Public Version of Revision 2 to Emergency Plan Implementing Procedure HNP-4851, Emergency Classification Determination Based on Effluent MonitorsML20063M405 |
Person / Time |
---|
Site: |
Hatch ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
---|
Issue date: |
08/05/1982 |
---|
From: |
Nix H, Rogers W GEORGIA POWER CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20063M400 |
List: |
---|
References |
---|
HNP-4851-01, HNP-4851-1, NUDOCS 8209140045 |
Download: ML20063M405 (10) |
|
Similar Documents at Hatch |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20106A6521992-02-29029 February 1992 Proposed Rev 3 to Ei Hatch Nuclear Plant Solid Radwaste PCP, Per GL 89-01 ML20106A6501992-02-0707 February 1992 Rev 7 to Ei Hatch Nuclear Plant ODCM, Reflecting Proposed Changes,Per GL 89-01 ML20056B3031990-08-0101 August 1990 Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval ML20149N1141988-01-0404 January 1988 Revised Second 10-Yr Interval Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20211H5491987-02-20020 February 1987 IGSCC-Susceptible Primary Pressure Boundary Stainless Steel Piping & Components Insp/Mitigation Program, 1987 Maint/Refueling Outage ML20245B8301986-12-10010 December 1986 Rev 0 to SO-OPS-05-1286, Spent Fuel Pool Transfer Canal Gates ML20245B8171986-12-0505 December 1986 Rev 0 to SO-OPS-02-1286, Processing of Water from Yard Drains ML20245B8201986-12-0505 December 1986 Rev 0 to SO-OPS-01-1286, Radwaste Discharges. Supporting Documentation Encl ML20203L9291986-08-0101 August 1986 Rev 0 to Training Procedure 72TR-TRN-002-0S, License Requalification Training Program ML20137V9031985-12-0505 December 1985 Rev 1 to Emergency Implementing Procedure 62RP-RAD-009-05, Airborne Radioactivity Concentration Determination ML20076J1871985-11-0808 November 1985 Rev 2 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp for Georgia Power Co ML20076J1911985-11-0404 November 1985 Rev 1 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20076J1961985-10-23023 October 1985 Rev 0 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20135F3161985-08-26026 August 1985 Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project ML20132E5471985-08-23023 August 1985 Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting ML20209F2391985-07-0101 July 1985 Recirculation,Rhr & Reactor Water Cleanup Sys Piping Weld Joint Insp/Mitigation Program for 1985 Maint/ Refueling Outage ML20128A0561985-06-25025 June 1985 Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20126E8331985-06-11011 June 1985 Emergency Plan Implementing Procedures & Deleted Title Sheets,Including Procedures HNP-8007 Re Decontamination of Clothing & Hats & HNP-8004 Re Dosimetry Issuance & Tracking ML20116D4401985-04-23023 April 1985 Revised Emergency Procedures HNP-8109 Re Continuous Air Monitors Models AM-3D & AM-33-1,HNP-8122 Re Radiation Monitor Model RM-16 & HNP-8146 Re Rascal Portable Rate Meter-Scaler/Model PRS-1 Operation & Calibr ML20245B7911985-04-17017 April 1985 Rev 0 to 10AC-MGR-04-0, Deficiency Control Sys. Supporting Documentation Encl ML20107G1421985-02-15015 February 1985 Revised Emergency Implementing Procedures,Including Rev 3 to HNP-8161 Re Eberline Model PCM-1 Portable Monitor Operation & Calibr & Rev 2 to HNP-8036 Re Waste Classification & Manifest Reporting Resin Shipments ML20215F7371984-12-26026 December 1984 Rev 1 to Administrative Control Procedure 40AC-FPX01-0, Fire Protection Program. Portions of Procedures 34AB-OPS-056-1S & 34AB-OPS-056-2S Encl ML20101B0551984-12-17017 December 1984 Rev 5 to Emergency Plan Implementing Procedure HNP-8134, Whole Body Counter Sys ML20108E0921984-11-29029 November 1984 Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3 ML20107H5701984-10-31031 October 1984 Detailed Control Room Design Review Program Plan ML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program ML20098G3401984-09-30030 September 1984 Offsite Dose Calculation Manual ML20098G3381984-09-30030 September 1984 Solid Radwaste Process Control Program ML20108E0741984-06-13013 June 1984 Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & Calibr ML20084H4971984-05-0101 May 1984 Rev 0 to Procedures Generation Package for Emergency Operating Procedures,Including plant-specific Technical Guidelines for Units 1 & 2,plant-specific Writers Guide & Implementation Plan for Emergency Response Project ML20086U4131984-02-29029 February 1984 Vendor Equipment Technical Info Program, Per Generic Ltr 83-28,Section 2.2.2,final Draft ML20087N9101984-01-26026 January 1984 Public Version of Transmittal & Title Page to Deleted Emergency Plan Implementing Procedures,Including Procedure HNP-8031 Re Determination of Specific Activity of Spent Resin & Curie Contents of Liner & 840322 Memo ML20087M7911984-01-25025 January 1984 Public Version of Transmittal & Title Pages of Deleted Emergency Plan Implementing Procedures HNP-8019, Insp of Steel Radwaste Shipping Drums & HNP-8422, Handling & Loading of Chem-Nuclear Cask & 840322 Memo ML20087M9321984-01-20020 January 1984 Public Version of Rev 7 to Emergency Plan Implementing Procedure HNP-8101, Teletector Model 6112B/D Operation & Calibr & Jm Felton 840322 Release Memo ML20081B6731984-01-18018 January 1984 Public Version of Rev 0 to Emergency Plan Implementing Procedure HNP-8161, Eberline Model PCM-1 Portal Monitor & Rev 17 to HNP-8008, Radiation Work Permit & Jm Felton 830307 Release Memo ML20087P0191984-01-13013 January 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8038 Re Waste Classification & Manifest Reporting & HNP-8042 Re Radiological Work Practices & 840326 Memo ML20079H9011983-12-0707 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8035 Re Pulmonary Function Screening Program & HNP-8016 Re Shipment of Radioactive Matl ML20093D4881983-10-31031 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
[Table view] |
Text
{{#Wiki_filter:__
.. . _ _ _. _...- . . _ . . . _ ___ . . . _ _ . _ ...m-.. ..
.f GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Emergency C1.assification Determination _
Based On Effluent Monitors PROCEDURE TITLE
. HNP-4851 PROCEDURE NUMBER Lab RESPONSIBLE SECTION N -
SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
----_-.. _ - _ - - - _ - - - - - - _ - - - - - - - --_--_---_---__- a_---__-_---__--_.----_--.
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE
' N.. -
HEAD MANAGER
~
2 PD9e 2
/
. /,
C/ 2/ ----
/
/ f&mn ' b
----- - - , . - - - . . (?a, J/.h. ) .~.
4
-_----..---_-_-_----_-__---_..--_-_-__------__. . U-w_.,4._ - _ _ M . , ___--_
gQJ 8
3 [. . 4 ! 3 '. 4 J /[ *
' ., pu d k h j'.,.7.
Md,
-----..--------meM- 'sW------Md.--
- - - - - - - - - - _ - - -.. - - W - - 9..g 4 e
-----m 8209140045 820023 HNP-9 PDR ADOCK 05000321 h F PDR
. M * **bb% # dtg g'
_ . _ _ _m.....__.____ . . _ _ _ . . . . _ . . _ _ _ . . . . . . _ _ _m.___.-
(.g CBOCCOU'.!G BEE'IO100 J1EOLn.IGI Q P.ROCCCURE NO. HNP- ----__ k _
.. /
Revis. ton No. .
D'-i)75
.Y8Ui$TFD nY--------------'
sj anc,ny..,?.~F):I A! /.O cwtui /.T ..]' i .:o?5_. -~ 7 --
t Namet Date; __ e f .
/
/ J / '{. WQ 'U 7 // / 8 l catt,V.,:' -
b A3 $5-f N < O', - -
h Y0 REVISION CHA.:GC5 MODE OF.CPERATION OR INTENT AS DEGCRIPED IN FSAR:
. ( ) Yes ( ) No CHANGE INVOt.VFS:
)'An unreviewed Safety Guestion
( ( ) T'e ch . Sp e c s. ( Neither (See back for S,foty Evaluation if required).
Safety Related i l ) Non-Safety Related ( )
Safety /Non-safety Status C:.ange ( ) Yes ( ) No s .c.
. Attach marked up copy of procedure to t h i's form.
!/ <(/
~
REASON FOR EZGUEST d/* / I(d_ [. / _
A Q 'f . j w // TA't7
.. igtfr/ h/kwpG st( Ah ~ hk/ kgr __ .b-l b l [2fa_
din e l& a .Ue f dv ds u et%f m A_--- s_ A 7i ,a t NWf2bv L. ,
2 .e. --4_=., &
g #
ee
-_e.y - --
- -4Q
. _-w_
. - - -= ---
~ ~ ~
b.
____- w e, ann ____-em- _ _ - me - e a.m - ese enn ncconnsson ArnRove.:_: c:49es ( )Mn _ __,[de.___dA____ _ _____
c.
O _ =y.n
- -- _ s. - - - - . _ _ - - - _ _
S,*k__-,b.$ -
.__ m ------
s PRB Nu:nber -
CDs,4{c'.".5 -w a fi
. s ., 4 s .l,a@.
~
r T 's * '.)
.
. . . . ~ s ~~.as . ;l -
_ manual, set , .. _ ,
~" '
- .,...c.:.. . :.. . . _ . ~ . -.,.n.--. 2- -.u..~ .a . a .~ .
E.1. Hatch Nuclear Piant a= aaoa = u ao HNP. 4851 S e Title Paga uvisio~ ~o
. a
- l o.n Georgia Power n$ ..m ~o
't See Title Page 1 of 8 !f EMERGENCY CLASSIFICATION DETERMINATION RASED ON EFFLUENT MONITORS NOTE This procedure supercedes HNP-4608 Revision 7. -
A. PURPOSE To describe a method for determining the Emergency Class using
. gaseous effluent monitors when releases are being made.
B. EMERGENCY CLASS RELEASE LIMITS
- 1. Alert Emergency: Gaseous releases are greater than 10 tiras Tech Spec Limits Section
. 2.1.3.a.
s s. ;.
- 2. Si te Area Emergency: Gaseous effluent monitors detect levels corresponding to greater than 50 mr/hr for 1/2 hour or greater than 500 mr/hr W.B. for two minutes (or five times these levels for thyroid) at the site boundary for adverse meteorology.
- 3. General Emergency: Effluent monitors detect levels corresponding to 1 rem /hr W.B. or 5 rem /hr thyroid at the site boundary under actual meteorological conditions.
C. REFERENCES
- 1. HNP-4621
- 2. HNP-4721
- 3. HNP-4850
- 4. Emergency Plan Section D.
4-m n7 %y p%y.
d I c yg ;$ ,,
v.v,..
,n
\
g;/ g* - <
.. * * *W 41 a i
m
. ....~...~ E: 1. Hatch Nuclear Plant raocamae ~o HNP. 4851 navis.o~ ~o I '
'See Title Page 2
- h. .. Georgia Power A . . . .
[ S,e e Title Page 2 of 8 D. RELEASE RATES -
Determine release in curies /sec for each release point using procedure HNP-4850.
(GNs)
- 1. Main Stack' = Ci/sec
- 2. Reactor Building Vent Unit 1 (GNvl) = Ci/sec Reactor Building Vent Unit 2 (GNv2) = Ci/sec Recombiner Building Vent Unit 1 (GNv3) = Ci/sec (if no alarm enter zero)
Su.a of Vents (GNv) = Ci/sec j
E. ALERT EMERGENCY Declare alert emergency if either of the following two equations are satisfied ins tantaneously.
1.703 GNs + 23.815 GNv Greater than 10 l 1.703 ( ) + 23.815 ( ) =
+ ) =
( ) .(
or I
1.0 X 10 2 GNs + 1.5 X 10 3 GNv Greater than 10 1.0 X 10 1 ( ) + 1.5 X 103 ( ) =
F. SITE AREA EMERGENCY Declare Site Area Emergency if the follcwing two equations are satisfied for time period.
4 k 1. GNs + GNv Greater than 1 for longer than 30 minutes
} O.9 1.2 E-2 t'
( ) +1 ) =
l i i O.9 1.2 E-2 4
- 2. GNs + GNv Greater than 1 for longer than 2 minutes 9.4 1.2 E-1
( ) + ( ) =
1 . 9.4 1.2 E-1 I .
1 i ~
I
)D g ' ? V' % ,QP y m
" J L*[ q%
+
3 ,, '
- m ,, ll %'!'i% .6 vyf*/wjl/
-na - j manual sti
,, E. l. Hatch Nuclear Plant ociou , ~o See Title Pags ""
HL vs%ON %O 1
c... Georgia Power d .. , o See Title Page 4 3 of 8
.G. ' GENERAL EMERGENCY i
- 1. Check air temperature difference ..
~
(Delta T) recorder and wind direction Delta T = *F -
recorder readings (W.D. recorder W.D. =
- indicates which direction the wind is coming fra'. m 2.
Based on Delta T, apply applicable Pasquill Category in Chart 1
. CHART 1 PASGUILL ATMOSPHERIC STABILITY CLASSIFICATION USING DELTA T MEASUREMENTS
- 1 +
, -0.9 -0.3 0 ,
)
~ ______________._____________________.___________________+0.9 ______________
C < - O. 9 - O. 9 5 D < - O. 3 - O. 3 4 E < + 0.9 + 0.9
___________________________________..________________________F> __________
PASGUILL CATEGORY
- 3. Determine average wind speeds for periods of release intervals from recorder P62-R900 (Hil-P658). Use the 150 foot elevation wind speed recording.
150 Foot level average wind speed U fso =
(uncorr.)
4.
Correct indicated wind speed to determine speed at top of main stack. Use table 2. ..
Us = (U150) X (Us) =
mi/hr TABLE 2 RATIO OF WIND SPEED AT MAIN STACK HEIGHT TO WIND SPEED AT MEASURED HEIGHT PASGUILL CATEGORY RATIO C 1.13 D 1.24 E 1.47 F 1.47
- 5. Using Us, U/so, Pasquill Category, and Tables 3, 4, 5, and 6, I
determine R/GNs, R/GNv, R/GIs, andR/GIQ7.%,,,, g w
*zpi,
, *e Q ' ,
*? NN **n
' ~ ; ni%' L>*: I %
GL pe
.#...,.y
!=1 7 S /lg )'* d i~ - * -
{: ~% - manual BGt
. . . a .--
' t E.1. Hatch Nuclear Plant . oa == ~o HNP- 4851
? "See' Title Pcg2 asvis.o o
!;' s.., Georgia Power d . . .,
3 See Title Page 4 of 8 i
- 6. Declare General Emergency if either of the following equations are satisfied. _
- a. (R/GNs)(GNs) + (R/GNv)(GNv) >1 *
, ( ) ( -) +( ) ( ) =
- b. (2 E-3)* +
((R/GIs)(GNs) (R/GIv)(GNv)) > 1 (2E-3)*(( ) ( ) + ( ) ( }) =
* (2 E-3) assumes that Iodine / Noble Gas ratio is 0.001. If ratio is known, multiply (2 E-3) by the factor calculated below and use the results instead of (2 E-3) in the
. equation.
Factor = known ratio
.001
=
e=
a i
l o
,a 1
1 1
1 -
U: > ~e m.
1
*y j
< s l
A ~~. ._ ,uz
~ , ? ms .p l
3 i
.y.,
"aQ u u: .,
. ., 3
-{ . . '> I; )7
.i m;u !t '
$ [e/
.= . A . .g g
.-..., manual set
< om i ,
E. l. Hatch Nuclear Plant awuat ~o i
Sea. Title Page HNP. 4851 ny,sio~ a 1l ', .... Georgia Power n 2
..m e j' See Title Page i
5 of 8 j -
TABLE 3 1
l PASGUILL C -
1 I ' WIND SPEED
' DOSE RATE PER RELEASE RATE REM-SEC Mi/HR Ci - HR NOBLE. GAS IODIrE STACK VENT STACK VENT R/Gns R/GNv R/GIs R/GIv O 5.0 E - 2 2.3 E - O 4.8 E + 1 2.3 E + 3 1 2.6 E - 2 1.3 E O 2.65 E + 1 1.2 E + 3 2 1.45 E - 2 6.5 E - 1 1.42 E + 1 6.8 E + 2 3 9.3 E-3 4.3 E - 1 9.2 E O 4.4 E + 2 4 6.7 E - 3 3.2 E - 1 6.7 E O 3.2 E + 2 5 5.3 E - 3 2.5 E - 1 5.4 E O 2.5 E + 2 6 4.4 E - 3 2.1 E - 1 4.5 E O 7 2.1 E + 2 3.7 E - 3 1.8 E - 1 3.8 E.O 1.8 E + 2 8 3.25 E - 3 1.55 E - 1 3.3 E O 1.6 2 + 2 9 2.85 E 1.38 F - 1 2.95 E O 1.4 E + 2 -
10 2.55 E - 3 1.24 E - 1 2.65 E O 1.25 E + 2 11 2.3 E - 3 1.15 E - 1 2.4 E O 1.15 E + 2 12 2.12 E - 3 1.02 E - 1 2.2 E O 1.05 E + 2 13 1.98 E - 3 9.5 E - 2 2.0 E O 9.6 E + 1 14 1.85 E - 3 8.8 E - 2 1.88 E O 8.9 E + 1 15 1.75 E - 3 8.2 E - 2 1.75 E O 8.3 E + 1 16 1.65 E - 3 7.7 E - 2 1.63 E O 7.8 E + 1 17 1.55 E - 3 7.3 E - 2 1.54 E O 7.4 E + 1 18 1.48 E - 3 6.9 E - 2 1.47 E O 6.9 E + 1 19 1.39 E - 3 6.5 E - 2 1.39 E O 6.6 E + 1 20 1.32 E - 3 6.2 E - 2 1.31 E'O 6.2 E + 1 21 1.26 E - 3 5.9 E - 2 1.25 E O 6.0 E + 1 22 1.2 E-3 5.8 E - 2 1.2 E O 5.7 E + 1 23 1.15 E - 3 5.4 E - 2 1.16 E O 5.4 E + 1 24 1.11 E - 3 5.2 E - 2 1.11 E O 5.2 E + 1 25 1.07 E - 3 5.0 E - 2 1.07 E O 5.0 E + 1 26 1.01 E - 3 4.8 E - 2 1.04 E O 4.8 E + 1 27 9.8 E - 4 4.6 E - 2 1.01 E O 4.7 E +'1 28 9.4 E - 4 4.5 E - 2 1.0 E O 4.5 E + 1 fI [ ' % ,,d I/*4 nn
.:" ng / /k manual set
. - . . . - - . . . . ~ . ..~.- . . . . . . . . . . _ , , _
I ' . - - E.1. Hatch Nuclear Flant ~ocewn ~o HNP. 4851 i',
rSee Title Page .. .,3.o~ ~a lj c.,, Georgia Power d ..m ~e
} See Title Page 6 of 8 I
j TABLE 4 ,
i l PASGUILL D _
i QIND' SPEED DOSE RATE PER RELEASE RATE (REM SFC)
Mi/HR Ci - HR i NOBLE GASES IODINE STACK VENT STACK VENT i R/GNs R/GN'v R/GIs R/GIs
. O 3.3 E - 2 2.8 E O 2.4 E + 1 3.1 E +3 i 1 1.4 E - 2 1.45 E O 1.4 E t 1 1.6 E t 3 2 7.0 E - 3 8.6 E - 1 7.6 E O 8.5 E + 2 3 4.7 E - 3 5.4 E - 1 4.8 E O 5.4 E + 2 4 3.4 E - 3 3.95 E - 1 3.6 E O 3.9 E + 2 I
5 2.75 E - 3 3.1 E - 1 2.85 E O 3.1 E + 2 2
6 2.3 E - 3 2.55 E - 1 2.33 E O 2.6 E + 2 7 1.9 E - 3 2.2 E - 1 2.05 E O 2.2 E + 2
~~
8 1.74 E - 3 1.9 E - 1 1.79 E O 1.9 E + 2 9 1.55 E - 3 1.70 E - 1 ~
1.58 E O 1.7 E + 2 10 1.38 E - 3 1.50 E - 1 1.4 E O 1.51 E + 2 11 1.25 E - 3 1.39 E - 1 1.28 E O 1.49 E 1 2 12 1.15 E - 3 1.28 E - 1 1.16 E O "t.38 E f a 13 1.05 E - 3 1.18 E - 1 1.08 E O 1.28 E + 2 14 9.9 E - 4 1.10 E - 1 1.0 E O 1.1 E + 2 15 9.3 E - 4 1.03 E - 1 9.3 E - 1 1.02 E + 2 16 8.8 E - 4 9.7 E - 2 8.7 E - 1 9.6 E + 1 17 8.2 E - 4 9.2 E - 2 8.2 E - 1 9.1 E + 1 18 7.8 E - 4 8.6 E - 2 7.8 E - 1 8.6 E + 1 19 7.4 E - 4 8.2 E - 2 7.4 E - 1 8.2 E + 1 20 7.0 E - 4 7.8 E - 2 7.0 E - 1 7.8 E + 1 21 6.5E 4 7.4 E -2 6.7 E - 1 7.4 E + 1 22 6.4 E - 4 7.0 E - 2 6.4 E - 1 7.0 E + 1 23 6.1 E - 4 6.7 E - 2 6.1 E - 1 6.8 E t 1 24 5.L E-4 6.3 E - 2 5.8 E - 1 6.5 E + 1 j 25 5.6 E - 4 6.2 E - 2 5.6 E - 1 6.2 E + 1
; 26 5.3 E - 4 6.0 E - 2 5.4 E - 1 6.0 E + 1 27 5.1 E - 4 5.7 E - 2 5.2 E - 1 5.7 E + 1 28 4.9 E - 4 5.6 E - 2 5.0 E - 1 5.5 E t 1 4
~
l f
1 1
4 -
1
't ID &*
1 jg "fa ta 5 :3 s
j ~
, , lb O 1,ep
'e s .. ,
s
# e 1 j ,1 y J
%f
; T..' -"
manual set
. .-.-. ~ . . . . - . . . . . - - . ~
ra.M E. l. Hatch Nuclear Plant ,7 4 ,
~
I Sg;p. 4R51
. nce. Title Page
.il
.... Georgia Power s g , , , , , ,
...s.,
2 See Title Page '
7 of a j u_ .
f
i PASGUILL E
; I4IND* SPEED DOSE RAT E PER RELEARE F.',TF ~ RFM-SFC) l Mi/HR
___ Cs_ _bR_
NOBLE GASES __
ICDItE ~ ~ ~
STACK VENT STACK (ENT l
R/GNs R/GNv R/GIs R/Giv O 1.2 E - 2 3.2 E O 1.45 E 1 3.2 E F 3 1 8.5 E - 3 1.75 E O 8.6 E O 1.85 E t 3 l' 2 4.5 E - 3 1.0 E O 4. 7EO 1.0 E t 3 3 2.9 E - 3 6.4 E - 1 3.1 E O 6.2 E t 2 4 2.15 E - 3 4.6 E - 1 2.2 E O 4.6 E t 2 5 1.7 E - 3 3.65 E - 1 1.7 E O 3.65 E + 2 j 6 1.41 E - 3 3.0 E - 1 1.44 E O 3.0 E t 2 7
1.2 E - 3 2.55 E - 1 1.25,E p 2.6 E F 2 8 1.05 E -3 2.2 E - 1 1.08 E O 2.25 E 4 2 9 9.2 E - 4 1.98 E - 1 9.5 E - 1 2.0 E t 2 10 8.2 E - 4 1.79 E - 1 8.6 E - 1 1.8 E t 2 11 7.4 E - 4 1.61 E - 1 7.7 E -1 1.65 E t 2 12 6.9 E - 4 1.49 E - 1 7.1 E - 1 1.5 E t 2 13 6.4 E - 4 1.38 E - 1 6.6 E - 1 1.38 E + 2 14 6.0 E - 4 1.29 E - 1 6.1 E - 1 1.29 E t 2 15 5.6 E - 4 1.20 E - 1 5.6 E - 1 1.2 E t 2 16 5.3 E - 4 1.12 E - 1 5.4 E .1 1.13 E t 2 17 5.0 E - 4 1.05 E - 1 5.0 E - 1 1.05 E t 2 18 4.7 E - 4 1.0 E - 1 4.8 E - 1 1.0 E t 2 19 4.5 E - 4 9.5 E - 2 4.5 E - 1 9.6 E t 1 20 4.3 E - 4 9.0 E - 2 4.3 E - 1 9.1 E t 1 21 4.1 E -' 4 8.6 E - 2 4.1 E - 1 8.7 E t 1 22 3.9 E - 4 8.2 E - 2 3.9 E - 1 8.2 E t 1 23 3.7 E - 4 7.8 E -2 3.8 E - 1 8.0 E t 1 24 3.6 E - 4 7.4 E - 2 3.6 E - 1 7.6 E t 1 25 3.4 E-4 7.2 E - 2 3.45 E - 1 7.3 E + 1 E6 3.3 E - 4 6.9 E - 2 3.3 E - 1 7.0 E t 1 4
27 3.2 E - 4 6.6 E - 2 3.2 E - 1 6.8 E t 1
, 28 3.05 E - 4 G.4 E - 2 3.1 E - 1 6.4 E t 1 4
i
'1 i
i '
l f
' A. 5 ,5 :
x.a _; . "#? ,,I7r i 4 P1 ,- k .f
, - ., ,1 1 -
m .. . 3 [
l:
o ,
+6 g manuai set}}