective given in Secti .D of Appendix I to 10 rt 50. The specified limits governin se of appropriate portions of the Liqu dwaste Treat-ment Syst e specified as a suitable fraction of the dose desig 'ec ives set in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluen 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by'iners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains con-nected to the Liquid Radwas e Treatment System.

I Restricting the quantity of radioac ive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the result'.ng concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNR~ICTED AREA.

3/4. 11.2 GASEOUS EFFLUENTS 3/4. 11.2. 1 specification is provided to ensure that the dose at any time at and bey the BOUNDARY from gaseous effluents from all units on the site will within th nnual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS e annual dose ts are the doses associated with the concentratio of 10 CFR Part 20, Appendix Table II, Column I. These limits provid asonable assurance that radioa ve material discharged in gaseous fluents will not result in the exposure o EMBER OF THE PUBLIC in a RESTRICTED AREA, either within or outside the SITE BO RY, to annual av ge concentrations exceed-ing the limits specified in, Appen B, Table of 10 CFR Part 20 (30 CFR Part 20.106(b)). For MEMBERS OF THE who may at times be within the SITE BOUNDARY, the occupancy of that MEMBE PUBLIC will usually be suffi-ciently low to compensate for a crease in atmospheric diffusion factor above that for the SITE BOUND . Examples of ca lations for such MEMBERS OF THE PUBLIC, with the appr ~ate occupancy factors, s be given in the OOCM.

The specified releas te limits restrict, at all times, corresponding gamma and beta do rates above background to a MEMBER OF THE LIC at or BOUNDARY to less than or equal to 500 mrems/year he ~hole beyond the S se ess than or equal to to the skin. These re body or rate 'ts 3000 mrems/year also restrict, at all times, the corresponding thyroid dose ra SHEARON HARRIS - UNIT 1 B 3/4 11-2

RADIOACTIVE EFFLUENTS BASES OOSc Continued above background child via the inhalation path~ay to less n or equal a 1500 mrems/year.

The required detection capabilities rad've material in gaseous was.e samples are tabulated in terms of the e mits of detection (LLOs). Detailed discussion of the LLO, and othe ectian lime n be found in HASL Pro-cedures Manual, HASL-300'sed annually), Currie, . "Limits for Quali-tative Detection an antitative Determination - App1icatio Radiochemis ry,"

Anal. Chem. . 6-93 (1968), and Hartwell, J.K., "Detection Limi ar Radia-ana yt~ aunting Techniques," Atlantic Richfield Hanford Company Repo 215 (June 1975).

3/4. 11. 2. 2 -Oracy~

s specification is provided to implement the requirements af Sections II.B, III. d IV.A af Appendix I, 10 CFR Part 50. The Limiting Condition for Op tion imp ents the guides set forth in Sect,ion I.B of Appendix I. The ON s:atements p ide the required operating flexibility and at tbe sam mme implement the gu> set forth iri Section IV.A of Appendix I ta ure that the releases of radioacti material in gaseous effluents to UNR ICTEO AREAS will be kept "as law as reasonably. achievable." The eillance Requirements implement the requirements i ection III.A of Appen I that conformance with the guides of Appendix I be show calculation procedures based on modeIs and data such that, the actual exposu of a ER OF THE PUBLIC. through appro-priate pathways i.s unlikely to be substa ally underestimated. The dose cal-culation methodology and parameters Iis in the OOCM for calculating the dases due to the actual release es of radioa e noble gases in gaseous effluents are consistent wi e methodology provi in Regulatory Guide 1.109, "Calculation of Annual 0 s to Man fram Routine Release f Reactor Effluents for the Purpose of E uating Compliance with 10 CFR Part 5 , ppendix I,"

Revision I, Octo 1977 and Regulatory Guide 1. 111, "Methods f stimating Atmospheric nsport, and Dispersion of Gaseous Effluents in Routin eleases fram Li ater Cooled Reactors," Revision 1, July 1977. The ODCM eq 'ans prov' far determining the air doses at and beyond the SITE BOUNDARY are ed n the historical average atmospheric conditions.

3/4.11.2.3 E - 00 E- 1. E- 3 ANO AOI E AT . IA Oep III.A and c fication is provided to implement .he requirements of Sections Operation are the gu Appendix I, 10 CFR Part 50. The Limiting Con t forth in Section II.C of

or x I. The ACTION statements provide the require ating fl y and at the same time implement the guides set forth in S of Appendix I to assure that the

'ts releases af'adioactive m in gaseous ef to UNRESTRICTED AREAS will be kept "as >s reasonably achievable." The ulational methods 'ed in the Surveillance Requirements implement the re SHEARON HARRIS - UNIT 1 B 8/4 11"3

RAOIOACTIVE EFFLUENTS BASES

" - IOOINE-131, IOOINE-133, TRITIUM. ANO RAOIOACTIVE MATERIAL IN A ii. LAi r RM (Continued in Section .A of Appendix I that conformance with the guides of endix I be shown by ca lational procedures based on models and data su that the ac.ual exposure o MBIBER OF THE PUBLIC through appropriat athways is unlikely ta be substa 'ally underestimated. The OOQf ca lational methodology and parameters for calcu ing the doses due ta the a al release rates af the subject materials are cansis~ t with the methodol provided in Regulatory 1.109, "Calculation of Ann I Ooses ta ' Ma ram Routine Releases of 'uide Reactar Effluents for the Purpose o valua Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 egulatory Guide 1. 111, "Methods for Estimating Atmospheric Transport and 'spe ion of Gaseous Effluents in Routine Releases from Light-'<later Cooled ctors," ision 1, July 1977. 'hese equa-tions also provide for determi 'ng the actual do based upon the historical average atmospheric canditi s. The release rate sp ifications for Iodine-131 iodine-133, tritium, an adianuclides in particulate wi th half-l.ives greater than 8 days e dependent upon the existing radion ide pathways to man in the areas at beyond the SITE BOUNDARY. The pathways were examined in the develo nt of the calculations were: (1) individual ipha tion of air bo~ne radi uclides,.(2) deposition of radionuclides onta green Iea egetatian with s equent cansumption by man, (3) deposition onta grassy areas wh milk ani s and meat producing animals graze with consumptian of the milk and m t man, and (4) deposition on the und with subseauent ex asure of man.

3/4. 11. 2. 4 S" U ERABILITY of the WASTE GAS HOLOUP SYSTEM and the VENTILATION EXHAUS TREATM STEM ensures that the systems will be available for us never gaseous eff1ue quire treatment prior ta release to the nment. The requirement that the riate portions of these s be used, when speci-fied, pravides reasanable a nce that the r es of radioactive materials in gaseaus effluents will be kept a is reasonably achievable." This terion 60 of Appendix A to Section II.O of Appe the use of app fraction

'o specification implements the requi ate portions 10 CFR af the n

Part 50 and Part 50.

systems 10 CFR 50.36a, General Oesign Cri-The were spe 'd sign objectives given in specific e dose design abjectives set forth in Sections II.B a limits governing a suitable I.C of A ix 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 down-explosive gas mixtures contained in the GASEOUS RAOMASTE TREATMENT SYSTEMlimits stream of the hydrogen recambiners is maintained belaw the flammability af hydrogen and oxygen. Automatic control features are included in theflamma- system to prevent the hydrogen and oxygen concentrations from reaching these bility limits. These automatic controlbelow features include isolatian of the source of oxygen to reduce the concentration the flammability limits. Maintain-ing the concentration of hydrogen and oxygen below their flaaeability limits SHEARON HARRIS -.

UNIT 1 B 3/4 11-4

RAOIOACTIVE E." FLULNTS BASES EXPLOSIVE GAS MIXTURE Continued provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 af Appen-dix A to 10 CFR Part 50.

3/4: 11. 2. 6 GAS STORAGE TANKS The tanks included in this speci, ication are those tanks for which the quanti:y of radioactivity contained is not limited directly ar indirectly by another Technical Specification. Restric ing the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's cantents, the resulting whole bady exposure to a 'ME!GER OF THE PUBLIC at the nearest SITE BQUNQARY will not exceed 0.5 rem. This is consistent, with Standard Review"Plan '1.3, Branch Technical Position ETSB 11-'5, .

'f "Postulated Radioactive Releases Oue to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

3/4.11. 3 L A 0 T E AS S ThTs 'ion General Design Cri implements the requirements cf 10 Appendix A to 10 CFR CFR 50.36a he process

, and param-eters, included in establishing PROGRAM may include, but are not limited to, waste e pH, was 'OLIDIFICATION agent/

catalyst r atio o>I cantent, waste principal chem>ca uents, and mi curin times.

3/4. 11. 4 T 0 s specification is provided to meet the dose limitations of 10 CFR Part

's that ve been incorporated inta 10 CFR Part 20 by 46 FR 18525. The spe tion req the preparation and submittal af a Special Report whene

'a-the calculated es due to releases of radioactivity and to radiatio ram uranium fuel cycle sou exceed 25 mrems to the whole body or any o , except the thyroid, which sha e limited to less than or equal to 7 rems. For sites containing up to four to a MEMBER OF THE PUBLIC ctors, it is highly unlikely the resultant dose if I exceed the dose Iimi of 40 CFR Part 190 the individual reactors remain wi twice the dos esign objectives of Appendix I and if direct radiation doses frc e uni d from outside storage tanks ar kept smaII. The Special Report will ~be a course of action that should result in the limitatian of the annu d to a MEMBER OF THE PUBLIC ta within the 40 CFR Part 190 limits. For e purpose f the Special Report, it may be assumed that the dose ccmmi to the MEMBER o the PUBLIC from other uranium fuel cycle, sources is ne ible, with the exceptio hat dose contributicns fram other nuclear fu cycle facilities at the same ss or within a radius of 8 km must be consi red. If the dose to any MEMBER OF THE BLIC is estimated to exceed t'.he irements of 40 CFR part 190, the Special Rep with a request for a vari e (provided the release conditions resulting in viola 'on of 40 CFR Part 19 ave not already been corrected), in accordance with the pro ians o 40 190.11 and 10 CFR 20.405c, is considered to be a timely request an ful" ls the re irements af 40 CFR Part 190 until NRC staff action is ceaplete SHEARON HARRIS - UNIT 1 B 3/4 11-5

RAOIOACTIVE "F."t UEHTS BASiS TO

" Cortinued The variance only relate e limits of 40 CFR , and does not apply in any way to the other requiremen imitation of 10 CFR Part 20, as addressed in Specifications . . and 3. . . An individual is not con-sidered a HEHBER 0 LIC during any period in w i she is engaged in carryin ny operation that is part of the nuclear fuel cyc SHEARON HARRIS

- UNIT 1 8 3/4 11-6

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QAOIOLCGICAL ENVIRONMENTAL HONITORING 8ASES 3/4.12.3 R A R 0 P The nt for participation in an approved Interlaboratory Com Program is provi e ure that independent checks

' on ision and accuracy of the measurements o tive in environmental sample.

matrices are performed as part ua 1 nce program for environmental monitoring in ord onstrate that the results are r the purposes of S . . 2 of Appendix I to 10 C."-R Part 50.

SHEARON HARRIS - UNIT 1 8 3/4 2-2

ADMINISTRATIVE CONTROLS PROCEOURES ANO PROGRAMS Continued C. Seconda. Mater Chemist Continued)

6. A procedure identifying (a) the authority responsible for he interpretation of the data and {b) the sequence and timing of administrative events required to initiate corrective action.

d. Backup Method for Oeterminin Subcoolin Ma in A program that will ensure the capability to monitor accurately he Reactor Coolant Sys em subcooling margin. This program shall include the following:

1. Training of personnel, and

2. Procedures for monitoring.

Post-Accident Samolin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples. The program shall include the following:

1. Training of personnel,

2. Procedures for sampling and analysis, and

3. Provisions for maintenance of sampling and analysis equipment.

Inspections of Water Control Structures A program to implement an ongoing. inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water intake and discharge channels, and the auxiliary reservoir channel. The program shall include the following:

1. The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part of plant startup operations.

2. Subsequent inspections at yearly intervals for at least the next 3 years. If adverse conditions are not revealed by these inspections, inspection at 5-year intervals will be performed.

Turbine Rotor Insaection A program to implement an ongoing inspection of the low pressure turbine rotor. The program shall be based upon:

Yendor recommendations for low pressure turbine rotor inspect~on intervals and procedural guidelines, and

+nfl 2. Using vendor methodology to recalculate the inspection interval if cracking in the rotor is ever found.

SHEARON HARRIS - UNIT 1 6-19

INSERT 2 (on Page 6-19)

h. Radioactive Effluent Controls Pro ram 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 radi.oactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the m'ethodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with 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 effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the 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 of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose 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,

INSERT 2 (on Page 6-19) continued 6.8.4 h. Radioactive Effluent Controls Pro ram Cont.

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 form 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, and

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.

i. Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements. of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the, monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

ADMINISTRATIVE CONTROLS ANNUAL REPORTS Continued film badge measurements. Small exposures totaling less. than 20~ of the individual total dose need not be accounted for. In the aggregate, at least BO" of the total whole-body dose received from external sources should be assigned ta specific major work functions; The results of specific activi y analyses fn which the reactor coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) reactor po~er history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior ta the first sample in which the limit was exceeded (in graphic and tabular format); (2) results of the last isotopic analysis for radio-iodine performed priot to exceeding the limit, results af analysis while limft was exceeded and results of ane analysis after the radio-iodine activity was reduced ta less than limit. Each result should fnclude date and tfme of sampling and the radioiodine concentrations; (3) cleanup flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior ta the first sample fn which the limit was exceeded; (4) graph of the I-131 concentra-tion (pCf/gm) and one other radiaidine isotope concentration (pCi/gm) as a .unction of time for the cturation of the specific activity above the steady-state level; and (5) the time duration when the specific activfty of the reactor coolant exceeded the radioioctine limit.

c. Oocumentatfan of all chaTlenges to the pressurizer power-operated relief valves (PORVs) and safety valves.

ANNUAL RAOIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.3 Rautine Annual Ractialogfcal Envf ranmental Operating Reports, coverin e operation of the unit during the previous calendar year, shall be subm pn ta May 1 of each year. The initial report shall be submitted May 1 the year fallowing initial crftfcalfty.

pr'a ed The Annual Ra ologfcal Environmental Operating Reports sha nclude summaries, interpretations, ct an analysis of trends of the resul f the radiological environmental surve ance activities for the report riad, including a cam-parison with preaperat 1 studies, with operati 1 controls, as appropriate, and with previous enviranme I surveillance orts, and an assessment of the observed impacts of the plant eration on e environment. The reports shall also include the results of the U nsus required by Specification 3-12 The Annual Radfalogfcal Envfra 1 Op ting Reparts shall include the results of analysis af all ological env nmental samples and of all environmental radiation surements taken dun the period pursuant ta the lacatfans specified f e table and ffgures fn th FFSITE DOSE CALCULATION MANUAL, as well a ummarized and tabulated results o ese analyses and measurements i e format of the table in the Radiologic Assessment Branch Technical P tion, Revision 1, November 1979. In the event at some individ-ual res are not available for inclusion with the report, th port shal1 be mitted noting and explaining the reasons for the missing resu . The

'ing data shall be submitted as saon as passible in a supplementary port.

SHEARON HARRIS - UNIT 1 6-21

INSERT 3 (on Page 6-21) 6.9.1.3 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 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.

INSERT 4 (on Page 6-22) 6.9.1.4 The 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. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid ~aste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

AQMINISTRATIYE CONTROLS A RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Continued The reports s also include the following: a summary descri

" n of the Radiological Envi tal Monitoring Program; at least t egible maps" covering all sampling lo ans keyed to a table giv distances and directions fram the centerline of the rea . the resul licensee participation in the Interlaboratory Comparison Prag e corrective action taken if the specified program is not being pe ed quired by Specification 3.12.3; reasons for nat conducting adiological En ental Monitoring Program as required by Specificat'IZ.I, and discussion of deviations from the sampling schedul able 3.12-1; discussion of environm 1 sample measure-ments that ed the reporting levels of Table 3.12-2 but are the result of pl effluents, pursuant ta ACTION b. of Specification 3.12.1; a iscussion 1 analyses in which the LLO required by Table 4.12-1 was not achiev SEMIANNUAL RAOIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.4 Rautine Semiannual Radioactive Effluent Release Reports covering the ration of the unit during the previaus 6 months of operation shall be sub-mi d within 60 days after January 1 and July 1 of each year. The period f t'h e rst report shall begin with the date of initial criticality.

The Semia ual Radioactive Effluent. Release Reports shall include a ummary of the quantiti of radioactive liquid and gaseous effluents and so d waste released from e unit as outlined in Regulatory Guide 1.21, " suring, Eval-uating, and Repo ng.Radioactivity in Solid Mastes and Rele es of Radioactive Materials in Liqui d Gaseous Effluents fram Light-Nate oled Nuclear Power Revision 1, e 1974, with data summarized on quarterly basis 'lants,"

following the format of endix B thereof. Far soli astes, the format for Table 3 in Appendix B shal e supplemented with th e additional categories:

class of solid wastes (as de ed by 10 CFR Part ), type of container (e.g.,

Type A, Type B) and SOLIDIFICA agent or ab ent (e.g., cement).

The Semiannual Radioactive Effluent eas Report ta be submitted within 60 days after January 1 of each year sh include an annual summary of hourly meteorological data collected over th pre 'ous year. This annual summary may be either in the form of an hour b our lis ng on magnetic tape of wind speed, wind direction, atmospheric"stabi ty, and proc itation (if measured), or in the farm of joint frequency di ributions of wind eed, wind direction, and atmospheric stability.~ Th same report shall in de an assessment of the radiatian doses due ta th adioactive liquid and gas s effluents released "One map shall aver stations near the E{CLUSIQN AREA BOUNDARY; ecand shall include the ore distant stations.

~"In lieu submission with the Semiannual Radioactive Effluent Release Repo , t4e licensee has the option of retaining this .summary of require me rological data on site in a file that shall be provided to the NRC n request.

SHEARON HARRIS - 'UNIT 1 6 22

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Continued fro the unit or station'uring the previous calendar year. Thii same repo shall iso include an assessment of the radiation doses from radioactive quid and gas us eff1uents to MEMBERS OF THE PUBLIC due to their activities side the SITE UNDARY (Figure 5.1-3) during the report period. All ass ions used in mak g these assessments, i.e., specific activity, exposure ime, and location, sha be included in these reports. The meteorological onditions concurrent with he time of release of radioactive materials in seous efflu-ents, as determin by sampling frequency and measurement, sha be used for determining the gas us pathway doses. The'ssessment of ra ation doses shall be performed in acco nce with the methodolagy and parame rs in the OFFSITE DOSE CALCULATION HANUAL DOCH).

The Semiannual Radioactive ffluent Release Report to e submitted within 60 days after January 1 of e year shall also inc de an assessment of radia-tion doses to the likely mast osed MEMBER OF PUBLIC from reactor releases and other nearby uranium fuel cy e sources, in uding doses from primary efflu-ent pathways and direct radiation, or the pr ious calendar year to show can-formance with 40 CFR Part 190, "Envi nmen Radiation Protection Standards for Nuclear Power Operation." Acceptable th ds far calculating the dose contribu-tion from liquid and gaseous effluents a given in Regulatory Guide 1.109, Revision 1, October 1977.

The Semiannual Radioactive Effluen elease Re rts shall include a list and description of unplanned release, fram the site to UNRESTRICTED AREAS, of radioactive materials in gaseo and liquid efflue ts made during the reporting period.

The Semiannual Radioactiv Effluent Release Reports sha include any changes made during the reporti period to the PROCESS CONTROL P GRAH and the DOCH, pursuant to Specifica ons 6.13 and 6.14, respectively, as 11 as any major change to Liquid, G caus, or Solid Radwaste Treatment System pursuant to Specification 6.IS It shall also include a listing of new lac ions for dose calculations an r environmental manitaring identified by the La Use Census pursuant to Sp ification 3.1Z.Z.

The Semian al Radioactive Effluent Release Reports shall also include he followin an explanation as ta why the inoperability of liquid or gase s effluen manitoring instrumentatian was nat corrected within the time spec ied in Sp ification 3.3.3.10 or 3.3.3.U., respectively; and a description of th eve leading ta liquid holdup tanks ar gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.II Z.6, respectively.

MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports of operating statistics and shutdawn experience shall be submitted an a monthly .basis ta the Directar, Office of Resource Management,.U.S. Nuclear Regulatory Commission, Mashington, O.C. 205H, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each manth fallowing the calendar month covered by the repor-SHEARQN HARRIS - UNIT 1 6-Z3

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) effective at specified times and gA records showing that these Orooedoree were followed; giiig

o. Records of facility radiation and contamination survey AM

6. 11 RADIATION PROTECTION PROGRAM 6.11.1 Pracedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Par. 20 and shall be approved, maintained, and adhered to far al.l operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to Paragraph 20.203(c)(5) af 10 CFR Part 20, in lieu of the "control device" or "alarm. signal" required by Paragraph 20.203(c), each hign radiatian area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) fram the radiation sour e or from any surface which the radiation penetrates shall be barricaded and conspicuously pasted as a high radiation area and entrance thereto shall be controlled by requiring issuance af a Radiatian Work Permit (RWP). Individuals qualified in radiation protection procedures (e.gee Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal ta or less than 1000 mR/h, pro-vided.they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or graup of individuals permitted to enter such areas shall be provided with or accompanied by ane or more of the following:

a. A radiation monitoring device that continuously, indicates the radiation dose rate in the area; or

b. A radiation manitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry inta such areas with this monitoring device may be made after the dose rate levels in the area have been es ab-Iished and personnel have been made knowledgeable of them; or

. c. An individual qualified in radiatian protection procedures, w'ith a radfatian dose rate monitoring device, who is responsible for pro-viding positive control over the activities ~ithin the area and who shall perform periodic radiatian surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In additian ta the requirements of Specification 6.12.1, accessible areas with radiation IeveIs greater than 1000 mR/h at 45 cm (1S in.) from the radi~ion source or from any surface which the radiation penetrates, shall be shall provided with. locked doors to prevent unauthorized entry, and the keys be maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1 6-26

INSERT 5 (on Page 6-26)

p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

INSERT 6 (on Page 6-27)

Changes to the PCP:

a ~ Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. 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 PNSC and the approval of the Plant General Manager.

INSERT 7 (on Page 6-27)

Changes to the ODCM:

a ~ Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. 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 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 PNSC and the approval of the Plant General Manager.

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 which 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.

AOMINISTRATIVE CQNTRQLS HIGH RAOIATIQN AREA {'Continued) and/ar health physics super'vision. Oaors shall remain locked except during periads of access by personnel under an approved KiP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RMP, direct or remote (such as closed circuit TY cameras) continuous sur veillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. Ouring emergency situations that involve personal injury or actions taken to prevent major equipment damage, continuous surveillance and radiation mani wring of the work area by a qualified individual may be substituted for the routine SIP procedure.

Far accessible individual high radiation areas, with radiation levels of greater than 1000 mR/h, that are located within large areas, such as BiR containment, where na enclosure exists for purposes of lacking and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

6. 13 PROCESS CONTROL PROGRAM PCP

.1 The PCP shall be approved by the Commission prior to implementation.

U.Z ense initiated changes ta the PCP:

a. Shall submitted ta the Commission in the Semian Radioac.ive Effluent ase Report for the periad in which e change(s) was made. This s ttal sha11 contain:

1. Sufficiently data d informati to totally support the rationale for the ch wi ut benefit of additional or suppl cmental infarmati o

2. A determinatian t the change nat reduce the overall duct to existing criteria conformance the solidified waste for soli astes; and ntatian of the fac that, the change has be viewed and Tound acceptable by the PNSC.

Shall became effective upon review and acceptance by the PNSC.

6.14 OFFSITE OQSE CALCULATION MANUAL OOCM The OOCM shall be approved by the Commission prior to implementatio

6. 14: 2 Licensee-init a s ta the QOCN:

a. Shall be submit ommission in 'annual Radioac.ive Eff1 ase Report for the period in which the was e effective. This submittal shall contain:

SHEARQN HARRIS - UNIT 1 6-27

ADMINISTRATIVE CONTROLS OF E DOSE CALCULATION MANUAL QDCM Continued Sufficiently detailed information to totally support the

'onale for the change without benefit of additio or supple-menta formation. Information submitted sho consist of a package o ose pages of the ODCM to be ged with each page numbered, date d containing the r on number, together with appropriate analys r evaluat justifying the change(s);

2. A determination that c e will not reduce the accuracy or reliability of d calculation setpoint determinations; and

3. D entation of the fact that the change ha een reviewed 'arid ound acceptable by the PNSC.

Shall become effective upon review and acceptance by he PNSC.

MAJOR CHANGES TO LIQUID GASEOUS AND SOLID RADWASTE TREATMENT SYSTEMS"

6. 15. Licensee-initiated major changes to the Radwaste Treatment Systems (liquid, aseous, and solid):

reported to the Commission in the Semiannual Ra active a0 Sh 1 be Effl t Release Report for the period in which the ev uation was scussion of reviewe .in accordance with Specification 6.5. The each chan shall contain:

1. A summary f the evaluation that led to e determination that the change ld be made in accordan with 10 CFR 50.59; Z. Sufficient detai information tot.ally support the reason for the change wi benefi of additional or supplemental information;

3. A detailed descriptio f e equipment, components, and pro-cesses involved and e inte aces with other plant systems;

4. An evaluation the change, whi sho~s the predicted releases of radioacti materials in liquid d gaseous effluents and/or quantity solid waste that differ f those previously predi in the License application an endments thereto;

5. A valuation of the change, ~hich shows the ected maximum osures, to a MEMBER OF THE PUBLIC in the UN ICTED AREA and to the general population, that differ from se previously es imated in the License application and amendments ereto; censees may choose to submit the information called for in this Specifi tion as part of the annual FSAR update.

SHEARON HARRIS - UNIT 1

ADMINISTRATIVE CONTROLS MAJOR CHANGES TO LIQUID 'GASEOUS AND SOLID RADWASTE TREATMENT SYSTBIS

6. comparison of the predicted releases of radioa ' materials, in id and gaseous effluents and in soli ste, to the actual re s for the period prior en the change is to be made.

7. An estimate of the expo plant operating personnel as a result of the chan, and

8. Oocumen on of the fact that the change reviewed and fo acceptable in accordance with Specificaton

b. all become effective upon review and acceptance in accordance h Specification 6.5.

SHEARON HARRIS - UNIT 1

INDEX DEFINITIONS SECTION PAGE 1.32 SITE BOUNDARY . . . . . . . . o 1-5 1.33 SLAVE RELAY TEST 1-6 1.34 (DELETED) 1-6 1.35 SOURCE CHECK . . ~ . ~ ~ ~ '"

~ 1-6 1.36 STAGGERED TEST BASIS 1-6 1.37 THERMAL POWER ~ ~ . ~ ~ 1-6 1.38 TRIP ACTUATING DEVICE OPERATIONAL TEST 1-6 1.39 UNIDENTIFIED LEAKAGE 1-6 1.40 UNRESTRICTED AREA 1-6 1.41 VENTILATION EXHAUST TREATMENT SYSTEM ~ ~ ~ 1-7 1.42 VENTING . ~ . . . . . . . . . . . . . ~ ~ ~ 1-7 TABLE lol FREQUENCY NOTATION 1-8 TABLE 1.2 OPERATIONAL MODES 1-9 SHEARON HARRIS UNIT 1 Amenchnent. No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE TABLE 3-3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS . . . . . . . . . . . . i ~ 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ o ~ 3/4 3-54 Movable Incore Detectors 3/4 3-56 Seismic Instrumentation 3/4 3-57 TABLE 3 '-7 SEISMIC MONITORING INSTRUMENTATION . . . ~ . . . . 3/4 3-58 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ , ~ ~ 3/4 3-59 Meteorological Instrumentation . 3/4 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION 3/4 3-61 TABLE 4,3-5 METEOROLOGICAL MONITORING ZNSTRUMENTATZON SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-62 Remote Shutdown System 3/4 3-63 TABLE 3,3-9 REMOTE SHUTDOWN SYSTEM . . . . ~ 3/4 3-64 TABLE 4.3-6 REMOTE SHUTDOWN MONZTORING INSTRUMENTATZON SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ , o 3/4 3-65 Accident Monitoring Instrumentation 3/4 3-66 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION . . . . . ~ 3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-70 TABLE 3.3-11 (DELETED) . ~ 3/4 3-73 Metal Impact Monitoring System . 3/4 3-74 (DELETED) 3/4 3-75 Explosive Gas Monitoring Instrumentation . . . . . . 3/4 3-82 TABLE 3. 3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION . . . o 3/4 3-83 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-86 TABLE 3/4.3.4 TURBINE OVERSPEED PROTECTION 3/4 3-89 SHEARON HARRIS UNIT 1 vi Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3 4.11 IOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS (DELETED) ~ 3/4 11-1 Liquid Holdup Tanks 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS (DELETED) 3/4 11-8 Explosive Gas Mixture 3/4 11-15 Gas Storage Tanks 3/4 11-16 3/4.11.3 (DELETED) . . o 3/4 11-17 3/4.11.4 (DELETED) 3/4 11-19 3 4.12 IO OGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (DELETED) . ~ ~ ~ . . . . . . . . . . ~ ~ . . . . . . . 3/4 12-1 I SHEARON HARRIS - UNIT 1 xii Amendment No.

INDEX BASES SECTION PAGE 3 4.10 SPECI TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . ~ o ~ . . . . . . . . . ~ ~ B 3/4 10-1 3/4.10.2 GROUP HEIGHT g INSERTION/ AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PHYSICS TESTS ~ ~ o o o . . o 0 ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS ~ o ~ ~ ~ ~ ~ ~ B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM SHUTDOWN . . . , ~ B 3/4 10-1 3 4.11 RADIO C IVE EF LUE TS 3/4.11.1 LIQUID EFFLUENTS ~ B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS o B 3/4 11-2 3/4.11.3 (DELETED) ~ . . o B 3/4 11-5 3/4.11.4 (DELETED) o . . . . . . o. o . ~ B 3/4 11-5 3 4.12 RADIOLOGICAL ENVIRO MENTAL MONITORING 3/4.12.1 (DELETED) ~ . . . . . . . . . . . . . . . . . . . . . . B 3/4 12-1 I SHEARON HARRIS - UNIT 1 xvi Amendment No.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.14 0 FS TE DOSE CALCULATION MANUAL ODCM . . . . . . . . . . . 6-27 6.15 DELETED . . . . . . . . . . . ~ . . . . . . . . . . . . . 6-28 SHEARON HARRIS UNIT 1 XX Amendment No.

DEFINITIONS MASTER RELAY TEST 1.18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER S OF THE PU LIC 1.19 MEMBER(S) OF 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 use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.

OPERABLE - OPERABILITY 1.21 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) are also capable of performing their related support function(s).

OPERATIONAL MODE MODE 1.22 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 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure 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 BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

SHEARON HARRIS UNIT 1 1-4 Amendment No.

DEFINITIONS PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid- radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

PURGE PURGING 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

UADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated 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 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2775 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all 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 withdrawn.

SITE BOUNDARY 1.32 For these Specifications, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SHEARON HARRIS UNIT 1 1-5 Amendment No.

DEFINITIONS SLAVE RELAY TEST 1.33 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION 1.34 Deleted from Technical Specifications and relocated to the PCP.

1.35 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed .to a source of increased radioactivity.

'TAGGERED TEST BASIS 1.36 A STAGGERED TEST BASIS shall consist of:

a~ A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.37 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATI G DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include ad)ustment," as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED ZEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED RE 1.40 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 radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

SHEARON HARRIS UNIT 1 1-6 Amendment No.

INSTRUME T 0 RADIOACTIVE L UID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION Specifications 3/4.3.3.10 and portions of 3/4.3.3.11 have been deleted from Technical Specifications and have been relocated to the ODCM.

Pages 3/4 3-76 through 3/4 3-81 have been deleted.

SHEARON HARRIS UNIT 1 3/4 3-75 Amendment No.

INSTRUMENTATION EXPLOSIVE GAS MONITORING NSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY: As shown in Table 3.3-13.

ACTION a~ With an explosive gas effluent monitoring instrumentation channel I Alarm/Trip Setpoint less conservative than required by the above specification declare the channel inoperable and take the ACTION shown in Table 3.3-13.  !

b. With the number of OPERABLE explosive gas monitoring I instrumentation channels less than the Minimum Channels OPERABLE, ~

take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days, and unsuccessful, prepare and submit a Special Report to the if Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c~ The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG. CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

SHEARON HARRIS UNIT 1 3/4 3-82 Amendment No.

TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GASEOUS WASTE PROCESSING SYSTEM HYDROGEN AND OXYGEN ANALYZERS 1/recombiner'PPLICABILITY

a. Recombiner Outlet Hydrogen Monitor 1/recombiner 50

b. Recombiner Outlet Oxygen Monitor ~

• 48

c. ComPressor Discharge Oxygen Monitor 48 Page 3/4 3-84 has been deleted.

TABLE 3.3-13 Continued T BLE NOTATIONS

• During GASEOUS RADWASTE TREATMENT operation CTION STATEMENTS ACTION 45 (NOT USED)

ACTION 46 (NOT USED)

ACTION 47 (NOT USED)

ACTION 48 With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, 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 operations.

ACTION 49 (NOT USED)

ACTION 50 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

ACTION 51 (NOT USED)

ACTION 52 (NOT USED)

SHEARON HARRIS - UNIT 1 3/4 3-85 Amendment No.

TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS RE UIRED

1. GASEOUS WASTE PROCESSING SYSTEM HYDROGEN AND OXYGEN ANALYZERS Recombiner Outlet Hydrogen Q(4)

Monitor

b. Recombiner Outlet Oxygen Q(5)

Monitor C~ Compressor Discharge Oxygen D Q(S)

Monitor Page 3/4 3-87 has been deleted.

TABLE 4.3-9 Continued TABLE NOT TIONS

• During GASEOUS RADWASTE TREATMENT SYSTEM operation.

(NOT USED)

(NOT USED)

(3) (NOT USED)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

SHEARON HARRIS - UNIT 1 3/4 3-88 Amendment No.

3 4.11 RADIOACTIVE EFFLUENTS 3 4.11.1 LI UID EF LUENTS Specification 3/4.11.1.1, 3/4.11.1.2 and 3/4.11.1.3 have been deleted from Technical Specifications and relocated to the ODCM.

Pages 3/4 11-2 through 3/4 11-6 have been deleted.

SHEARON HARRIS UNIT 1 3/4 11-1 Amendment No.

DIOACTI E LUE TS 3 4.11.

~ ~ G SEOUS EFFLUE TS Specifications 3/4.11.2.1, 3/4.11.2.2, 3/4.11.2.3 and 3/4.11.2.4 have been deleted from Technical Specifications and relocated to the ODCM.

Pages 3/4 11-9 through 3/4 11-14 have been deleted.

r SHEARON HARRIS UNIT 1 3/4 11-8 Amendment No.

RADIOACTIVE EFFLUENTS 3 4.11

~ ~ 3 SOLID RADIOACTIVE WASTES Specification 3/4.11.3 has been deleted from Technical Specifications and relocated to the PCP.

Page 3/4 11-18 has been deleted.

SHEARON HARRIS UNIT 1 3/4 11-17 Amendment No.

RADIOACTIVE EFFLUENTS 3 4.11.4

~ ~ TOT DOS Specification 3/4.11.4 has been deleted from .Technical Specifications and relocated to the ODCM.

SHEARON HARRIS UNIT 1 3/4 11-19 Amendment No.

3 4.12 RADIOLOGICAL ENVIRONMENTAL ONITORING Specifications 3/4.12.1, 3/4.12.2 and 3/4.12.3 have been deleted from Technical Specifications and relocated to the ODCM.

Pages 3/4 12-2 through 3/4 12-14 have been deleted.

SHEARON HARRIS UNIT 1 3/4 12-1 Amendment No.

INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM Continued This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

3 4.3.3.6 ACCIDENT ONITORING I STRUMEN TION The OPERABILITY of the accident monitoring instrumentation ensures that suffi-cient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.

3 4.3.3.7 DELETED 3 4.3.3.8 DELETED 3 4.3.3.9 METAL IMPACT MONITORING SYSTEM The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components. The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3 4.3.3.10 DELETED SHEARON HARRIS UNIT 1 B 3/4 3-5 Amendment No.

INSTRUMENTATION BASES 3 4.3.3.11 PLOSIVE G S MONITORI G INSTRU ENTATION This instrumentation provides for monitoring and controlling the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE TREATMENT SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3 4.3.4 TU BINE OVERSPEED PROTECTION This specification is provided to ensure that the .turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

SHEARON HARRIS UNIT 1 B 3/4 3-6 Amendment No.

3 4.11 RADIOACTIVE EFFLUENTS BASES 3 4.11.1 LI U D EFFLUENTS 3 4.11.1.1 DELETED 3 4.11.1.2 DE ETED 3 4.11.1.3 DELETED 3 4.11.1.4 LI UID HOLDU TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3 4.11.2 GASEOUS EFFLUENTS 3 4.11.2.1 DELETED 3 4.11.2.2 DELETED 3 4.11.2 3 DELETED 3 4.11.2.4 DELETED 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 GASEOUS RADWASTE TREATMENT SYSTEM downstream of the hydrogen recombiners 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 oxygen 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 radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

SHEARON HARRIS UNIT 1 B 3/4 11-1 Amendment No.

3 4.11.2.6

~ ~ ~ GAS STORAGE T NKS The tanks included in this s pecification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification. 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 whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

3 4.11.3 DELETED 3 4.11.4 DELETED Pages B 3/4 11-3 through B 3/4 11-6 have been deleted.

SHEARON HARRIS UNIT 1 B 3/4 11-2 Amendment No.

3 4.12 DIO OGICAL ENVIRONMENTAL MONITORING BASES 3 4.12 F 1 DE D 3 4 12.2 DELE ED 3 4.12.3 DE ETED Page B 3/4 12-2 has been deleted.

SHEARON HARRIS - UNIT 1 B 3/4 12-1 Amendment No.

DMINIST T VE CONTROLS PROCEDURE PROGRAMS Continued

h. Radioactive Effluent Controls Pro r 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 the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance, tests and setpoint determination in accordance with the methodology in the ODCMg

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoiing, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with 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 effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and pro)ected dose contributions from radioactive effluents for the 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 of radioactivity when the pro)ected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose 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, SHEARON HARRIS UNIT 1 6-19a Amendment No.

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued

h. Radioactive Effluent Contro s Pro ram Cont.

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 form 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, and

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.

i. adiolo ical Enviro me tal Monitorin Pro ra A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are the results of this census, and made if required by

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks of the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part-of the quality assurance program for environmental monitoring.

SHEARON HARRIS UNIT 1 6-19 b Amendment No.

ADMINIST IVE CONTROLS ANNUAL REPORTS Continued film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functionsg

b. The results of specific activity analyses in which the reactor 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 (in graphic and tabular format); (2) results of the last isotopic analysis 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 of sampling and the radioiodine concentrations; (3) cleanup 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 (pci/gm) and one other radio-iodine isotope concentration (pCi/gm) as a function of time for the duration of the specific activity above the steady-state levels and (5) the time duration when 'the specific activity of the reactor coolant exceeded the radioiodine limit..

c. Documentation of all challenges to the pressurizer powei-operated relief valves (PORVs) and safety valves.

ANNUAL DIOLOGICAL ENVIRONMENTAL OPE TING REPORT 6.9.1.3 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 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.

SHEARON HARRIS - UNIT 1 6-21 Amendment No.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.4 The 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. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the ob)ectlves outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part'50.

SHEARON HARRIS UNIT 1 6-22 Amendment No.

ADMINISTRAT CONTRO S MONTHLY OPERAT NG RE ORTS 6.9.1.5 Routine reports of operating statistics and shutdown experience 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 Administrator of the Regional Office of the NRC, no later than t'e 15th of each month following the calendar month covered by the report.

SHEARON HARRIS UNIT 1 6-23 Amendment No.

ADMINISTRAT CONTROLS RECORD RETENTION Continued effective at specified times and QA records showing that these procedures were followedg

o. Records of facility radiation and contamination surveys; and

p. Records of reviews performed for changes made to the OFFSITE DOSE

'ALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 IATION PRO ECTION PROG 6.11.1 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 RADIATIO RE 6.12.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c), each high.

radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates 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). Individuals qualified in radiation protection procedures (e.g., Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into. such high radiation areas. 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 that continuously indicates the radiation dose rate in the arear'r

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been estab-lished and personnel have been made knowledgeable of them; or

c. An individual qualified in radiation protection procedures, with a ,

radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and who shall perform periodic radiation surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, accessible areas with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1 6>>26 Amendment No.

ADMINIST IVE CONTROLS HIGH RADI IO Continued and/or health physics supervision. Doors 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 areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous sur-veillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. During emergency situations that involve personal injury or actions taken to prevent major equipment damage, continuous surveillance and radiation monitoring of the work area by a qualified individual may be substituted for. the routine RWP procedure.

For accessible individual high radiation areas, with radiation levels of greater than 1000 mR/h, that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 ROCESS CONTROL PROG PCP Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. 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 PNSC and the approval of the Plant General Manager.

,, 6.14 OFFSI E OSE CALCULATION NUAL ODCM Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be

, retained as required by Specification 6.10.3p. This documentation shall contains

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and SHEARON HARRIS - UNIT 1 6-27 Amendment No.

ADMINISTRATI CONTROLS

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 PNSC and the approval of the Plant General Manager.

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 which 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.

Page 6-29 has been deleted.

SHEARON HARRIS UNIT 1 6-28 Amendment No.

ENCLOSURE TO SERIAL: NLS-92-132 ENCLOSURE 6 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (GENERIC LETTER 89-01)

OFFSITE DOSE CALCULATION MANUAL CHANGES

Attachment 1 Page 1 of 4 ATTACHMENT 1 Solid Radwaste Programmatic 'Controls gC, PLP-300, Rev. 0 Page 21a of 21

At:achment 1 Page 2 of 4 DEFINITIONS SOLIDIFICATION 1.34 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

3/4.11.3 SOLID RADIOACTIVE WASTES LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be solidified or dewatered in'accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposaL site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTION:

a. With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend'hipment of'he inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures, andlor the Solid Waste, System as necessary to prevent recurrence.

With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:

If any 'test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRA"a and a subsequent test verifies SOLIDIFICATION. SOLIDIFICAT10N of the batch,may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; PLP-300, Rev. 0 Page 21b of 21

Attachment 1 Page 3 of' SOLID RADIOACTIVE WASTES SURVEILLANCE RE UIREMENTS (Continued) 4.11.3 (Continued)

b. .If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure .SOLIDIFICATION of subsequent batches of waste; and C ~ With the "installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process .wastes as necessary to satisfy all applicable transportation and disposal requirements.

BASES 3/4.11.3 SOLID RADIOACTIVE WASTES This specification implements the requirement's of 10 CFR 50.36a, 10 CFR 61, and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM'ay include, but are not limited to, waste type, waste pH, waste/Liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Formally part of Technical Specification 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 after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of 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 Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B PLP-300, Rev. 0 Page 21c of 21

Attachment 1 Page 4 of 4 ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOATIVE EFFLUENT RELEASE REPORT (Continued) 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 10 CFR Part 61), type of container (e.g., Type A, Type B) and SOLIDIFICATION agent or absorbent (e.g. cement).

The Seminannual Radioactive Effluent Release Reports shall include any major changes to Solid Radwaste Treatment Systems pursuant to Specification 6.15.

MAJOR CHANGES TO SOLID RADWASTE TREATMENT SYSTEMS"- (Formally part of Technical Specification 6.15)

Licensee-initiated major changes to the Solid Radwaste Treatment Systems:

a~ Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was gC reviewed in accordance with Specification 6.5. The discussion of each change shall contain'. oi~

1. A summary .of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59>,

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the uipment, components, and processes involved and the. .erfaces with other plant systems',

4. An evaluation of the change, which shows the predicted quantity of solid waste that differ from those previously predicted in License application and amendments theret'o;

'he h

5. A comparison of the predicted releases in solid waste, to the actual" releases for the period prior to when the change is to be made;

6. An estimate of the exposure to plant operating personnel as a result of the change', and

7. Documentation of the fact that the change was reviewed and found acceptable in accordance with Specification 6.5.

b. Shall become effective upon review and acceptance in accordance with Specification 6.5.

"-Licensees may choose to submit the information called for in this Specification as part of the annual FSAR update.

PLP-300, Rev. 0 Page 21d of 21

Attachment 2, SHEARON HARRIS NUCLEAR POWER PLANT Ui~lIT NOS. 1 AND 2 DOCKET NOS. 50-400 AND 50-401 ENVIRONMENTAL REPORT ACCEPTANCE REVIEW QUESTIONS AND RESPONSES

ER Question 291.1 (Section 2.1.3)

Provide clarification of the statement that: "Because a reasonable sport fishery is expected to develop in the reservoir, limited fishing success in the area affected by plant discharges is expected."

Response: The word "Although" should be substituted for the word "Because." The sentence should read, "Although a reasonable sport fishery is expected to develop in the reservoir, limited fishing success in the area affected by plant discharges is expected."

As discussed in Sections 5.1.3 and 5.3, the thermal and chemical effects of the cooling tower blowdown are expected to be minimal and to be restricted to a small mixing zone (ranging from 90 to 200 acres). Fishing success in the mixing zone area, which represents only two to five percent of the reservoir's surface area, is not expected to be as good as in other parts of the reservoir. For the most part, the anticipated lower fishing success in the mixing zone area will result from the lack of favorable habitat for the expected important species largemouth bass and sunfish species. The mixing zone area will be relatively deep (40-50 feet) with steep shorelines and limited shallow areas.

ER question 291.2,. (Section 2.2.0)

Provide copies of references 2.2.0-6, 2.2.0-7, and 2.2.0-11 which were cited in this section.

Response: Copies of these references (listed below) are enclosed.

Reference 2.2.0-6 Annual Report: Shearon Harris Nuclear Power Plant, Baseline Monitoring Program, Aquatic Biology Unit, 1976 and 1977.

Y Reference 2.2.0-7 Shearon Harris Nuclear Power Plant, Annual Environmental Monitoring Report, Water Chemistry, Aquatic Biology, Terrestrial Biology, 1978.

Reference 2.2.0-12 Cape Pear Steam Electric Generating Plant 316(b)

Demonstration.

• Amendment 1 to the Environmental Report changed the number of Reference 2.2.0-11 to Reference 2.2.0-12.

ER Question 291.3 (Section 2.4.1)

Provide completion schedule for filling the main reservoir and for constructing intake structure on the Cape Fear River.

Response: Filling of the, main reservoir began in November, 1980, and as of January 4, 1982, the main reservoir water level was at Elevation 200.2 feet. Based on this actual water level and average and drought flow conditions, it is expected that the main reservoir will be filled as indicated below:

Min. Operating Normal Operating Level Level (205 Ft.) (220 Ft.)

Average Flow April 1982 March 1983 Drought Flow February 1983 Early 1986 Analysis of the main reservoir is presently being conducted. It has not yet been determined if the reservoir makeup system will be needed for Unit 1 or only later for Unit 2. A constructon schedule will be prepared upon completion if this analysis.

ER Question 291.4 (Section 3.4.2.8.3 and Section 3.4.2.9)

In the description of the intake traveling screens, it is indicated that baskets will be affixed for collection and removal of debris and that the debris will be deposited in a landfill on site. Could these screen baskets also function in the return of live fish to the Cape Fear River and/or the in Reservoir?

Response: The "baskets" described in Sections 3.4.2.8.3 and 3.4.2.9 are actually ledges or shelves at the bottom of each framed screen panel which serve to lift trash as the screens are rotated.

These ledges ("baskets") are not designed for use in returning live fish to the Cape Fear River or the main reservoir.

Generally, live fish will not remain on the ledges as the screens rotate.

As discussed in Section 5.1.3.4 of the OL-ER, the SHNPP intake structures on the Cape Fear River and at the plant were designed by following the recommendations set forth in EPA's April 1976, Develo ment Document for Best Technolo y Available for the Location, Desi n, Construction and Capacity of Coolin Water Intake Structures for nimizin Adverse Environmental Impact.

Mi The recommended design features include (1) use of a closed-cycle cooling system, (2) low intake velocities (less than 0.5 fps), (3) placement of the intakes in deeper, less productive waters, an'd (4) structural features (smooth surfaces, etc.) to minimize the intake structure's "attractiveness" to fish.

By conforming to these EPA recommended specifications, the impingement rates at the SHNPP intake structures will be minimal. This assessment was supported by written testimony presented on October 5, 1977, to the Atomic Safety and Licensing Board by Clarence R. Hickey, Jr., a fisheries biologist for the

U.S. Nuclear Regulatory Commission. He stated that the SHNPP intake design "should result in low levels of impingement of reservoir fishes." Further, E. T. Heinen, then Chief of the Ecological Review Branch of Region IV EPA, stated in a letter dated August 30, 1977, to C. W. Hollis, Chief of the Regulatory Functions Branch of the U.S. Army Corps of Engineers in Wilmington, N.C., that, "no specific provisions for nekton return axe necessary to this [the SHNPP] intake structure."

With the general agreement among the involved state and federal regulatory agencies and CPSL that impingement rates should be low at the SHNPP intake structures, and that a nekton return system is not necessary, no plans have been made to modify the traveling screen wash system for the return of live fish to the river or reservoir.

ER Ques tion 291. 5 ( Section 12. 2)

Provide the status of demonstrations (or determinations) that the intakes comply with Section 316(b) of the Clean Mater Act.

Response: The design of both intakes was discussed with the appropriate agencies. CP&L has since been verbally informed that both intakes meet the criteria of Section 316(b) of the Clean Water

ER Question 291.6 (Appendix B)

The draft  %'DES permit does not place limits of 0.5 ppm (max) and 0.2 ppm (average) on chlorine in cooling tower blowdown as discussed in OL-ER Section 5.3.3. Provide clarification of this matter.

~Res ense: The iinel NPDEE permit will include chlorine limitstions.

ER Question 310.1 (Section 2.1.2)

Update the projected population using the 1980 preliminary census counts. In addition, update the population centers listed in Section 2.1.2.2 of the OL-ER that are within a 50~ile radius of SHNPP. Futhermore, update the transient population estimates found in Section 2.1.2.3 of the OL-ER.

Response: Tables 2.1.2-1, 2, 3, 4, and 5 have been updated using 1980 census data. These tables are attached with the response to ER Question 470.1. The new population estimates and population projections have been prepared based on the following references:

N.C. Office of State Budget and Management. Research and Planning Services.

July 1981. Update North Carolina Population Projections. 49 p.

N.C. Office of State Budget and Management. Research and Planning Services.

August 1981. 1980 Population of Final Census Designated Places. 2 p.

U.S. Department of Commerce. Bureau of the Census. July 1977. Projections of the Population of the United States: 1977 to 2050. P-25, No. 704. 87 p.

U.S. Department of Commerce. Bureau of the Census. March 1981. 1980 Census of Population and Housing. North Carolina. Final Population and Housing Unit Counts. PHC80-V-35. 30 p.

The discussion of population concentrations within a 50-mile radius of SHNPP presented in Section 2.1.2.2 of the OL-ER remains valid with one exception. The second sentence in that section should now read, "Six other smaller cities and towns have populations greater than 10,000."

The transient population estimates in Section 2.1.2.3 also are still valid with the following exceptions:

1. The maximum daily number of people attending the N.C. State Fair in 1981 was 110,925. The total attendance for the nine-day 1981 fair was 643,457.

2. Industries and businesses in the Research Triangle Park employ about 19,000 workers.

3. In Moncure, 1,300 workers are employed by the principal industries located there.

4. In Apex, 2,200 workers are employed by the principal industries located there.

5. The Harris Energy 6 Environmental Center has 150 permanent employees. Up to 60 additional people a day attend training sessions at the Center. The associated Visitors Center currently attracts an average of 63 people daily.

ER Question 310.2 (Section 2.1.2 and Section 2.1.3)

Identify any changes in land use plans within a 50~ile radius of the plant that may affect the pattern of population growth.

~Res ense: There are no known changes in land use plans within a 50~le radius of the plant (Section 2.1.3) that are significant enough to affect the pattern of population growth described in Section 2.1.2.

ER Question 310.3 (Section 5.5)

Identify any place where traffic congestion or problems of interference with patterns of local traffic might be anticipated due to plant operation or maintenance.

Response: During the construction of the Harris plant facilities, the peak manpower on site has reached 4,000 including 3,200 craftsmen and 800 support personnel during April, 1980. We do not anticipate that the on-site manpower will again rise to that level even when plant facilities become operational. During this past period of peak manpower on site, the only traffic problem experienced was a delay problem at the intersection of North Carolina Secondary Roads 1127 and 1135 which is near CP&L's Harris Energy and Environmental Center. This delay problem at the intersection of Secondary Roads 1127 and 1135 is not expected to be significant during plant operation due to the lesser number of people employed on site.

ER Question 310.4 (Section 4.2)

Provide documentation of any communication between CPGL and the State Historical Preservation Officer (SHPO) concerning impacts of the transmission corridors other than the 500 kV Harris-Harnett line on cultural resources.

Response: Attached is a copy of all correspondence between CPGL and the State Historical Preservation Officer for the proposed Harris Plant-Asheboro 230 kV Line and the Harris Plant-Fayetteville 230 kV Line. The Harris Plant-Wake 500 kV Li.ne is excluded from this response since cancellation of Units 3 and 4 do not require its connection at the SHNPP site.

The Harris Plant-Cape Pear Plant 230 kV Line was constructed parallel to an existing line and the Harris Plant-Method 230 kV Line was constructed along an existing. line's corridor. These lines did not involve extensive interaction between CPSL and the State Historic Preservation Office.

The Harris-Puquay-Erin (North) 230 kV Line was located in 1975. Since all correspondence was through personal interview, no written correspondence is available. Interviews were held by Mr. Ken Rudder (CP6L) with Mr. Pat Garrow (N.C. Department of Archives 6 History, Archaeology Section) and Ms. Kathaleen Pepi (N.C. Department of Archives 6 History, Historical Section) on June 18 and June 13, 1975, respectively.

The Harris-Lillington-Erwin ( South) 230 kV Line is proposed as predominantly (80%) a rebuild of an existing line. No extensive interaction with the State Historic Officer was necessary.

ER Question 310.5 (Section 4.5)

Provide the updated number and distribution over the time the four units come on line of operation and contract workers, and their payrolls. How many workers would be hired locally and where would they be likely to live?

~Res oese: The following attachments provide a breakdown of the number and distribution over the time the two units come on line of operation and contract workers. Attachment I illustrates the number and distribution of man/years based on current estimates. Attachment II illustrates the payroll distribution for each year also based on current estimates.

Based on the results of a current contract Employee Travel Distance Survey, we estimate that between thirty and forty percent of our work force are hired and are likely to live within the local area. Local being defined as "within a 25 mile radius of the work site." This would include area in and around Raleigh, Cary, Garner, Durham, Chapel Hill, Sanford, Apex, and Fuquay-Varina.

ATTACHMENT I SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1 AND 2 PROJECT ESTIMATED MAN/YEARS Daniel Contracts (Inc. Manual (Inc. Guards CP&L Site CP&L Site CP&L QA Ope'rations Total As of 12/81: 8,856 1,369 513 166 10,904 1982 3,135 451 167 106 3,859 1983 3,397 181 170 141 3,889 1984 2,282 373 170 157 520 3,502 1985 1,582 309 170 162 540 2,763 1986 921 138 144 590 1,838 1987 418 37 109 123 632 1,319 1988 209 41 107 632 997 1989 632 632 TOTAL 20,800 2 f773 1,478 1,106 3,546 29,703

ATTACHMENT II SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1 AND 2 PROJECT ESTIMATED PAYROLL BY YEARS (in thousands of dollars)

Daniel Contracts (Inc. Manual 4Inc. Guards CPSL Site CP&L Site CP6L QA Operations Total As Of 12/81: 169,493 32,961 17,967 7,356 227 777 1982 78,708 5$ 840 5 $ 438 4$ 069 94,055 1983 94,760 2,476 5,969 5$ 401 108,606 1984 70,377 3,994 6,500 6,366 5,500 92,737 1985 54,539 4,914 7,085 7,023 6,200 79,761 1986 33,748 829 6,282 6,754 6,900 54,513 1987 18,522 819 5,424 6,381 7,988 39,134 1988 9, 168 205 2,275 6,128 8,667 26,443 1989 9,404 9,404 TOTAL 529,315 52,038 56,940 49,478 44,659 732,430

ER Question 310.6 (Section 5.5)

Provide yearly dollar estimates (1984 dollars) of purchases of local goods and services for operation and maintenance as all four units come on line. Where will these purchases be made?

Response: The following SHNPP Operation & Maintenance estimates as the two units come on line were taken from a report entitled "20 Year Projected Long Range Operation and Maintenance Costs" submitted to CP&L's Treasury Department by memorandum from B. J. Furr and J. B.

McGirt dated February 25, 1981:

Year Unit 1 Unit 2 Total 1985 $ 10.5M $ 10. 5M 1986 $ 34.0M $ 34. OM 1987 $ 36.7M $ 36.7M 1988 $ 39.7M $ 29.6M $ 69.3M 1989 $ 42.8M $ 43.4M $ 86.2M These purchases will be made through the Corporate Purchasing Department in Raleigh, who will solicit bids from qualified suppliers.

ER Question 310.7 (Section 5.5)

Provide an estimate of federal, state, and county income taxes, if any, generated from the operation and maintenance work force.

Response: The following table reflects the amount of federal and state income taxes generated from the operation and maintenance work force:

Year Federal State 1984 $ 1.1M $ ,385,000 1985 $ 1.2M 434,000 1986 $ 1.38M $ 483,000 1987 $ 1.60M $ 559,000 1988 $ 1.33M $ 606,690 1989 $ 1,88M $ 625,280

~~ \ 4 ~

ER Question 320.1 Provide the most recent and estimated projection to 1984 of the delivered costs for coal, No. 2 oil, No. 6 oil, natural gas, and nuclear fuel in cents per million BTU.

Response: The following table provides fuel cost projections through 1984:

FUEL COST PROJECTION f/mTU Year Coal No. 2 Oil No. 6 Oil Natural Gas Nuclear 1981 175 739 550 425 38 1982 206 761 582 493 42 1983 227 812 628 601 44 1984 262 899 699 704 48

iR Question 470.1 (Section 2.1.2 and Section 2.1.3)

The print on Tables 2.1.2-1, 2, 3 and 5, and on Tables 2.1.3-2, 3, and 4 is too small to read. Provide revised tables which are readable. Also most of the data in these tables and in Table 2.1.2-4 should be rounded off to three significant figures. Reporting these types of data with up to nine significant figures may reflect poor quality and efficiency control.

Response: As requested, these tables were revised and they are attached.

Numbers within Tables 2.1.2-1, 2, 3, 4, and 5 and Tables 2.1.3-2, 3 and 4 are reported to three significant figures. However, totals are reported as sums of respective columns and, as such, are not necessarily reported to three significant figures. Additionally, because all data in Table 2.1.2-4 is reported to three significant figures, these numbers may not agree with column totals reported in other population tables.

TABLE 2.1.2-1 POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 0 TO 1 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N

NNE NE ENE E

ESE SE SSE S 0 0 0 SSW 0 0 0 SW 0 0 0 WSW 0 0 0

.0 0 0 0 0 0 0 0 TOTAL

TABLE 2.1.2-1 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 1 TO 2 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 0 0 0 0 0, 0 NNE 0 0 0 0 0 0 NE 0 0 0 0 0 0 ENE 0 0 0 0 0 0 E 0 0 0 0 0 0 ESE 0 0 0 0 0 0 SE 0 0 0 0 0 0 SSE 0 0 0 0 0 0 S 0 0 0 0 0 0 SSW 0 0 0 0 0 0 SW 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 25 28 32 40 48 56 64 65 TOTAL 25 28 32 40 48 56 64 65

TABLE 2.1.2-1 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 2 TO 3 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 30 34 38 47 56 66 76 77 39 44 50 62 74 87 100 101 47 53 60 74 89 104 119 120 3 3 4 5 6 7 8 8 E 8 9 10 12 14 16 18 18 ESE 17 19 22 27 32 37 42 43 SE 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 0 S

SSW SW 0,

0 7

0 0

8 0

9 0

0 10 10 0

0 WSW 0 0 0 0 0'5 17 20 16 18 21 17 19 22 19 21 24 21 23 26

'5 23 28 25 27 30 25 27 30 95 105 114 134 155 176 197 200 TOTAL 296 327 362 432 504 578 652 659

TABLE 2.1.2-1 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 3 TO 4 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 38 42 47 57 67 78 89 90 NNE 43 49 55 68 82 96 110 111 NE 43 49 55 68 82 96 110 111 ENE 72 82 92 114 137 160 183 185 E 62 70 80 99 118 138 158 160 ESE 69 78 89 110 132 154 176 178 SE 56 63 71 88 105 123 141 143 SSE 53 60 68 84 100 117 134 136 S 28 30 32 36 40 44 48 48 SSW 26 27 29 32 35 38 41 41 SW 26 27 29 32 35 38 41 41 WSW 26 27 29 32 35 38 41 41 26 27 29 32 35 38 41 41 26 27 29 32 35 38 41 41 26 27 29 32 35 38 41 41 26 27 29 32 35 38 41 41 TOTAL 646 712 792 948 1108 1272 1436 1449

TABLE 2.1.2-1 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 4 TO 5 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 45 50 55 66 77 88 99 100 NNE 55 62 71 88 106 124 142 144 NE 55 62 71 88 106 124 142 144 ENE 76 86 98 122 146 171 196 199 E 97 110 124 154 185 216 248 251 ESE 97 110 124 154 185 216 248 251 SE 91 102 115 141 168 195 222 224 SSE 48 51 56 64 72 80 88 88 S 34 36 38 42 46 50 54 54 SSW 34 36 38 42 46 50 54 54 SW 34 36 38 42 46 50 54 54 WSW 34 36 38 42 46 50 54 54 W 34 36 38 42 46 50 54 54 WNW 34 36 38 42 46 50 54 54 NW 34 36 38 42 46 50 54 54 NNW 34 36 38 42 46 50 54 54 TOTAL 836 921 1018 1213 1413 1614 1817 1833

TABLE 2.1.2-1 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND TEN MILES OF THE SHNPP 5 TO 10 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 439 477 519 603 689 776 863 871 NNE 863 978 1110 1370 1650 1930 2210 2240 NE 3760 4250 4820 5970 7160 8380 9610 9730 ENE 871 987 1120 1390 1660 1950 2230 2260 1490 1690 1920 2380 2850 3330 3820 3870 ESE 2550 2890 3280 4060 4870 5700 6540 6620 SE 764 846 939 1130 1320 1510 1700 1720 SSE 575 623 675 777 881 985 1090 1100 S 515 556 601 690 779 869 959 968 SSW 449 487 529 613 699 786 873 881 SW 600 653 710 827 946 1070 1190 1200 WSW 690 750 816 948 1080 1220 1360 1370 607

'030 646 687 770 853 937 1020 539 570 603 668 733 798 863 869 368 390 411 455 499 543 587 591 340 360 380 421 462 503 544 548 TOTAL 15420 17153 19120 23072 27131 31287 35459 35868

TABLE 2.1.2-2 AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND TEN MILES OF THE SHNPP 0 TO 1 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 0 0 0 0 0 0 ENE 0 0 E 0 0 ESE 0 0 SE 0 0 SSE 0 0 S 0 SSW 0 SW 0 WSW 0 0

0 0

0 TOTAL

TABLE 2.1.2-2 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND TEN MILES OF THE SHNPP 1 TO 2 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 0 0 0 NNE 0 0 0 NE 0 0 0 ENE 0 0 0 E 0 0 0 ESE 0 0 0 SE 0 0 0 SSE 0 0 0 S 0 0 0 SSW 0 0 0 SW 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 ll 3 32 TOTAL 32

TABLE 2.1.2-2 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND TEN MILES OF THE SHNPP 2 TO 3 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 13 38 NNE 17 50 NE 20 60 ENE 1 4 E )0 ESE 22 SE 0 SSE 0 S 0 0 SSW 0 .0 SW 1 6 WSW 0 0 W 5 14 WNW 5 16 NW 6 18

, NNW 35 105 TOTAL 114 30 343

TABLE 2.1.2-2 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA .BETWEEN ZERO AND TEN MILES OF THE SHNPP 3 TO 4 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 15 46 NNE 19 55 NE 19 55 ENE 31 93 E 27 80 ESE 30 89 SE 24 71 SSE 23 68 S 27 SSW 24 SW 24 WSW 24 W 24 WNW 24 NW 24 NNW 24 TOTAL 253 752

TABLE 2.1.2-2 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND TEN MILES OF TMi SHNPP 4 TO 5 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 18 53 NNE 24 72 NE 24 72 ENE 33 99 E 42 11 125 ESE 42 11 125 SE 38 10 114 SSE 17 4 50 S 11 3 32 SSW 11 3 32 SW 11 3 K 32 WSW 11 3 32 ll 32 ll 32 ll 32 11 32 TOTAL 326 86 966

TABLE 2.1.2-2 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND TEN MILES OF THE SHNPP 5 TO 10 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 158 42 470 NNE 375 100 1110 NE 1630 435 , 4840 ENE 378 101 1120 E 649 173 1930 ESE 1110 296 3290 SE 301 80 894 SSE 202 54 601 S 180 48 533 SSW 161 43 477 SW 217 58 646 WSW 249 67 740 198 53 587 170 45 505 116 31 343 107 29 318 TOTAL 6201 1655 18404

TABLE 2.1.2-3 POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE .YEARS 1985 TO 2031 BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 0 TO 10 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 552 603 659 773 889 1010 1130 1140 KK 1000 1130 1280 1590 1910 2240 2560 2590 NE 3900 4420 5000 6200 7440 8710 9980 10100 ENE 1020 1160 1310 1630 1950 2280 2620 2650 E 1660 1880 2130 2640 3170 3700 4250 4300 ESE 2740 3100 3510 4350 5220 6110 7000 7090 SE 911 1010 1130 1350 1590 1830 2070 2090 SSE 676 734 799 925 1050 1180 1310 1320 S 577 622 671 768 865 963 1060 1070 SSW 509 550 596 687 780 874 968 976 SW 665 721 783 908 1040 1160 1290 1310 WSW 750 813 883 1020 1170 1310 1460 1470 W 682 725 771 863 955 1050 1140 1150 WNW 616 651 689 763 837 911 985 991 NW 448 474 500 553 606 659 712 716 NNW 520 556 593 669 746 823 900 908 TOTAL 17226 19149 21304 25689 30218 34810 39435 39871

TABLE 2.1.2-3 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 10 TO 20 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 17100 18600 20100 23100 26100 29200 32200 32500 NNE 5520 6030 6590 7700 8850 10000 11200 11300 NE 50100 56800 64300 79600 '95600 112000 128000 130000 ENE 43400 49200 55700 69100 82900 97000 111000 113000 E 8430 9550 10800 13400 16100 18800 21600 21800 ESE 6950 7790 8750 10700 12700 14800 16800 17000 SE 5710 6190 6720 7750 8790 9840 10900 11000 SSE 5260 5700 6180 7120 8070 9030 9990 10100 S 2970 3220 3490 4020 4560 5100 5640 5690 SSW 5090 5550 6040 7050 8080 9120 10200 10300 SW 18500 20200 22100 25800 29600 33500 37500 37.800 WSW 4060 4410 4790 5550 6340 7140 7940 8020 W 1990 2100 2220 2460 2700 2940 3180 3210 WNW 3640 3850 4070 4510 4950 5400 5840 5880 NW 2950 3120 3300 3660 4020 4380 4750 4780 W 26500 29600 33200 40200 47200 54300 61400 62100 TOTAL 208170 231910 258350 311720 366560 422550 478140 484480

TABLE 2.1.2-3 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS 'FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 20 TO 30 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 92500 99000 106000 120000 133000 147000 160000 162000 iVEE 42000 44800 47800 53600 59500. 65400 71300 71900 NE 57600 65300 73900 91600 110000 129000 147000 149000 ENE 79900 90600 103000 127000 153000 178000 205000 207000 E 14700 16000 17500 20400 23400 26400 29500 29800 ESE 5810 6170 6550 7300 8050 8810 9560 9630 SE 23300 25200 27200 31200 35200 39300 43300 43700 SSE 9370 10100 10800 12300 13700 15100 16600 16700 S 8950 9670 10400 11900 13500 15000 16500 16700 SSW 4780 5200 5670 6610 7570 8530 9500 9600 S'W 5680 6290 6980 8390 9850 11300 12900 13000 WSW 3120 3380 3680 4280 4890 5520 6140 6200 4700 4970 5250 5820 6390 6960 7530 7580 3440 3620 3810 4200 4580 4960 5350 5380 5100 5300 5530 5930 6330 6720 7110 7150 17000 19100 21500 26200 30900 35600 40400 40800 TOTAL 377950 414700 455570 536730 619860 703600 787690 796140

TABLE 2.1.2-3 (continued)

POPULATION ESTIMATES FOR 1980 R%)

POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 30 TO 40 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 16900 18200 19700 22500 25400 28200 31100 31400 14500 15000 15600 16600 17600 18600 19600 19700 13700 15300 17100 20700 24400 28200 32100 32400 18700 21100 23800 29300 35000 40900 46700 47300 E 11400 12100 12900 '14300 15800 17300 18800 18900 ESE 19000 20200 21500 23900 26400 28800 31300 31600 SE 12300 13200 14100 15900 17800 19600 21500 21700 SSE 14900 15800 16800 18500 20200 21900 23500 23700 S 114000 121000 128000 141000 154000 166000 179000 180000 SSW 3860 4230 4650 5490 6350 7220 8090 8170 SW 12800 14500 16500 20600 . 24900 29300 33800 34200 WSW 7090 8020 9060 11200 13500 15800 18200 18400 W 8830 9480 10200 11500 12900 14300 15700 15900 WNW 11000 11700 12400 13900 15400 16800 18300 18500 NW 34100 34200 34300 34100 33800 33400 32900 32800 NNW 21800 23400 25100 28500 31800 35100 38400 38700 TOTAL 334880 357430 381710 427990 475250 521420 568990 573370

TABLE 2.1.2-3 (continued)

POPULATION ESTIMATES FOR 1980 AND POPULATION PROJECTIONS FOR THE YEARS 1985 TO 2031 BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 40 TO 50 MILES DIRECTION 1980 1985 1990 2000 2010 2020 2030 2031 N 8410 8910 9440 10500 11500 12600 13700 13800 NNE 8070 8190 8310 8490 8660 8810 8950 8970 NE 13900 14700 15400 16900 18400 19900 21400 21500 ENE 10000 10600 11300 12600 13900 15200 16500 16700 E 14200 15100 15900 17600 19300 21000 22600 22800 ESE 10200 10800 11500 12800 14000 15300 16600 16700 SE 7070 7410 7760 8460 9170 9870 10600 10600 SSE 12500 13200 13900 15300 16600 17900 19200 19300 S 101000 108000 114000 126000 138000 149000 160000 161000 SSW 12700 14100 15500 18600 21800 25000 28200 28500 SW 20400 23200 26300 32800 39600 46600 53700 54400 WSW 8770 9740 10800 13100 15400 17800 20200 20500 W 34400 37400 40600 47000 53600 60200 66800 67400 WNW 24200 25800 27500 30800 34100 37500 40900 41200 NW 64300 64900 65600 66200 66600 66800 67000 '7000 iVNW 9380 9650 9950 10500 11000 11500 12000 12000 TOTAL 359500 381700 403760 447650 491630 534980 578350 582370

TABLE 2 ' ~ 2-4 CUMULATIVE POPULATION ESTIMATES AND PROJECTIONS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 0-1 0-2 0-3 0-4 0-5 0-10 1-20 0-30 0-40 0-50 1980 0 25 321 967 1800 17200 225000 603000 938000 1300000 1985 0 28 355 1070 1990 19200 251000 666000 1020000 1400000 1990 0 32 394 1190 2210 21300 280000 735000 1120000 1520000 2000 0 40 472 1420 2630 25700 337000 873000 1300000 1750000 2010 0 48 552 1660 3070 30200 397000 1020000 1500000 1990000 2020 0 56 634 1910 3520 34800 457000 1160000 1680000 2210000 2030 0 64 716 2150 3970 39400 518000 1310000 1880000 2460000 2031 0 65 724 2170 4000 39900 524000 1320000 1890000 2470000

TABLE 2.1.2-5 AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 0 TO 10 MILES AGE AGE AGE DIRECTION 0-1.3 14-18 OVER 18 204 54 607 435 116 1290 1690 451 5030 443 118 1320 E 721 192 2140 ESE 1190 317 3530 SE 363 96 1080 SSE 242 64 719 S 200 53 592 SSW 180 48 533 SW 238 64 708 WSW 268 72 796 222 59 657 194 51 577 141 38 417 172 46 511 TOTAL 6903 1839 20507

TABLE 2.1.2-5 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 10 TO 20 iMILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 6020 1610 17900 NNE 2030 542 6030 NE 21700 5810 64600 ENE 18900 5040 56000 E 3660 976 10900 ESE 2900 774 8610 SE 2020 540 6010 SSE 1860 496 5520 S 1050 280 3120 SSW 1860 495 5510 SW 6810 1820 20200 WSW 1460 389 4330 625 167 1860 1150 306 3410 932 249 2770 10800 2880 32000 TOTAL 83777 22374 248770

TABLE 2.1.2-5 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 20 TO 30 Mi ILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 30700 8210 91300 NNE 13800 3670 40900 NE 25000 6680 74300 ENE 34700 9260 103000 E 5370 1430 16000 ESE 1860 497 5530 SE 8110 2170 24100 SSE 3160 844 9390 S 3100 828 9220 SSW 1740 464 5160 SW 2250 601 6690 WSW 1120 300 3340 W 1480 395 4390 WNW 1060 283 3150 iNW 1470 393 4380 NNW 7050 1880 20900 TOTAL 141970 37905 421750

TABLE 2.1.2-5 (continued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 30 TO 40 MILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 N 5850 1560 17400 NNE 4110 1100 12200 NE 5580 1490 16600 ENE 7970 2130 23700 E '3660 977 10900 ESE 6100 1630 18100 SE 4110 1100 12200 SSE 4690 1250 13900 S 35700 9540 106000 SSW 1450 388 4320 SW 5660 1510 16800 WSW 3070 820 9130 2980 796 8860 3550 948 10600 7990 2130 23700 7330 1960 21800 TOTAL 109800 29329 326210

TABLE 2.1.2-5 (concinued)

AGE DISTRIBUTION FOR THE YEAR 2008 FOR THE AREA BETWEEN ZERO AND FIFTY i41ILES OF THE SHNPP 40 TO 50 iiILES AGE AGE AGE DIRECTION 0-13 14-18 OVER 18 2670 713 7940 2040 543 6050 4270 1140 12700 3220 859 9560 E 4470 1190 13300 ESE 3250 868 9660 SE 2130 568 6320 SSE 3850 1030 11400 S 31900 8520 94800 SSW 4980 1330 14800 SW 9000 2400 26700 WSW 3520 940 10500 12300 3290 36600 7890 2110 23400 15700 4190 46600 2570 686 ,

7630 TOTAL 113760 30377 337960

TABLE 2.1 ~ 3-2 1980 AGRICULTURAL PRODUCTION OF K@OR CROPS BETWEEN ZERO AND FIFTY HILES OF THE SHNPP 0 TO 10 iMLES SWEET CORN FOR DIRECTION SOYBEANS TOBACCO POTATOES GRAIN N 134000 286000 28600 316000 NNE 288000 708000 82800 316000 NE 288000 708000 82800 316000 ENE 288000 708000 82800 316000 E 288000 708000 82800 316000 ESE 288000 708000 82800 316000 SE 486000 775000 182000 767000 SSE 574000 748000 230000 1020000 S 388000 512000 144000 746000 SSW 181000 319000 24100 287000, SW 180000 306000 21600 284000 WSW 195000 344000 26200 276000 90100 143000 8220 310000 66500 99700 4720 317000 66500 99700 4720 317000 80900 135000 8870 332000 TOTAL 3882000 7307400 1097030 6552000 All data reported in kilograms Basis: Reference 2.1.3-1

TABLE 2.1.3-2 (continued) 1980 AGRICULTURAL PRODUCTION OF MAJOR CROPS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 10 TO 20 MILES SWEET CORN FOR DIRECTION SOYBEANS TOBACCO POTATOES GRAIN N 273000 531000 24800 758000 NNE 686000 1690000 182000 771000 NE '37000 2060000 241000 918000 ENE 795000 1950000 228000 871000 E 917000 2250000 274000 1010000 ESE 1220000 2370000 1290000 2030000 SE 2060000 2480000 856000 3710000 SSE 2140000 2560000 890000 3860000 S 2150000 2570000 892000 3870000 SSW 1240000 1730000 371000 1850000 SW 770000 1310000 93000 790000 WSW 592000 986000 66300 849000 W 173000 224000 4440 956000 WNW 175000 228000 4500 969000 NW 172000 223000 4590 937000 iiW 316000 399000 14400 1200000 TOTAL 14516000 23561000 5436030 25349000 All data reported in kilograms Basis: Reference 2.1.3-1

TABLE 2.1.3-2 (continued) 1980 AGRICULTURAL PRODUCTION OF i~OR CROPS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 20 TO 30 MILES SWEET CORN FOR DIRECTION SOYBEANS TOBACCO POTATOES GRAIN N 636000 1180000 56300 1360000 NNE 654000 1610000 115000 806000 NE 1420000 3490000 408000 1560000 ENE 1440000 3550000 415000 1580000 E 2740000 4600000 5110000 5800000 ESE 3460000 5240000 7570000 8060000 SE 3560000 4410000 2310000 6670000 SSE 3280000 3630000 1280000 5840000 S 3530000 4070000 1420000 6330000 SSW 2900000 3630000 1120000 5050000 SW 823000 1610000 103000 1120000 WSW 540000 1070000 59900 1230000 319000 413000 8170 1760000 332000 437000 8430 1720000 873000 1180000 27300 3100000 894000 1120000 49100 2670000 TOTAL 27401000 41240000 20060200 54656000 All data reported in kilograms Basis: Reference 2.1.3-1

TABLE 2.1.3-2 (continued) 1980 AGRICULTURAL PRODUCTION OF MAJOR CROPS BETWEEN ZERO'ND FIFTY MILES OF THE SHNPP 30 TO 40 MILES SWEET CORN FOR DIRECTION SOYBEANS TOBACCO POTATOES GRAIN N 1000000 1690000 79200 2380000 NNE 1190000 3530000 129000 1750000 NE 2060000 4730000 463000 2420000 ENE 2380000 5270000 1720000 3300000 E 4720000 7170000 10400000 11000000 ESE 4670000 7090000 10300000 10900000 SE 4930000 5670000 6210000 13900000 SSE, 4250000 2100000 1220000 8120000 S 4130000 1740000 805000 6710000 SSW 3660000 1650000 249000 3430000 SW 490000 1440000 70600 1300000 WSW 506000 1340000 63900 1540000 817000 602000 9750 4550000 925000 1040000 16900 4430000 1390000 1960000 33700 5010000 1320000 1710000 60100 , 4200000 TOTAL 38438000 48732000 31830150 84940000 All data reported in kilograms Basis: Reference 2.1.3-1

TABLE 2.1.3-2 (continued) 1980 AGRICULTURAL PRODUCTION OF MAJOR CROPS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 40 TO 50 Mi ILES SWEET CORN FOR DIRECTION SOYBEANS TOBACCO POTATOES GRAIN 499000 5030000 31100 44 10000 1450000 4920000 26500 2840000 3100000 5880000 449000 4860000 3230000 6670000 3220000 6090000 E 5420000 10800000 10400000 ,18100000 ESE 7400000 9120000 9870000 22000000 SE 6210000 5200000 5200000 22900000 SSE 6030000 3830000 3280000 16600000 S 5970000 2320000 865000 8940000 SSW 7730000 1630000 99600 5190000 SW 642000 1750000 87400 1650000 WSW 607000 1490000 77400 1780000 1210000 778000 12200 6750000 1120000 1670000 21700 5980000 1390000 2810000 40500 5620000 1160000 3520000 43800 4510000 TOTAL 53168000 6? 418000 33724200 138220000 All data reported in kilograms Basis: Reference 2.1.3-1

TABLE 2.1.3-2 (continued) 1980 AGRICULTURAL PRODUCTION OF MAJOR CROPS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP CUMULATIVE TOTALS CORN FOR SECTOR SOYBEANS TOBACCO POTATOES GRAIN 00 TO 10 3882000 7307400 1097030 6552000 00 TO 20 18398000 30868400 6533060 31901000 00 TO 30 45799000 72108400 26593260 86557000 OO TO 40 84237000 120840400 58423410 171497000 00 TO 50 137405000 188258400 921467 10 309717000 All data reported in kilograms Basis: Reference 2'.1.3-1

TABLE 2.1.3-3 1980 LIVESTOCK STATISTICS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 0 TO 10 MILES MILK BEEF DIRECTION COWS COWS HOGS CHICKENS N 93 242 649 11800 NNE 101 108 618 5030 NE 101 108 618 5030 ENE 101 108 618 5030 E 101 108 618 5030 ESE 101 108 618 5030 SE 72 123 801 3140 SSE 54 152 909 3100 S 62 205 808 6700 SSW 51 230 613 6420 SW 47 234 611 6140 WSW 44 214 592 4950 W 80 288 652 13000 WNW 89 302 663 14800 NW 89 302 663 14800 NNW 94 307 694 15100 TOTAL 1280 3139 10745 125100 Milk cows defined as milk cows and heifers that have calved.

Beef cows defined as beef cows and heifers that have, calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-3 (continued) 1980 LIVESTOCK STATXSTICS BETWEEN ZERO AND FIFTY MXLES OF THE SHNPP 10 TO 20 MILES MILK BEEF DIRECTION ~

COWS COWS HOGS CHXCKENS N

i&EE 219 231 730 377 1200 1370

'9600 14500 NE 292 312 1790 )4600 ENE 277 296 1700 13900 E 318 342 1970 15900 ESE 232 408 3420 13800 SE 117 409 2940 3030 SSE 118 422 3040 2940 S 118 423 3050 2950 SSW 71 516 2170 1400 SW 47 582 1750 582 WSW 116 698 1840 14700 268 937 2010 46000 271 949 2030 46600 265 909 1940 44500 453 852 1670 35900 TOTAL 3413 9162 33890 300902 Milk cows defined as milk cows and heifers that have calved.

Beef cows defined as beef'ows and heifers that have calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-3 (continued) 1980 LIVESTOCK STATISTICS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 20 TO 30 MILES MILK BEEF DIRECTION COWS COWS HOGS CHICKENS N 515 985 1090 27800 NNE 187 813 933 23500 NE 496 530 3040 24800 ENE 504 539 3090 25200 E 231 911 10100 23100 ESE 101 1120 13900 22600 SE 184 761 6270 7300 SSE 175 640 4500 6600 S 191 693 4940 5970 SSW 160 752 4520 4680 SW 46 818 2970 5910 WSW 169 1030 3120 30200 493 1720 3700 84700 499 1590 3250 73700 1160 1700 1860 32800 1240 1280 2100 38300 TOTAL 6351 15882 69383 437160 Milk cows defined 'as milk cows and heifers that have calved.

Beef cows defined as beef cows and heifers that have calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-3 (continued) 1980 LIVESTOCK STATISTICS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 30 TO 40 MILES MILK BEEF DIRECTION COWS COWS HOGS CHICKENS N 976 1520 1890 43600 NNE 404 1240 2560 49200 NE 500 991 6660 58600 ENE 625 877 6450 38200 E 138 1530 19000 31000 ESE 136 1520 18800 30700 SE 179 1090 21100 44000 SSE 170 752 7060 33300 S 167 748 4170 28800 SSW 53 652 4560 8490 SW 19 934 4280 15600 WSW 102 1030 4360 25900 900 1730 5410 117000 1100 1970 4230 87900 1800 2620 1960 28000 1790 2080 2720 47400 TOTAL 9059 21284 115210 687690 Milk cows defined as ad.lk cows and heifers that have calved.

Beef cows defined as beeS cows and heifers that have calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-3 (continued) 1980 LIVESTOCK STATISTICS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 40 TO 50 MILES MILK BEEF DIRECTION COWS COWS HOGS CHICKENS 471 1810 4540 36800 506 1700 3600 73900 173 1640 14500 124000 146 1320 14600 159000 E 132 1510 22600 79100 ESE 173 1710 26700 95300 SE 207 916 34900 89600 SSE 223 976 21700 66100 S 182 890 5930 31000 SSW 46 507 5950 1230 SW 30 1170 5500 20200 WSW 79 1190 6610 26400 W 1240 1880 7090 148000 WNW 1180 1990 '4890 99000 NW 1690 2760 2100 29800 1450 2540 2880 29800 TOTAL 7928 24509 184090 1109230 Milk cows defined as milk cows and heifers that have calved.

Beef cows defined as beef cows and heifers that have calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-3 (continued) 1980 LIVESTOCK STATISTICS BETWEEN ZERO AND FIFTY MILES OF THE SHNPP CUMULATIVE TOTALS MILK BEEF SECTOR COWS COWS HOGS CHICKENS 00 TO 10 1280 3139 10745 125100 00 TO 20 4693 12301 44635 426002 00 TO 30 11044 28183 114018 863162 00 TO 40 20103 49467 229228 1550852 00 TO 50 28031 73976 413318 2660082 Milk cows defined as milk cows and heifers that have calved.

Beef cows defined as beef cows and heifers that have calved.

Basis: Reference 2.1.3-1

TABLE 2.1.3-4 ANNUAL GAME SPECIES HARVEST BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 0 TO 10 MILES DIRECTION WATERFOWL WHITETAIL DEER WILD TURKEY N 28 0 NNE 69 0 NE 69 0 ENE 69 0 E 69 0 ESE 69 0 SE 50 0 SSE 34 0 S 22 0 SSW 9 0 SW 5 0 WS'W 8 0 W 9 4 0 WNW 10 4 0 NW 10 4 0 NNW 13 4 0 TOTAL 543 34 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

4 TABLE 2.1.3-4 (continued)

ANNUAL GAME SPECIES HARVEST BETWEEN ZERO AND FIFTY MlLES OF THE SHNPP 10 TO 20 MaLES DIRECTION WATERFOWL WHITETAIL DEER WILD TURKEY N 15 16 NNE 142 8 NE 199 4 ENE 189 4 E 217 4" ESE 167 5 SE 87 2 SSE 88 2 S 88 0 SSW 31 0 SW 0 0 WSW 7 0 22 13 1 23 13 1 22 13 1 13 18 1 TOTAL 1310 116 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

TABLE 2.1.3-4 (continued)

ANNUAL GAME SPECIES HARVEST BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 20 TO 30 MILES DIRECTION WATERFOWL WHITETAIL DEER WILD TURKEY N 3 32 NNE 55 25 NE 337 6 ENE 343 6 E 198 14 ESE 131 18 SE 144 5 SSE 152 12 S 154 8 0 SSW 112 4 0 SW 24 8 0 WSW 34 13 1 41 24 44 21 93 25 0 42 TOTAL 1865 263 12 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

TABLE 2.1.3-4 (continued)

ANNUAL GAW SPECIES HARVEST BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 30 TO 40 MILES DIRECTION WATERFOWL WHITETAIL DEER WILD TURKEY N 4 50 NNE 117 59 NE 295 35 ENE 432 14 E 178 24 0 ESE 176 24 0 SE 148 39 0 SSE 336 99 0 S 370 105 SSW 261 23 SW 70 14 WSW 65 16 W 19 34 2 WNW 91 30 3 NW 200 27 8 NNW 57 51 4 TOTAL 2819 644 20 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

TABLE 2.1.3-4 (cont:inued)

ANNUAL GAi4E SPECIES HARVEST BETWEEN ZERO AND FIFTY MILES OF THE SHNPP 40 TO 50 MILES DIRECTION WATERFOWL WHITETAIL DEER WILD TURKEY 165 84 13 92 99 1 54 91 1 56 65 0 E 246 26 ESE 187 25 SE 114 76 SSE 309 114 W 510 118 SSW 531 30 SW 94 32 WSW 103 125 W 7 50 1 WNW 225 28 1 NW 416 20 5 NNW 115 97 22

, 3224 1080 47 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

TABLE 2.1.3-4 (cont:inued)

ANNUAL GAME SPECIES HARVEST BETWEEN ZERO AND FIFTY MILES OF THE SHNPP CUMULATIVE TOTALS SECTOR WATERFOWL WHITETAIL DEER WILD TURKEY 00 TO 10 543 34 00 TO 20 1853 150 00 TO 30 3718 413 17 00 TO 40 6537 1057 37 00 TO 50 9761 2137 Basis: References 2.1.3-3, 2.1.3-4, and 2.1.3-5

ER Question 470.2 (Section 2.1.3)

On Table 2.1.3-2 (page 2.1.3-5) report the data (Agricultural Production of Major Crops) in uniform metric units kilograms.

Response: The table was updated and revised to report the data in kilograms as requested. Bushels of soybeans were converted to pounds by the conversion factor of 60 pounds of soybeans per bushel. Bushels of corn were converted to pounds of corn using the conversion factor of 56 pounds per bushel. These conversion factors were obtained from the N.C. Crop and Livestock Reporting Service of the N.C.

Department of Agriculture. All values were then converted from pounds to kilograms. The revised tables are provided with the response to ER Question 470. 1.

ER Question 470.3 (Section 2.4.2)

The print on Tables 2.4.2-11 through 16 and on Table 2.4.2-21 is too small to read. Provide revised tables which are readable.

Response: Revised Tables 2.4.2-11 through 16 and 2.4.2-21 are attached.

SHNpp ER Tabl~ 2./4,2-ll RESERVOIR ANALYSIS NORMAL OPERATIONS ~L POUR UNITS CRITICAL PERIOD FEBRUARY 92> - REBRUARY 1926 MAIN RESERVOIR OPERATIOH CORR, FOR MATER USE AUX. MATER USE CREEK MAIR%AUX NET CREEL AVAIL NAT DIR AUXIMAIH FORCED 6 IHFInu DA R/O INIMM ASOVE RML AREA NET EVAP NET EVAP ~ STOR USE SIOR, USE EHD Mo.

MAIN + AUX INHgW NET EVAP DA~79. 5 64.00/79. 50 SEEPAGE (2) 'ee f f efc cfog hept Aeyt Aeyt fn. fn. i Ft Ace AeFt Aeyt Aeyt Ft Ac Aeyt A. Horst Monthly Evop. Cond ft foe 20314 3375 2.44 1. 70 0. 74 250 317 20 220.0 4118 254 274 3648 0 0 220.0 4118 0 1925 88. 7 71.4 5.0 66.4 3682 16632 18414 22194 3835 4.41 2.31 2.10 250 317 55 220.0 4118 721 776 C&11 0 0 220.0 4118 831 82.7 66 ' 5.0 61.6 3780 t

19362 3874 6. 28 2.57 3.71 250 317 98 220.0 4118 1273 1371 5245 0 220.0 4118 2812

57. 1 46.0 5.0 41.0 .2433 16929 13563 16176 4223 7.70 4.11 3.59 250 I

'17 9$ 220.0 CDS 1232 1327 5550 0 220.0 4118 2937 59.1 47.6 5.0 42.6 2613 5243 8.21 2.60 5.61 2$ 0 317 148 220.0 4118 1925 2073 7316 465C 4654 218.9 39S9 2079<>>

18. 4 14.8 5.0 9. 8 583 2079 2662 2673 3275 5585 9.23 I ~ 98 7.25 250 ~'17 192 218.9 3959 2392 2584 8168 4893 Ssae 217.9 3817 26130) 18.4 14.8 5.0 9.8 602 5.0 11.7 716 3C65 4181 $ 467 8.51 3.42 5.09 250 '17 134 217.9 3817 1619 1753 7221 3040 12587 217. 2 3726 346sfs) 20.7 16.7 "407 4.36 1.94 250 317 51 217 2 3726 602 653 4831 2652 15239 216.5 3643 2079~3) 8.3 6.7 $ .0 1.7 100 2079 2179 6.30 14 416$ 4.64 2.16 2.48 250 317 66 216.$ 3643 753 819 4983 4969 20208 215.1 347S 0 6.5 5.2 $ .0 0.2 14 0 2461 3807 2.99 2.56 0.43 250 317 12 215.1 3478 125 137 3943 1482 21690 214.6 3428 20~<>>

14+2 11.4 5.0 6.4 382 2079 24.0 19.3 5.0 14.3 879 2475~ ) 3354 3662 I 54 2.70 -1.16 250 317 -31 214.6 3428 -331 3300 -54 21636 214.7 3430 4140 8217' 12357 3625 1. 42 4.29 2,87 2SO 317 -76 214.7 3430 820 -896 2729 9628 12008 217. 3 3744 el 170) 1926 90.0 72.5 5.0 67.$

16335 20432 3375 2.44 1 ~ 70 0.74 250 317 20 217..3 3744 231 251 3625 12008 0 220.0 4118 IIS36

98. 0 78.9 5.0 73.9 4097 I

8. HoteLtl Monthly Evop Cond ftfon

88. 71 ~ 4 5.0 66.4 3682 16632 20314 3097 2.08 1.70 0.38 2SO '17 10 220.0 411S 130 ICO 3237 0 220.0 4118 0 1925 F 7 3656 3.91 2.31 1. 60 250 ,'17 42 220. 0 4118 549 591 42C7 0 220.0 4118 467 M el.l 66. 6 5.0 61.6 3780 IS414 22194 78 220.0 4118 1090 4893 0 220.0 4118 2460 41.0 16929 19362 3803 5.52 2.57 2.95 250 317 1012 0 57.1 46.0 5.0 2433 ,

13563 16176 4106 6.77 F 11 2.66 250 317 70 220.0 4118 913 983 S089 ;0 0 220.0 4118 2476 59.1 47.6 5.0 42.6 2613 18.4 14.8 5.0 9.8 583 2079 2662 5103 l. 28 2 '0 4.68 2$ 0

(

317 124 220.0 4118 1606 1730 6833 C171 4171 219.0 3973 2079~3) 18.4 14.8 5.0 9.8 602 2673 3275 $ 32$ 7.23 I~ 98 5.25 250 317 139 219.0 3973 1738 1877 7202 3927 8098 218.2 Ses9 2673~3) 20.7 16.7 5.0 11 ~ 7 716 3465 4181 5285 6.6& 3.42 3.26 250 '17 86 218.2 3859 1048 1134 6420 2239 10336 217.7 3465~3>

8.3 6.7 5.0 1. 7 100 2079 2179 4024 5.50 l. 14 250  ;

317 217.7 3794 360 390 4415 2236 12572 217. 2 3727 2079 14 3897 3.55 2.16 1. 39 250 317 37 217.2 3727 432 469 4365 4351 16923 216.1 3588 0 6' 5.2 5.0 0.2 14 0 14.2 11.4 5.0 6.4 382 2079 2461 3561 2.31 2.56 -0.2S 250 '17 216.1 3588 -75 -82 3480 1019 17942 215.8 3555 2079' 1926 D 24.0 19. 3 5.0 14.3 879 2475~ ) 3354 3388 I 33 2.70 -1.37 250 317 215.8 3555 -406 -C42 29C6 -CO8 17S34 215.9 Ssds 2475<3) 8217<4) 3388 1.19 4.29 <<3.10 250 317 82 215.9 3568 -922 1004 2384 -99/3 7561 218. 3 3875 8217' 90.0 72.5 5.0 67.5 41CO 12357 20432 3097 2.08 1.70 0.38 250 317 10 218.3 3875 123 133 3230 -7561 0 220.0 4118 6694 98.0 78 ' 5.0 73.9 4097 1633$

NOTES: (1) Excluding Direct Rainfall.

(2) Assumes Auxiliary Reservoir maintained at Normal Water L vel by pumping from Hain Reservoir.

t (3) Limited to available makeup.

Amendment No. l (4) Limited by required filling of New Hope Reservoir.

i 2./4.2 36

V'4 A'1 C:

~ ys SHNPP ER Table 2.4.2-12 RESERVOIR ANALYSIS NORMAL OPERATlON ALL POUR UNITS CRITICAL PERIOD MARCH 1933 APRIL ]934 MAIN RESERVOIR OPERATION CORR. FOR MAKEUP HAIN + AUX. NET CREEK FROM TOTAL WATER USE INFLAN DA R/0 INFLOW ASOVE CAPE AVAIL~ NAT. DIR NET

"" R LSE AUX. RES. MAIN RES ~ AUX. + NAIN FORCED 4 INCR Dhi79.5 64.00/79 50F SEEPAGE HAIN W AUX. INFLOW MAIN RES ~ EVAP ~ RF EVAP ~ ~AREA CONS NET EVAP. hET EVAP ~ h~ EVAP.

'TOR.

AlP USE STOR. USE D IXI.

MO. cfs cfs cfs cfs hcFt AcFt AcFt ln. ln. In.

F,(2)

Ft Aes Use-Acpt Ft Acs AcFt AcFt pr Aept Ft Ac A,F."'2633 Worst Nonthly Evsp. Condltlon 1933 91.6 73.7 5.0 250, 220,0 4118 824 887 4722 p 220.0 4118 503 M 68.7 4219 18414 3835 4.41 2. 01 2. 40 317 63 122.1 98.3 5.0 93.3 17820 250 317 220.0 4118 326 351 4225 220.0 4118 0 A 5542 23362 3874 6.28 5,33 0.95 I 6086 p 0 220.0 4118 4594 H 36.4 29.3 5.0 24.3 1492 12078 13570 4223 7. 70 2 66 5 04 250 317 220.0 4118 1730 1863 2502 7745 5471 5471 218.8 3935 2079( )

J 10.3 8.3 5.0 3.3 196 2079 2275 5243 8. 21 1.44 6.77 250 317 179 220.0 4118 2323 217.2 3725 693'3)

J 11.2 9.0 5.0 4.0 247 693 940 5585 9. 23 2.12 7.>> 250 317 188 218. 8 3935 2331 2519 8104 7165 12635 6306 v -8037 4598 218.9 3961 13464(3)

A 24.0 19.3 5.0 14.3 879 13464 14343 5467 8.51 6.02 2.49 250 317 66 217.2 3725 773 839 S 15.2 12.2 5.0 7.2 430 7920 8350 4177 6.30 0.83 5.47 250'17 144 218.9 3961 1805 1949 6127 -2223 2375 219.4 4030 7920(3) 0.9 1358 5523 5470 7845 218.3 3866 0 0 7.3 5.9 5.0 54 0 54 4165 4.64 0.89 3.75 250 317 99 219.4 4030 1259 N 4.3 3.5 5.0 -1.5 -91 0 -91 3807 2.99 I ~ 48 1.51 250I 317 40 218. 3 3866 487 527 4333 4425 12270 217 ' 3736 0 3871 3669 15939 216.3 3621 0 D 10.3 8.3 5.0 3.3 202 0 202 3662 1.54 0.92 0.62 250 317 16 217.3 3736 793 209 215.7 1287(3) 1934 J 9.3 7.5 5.0 2.5 153 1287 14CO 3625 1.42 I ~ 77 -0. 35 250 317 216.3 3621 106 -115 3510 2071 18009 3552 u88(3)

F 17.2 13.8 5.0 8.8 490 >>88<4) 1678 3375 2.44 3.09 -0.65 250 -17 215.7 3552 -192 209 3165 1487 19496 215 ' 3503 317

-181 -197 3638 -18086 1410 219. 7 4063 18117 M 79.2 63.8 5.0 58.8 3607 18117 21724 3835 4.41 5.03 -0.62 250 317 -16 215.3 3503 5038 -1410 0 220.0 4118 242 A 136.0 109.5 5.0 104.5 6206 17622 23828 3874 6.28 3.09 3.19 2SO 317 84 219. 7 4063 1080 1164 B. Nornsl Monthly Evsp. Cond( t(on 1933 M 91.6 73. 7 5.0 68.7 4219 18414 22633 3656 3.91 2.01 1.90 220,0 4>>8 652 702 4358 220.0 4>>8 139 250 317 A 122.1 98.3 5.0 93.3 5542 17820 23362 3803 5.52 5. 33 0. 19 250 317 5 220.0 4>>8 65 70 3873 220.0 4>>8 0 5625 0 0 220.0 4118 4133 M 36.4 29.3 5.0 24.3 1492 12078 13570 4106 6.77 2.66 C.>> 250 317 109 220.0 4118 1410 1519 J 10.3 8.3 5.0 3.3 196 2079 2275 5103 7.28 1.44 5.84 154 220.0 4>>8 2004 2158 7261 4987 4987 218.9 3949 250 317 217 ~ 5 3769 693'"

J 11.2 9.0 5.0 4.0 247 693 940 5325 7.23 2.12 5;ll 250 317 22p.p 4>>8 1682 1817 7142 6202 11189 5510 8833 2356 219.4 4031 13464( )

A 24.0 19. 3 5.0 14.3 879 13464 IC343 52&5 6.68 6.02 0.66 317 17 218 9 3949 224 250 S 15.2 12.2 5.0 7.2 430 7920 8350 4024 5.50 0.83 4.67 123 217.5 3769 1569 1692 5716 -2356 0 220.0 4>>8 7642 250 317 4880 4826 4826 218 9 3954 0 0 7~3 5.9 5.0 0.9 54 0 54 3897 3.55 0.89 2.66 25C 317 70 219. 4 4031 913 983 3948 8774 218.1 3840 0 N 4.3 3.5 5.0 -1.5 -91 0 -91 3561 2.31 1.48 0.83 250 317 22 220.0 4118 273 295 3856 3530 3328 12102 217.3 3741 0 D 10.3 8.3 5.0 3.3 202 0 202 3388 1.33 0.92 0.41 25( 317 11 218.9 3954 131 142 216.9 3687 1287(3) 1934 J 9.3 7.5 5.0 2.5 153 1287 1440 3388 l. 19 1. 77 W. 58 25( 317 -15 218.1 3840 -181 -196 3192 1752 13854

)

17.2 13.8 5.0 8.8 -I Ol -310 -337 2760 1082 14936 216 ' 3653 1188 F 490 1188 1678 3097 2. 08 3 09 25( 317 . -27 217.3 3741

~

I 79.2 63.8 5.0 58.8 3607 1.>>7<4) 21724 3656 3.91 5.03 -l. 12 -30 216.9 3687 341 -371 3285 -14936 0 220.0 4>>8 14614 25(. 317 4701 220.0 4118 0 A 136.0 109.5 5.0 104.5 6206 17622 23828 3803 5.52 3.09 2.43 250 317 216.6 3653 834 NOTES: (1) Excluding Direct Rainfall.

(2) Assumes Auxiliary Reservoir maintained ne at a Normal orma Water .Level by pumping from Main Reservoir. Amendment No. l (3) Limited to available makeup. I (4) Limited by required filling of New Hope Reservoir 4 2-37

SHNPP <<

I Table 2.4 <<2-l3 RESERVOIR ANALYSIS

~

NORMAL. OPERATIONS

- LL FOUR UNITS CRITICAL PERIOD MA~ > - APRIL 1942 OPERATIOH TOZAL USE l1ATER USE AUX+ RES e'ES.

'QTER HAIR + AUI. SET CREEE 'ESERVOIR PIDU'~

INFIARf DA R/0 IRFLNI AemtE AVAIL. EVAP ~ RAT. DIR HAIN RES AUE. + HAIK m.

RlD Ho AREA CAPE FEAR mr STOR. USE STOR. USE oh~79.$

cfc

64. 00/79. 50 efo SEEPAGE efo ef c

+ AUZ.

AcPt Aeyt EVAP fa. fa.

SET EVAP.

n" 00RS.

Uoc-hcyt hco hcFt Evhpo RET EVAPo JF Ac M, L s a v F"'>. Coaelt foa 6300 5599 5599 218.7 3931 0 1941 H 20. 4 16. 4 5.0 1 l. 4 101 0 701 4223 7.70 2.08 250 317 . 148 220 4118 1929 2077 g 43s6(3) 69S6 I 2032 7631 218. 3 3813

18. I 14.6 5.0 9.6 $ 69 4356 492$ 5243 8.21 3.31 4.84 250 12e 2i8.7 3931 1586 1714

-$ 26 569 5016, 7631 0 220. 0 4118 418 253. 7 204.2 5.0 199+2 12229 9999 22228 $ 585 9+23 10. 86 -1.63 250 317 218. 3 3873 4118 1133 1866 1333 I 5480 5480 218.8 3935 S94")

31.1 2S 5 5.0 20.5 1259 594 1853 5467 8.$ 1 3.46 s.os 317 133 220. 0 1690 5867 3498 8978 218.0 3834 2118(')

10 2 8.2 5.0 3. 2 191 2178 2369 4177 6. 30 1.53 4.77 317 218.8 393$ 1564 ~

938 5102 4960 13938 216 9 368$ 0 9.1 7.3 5.0 2.3 143 0 143 4165 4.64 1.93 2.71 317 72 218.0 3834 866 1 821 4634 4606 18544 215 6 353$ 0 6.8 5.5 5.0 0.5 28 0 28 3807 2 +99 0.51 2.48 250 317 66 216.9 3685 761 I 693(3) 693( ) 250 317 215 e6 353S ~14 2741, -273 18271 2157 3$ 44 D 53.3 42.9 5.0 37.9 2327 3020 3662 1.54 2.8$

0(4) 3544 41 3667 2407 20618 215.0 3462 0 1942 J 31.7 25. 5 5.0 20.5 1259 1259 362S 1.42 1.29 O.is 317 3 215. 7

%684 13994 216. 8 3683 712e(3)

71. 4 51. 5 5.0 52.5 2909 7128( ) 10037 331$ 2.44 2.51 ~.07 250 317 215+0 3462 20 22

'353 250 I

317 216 8 3683 -193 210 362S -13994 0 220.0 4118 10598 H 148. 3 119 4 5.0 114.4 7021 18414 25435 383S 4.41 5.04 17 4118 1579 1701 5574 0 0 220.0 4118 2782 A 64. 6 52. 0 5.0 47.0 2792 12474 15266 3874 6,28 1.68 4 6o 250 317 122 220+0 263.67 Hoathly Eve . Coahitfoa 1941 20.4 16. 4 5.0 11 4 701 0 701 4106 6 '7 2.08 4.69 250 317 124 220 4118 1609 1133 5839 ) 5138 $ 138 218. 8 3945 0 250 317 103 218.8 3945 1285 1388 6492 I i567 6705 2ie.s 3899 43s6(3) 18.1 14,6 5.0 9.6 569 4356 4925 5 103 7 28 3.37 3.91 2$ 3.7 204+2 5.0 199.2 12229 9999 22228 532S 7 23 10 86 -3.63 250 317 -96 218.5 3899 -1180 1276 4050

)

&705 0 220.0 C118 0 2$ 0 311 85 220.0 4118 110$ 1190 647$ 4622 4622 218.9 3960 s94(3) 31;7 25.5 5.0 20+5 1259 594 1853 5285 6.68 3.46 3 ~ 22 (

1.53 250 317 10$ 218.9 3960 1310 141S SC39 f 3070 7692 218.3 3871 2178(3)

10. 2 8.2 5.0 3. 2 191 2118 2369 4024 5.50 3. 97 9.1 7.3 5.0 2. 3 143 0 143 3897 3+SS 1. 93 le62 250 311 218.3 3871 523 4C62 4320 12011 217. 3 3744 0 6.8 5.5 $ .0 0.5 28 0 28 3561 2.31 0.51 1. 80 250 317 48 217 3 374C $ 62 610

~'170,',

4142 16153 216.3 3614 0 693(4) -3. 06 317 216.3 3614 %21 2386 I %34 15519 216.4 3634 693(3) 53.3 42,9 5.0 2327

'7.9 3020 3388 1 ~ 33 250 1942 31.7 25.$ 5.0 20.5 1259 0(4) 1259 3388 1.19 1. 29 &.10 250 317 216.4 3634 -30 33 335$ Ii 2096 17615 215.9 3566 0 2.08 2.51 0.43 215.9 3566 128 2958 I -7079 10536 217 7 3788 7128(3) 71.4 syo 5 5.0 . 52.5 2909 712K 10037 . 3097 250 317 148.3 119.4 $ .0 114.C 7021 18414 25435 3656 3e91 5.04 - l. 13 250 317 217.1 3788 -357 -387 3269 ( -10536 0 220.0 4118 6784 64.6 52.0 5.0 47.0 2792 12474 15266 3803 5.52 1.68 3.84 250 317 101 220.0 4118 1318 1419 5222 i 0 220.0 4118 2430 Z53.35 NOTES: (1) Excluding Direct Rainfall.

(2) Assumes Auxiliary Reservoir maintained at Normal Rater Le vel by pumping from Main Reservoir.

(3) Limited to available makeup; (4) Limited by required filling of New Hope Reservoir. Amendment No. 1 2.4,2~3S

I I

'A

'f e

SHNPP ER Table 2.4 2 l4 f

RESERVOIR ANALYSIS NORMAI. OPERATIONS ALL FOUR UNITS CRITICAL YEAR 1925/26 iWORST MONTHLY EVAP<< CONDITIONS MONTHS OF NO"EMBER AND DECEMBER CORR POR MAIN RESERVOIR OPERATION NAI!HAUX MET CREIX lROI TOTaL FORCED MAT MATER USE AUX RES mum

~~

AEWE CAPP AVAIL~37 EVAP DIE NET EVAP, DUE TO NET EVAP MAIN REB ~ AUX@BAIN STOR.

DA R/0 IMFLO "> 64.00/79. SO SEEPACE MAIN+AUX PEAR INFLOW MAIN RES MAIN RES ~ RF <<NAT. KV-RP m.~ 7 AREA CONS. USE AREA NET EVAP NET EVAP, STOR USE RllL AREA MONIH

~VFA ~f ~AFt ~ AtFt ~ln ~n << A P <<P A P <<F AtFt Ft AC OCT. 25 31 20208 215 ~ I 3478 NOV 2$ I I 3 I 0 5.0 -4.0 -8 0 -8 119 0.10 0.38 0. 28 250 317 -7 215 I 3478 81 38 20246 215.1 3477 2 7.9 6 4 $ .0 I4 3 198 201 119 0 09 0.86 -0.77 250 317 20 21$ I 3477 223 -243 -124 32$ 19921 21$ 2 3488 6.0 4.8 5 0 -0.2 0 0 123 0.09 0.00 0.09 250 317 215.2 3488 26 28 152 152 20073 21$ .1 3483 4 5.1 4.1 5.0 0,9 -2 130 0,14 0,00 0,14 250 317 21$ I 3483 41 4$ 174 176 20249 21$ I 3477 5 4.5 3.6 $ .0 -1.4 -3 3 130 0,14 0,00 0.14 250 317 215 1 3477 41 45 174 177 20426 21$ ,0 3471 6 4,5 3.6 5.0 1,4 3 0 -3 117 0 11 0,02 0,09 250 317 215.0 3471 26 28 145 148 20$ 74 215.0 3466 7 2,9 2 3 5,0 -2,7 5 0 5 114 0.08 0.06 0,02 250 317 215 0 3466 6 7 126 20700 21$ .0 3462 8 4,0 3<<2 5.0 -1,8 4 ~ 0 ID 0.08 0,31 0.23 t

2$ 0 317 6 21S.O 3462 66 72 48 20748 214.9 3460

'9 7 2 $ .8 5,0 0.8 2 0 126 0 10 0,00 0,10 250 317 214 9 3460 29 32 157 1$ 6 20904 214.9 34SS 10 5.9 4,7 5 0 0<<3 0 0 130 0,12 0.00 0.12 250 317 214,9 345$ 35 38 168 168 21072 214 ~ 8 3449 ll 10.3 8.3 5 0 3.3 7 0 7 f37 0 14 0.00 0. 14 250 317 214 8 3449 40 44 181 174 21246 214. 8 3443 12 8.7 7,0 $ .0 2.0 4 198 202 135 0.14 0.64 -0.50 250 317 13 214.8 3443 -143 -156 22 -224 21023 214 9 34SI 13 9.4 7 6 50 2.6 5 99 104 137 0.1$ 0.00 0. 15 2SO 317 214.9 3451 43 47 21103 214. 8 3448 I

14 15.7 12.6 5.0 7,6 15 0 15 134 0. 13 0.00 0,13 250 317 214.8 3448 37 40 17$ 160 21262 214. 8 3442 15 8.4 6 8 5.0 1,8 3 0 3 128 0.07 0.06 0.01 250 317 214.8 3442 3 3 131 128 21390 2 14.7 3438 16 13o3 10 7 5.0 5,7 11 198 209 135 0.12 0.03 0.09 250 317 214.7 3438 26 28 163 - 46 21344 214. 8 3440 17 11.6 9.3 5,0 4,3 9 396 405 128 0.08 0.00 0.08 250 317 214.8 3440 23 2$ 153 -2$ 2 21092 214. 8 3448 18 9.4 7 6 5.0 2.6 5 0 132 0,07 0.00 0.07 250 317 214.8 3448 20 22 154 149 21241 214. 8 3443 19 6.7 5 4 5.0 0.4 0 134 0. 11 0.03 0.08 2$ 0 317 214.8 3443 23 2$ 159 158 21400 214.7 3438 20 8.8 7,1 5,0 2 I 4 396 130 0.08 0,02 0.06 250 317 214. 7 3438 17 19 149 251 21148 214. 8 3446 i

21 4.9 3 9 $ .0 II~ 2 594 $ 92 132 0.10 0.00 0.10 250 317 214.8 3446 29 32 163 -429 20720 214 9 3461 22 3,8 3,1 $ .0 -19 -4 0 -4 130 0.08 0.00 1 0 08 250 317 214.9 3461 23 2$ 155 159 20879 214 9 3456 1

NOTESI (1) Assumed only 50% of daily inflow based on Deep River at Ramseur-(2) Limited by required filling of New Hope Reservoir'3)

Excluding Direct Rainfall.

(4) Assumed Auxiliary Reservoir maintained at mini+i water level by pumping from Main Reservoir. Amendment No. l 2.4.2-39 l

1 HNPP ER Table 2.'4.2-14 (Cont'd)

CORE FOR MAIN RESERVOIR OPERATION MAIRHLUX NET CREEN TOIAL NAT, NILTER USE hlJX, RES INCR, CREEK DA R/0 INFLCM ABOVE CAPE~ 7 AVAlr.~37 DIR AXT EVAP; TO NET KVAP MAIN RES AUXtWLIN FORCED + SIOR r INFu 64.00/79 F 50 MAIN+AUX INFLOU MAIN RES MAIN RES+ ~RAT EV RF RNI.<4> AREA hET EVAP.

MONTH i VEIII ~ ~f 8EEPACE

~h ~In ~l ~F AC CONS USE RNL FV AREA NET EVAP AcFc NET EVAP.

~AT USE

~At STOR

~A USE AC NOV 25 23 10,1 8,1 $ ,0 3.1 130 0,09 0.00 0.09 250 317 214 9 3456 26 28 1$ 8 1$ 2 21031 214,9 3450 24 5.9 4.7 5.0 0 3 130 0.10 0.00 0,10 250 317 214,9 34SO 29 32 161 162 21193 214 8 3445 1

25 5.$ 4.4 $ .0 -0.6 13$ 0 14 0.00 0,14 250 317 214,8 3445 179 180 21373 214,7 3439 26 4.2 3i4 5.0 -1,6 3 -3 117 0,09 0.12 -0.03 I

250 317 214 7 3439 9 10 108 lll 21484 214,7 343$

27 9.4 7.6 $ .0 2.6 108 0 02 0 03 -0.0) 250 317 214,7 3435 -3 3 105 100 21583 214.7 3432 28 $ .3 4.3 5 0 0,7 10$ 0 00 0.00 0,00 250 317 214.7 3432 10$ 106 21690 214,6 3428 29 2,9 2+3 5.0 2 7 -5 -5 114 -0.01 0,00 -0.0) 250 317 214 6 3428 3 -3 lll 116 21806 214.6 3424 30 9.4 F 6 $ .0 2.6 124 0 02 0.00 0.02 250 317 214.6 3424 130 12S 21931 214 6 3420 I

DEC. 2$ 1 6.4 5 2 5,0 0,2 123 0,04 0 03 0.01 250 317 214.6 3420 126 126 220S7 214. 5 3415 I

2 6.4 $ .2 $ .0 Oo2 114 0.08 0.76 W. 68 250 317 18 214,$ 3415 -194 212 98 -98 21959 214. 6 3419 I

3 6.2 $ .0 5,0 0.0 106 0.02 0 01 0,01 250 317 214 6 3419 109 109 22068 214,5 341$

I 4 6.2 $ .0 $ .0 0,0 114 0,00 0 00 0.00 250 317 214 5 3415 0 114 114 22182 214,5 3411 5 $ .1 5.0 0 9 2 2 117 0,06 0.05 0.01 2$ 0 317 214,5 3411 3 120 122 22304 214.5 3407 I

6 4.0 3,2 5.0 -1. 8 -4 -4 117 0,0$ 0 00 0.0$ 250 317 214.S 3407 14 15 132 136 22440 214.4 3402 7 9.1 7.3 5,0 2.3 5 115 0 08 0 08 250 317 214,4 3402 23 140 13$ 22575 214,4 3398 8 6.9 5.6 5,0 0.6 103 0.03 0,00 0,03 250 317 214.4 3398 112 111 22687 214 3 3394 9 6.3 $ ,1 5,0 0.1 103 0,00 0.00 0.00 250 317 214.3 3394 103 103 22789 214 3 3390 I

10 6.9 5.6 5,0 06 115 0.04 0.00 0.04 250 317 214 3 3390 12 127 126 22916 214.3 3386 I

11 6,3 $ ,1 $ .0 0,1 123 0.06 0,06, 250 317 214 3 3386 17 19 142 141 230S7 214 2 3381 12 4.9 3.9 5 0 2 132 0.08 0. 00 0.08 250 317'17 214.2 3381 23 25 157 159 23216 214.2 3376 13 3.4 2,7 5,0 2,3 4 128 0.04 0.00 0 04 2$ 0 214.2 3376 12 140 14$ 23361 214.1 3371 14 9 8 7 ' 5,0 2+9 124 0.04 0.00 0.04'0.06 250 317 214.1 3371 12 136 131 23491 214.1 3366 15 6.9 5.6 5.0 0.6 11$ 0.06 0.12 250 317 -2 214.1 3366 -17 19 96 95 23587 214,1 3363 16 6.2 5.0 5.0 0,0 114 0,04 0 03 0.01 250 317 214,1 3363 117 117 23704 214.0 3359 17 6.2 5,0 5.0 0.0 11$ 0.01 0 13 250 317 -3 214 0 3359 -37 78 78 23782 214,0 3356 18 6.4 5.2 5.0 0.2 0 121 0 04 0.00 250 317 214 0 3356 12 133 133 23915 214.0 3351 19 4.5 3.6 5.0 -1,4 3 128 0.07 0.42 0. 35I, 2$ 0 317 214.0 3351 98 107 21 24 23939 213.9 33S1 20 7.1 5.7 50 0,7 132 0.08 0 38 -0. 30 250 317 -8 213 9 3351 - 92 40 39 23978 213.9 3349 NOTES: (1) Assumed only 50% of daily inflow based on Deep ver at Ramseur.

I (2) Limited by required filling of New Hope Reservoir, (3) Excluding Direct Rainfall.

(4) Assumed Auxiliary Reservoir maintained at mini~'ater level by pumping from Main Reservoir. Amendment No.

Glum W 2

4.2-4O 1

0

~ "g v

lA

~ I jl3 SBNPP ER Table 2..2-14 (Cont'd)

CORE FOR NAIN RESERVOIR OPERATION TOIAL MATER USE AUX, RES INCR, NhllHAUX PFXFI Dh R/0 INFLCM AEWE CAFE<" AVhld37 DIR 1ET EVAP. To NET EVAP NAIN RES, AUX%BAIN FORCED +

I NAIRthUX INFIAIM MAIN RES, NAIN RESP RF ~ NAT, B RF an.<4> AREA CONS USE AREA NET EVAP, NET EVAPA NET EVAP, USE SIOR. USE 64.00/7 9. 50 8EEFACE

~c ~i ~hc ~h ~ln ~n n AC Ac c Ac ~A ~AP

!P,

~AP ~A 4.7 0 11$ 0.01 0.63 250 317 -16 213 9 3349 173 189 -74 23894 214.0 3352 21 12 ~ 1 9.7 SAO 9 9 40,6 80 396 476 124 0.05 0.14 -0.0) 2$ 0 317 2 214.0 3352 25 27 96 380 23514 214, 1 3365 22 56.6 45.6 5 0 669 0.06 0.00 OAO 250 317 214, I 3365 17 19 142 -$ 26 22988 214. 2 3383 23 53,0 42,7 $ .0 37.7 75 594 124 628 126 o.oo 0. 250 317 214 2 3383 11 12 138 -489 22498 214,4 3400 24 27,4 22.1 $ .0 17,1 34 594 14,3 5,0 93 18 495 $ 13 123 OA09 O.OO OAO 2SO 317 214,4 3400 26 28 151 -363 22136 214.5 3413 25 17.8 11,3 5.0 6.3 12 396 408 114 0.06 0.00 0.0 2$ 0 317 214, 5 3413 17 19 133 276 21860 214.6 3422 26 14,0

$ .0 4.2 8 0 8 112 0.05 0 00 0.0 2SO 317 214.6 3422 14 15 128 119 21979 214.6 3418 27 11,4 9 2 14,1 5,0 9.1 18 0 18 106 0,00 0.00 250 317 214.6 3418 0 0 106 88 22067 214.5 3415 28 17A5 0.05 0.0 250 317 214.5 3415 14 15 13$ 127 22195 214.$ 3411 29 10,7 8,6 $ .0 3.6 7 0 7 119 22300 214.$ 3407 30 IS.O 12 ' 5.0 14 0 14 110 0.03 0,00 0.0 250 317 214 5 3411 9 10 119 105 22412 214 4 3403 9' 5,0 4.2 0 117 0.01 0.00 0,0 2$ 0 317 214.5 3407 3 3 120 112 31 11.4 8 8 NOTES: (1) Assumed only 50% of daily inflow based on Deep eI at Ramseur.

(2) Limited by required filling of New Hope Reservoir (3) Excluding Direct Rainfall.

(4) Assumed Auxiliary Reservoir maintained at minim water level by pumping from Main Reservoir. Amendment No. l

.4.2-4>

0 O.

SHNPP ER Table 2.4.2 15 NORMAL OPERATION

- ALL FOUR UNITS 100- YEAR RN PERIOD DROUGHT CORR. FOR NET INFLOL( DIR. NET EVAP. 'S ~ OL'ERA IN MAIN RESERVOIR OPERATIO'( REQUIRED

~ NAT. EVAP. ((A'iXR USE A(D( TOTAL TOTAL R((L 8 RES. PUMPINC FROM INFLO(( MAIN + A(D(. ABOVE MAIN + AVAILABLE R.F. RES D.A.~79.5 D.A, R/0 SEEPACE A((X. BL'( C E FEAR") FNFLO(((2) R.F. 8('E To NET EVAP. MAIN RES. MAIN RES. MATER USE STORAGE END OP AREA CAPE FEAR RIVER (3) 64/79 ' AREA CON. USE NET EVAP FORCED EVAP MAIN + AUX. USE MNIN cfs cfs cfs AcFt AeF t AcF t ( .. I . (

I scs AeFt. sc AcPt AcPt. AcPt AePt AeFt AcFt 28.2 5.0 23.2 1423 9009 10432 7.70 2.16 5.54 250 317 146 220.0 4118 1901 5700 7747 0 0 220.0 4118 6324

51. 6  !

12.5 3.6 5.0 -I 4

~ - 82 6930 6848 8.21 1.17 7.04 25(( 317 220.0 4118 2416 S630 8232 1384 1384 219.7 4064 6930 12.5 3.6 5.0 -1.4 - 85 1584 1499 9.23 I 72 7.51 I

317 198 219.7 4064 2543 5970 8712 7212 8596 218.1 3845 1584(4)

-1.4 495 410 8.51 4.88 3.63 25(i 317 218.1 3845 1163 5870 7129 6718 15315 216. 5 3641 495( )

12.5 3.6 5.0 85 I so 0 -297 6.30 0.67 5. 63 25(I 317 149 216,5 3641 1708 5590 1447 7744 23058 214.2 3381 0 4.1 o.n 5.0 297

-s.n -307 -307 4 ~ 64 072 3.92 250 317 104 214.2 3381 1104 5570 6778 7085 30143 211.9 3139 0 4.1 n.o s.n 0 t

-S.n 0 -297 2.99 1.20 1.19 2SDI 317 47 211.9 3139 468 5250 5765 6062 36206 209.9 2936 0 4.1 0.0 S.n 297 209.9 2936 193 5170 5384 5295 41SOO 208.0 2756 396(4) 4.1 n.o 5.0 -5.0 -307 396 89 1.54 0.75 0.19 25(m 317 21 1.42 1.44 &.02 25(( 317 1 208.0 2756 5200 5195 2582 44083 207.1 2662 1190 51.6 28.2 5.0 23.2 1423 1190 2613

- - 2480( )

t s.n 23.2 1285 2480 3165 2.44 2 51 W. 07 25( 317 2 207.1 2662 16 4700 4683 918 4S001 206.7 2627 51.6 28.2 51.6 28.2 5.0 23.2 1423 14800 16223 4.41 I ~ 63 2.78 25(( 317 73 206 7 2627 609 S360 6042 -10180 34820 210.4 2982 14800 6.28 4.33 1.95 25(( 52 210 4 2982 485 5310 5846 -12955 21866 214.6 3422 11424( )

51.6 28.2 5.0 23.2 1377 17424 18801 317 KEY: (1) As limited by pumping (300 cfs) and withdrawal restrictions (2) Excluding Direct Rainfall (3) Assumes Auxiliary Reservoir maintained at Normal Water Level b/ pumping from Main Reservoir (4) Limited to available makeup.

NOTES: (1) Revised Buckhorn Flow.

(2) 100% load factor cooling towers.

(3) Mechanical draft towers (100% fan flow at all times).

(4) Filling of New Hope Reservoir coincident with filling of Shearon Harris Reservoir.

Amendment No.

(5) 5 cfs blowdown.

2 4,2-42

f SHNPP E Table 2.4.2-16 NORMAL OPERATION - ALL FOUR UNITS 100 YEAR RETURN PERIOD DROUGHT

- WORST MONTHLY EVAP. CONDITION MAIN RESERVOIR OPERATION TOTAL DIR. NET EVAP. 'MATER USE AUX. RES ~

PROM FORCED RF<3> AUX+MAIN FORCED@ INCR. STOR. TOTAL CREEE FOR IRVIOU ABOVE AVAIL. -NAT. EV-RF DUE TO NET EVAP NET EVAP ~ USE STOR. USE RNL AREA mE"'cFt AREA CONS. USE AREA EVAP NET EVAP.

INFLOdI3 MAIN + AUX. IMPIOUS HAIN RES.

SEEPACE t t fn. In. in. AC Ac'F t Pc AC AcF c AcFt AcFc AcF t Ft AC DAV cfc cfc cfc AcFc AcF AcF 41500 208.0 2756 2$ 0 317 DEC 31 208.0 2755 2756 126 141 12 22 41522 250 15 208. 0 JAN I 0 $ .0 -10 0 -10 153 0.01 0.56 55 317 16 167 177 41699 208.0 2749

-5 -10 152 0.06 0.00 0.06 250 317 208.0 2755 14 2 0 $ .0 10 0 16 163 173 41873 207.9 2743

-5 -10 148 0. 06 0.00 0.06 250 317 208.0 2749 14 3 0 5.0 0 10 t 2743 147 156 42029 207.8 2737 4 0 5.0 10 0 -10 144 0.01 0.00 0.01 250 317 207.9 143 153 42182 207.8 2732 5 0 5.0 -10 0 -10 IC8 0.02 0. 04 &.02 250 317 207.8 2737 150 160 42342 207.7 2726 6 0 5.0 -10 0 10 155 W.02 0.00 W. 02 250 317 207.8 2732 5 154 164 42506 207.7 2720 7 0 5.0 -10 0 -10 157 W.OI 0.00 &.01 250 317 207.7 2726 148 158 42664 207,6 2714 8 0 5.0 -5 -10 0 -10 148 0. 00 0.00 0.00 250 317 207.7 2720 2 IC1 1$ 1 42815 207.5 2709 9 0 5.0 -10 0 -10 144 &.01 0.00 .01 250 317 207.6 2714 153 163 42978 207 5 2703

-10 -10 ICE 0.02 0.00 0.02 250 317 207.5 2709 10 0 5.0 0 43149 207.4 2697 207.5 2703 12 161 170

-$ -10 148 0.05 0.00 0.05 2$ 0 317 11 0 $ .0 10 0 2692

-32 122 132 43281 207.4

-10 0 -10 155 0.01 0.14 W. 13 250 317 207.4 2697 12 0 SeO 207.3 2686 0 162 172 43453

-5 -10 162 0.01 0.01 0.00 2$ 0 317 207.4 2692 13 0 5.0 10 0 436C6 207.2 2679 250 317 207.3 2686 13 15 183 193 14 0 5.0 10 0 10 168 0.06 0.00 0.06 10 176 186 43832 207.2 2672 "5 -10 -10 166 0.04 0.00 0.04 250 317 207.2 2679 9 1S 0 5.0 0 4 162 172 44004 207.1 2665

-5 -10 -10 157 0.02 0.00 0.02 250 317 207.2 2672 16 0 5.0 0 44183 207.0 2659 207.1 2665 9 10 169 179 17 0 5.0 -10 0 -10 159 0.04 0.00 0.04 250 317 207.0 2659 16 18 176 186 44369 206.9 26S1 18 0 5.0 -10 0 -10 159 0,07 0.00 0.07 250 317 13 16$ 175 44544 206.9 264S

-10 0 -10 150 0.06 0.00 0.06 250 317 206.9 2651 19 0 5.0 206.8 2638 206.9 2645. 15 17 169 179 44723 20 0 5.0 10 0 10 152 0.07 0.00 0.07 250 317 I'50 20 177 187 4C909 206.7 2631

-10 -10 157 0.08 0.00 0.08 317 206.8 2638 18 21 0 5.0 0 t 44961 206.7 2629 206.7 2631 -107 42 52 22 0 5.0 -5 10 0 -10 162 0.09 0.58 W.49 250 3LF 13 206.6 2621 23 0 5.0 -10 0 10 16C '.09 0.00 0.09 250 317 206.7 2629 20 22 I

186 196 45157 0 155 165 45322 206.6 2615 5.0 10 0 -10 1$ 5 0.00 0.00 0.00 250 317 206.6 2621 24 0 206.5 2609

-10 0.08 0.11 &.03 317 206 6 2615 -8 145 155 45476 25 0 5.0 -5 -10 0 152 250 1$ 170 180 45656 206 4 2602 5.0 -10 0 -10 155 0.06 0.00 0.06 250 3l 7 206.5 2609 13 26 0 26I8 317 206.4 2602 20 22 179 ~05 45251 206.6 27 0 5.0 10 594 157 0.09 0.00 0.09 250 22 179 %05 44846 206.8 2633

-10 594 157 0.09 0.00 0.09 250 317 206.6 2618 20 28 0 5.0 45017 206.7 2627 206.8 2633 4 5 162 172

-10 157 0.02 0.00 0.02 250 317 29 0 5.0 0 10 45192 206.6 2620 317 206.7 2627 9 10 165 175 30 0 5.0 10 0 10 155 0.04 0.00 0.04 250 206.6 2620 15 17 163 773 45365 206.5 2613

-5 -10 146 0.07 0.00 0.07 250 317 31 0 5.0 10 0 NOTES: (1) Assumes zero inflow for January, February, and March.

(2) Ratio of annual 100-year flow CF/1933-34 flow CFxDaily Flow (1933 34). Rearranged to give more conservative drawdown. Also makeup limited by required fil]ing(of New Hope Reservoir.

(3) Ratio 100-year drought to minimum year flow (1933-34) x daily rainfall (1933-34).

Amendment No. 1 2'4.2-43 4

y/

SBNPP FR Table 2 4 '-16 (Cont'd)

HAIN RESERVOIR OPERATION HAKEUP PRDH TOTAL DIR. NET EVAP. HATER USE AUI CREEK FOR CAPE<2> AVAIL. EVAP. RE~33 -NAT. EV-RF DUE TO NET EVAP. AUXCHAIN FORCtTH'NCR STORo TOTAL INEIDMfO SEEPACE HAIN%AUX. FEAR INFIDEL HCIN RES RNL AREA CONS. USE RNL AREA EVAP. NET EVAP NET EVAP. USE STOR. USE FNL AREA DAY efc cfe efc AeFc AcF t AeFt AeF c fc. in, Fc AC hcF t Ft AC AcF t hcPt AcEc AcFt AeFt Fc AC 31 45365 206. 5 2613 1 5.0 -5 -10 0 -10 146 0.06 0.77 -0.71 250 '17 19 206. 5 2613 -155 -174 27 -17 45348 206.5 2614

2. 5.0 -5 -10 495 150 0.01 0.00 0.01 250 '( 3D 206.5 2614 2 152 -333 45015 206.7 2627 3 5.0 -1D 396 161 0.01 0.00 0.01 250 317 206.7 2627 2 163 -223 44792 206.8 263S 4 5.0 -10 396 159 0.03 0.00 0:03 250 '17 206.8 2635 7 8 166 -220 44573 206.9 2644 5 5.0 -5 -10 396 150 0.08 0.01 0.07 250 I 317 206.9 2644 15 17 167 219 44354 206.9 2652 6 5.0 -5 -10 396 157 0.10 0.00 0.01 2S0 I 317 206 9 2652 22 182 44149 207.0 2660 7 5.0 10 396 162 0.12 0.00 0 '2 250 I 317 207,0 2660 27 192 -194 43955 207 I 2667 8 5.0 -5 -10 0 -10 159 0.03 0. 00 0.03 250 I 317 207,1 2667 166 176 44131 207.0 2660 9 5.0 -5 -10 0 -10 150 0.08 0.05 0.03 250 (

317 207.0 2660 1$ 7 167 44299 2D7 0 2654 10 5.0 -5 -10 0 10 155 0.02 0.00 0.02 250, 317 207.0 2654 160 170 44469 206.9 2648 11 5.0 -5 -10 0 "10 168 0.08 0.1S -0.07 250 "

317 2 206.9 2648 15 -D 151 161 44629 206. 8 2642 12 5.0 -30 0 -10 161 0.02 0.37  %.35 250 317 -9 206.8 2642 -77 7$ 85 44714 206. 8 2638 13 $ .0 -5 -10 0 10 161 0.12 0.00 0.12 250 "

317 206.8 2638 26 191 200 44914 206.7 2631 14 5.0 -5 -10 0 -10 IS 2 0.08 0.00 0.08 250 I 317 206.7 2631 18 20 172 182 4S096 206.6 2624 IS 5.0 -S 10 0 -10 148 0.02 0.00 0.02 250 I 317 206.6 2624 4 5 153 163 4S259 206. 6 2617 16 5.0 -5 10 0 10 150 0.05 0.00 0.05 250 '317

, 206.6 2617 ll 12 162 172 45431 206.5 2611 17 5.0 -10 0 -10 150 0.01 0.00 0.01 206.5 2611 2 152 162 45593 206.4 2604 18 5.0 -5 -10 0 -10 155 0.12 0.00 0.12 250 317 206.4 2604 26 29 184 194 .CS787 206.4 2597 19 5.0 -5 -10 0 -10 148 0.03 0.46 &.43 250 317 206.4 2597 -93 104 44 53 4S841 206.3 2594 20 5.0 -5 -10 Or 10 150 0 ~ 10 0.00 0.10 250 317 206.3 2594 22 174 184 4602S 206.3 25&7 21 $ .0 10 0 10 146 0.03 0.00 0.03 250 317 206.3 2587 6 7 153 163 461&8 206.2 2581 22 5.0 -10 0 -10 152 0.08 0.03 0.05 250 317 206 2 2581 ll 12 164 174 46362 206 1 2S74 23 5.0 10 0 -10 152 0.11 0.00 0.11 250 ,

317 206.1 2574 24 27 178 188 46550 206.0 2566 24 5.0 -5 -10 0 -10 152 0.10 0.00 0.10 2$ 0 317 206.0 2566 21 24 176 186 46736 206.0 2558 25 5.0 -5 10 0 10 157 0.11 0.31 -0.20 250 317 -5 206.0 2558 ~3 -48 109 119 46855 205.9 2553 26 5.0 10 0 -10 166 0 ~ 16 0.37 &.21 250 317 -6 205.9 2553 ~5 -51 116 126 46981 20S.S 25CS 27 $ .0 -10 0 -10 164 0.14 0.00 0.14 250 317 205.8 2548 30 34 197 207 47188 205.8 2$ 40 28 $ .0 -10 0 -10 153 0:05 0.00 0.0$ 250 3)7 205.8 25CO 11 12 165 175 47363 205.7 2532 NOTES: (1) Assumes zero inflow for January, February, and March.

(2)

(3)

Ratio of annual 100-year flow CF/1933-34 flow CFxDaily Flow (y9y 3-34) conservative drawdown. Also makeup limited by required fillingIof New Ratio 100-year drought to minimum year flow (1933-34) x dainty r'mendment ~ Rearranged Hope ainfall (1933-34).

g.2-44 Reservoir.

to give more No. 1

SHHpp FR Table 2.4.2-16 (Cont'd)

MAIN RESERVOIR OPERATION DIR. NET EVAP VATER USE AUE NAIN RES ~

NET CREEK TOTAL FORCED CREEK POR INFGC7 ASOVE CA E'" AVAIL. EVAP. EVAP. RF'" -NAT. EV-RF DUE TO NET EVAP. INCR STOR. TOTAL NET EVAP NET EVAP USE STOR. USE RNL AREA INFLOd17 MA1NthUX. FEAR INFIAC7 NAIN RES. Cem. USE ENL AREA EVAP DAY cfc SEEPACE cfs cfa hcFc hcFc Fc, AC AcFt Fc AC - AcFc AcFt AcFc Ft hc 473&3 20S.7 2S32 28 3D 26 172 -313 47050 20S 8 254S 1 5.0 -5 -10 495 4&5 146 0. 11 0.00 0.11 250 20$ .7 2532 23 20$ .8 2545 32 36 189 -296 46754 205.9 2558 2 $ .0 -5 10 49$ 485 153 0.15 0.00 0. 15 250 317 0.06 317 205.9 2558 13 15 167 219 46535 206.0 2567 3 $ .0 -10 396 386 153 0.06 0.00 250 3D 206.0 2567 11 12 1S2 234 46301 206.1 2576 4 5.0 -S -10 396 386 140 0.05 0.00 0.0> 250 3D 24 27 182 92 46393 206.1 2572 5.0 -5 -10 99 89 15$ 0.11 0.00 0.11 250 206.1 2576 5

6 $ .0 -10 396 $ 86 159 0.14 0.00 0.14 250 3D 206 I 2572 30 34 193 -193 46200 206+2 2580

-6 206.2 2580 -52 58 SS -199 46001 206.3 2588 7 5.0 -10 297 287 146 0.10 0.34 W. 24 250 317 3D 206.3 2588 22 25 172 -214 45787 206.4 2597 8 $ .0 -5 -10 396 386 148 0.10 0.00 0. 10 0.00 0.15 206.4 2597 32 36 191 -393 45394 206.5 2612 9 5.0 -5 -10 594 584 15$ 0.15 317

0. 01 206.$ 2612 2 2 150 -236 45159 206.6 2621 10 5.0 -5 -10 396 386 148 0.0$ 0.04 317

~

19 16C -223 44936 206.7 2630 11 5.0 -5 -10 396 386 144 0.00 0.08 317 206.6 2621 17 0.08'.ll 206.7 2630 24 27 177, -209 44727 206.8 2638 12 5.0 -5 10 396 386 150 0.00 0. 11 250 317 0.13 206.8 2638 29 32 187 44726 206.8 2638 1$ 5.0 10 198 188 15S 0.14 0.01 250 I 317 0.15 0.34 W. 19 -5 206. 8 2638 -42 -47 IIS -73 44653 206.8 2641 14 $ .0 -10 198 188 162 250 I 317

-20 -251 44402 206.9 2650 15 5.0 -5 -10 396 386 155 0.07 0.15 &.08 250 i 317 206.8 2641 18 135 16 5.0 -10 594 584 1$ 3 0.11 0.00 0.11 250 '17 206.9 2650 24 27 180 43998 207.1 2665 I

'17 207.1 2665 33 37 196 388 43611 207 ' 2680

-5 -10 0.15 0.00 0.1$

'D 17 $ .0 594 584 159 250 207.2 2680 31 35 192 -392 43219 207.4 2694 18 5.0 -5 -10 594 584 1$ 7 0.16 Oo02 0.14 250

-0.24 -6 207.4 2694 -SC -60 99 -485 42733 207. 6 2712 5.0 5 -10 594 584 159 0.1$ 0.37 250 317 19 20 $ .0 -10 594 $ 84 162 0.18 0.17 0.01 250 '17 207 6 2712 2 2 16$ &20 4231C 207 7 2727 21 $ .0 -5 -10 594 584 162 0.17 0.16 0+01 2SO '17 207.7 2727 =

2 2 165 %20 41894 207.9 2742 207.9 2742 43 48 212 -372 41522 208.0 2755 22 5.0 -5 10 594 584 164 0.19 0. 00 0. 19 250 317 t 208.2 2768 208.0 2755 37 41 207 -377 41145 23 $ .0 -5 -10 594 584 166 0. 16 0.00 0.16 250 317 208. 2 2768 44 49 211 -373 40772 208.3 2781 24 5.0 -10 594 584 162 0 ~ 19 0.00 0.19 250 317 208.$ 2781 3p

'89

', -396 40376 208.4 279$

25 5.0 -10 594 584 155 0.16 0.03 0.13 250 I 317 208.4 2?9S 30 33 195 3&9 39987 208.6 2S09 26 5.0 -5 -10 594 5&C 161 0.13 0.00 0.13 250 317 2&8.6 2&'A 33 57 195 389 PRSSS 203.7 28"2 27 5.0 10 594 584 159 0 ~ 14 0.00 0 ~ 14 250 'i 317 g 28 5.0 -10 594 584 ISS 0.15 0.00 0 ~ 15 250 '17 20' 2822 35 39 19C I

392C8 20S.9 2835 I

208.9 2835 35 39 196 I -388 38821 209.0 284&

29 5.0 10 594 584 157 0.15 0.00 0.15 2SO I

317 0.16 209.0 2848 38 42 208 -376 3SCCS 209.1 2861 30 5.0 -5 -10 594 584 166 0. 16 0.00 250 I $ 17 I 0.23 209.1 2861 55 61 2 29 -355 38090 209.2 2873 31 5.0 10 594 584 168 0.23 0.00 250 317 I

l NOTES: (l) Assumes zero inflow for January, February, and March. I (2) Ratio of annual 100-year flow CF/1933-34 flow CFxDaily Flow (]93'3 34) ~ Rearranged to give more conservative drawdown. Also makeup limited by required filling ~zf New Hope Reservoir.

(3) Ratio 100-year drought to minimum year flow (1933-34) x daily ra'infall (1933 34) ~

Amendment No. 1 2 '4.2-4~

t

TABLE 2.4.2-21 AUXILIARYRESERVOIR OPERATION LOSS OF ALL OTHER WATER SOURCES SIMULTANEOUS ACCIDENT CONDITION IN ONE UNIT AND NORHAL SHUTDOWN OF THREE UNITS Time After Inst.

Heat Accident Rejection Avg. For Period Effective Area Unit Load Forced Evap.

Rate Forced During Evap.

Period Worst Natural Evap.

During Period To tal Storage 'f Summation Residual Use In Storage Period Use Storage At End of Period Water Level In Auxiliary Pond at End of Period mo =10 Btu/hr 10 Btu/hr 10 sf Btu/sf/hr in/mo in ac ft. in ac. ft. ac. ft. ac. ft. ac. ft. ft.

0.0 1270 4400 250.0 600 "

9. 31 64. 5 5. 87 1.47 26 2.3 58 84 84

0. 25 257 4316 249. 7 243 9. 15 26. 6 2. 27 0. 57 10 2. 3 58 68 152

0. 25 257 4248 249. 4 223 8. 97 24. 9 2.04 0.51 9 2.3 58 67 219

0. 50 229 4181 249. 3 214 8. 92 24.0 2.04 0.51 9 2.3 58 67 286

0. 75 217 4114 249. 0 205 8. 85 23. 2 2. 13 1. 07 19 4. 25 106 125 411

1. 00 210 3989 248. 4 195 8. 72 22. 4 1. 92 0. 96 17 4. 25 106 123 534

-1. 50 199 3866 249. 1 187 8. 60 21. 7 1. 73 0. 87 16 4. 10 103 119 653

2. 00 190 3747 247. 8 180 8. 50 21. 2 1. 62 0. 81 14 4. 10 103 117 770 2 ~ 50 183 3630 247. 2 175 8. 29 21. 1 1. 56 0. 78 14 3. 89 97 111 881 F 00 177 3519 246. 9 170 8. 20 20. 7 1. 62 0. 81 14 3. 89 97 111 992

3. 50 173 3408 = 246.5

4. 00 167

ER Question 470.4 (Section 3.5.1)

On Table 3.5.1-1 (page 3.5.1-8), the seventh nuclide form the top should.,be Tc-99m instead of To-99m.

Response: Table 3.5.1-1 will be revised to read Tc-99m instead of To-99m.

ER Question 470.5 (Section 3.5.3)

On Table 3.5.3-7 (page 3.5.3-24), the seventh nuclide from the top should be Tc-99m instead of To-99m.

Response: Table 3.5.3-7 will be revised to read Tc-99m instead of To-99m.

ER Question 470.6 (Section 5.2.2)

On Table 5.2.2-2, are the total C/MPC ratios for on the ground and in vegetation (values 9.18E + 07 and 4.70E + 03, respectively) correct?

Response: The values 9.18E + 07 and 4.70E + 03 should be deleted from Table 5.2.2-2.

ER Question 470.7 (Section 5.2.3)

On Table 5.2.3-1, correct the DOSE Units (should not be mred/yr./unit).

~Res ouse: The DOSE Units on Table 5.2.3-1 should be revised to read mrad/year.

ER Ques tion 470. 8 (Section 5.2. 5)

On Table 5.2.5-1, specify the units for the integrated doses.

Response: The units for integrated doses on Table 5.2.5-1 should be mrem/year.

ER Question 470.9 (Section 6.1.5)

On Table 6.1.5-2, include the value of the Dose for Fallout(1969). Also identify the source of the Dose data more specifically, i.e., identify the specific references from which each set of data, were obtained or derived.

Response: Table 6.1.5-2 has been revised and is attached.

SHNPP ER TABLE 6 '.5-2 NATURAL BACKGROUND AND MANMADE EXPOSURES Dose Natural Background (mrem/yr)

Cosmic Radiation Radionuclides in the Body 18 External Gamma Radiation 40 Total 102 Manmade Exposures Medical & Dental 73 Fallout Occupational Exposure 0.8 Nuclear Power 0.003 Total 77.803 Advisory Committee on the Biological Effects of Ionizing Radiations, The Effects on Po ulations of Exposure to Low Levels of Ionizing Radiation, U.S. National Academy of Sciences, National Research Council, Washington, D.C. 1972, Page 50.

ER Question 470.10 (Section 6.1.5)

On Table 6.1.5-5, the column heading for 148 Ba should read 140 Ba.

Response: The column heading 148 Ba 'on Table 6.1.5-5 will be revised to read 140 Ba.