ML20065T446
| ML20065T446 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/30/1988 |
| From: | Brad Bishop, Meyer T, Yanichko S WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20065T434 | List: |
| References | |
| GL-88-11, MT-SMART-216(88, MT-SMART-216(88), NUDOCS 9012280128 | |
| Download: ML20065T446 (23) | |
Text
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.MT-SMART-216(88) 1 '-=i l
RESPONSE--TO-U.S. NUCLEAR REGULATORY-COMMISSION GENERIC LETTER 88-11 FOR -? THE BRAIDWOOD UNIT 1 REACTOR VESSEL
. i by i-i
.B. A. Bishop S. E. Yanienko i
WORK PERFORMED FOR' COMMONWEALTH EDISON COMPANT . i C
. Approved By: d% h -
T.A.Meyer,Manageh l.
- Structural! Material s-_ and .Rel iabili ty
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Technologyi November 1988 s WESTINGHOUSE ELECTRIC CORPORA 110N Energy Systems Business Unit- u P.O. Box 2728 - l, Pittsburgh, Pennsylvania- 15230-2728 l' mo..tiieselo? 9012280128 901219 PDR- ADOCK 05000456 P PDR 4.. ,
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TABLE OF CONTENTS
.. t Page TABLE OFcCONTENTS i LIST OF TABLES ii LIST OF FIGURES ,
. iii
- 1. INTRODUCTION. 1
-2.. REGULATORY GUIDE 1.99 - REVISION 2 METHODOLOGY 3
- 1. Survoillance Data.Not:Available 3 2.- . Surveillance Data Available 5
- 3. TECHNICAL ANALYSIS. 6 1.. Identif.ication and Location of Beltline Region Materials 6 ;
- 2. - Definition of Plant Specific Material Properties 6
- 3. Neutron Fluence Values 9 +
;4. Adjusted-Reference. Temperature Values For Heatup and-T Cooldown Curves- 9
- 5. Applicability Date of Current Pressure-Temperature-Limits 9
- 4. ' DETERMINATION OF RT PTS VALUES 13 .
' 5. CONCLUSIONS 15
- 6. REFERENCES 16
. APPENDIX-A - WELD QUALIFICATION TEST CERTIFICATION 17
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z ,7 i.. LIST'0F' TABLES Table. T-itle Page l' Braidwood Unit 1 Reactor Vessel Beltline Region Material 8 Properties
- 2. Calculation of Adjusted Reference Temperature fcr -11 Limiting Braidwood Unit _1 Reactor Vessel Material Circumferential Weld Seam-
- 3. .-Braidwood Unit 1: Reactor' Vessel Beltline RT Values at 14 PTS .
End of Life-(32 EFPY) Using Regulatory Guide'1.99.- .: Revision 2
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-LIST OF FIGURES
- 1. .
. Figure Title Page
- 1 Identification and Location of Beltline Region Material for the Braidwood Unit 1 Reactor' Vessel 7 2 Fast Neutron Fluence-(E.> 1 MeV) as a function of Full 10 Power Service, Life (EFPY)
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.3. Braidwood Unit 1-Adjusted. Reference Temperatures Using
. 12 ;
Regulatory Guide 1.99 - Revision 2 l ([
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V RESPONSE TO U.S. NUCLEAR REGULATORY COMMISSION GENERIC LETTER Spell FOR THE BRAIDWOOD UNIT 1 REACTOR VESSEL 1 ~. INTRODUCTION' The U.S. Nuclear Regulatory Commission issued Generic Letter 88-11, "NRC Pos4 tion on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations,"[1] on July 12, 1988. The purpose of the generic letter was to call attention to' Revision 2 to Regulatory Guide 1.99, " Radiation Embrittlement of Reac, tor Vessel Materials,"[2] which.became effective May 31, 1988.
^
Within 180 days of the effective date of the Regulatory Guide (November 27, 1988), each licensee-must submit the results of a technical analysis relative to the implementation of this new regulation.- This analysis includes the following:. . 1)- Recalculation of adjusted refe 'nce temperature values at the 1/4 and 3/4_ reactor vessel wall thickness locations for all potentially limiting materials using Regulatory Guide 1.99 Revision 2 and making a comparison of these values with the reference trweratures that ' were the basis for the pressure-tempe* ature (P/T) li: nits in the current plant Technical Specificaticas.
- 2) Determining the date of applicability of the P/T limits using Regulatory Guide Revision 2.
s
- 3) If the use of the Revision 2-methodology may result in a modifica-l tion of the P/T limits contained in the Technical Specification, a proposed schedule must be defined for whatever actions need to be taken, including those required to address an expected restriction in operating flexibility. If such actions are.necessary (e.g.,.new P/T' limits, procedure and hardware modifications, etc.), a schedule for completion (fully implemented and operational) is negotiable as uwmm io 1
- c. .
long as all actions are completed within two plant outages (approxi-mately 3 years) after the effective date of Revision 2 to Regulatory I Guide:1.99. 4)- Recalculation of reference temperatures for pressurized thermal shock (RTPTS), if so desired by the licensee, since the NRC is
. presently 'considering an amendnent to the PTS Rule,10 CFR 50.61 (3). This amendment will replace the equations for RT PTS in the ~
PTS Rule with the calculational procedure of Revision 2 to-Regulatory', Guide 1.99,-but will not change the screening criterion. ] Following a discussion of the. Regulatory Guide 1.99 Revision 2 methodology.in section 2, the results of the above technical analysis are then provided. Items 1 and-2 are presented in section 3, and revised RTPTS values (item 4) are shown in section 4. Conclusions'are given in section 5 and are followed. by'the:refe'rences for the report in section 6. . i a L l 1 l L Nwe 11tssa 1o g
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- 2. REGULATORY.-GUIDE-1.99-- REVISION 2 METHODOLOGY (2) 2.1 Surveillance Data Not Available When credible surveillance data from the reactor in-question are not available, calculation of neutron radiation embrittlement of the beltline reactor vessels of light-water reactors should be based on the procedures below.
The adjusted reference, temperature (ART) for each material in the beltline is given by the following expression: ART = Initial RTNDT + ARTNDT + Margin '(1) Initial RT NDT is the reference temperature for the unirradiated material-as defined in Paragraph NB-2331 of Section 111 of the ASME Boiler and Pressure . Vessel Code (4). If measured values of initial RT NDT f r the material in question are not available, generic mean values for that class
- of material may' be used if there are sufficient test results to establish a mean and standard deviation for the class.
.ARTNDT. is the mean value of the adjustment in reference temperature caused -
by irradiation and should be calculated as follows: ART NDT = (CF) f(0.28 - 0.10 log f) (2) CF (*F) Is the chemistry factor, a function of copper and nickel content. CF is given in tables for welds _and base metal-(plates and forgings) in the Guide and linear interpolation is permitted to obtain the value. In the table, the
" weight percent copper" and " weight percent nickel" are the best-estimate values for the material, which will normally be the mean of the measured values for a plate or forging or for weld samples made with the weld wire heat number that matches the critical vessel weld. If such values are not
*The class for estimating initial RT is generally determined, for the welds with which this guide is conceNd, by the type of welding flux (Linde 80 or other); for base metal, by the ASTM Standard Specification, uwmm io 3
available, the upper limiting values given in the material specifications-to which the vessel was built may be used. If not available, conservative estimates (mean plus one standard deviation) based on generic data may bc ,ced m if justification-is provided. If there is no information available. 0.35% copper and 1.0% nickel should be assumed. ,
-The. neutron fluence at any depth in the vessel wall, f(10 19 n/cm2 , E > 1 MeV'),
is determined as follows: r
-0.24x) (3) f = f'urf s (e 19 n/cm2 , E > 1 MeV) is the calculated value of the where~fsurf (.10 neutron fluence at the inner wetted surface of the vessel at the location of the, postulated'dofect, and x (in inches) is the depth into the vessel wall measured from the vessel. inner (wetted) surface. Alternatively,'if dpa calculations are made as part of .the fluence analysis, the ratio of dpa at the -
~. depth in question to dpa at the inner surface may be substituted for the exponential attenuation factor in equation 3.
l= ; The fluence factor, f(0.28 -.0.10 log f) , is determined by calculation or q
.fromia figure in'the guide.
g " Margin" is the quantity, 'F, that is to be added to obtain conservative, upper-bound values of adjusted reference temperature for the calculations required by Appendix.G to:10 CFR Part 50.
-Ma'rgin = 2 a 2 , ,2 (4)
Here',-og is the standard deviation for the initial RTNDT. If a measured L
- value of= initial RT NDT f r the material in question is available, og is L :to be estimated from the precision of the test method. If not, a generic mean
- values for that class of material are used, og is the standard deviation obtained from the set of data used to establish the mean.
The standard deviation for ART NDT' A, is 28'F for welds and 17'F for. base metal, except that o need3 not exceed 0.50 times the mean value-of ART NDT' un,-mus to 4 l-
- l. . . .
2.2 Surveillance Data Available When two or more credible surveillance data sets become available from the reactor in question,-they may be used to determine the adjusted reference temperature of the beltline materials.
.The adjusted reference temperature should be obtained as follows. First, if there is clear evidence that the copper or nickel content-of the surveillance weld differs from that of the vassel weld, i.e., differs from the average for the weld wire heat number associeted with the vessel weld and the surveillance weld, the measured values of ARi @T should be adjusted by multiplying them by the ratio of the chemistry factor for the vessel weld to that for the surveillance weld. Second, the surveillance data should be fitted using equation 2 to chtain the relationship of ART to fluence. To do.so, the NDT l chemistry factor, CF, is calcul.ated for the best fit by multiplying each adjusted ARTNDT by-its corresponding fivence factor, summing thi. products, l and dividing by the sum of the squares of the fluence factors. The resulting l value of CF.when entered in equation 2 will give the relationship of _
I ARTNDT to fluence that fits the plant surveil' lance data in such a way as to minimize the sum of the squares of the errors. I To calculate'the margin in this case, equation 4 is used; the values given there for a o 3-may_be cut in half. 4
-If this procedure gives a higher value of adjusted reference temperature than -!
that given.by_using-the procedures in section 2.1, the surveillance data should be used. If this procedure gives a lower value, either may be used. l For-plants having surveillance data that are credible in all respects except that the material does not represent the critical material in the vessel, tho
- calculative procedures in this guide should be used to obtain mean values of shift, ART In calculating the margin, the value of a 3may be NDT.
t- reduced .from -the values given in the last paragraph of section 2.1 by an amount to be decided on a case-by-case basis, depending on where the measured values fall relative to the mean calculated for the surveillance materials, me..m* " 5 L
- 3. TECHNICAL ANALYSIS 3.1 Identification and Location of Beltline Region Materials Figure 1 identifies and indicates the location of all beltline region materials for the Braidwood Unit 1 reactor vessel. The beltline region is defined to be "the region of the reactor vessel (shell material including welds, heat affected zones, N plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor 1 vessel that are predicted to experience suf ficient neutron irradiation damage to be considered in the selection of the most limiting material with regard to radiation damage" [2].
3.2 Definition of Plant-Specific Materiai Properties, The pertinent chemical and mechanical properties of the baltline region shell - forgings and girth weld materials of the Braidwod hii; 1 reactor vessel are given in table 1. The " weight percent copper"(Cu) and " weight percent nickel"(Ni) material chemistry values.and the initial RTNDT (I) values shown in the table are the same as those used in the Braidwood Unit 1 pressurized thermal shock sub:nittal [5] except as noted. The chemistry factors and " margin" (M). terms that are also shown in table 1 were determined in accordance with the Regulatory Guide 1.99 Revision 2 methods described .in section 2. The chemistry factors and margins are based upon material chemistry mea'surement information since credible surveillance data are not yet available for .the Braidwood Unit i reactor vessel materials. un .msu ,o s
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Forging
.' EE 49D383/49C344-1-1 270'- 90' f
e. N CORE s 180'
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Forging 490867/490813-1-1 b w 270 90' l I E 180' FIGURE I IDENTIFICATION AND LOCATION OF BELTLINE REGION MATERIAL FOR THE BRAIDWOOD UNIT 1 REACTOR VESSEL M10e-11144410 7
l TABLE 1 BRAIDWOOD UNIT 1 REACTOR VESSEL BELTLINE REGION MATERIAL PROPERTIES Cu Ni 1(8) M(b) . Material (Wt.%) (Wt.%) CF (*F) (*F) Intermediate Shell 0.05 0.73 31 -30 34 Forging 490383/49C344-1-1 Lower Shell 0.03 0.73 20 -20 34 Forging 490867/490813-1-1 Circumferential Weld WF 562 0.04(c) 0.67(c) 54 40 56 (a) The initial RTNDT (1) values for the forgings and weld are measured values. (b) Maximum margin (M) as per Reg. Guide 1.99, rev. 2; the standard deviation for the initial RT NOT margin term is assumed to be zero since the initial RTNDT values were obtained from conservative (i.e., " upper bound") test results. Smaller values are obtained when 3o = 1/2 ART NDT' (c) These values from Weld Certification Test Report WF562 (Appendix A) are higher than the values of 0.03% Cu and 0.67% Ni used in the PTS submittal
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_ _ _ - --_ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ - _ - . - - _ _ m
Drvwell Temeerature V Time Temeerature Zustification 0700 129'F Normal 0800 129'F Temperature increase until ESW system is made available for drywell cooling 0802 135'F Drywell cooling in-service 1200 115'F A
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l l l Drvwell Pressure T.ip_q Pressure Justification 0700 1.9 psig Accident events have no effect on drywell pressure 1200 1.9 psig O O 3-9 -
l 1 I l Torus Pressure l Time Pressure Justification : 1 0700 -0.1 psig Normal pressure 1200 0.1 psig i, ( l l l l l k 3-10 j l l l
q Torus Water TemDerature Time Temoerature Justification 0700 76*F Normal temperature 0802 76"F HPCI/RCIC controlling ve7sel level and pressure 1200 82*F 1 l l l l I V 3-11
<- HREM
( Turbine Buildina Exhaust x_- Time Hiah Rance Just' fication 0700 0 mR/hr Normal HREM reading 0845 0 mR/hr l Break in main steam line drain l pipe releasing activity in steam tunnel and Turbine Building 0900 0.1 mR/hr Release through Turbine Building ventilation initiated 0915 0.25 mR/hr Release through ventilation , exhaust continues ' 1130 0.25 mR/hr (T \~s' Activity in Turbine Building has diminished 1145 -0 mR/hr ( \-) 3-12
,m- Drywell Radiation Monitor Tiine Dose Rate JustificatioD 0700 8 R/hr Normal reading at 100% power 0800 8 R/hr Reactor scram l 0802 2 R/hr Normal reading 1200 1 R/hr C\ V O 3-13
VESSEL LEVEL-W 250---~~~~~~~~<----~~~~~~~r----~~~~~~r---------~~ V - I 200-
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. - - - " - - t. -. ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 T ing ---_--_-----9-_.--..~.._---p.-_--_--_--_p'-_-----___.-
A , i T-so...---.-.- -.-.-.4._--_-.---- --;.~..-.--.--- -- +.-~.--_-.-.-. .j p I i i 0700- 0800 0802 0807 1200 TIME u l:__ r-UESSEL PRESSURE 1000 - - "--~~"-~~~:-~~~~~ . -~~r.-~~~~~~- --:. 800-~~~---------i.~~---~~~~~4.--~~-------;.-----~~~~~--I. P : : : : i 600-- ----~~ --"-i--~~ ----- - : -~~~~~---t~~~~~~~~~~~: t S : : : s
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3-14 l la
l 1 l SECTION 3-I X .. James A. FitzPatrick Nuclear - er-Plant
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1990-Partial Scale Emergency 'Xercise December 19, 1990 I DOSE ASSESSMENT DISPLAYS The following displays are examples of the type of MMRAS-Computer Model outputs used to obtain dose projections. The outputs were ! obtained for a projected single phase steam line break at 15-minute intervals over the projected release duration. On the day of-the exercise, actual meteorological conditions will be used to determine the direction and concentration of the atmospheric release. i l: _ O 3-15
-.m-. x.,...,... . _ . _ . , ., _ ..m,. , _.,,
O Continuous release, due to Steam Line break Isotope Source Strength Isotope Source Strength (Ci/sec) KR-83M 0.000E-01 MN-54 0.000E-01 KR-85M 2.652E-01 C0-58 0.000E-01 KR-87 5.188E-01 CD-60 0.000E-Oi KR-88 7.288E-01 FE-59 0.000E-01 XE-133 2.173E+00 ZN-65 0.000E-Oi XE-135M 0.000E-01 SR-89 0.000E-Oi XE-135 2.812E-01 SR-90 0.000E-01 XE-138 0.000E-01 SB-125 0.000E-Oi I-131 3.200E-03 TE-132 0.000E-Oi I-132 5.200E-03 CS-134 0.000E-Oi I-133 8.400E-03 CS-136 0.000E-01 I-134 9.200E-03 CS-137 0.000E-01 1-135 7.200E-03 BA-140 0.000E-01 H-3 0.000E-01 LA-140 0.000E-01 Total ~ release is 4.000E+00 Ci/sec ({]) Do you wish to change total source strength value (Y/N)? E O 3-16
i PLUME DISPLAY i (ggAt 7ing) e g.15 n ii-0CT-90 10 . ,.' 12: 4 ON. .., I g "
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/ MAX LO!E; RATE 5 (MREM /Hr )
(mils,dsg) .W.Eody C. Thy. f W5 (mph) 3.2 i s.E( .0, .0) 0.CE-01 0.0E-01 WD (deg) 63.2 2Ml( .0, .0) 0.0E-01 0.0E-Oi 59 A Sh G SMl( .0, .3) 0.0E-01 0.0E-01 10Ml( .0, .0) 0.0E-01 0.0E-01 3-17
l (N x.) : OFF-SITE RECEPTORS (REAL-TIME) 0- 0:15 11-00T-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma. Skin Whole Skin Child (Miles) (Degree) Body Thyroid THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT O i " ENTER-(i=page one, LINE FEED =page forward, B=page back, M= menu) : _ l
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0FF-SITE RECEPTORS (REAL TIME) 0- 0:30 li-0CT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 2 i 1.5 222.6 .66 1.1 .16 .28 .70 4 i .8 221.3 1.5 2.5 .38 .62 1.2 THE GAMMA VOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT O ENTER (i=page one, LINE FEED =page forward, B=page back, M= menu) : a 3-20
.i PLUME DISPLAY ' (REAL TIME) 0- 0:45 1-1-007-90 0
1 ~2 .*' 3- 337. 5 1 22.5 r 215 45 i 26 27 232.5 j 67.5 1 LAKE ONTAR IO 270 - 5 4 3 2 1/N3 Ns g N _- 30
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i l { OFF-SITE RECEPTORS (REAL TIME) 0- 0:45 11-0CT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 2 i 1.5 222.6 .92 1.3 .40- .60 .72 4 i .8 221.3 0.00E-01 0.00E-01 .38 .62 1.2 5 i 1.0 206.6 1.2 1.7 .31 .43 4.45E THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT O >g ENTER (i=page one, LINE FEED =page forward, B=page back, M= menu) : [
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, . _ _ _ _ . .__.__.. _ _ ~ _ _._ _ ._ _ _. _ _ _ _ _ _ _ _ .-. _.
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(mile,deg) ,W.Sody- C. Thy.
-W5 L(mph)- .3,4 j ( 1.5,193.8)-2.5E+0i c.B 5.3E+02 1 WD<(deg) - 20, 3 -
I 2MI( i.6.196.5) 2.iE+0i 4.0E+02 5 v -- E Sh G- SMl( .0 .0)-0.0E-01: 0.0E-01 10Ml( . 0 ,_
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O OFF-SITE RECEPTORS (REAL TIME) 0- 1: 0 ti-0CT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Lyree) Body Thyroid 2 i 1.5 222.6 0.00E-01 0.00E-Oi .40 .60 .72 3 1 2.0 201.2 14. 36. 3.4 9.1 59, 4 i .8 221.3 0.00E-Oi 0.00E-Oi .38 .62 1.2 5 1 1.0 206.6 0.00E-01 0.00E-01 .31 .43 4.45E-02 7 1 1.0 173.6 5.5 8.0 1.4 2.0 2.0 24 3 3.0 209.5 5.7 17. 1.4 4.2 33. 25 3 2.9 208.2 3.i 8.4 .77 2i 16, 27 3 1.9 205.2 3.4 6.7 .85 1.7 7.4 THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT O ENTER (i=page one, LINE FEED =page forward, B=page back, H= menu) : 8 3-24
i l PLUME DISPLAI , (gggt 7 igg) c. 1 15 ) 11-007-90 l 0 p. - ' i
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.WD.(deg) 13.1 i.5,177.0) 5.0E-01 8.2E+00
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t jy ' A> _ 0FF-SITE RECEPTORS (REAL TIME) 0--1:15 11-00T-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child-
.(Miles) (Degree) Body Thyroid 2 1 1.5 222.6 0.00E-01 0.00E-01 .40 .60 .72 3 1 2.0 201.2 0.00E-01 0.00E-01 3.4 9.1 59, 4 i .8 221.3- 0.00E-Oi 0.00E-01 .38 .62 1.2
-5 i 1.0 206.6 0.00E-Oi 0.00E-01 .31 .43 4.45E-02 7 1 1. 0 - 173.6 0.00E-01 0.00E-01 1.4 2.0 2.0 24 3 3.0 209.5 0.00E-01 0.00E-01 1.4 4.2 33.
-25 3 2.9 208.2 0.00E-01 0.00E-01 .77 2.1 16, 27- 3 1.9 205.2 0.00E-01 0.00E-01 .85 1.7 7.4-130 3 2.6 184.9 .52- .81 .13 .20 .33 E.. 31- 3 2.0 182.3 .67 .97 .17 .24 .17 l
Of h ENTER (i=page one, LINE FEED =page forward, B=page back, H= menu) : I o l l l O 3-26
l I i kf A: i 1 0FF-SITE RECEPTORS (REAL TIME) 0- 1:15 0CT-90
-ERPA- -Receptor Dose Rate (mR/hr) Cumulative Dose (MREM)
Distance Direction Gamma Skin Whole Skin Child
-(Miles) (Degree) Body- Thyroid
.88 11 4.9 210.5 .15 .21 3.72E-02 5.37E-02 6.23E-03 THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT ENTER'(i=page one, LINE FEED =page. forward, B=page.back, M= menu) : E I'
3-27 l l
. . . _ . _ _ . _ _. ._ _ _ _ _ _ _ _ __ _. _ = _ .
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l' 135 e g ' MAX D05E RATE 5 (MREM /Hr ) smile,deg) .W.Sody C. Thy' . W5-(mph) E.0 -
- .B(-1.4,158.5) 1.iE+00 7.0E+00 WD'(deg). 1.6 I EMI. 1.?',167.7) 5.5E-01 4 . 7 E + 0 0 --
Sv A - Sh G EM:( 4.7,1?1,7) 2.4E-01 2.EE+00 10MI( .0, .0) 0.0E-01 0._0E-01. 3-28
1 l O 1 L) ! 0FF-SITE RECEPTORS (REAL TIME) 0- 1:30
.ii-0CT-90
-ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM)
Distance Direction Gamma- Skin Whole Skin Child (Miles) (Degree) Body Thyroid ' 2 i- 1.5 222.6 0.00E-01 0.00E-01 .40 .60 .72 3 1- 2.0 201.2 0.00E-Oi 0.00E-Oi 3.4 9.1 59. 4 i .8 221.3 0.00E-Oi 0.00E-01 .38 .62 -1.2 5 i 1.0 206.6 0.00E-01 0.00E-01 .31 .43 4.45E-02 L7 i 1.0 173.6 0.00E-01 0.00E-01 1.4 2.0 2.0 8 i 1.7 169.0 .79 1.1 .20 .28 4.70E-02 i 9 i 1,1 153.7 2.3 3.4 .58 .85 .53 24- 3 3.0 209.5 0.00E-01 0.00E-01 1.4 -4. 2 33. 25 3 2.9 208.2 0.00E-Oi 0.00E-01 .77- 2.1 16. n lQ ENTER (i=page one, LINE FEED =page forward,-B=page back, M= menu) : 5 r t v / b 3-29
O OFF-SITE RECEPTORS (REAL TIME) 0- 1:30 ti-0CT-90 ERPA Receptor Dose _Ratt (mR/hr) Cumulative Dose (MREM)
~~~~~
6Istance~~~6INetio~n ~~5555a'~~~~5kI~'~ n "UhoIe~~~~~~ Skin ~~~~~~ChIId (Miles) (Degree) Body -Thyroid I 27 3 1.9 205.2 0.00E-01 -0.00E-01 .85 1.7 7.4 28 3 3.9 188.9 .29 .41 7.28E-02 .10 1.07E-02 30 3 2.6 184.9 0.00E-01 0.00E-01 .13 .20 .33 L 31 - 3 2.0 182.3 0.00E-01 0.00E-01 .17 .24 .17 L 45 4.0 186.8 .35 .63 8.74E-02 .16 .54 l 47. 5 4.0 183.2 .34 .52 8.43E-02 .13 .19-87- 11 6.2 204.0 9.88E-02 .15 2.47E-02 3.68E-02 2.56E-02 88 11 '4.9 210.5 0.00E 0.00E-Oi 3.72E-02 -5.37E-02 .6.23E-03 l _ 89 11 _ 6.0 204,i .10 .15. 2.59E-02 3.75E-02 6.56E-03 THE_ GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT l( ENTER (i=page one,-LINE FEED =page forward, B=page back, M= menu) :-_m LO 3-30
l l
',(
l PLUME DISPLAY ' (REAL THE) 0- 1 45 l 11-007-30 13:37
- g. 337.5 I 13.5 Af N.
215- 45 15 2? \ \ 2?2.5 ' LA g 0NTAR e 0
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-15
\ 135 255 20 MAX D05E. RATES (mREH/Hr )
j mile,deg) .W. Body C. Thy.
'W5 (mph) 5.5 i e.B( i.5.133.0) 1,7E+00 1.0E+0i
. WD-(deg) 342.5 EMl( 2.1.151.0) 5.iE-01 5.4E+00 SV A ib G SMl(-4.9,174.3).2.8E-01 3.iE+00.
10Ml( .0, .0)-0.0E-Oi 0.0E O L 3-31
I J l l Lh 0FF-SITE RECEPTORS (REAL TIME) 0 ;1:45-11-0CT-90 ERPA' Receptor Dose Rate (mR/hr) Cumulative Dose _(MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) _( Degree) Bady Thyroid 2 i 1.5 222.6 0.00E-Oi 0.00E-01 .' 4 0 .60 .72 3 1 2.0 201.2 0.00E-01 0.00E-Oi 3.4 9.1 59. 4 i .8 221.3 0.00E-01 0.00E-01 . 38- .62 1.2 5 i :1.0 206.6 0.00E-01 0.00E-01 .31 .43 4.45E-02 7 i 1.0 -173.6 0.00E-01 0.00E-01 1.4 2.0 2.0 8 i 1.7 169.0 0.00E-01 0.00E-01 .20 .28 4.70E-02 9 i :1.1 153.7- 0.00E-Oi 0.00E-01 .58 .85 .53 10 1- - 1, .0 128.8 5.3 9.4 1.3 2.4 6.0
'11 i 1.2 135.2 2.8 '4.5 .70 1.1 1.7
() ' ENTER (i=page one,.LINE FEED =page forward, B=page back, M= menu) : 5 l - l. l' l 1 1' l l O 3-32
). '
OFF-SITE RECEPTORS (REAL TIME) 0- 1:45 11-00T-90
.ERPA Receptor Dose Rate (mR/hr)- Cumulative Dose (MREM)
Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid I l i 12 1 2.0 151.6 .77 1.2 .19 .31 .59 17 2 1.8 151.9 .68 .95 .17 .24 5.66E-04
.24 -3 3.0 209.5 0.00E-01 0.00E-01 1.4 4.2 33, 25 3 2.9 208.2 0.00E-01 0.00E-01 .77 2.1 .16, 27 3- 1.9 205.2 0.00E-01 0.00E-01 .l5 8 1.7 7.4 28 3 3.9- 188.9 0.00E-01 0.00E-01 7.28E-02 .10 1.07E-02 30 3 2.6 184.9 0.00E-01 .0.00E-Oi .13 .20 .33
.31 3- 2.0 182.3 0.00E-Oi 0.00E-01 .17 .24 .17 45 5 4.0 186.8 0.00E-Oi 0.00E-01 8.74E-02 .16 .54 47 5 4.0 183.2 0.00E-Oi 0.00E-01 8.43E-02 .13 .19 5, .
(.. ENTER (i=page one,.LINE FEED =page forward, B=page back, H= menu) : . LO 3-33
t O OFF-SITE RECEPT 0RS (REAL TIME) 0- 1:45 l 11-007-90 l ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) l.' ___________________ __________________ _______________________________ Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 48 5 6.2 181.4 .12 .18 3.01E-02 4.44E-02 1.96E-02 49 5 2.7 162.6 .59 .82 .15 .20 1.86E 50_ 5 3.8_ 166.6 .39 .59 9.63E-02 .15 .18 51 5- 3.1 163.5 .52 .93 .13 ,23 .71 52 5 . 3. 6_ 164.7 .40 .58 9.31E-02 .14 8.97E-02 59 6 3.7 168.4 .43 .75 .11 .19 .54 79 10 5' 8-
, 180.2 .15 .25- 3.64E-02 6.14E-02 ,15 87 11- 6.2 204.0 0.00E-01 0.00E-01 2.47E-02 3.68E-02 2.56E-02 88 11 4.9 210.5 0.00E-01 0.00E-Oi 3.72E-02 5.37E-02 6.23E-03 89 11- 6.0 204.1 0.00E-01 0.00E-01 2.59E-02 3.75E-02. 6.56E-03 O
v ENTER (i=page one, LINE FEED =page forward, B=page back, M= menu) : ! i 1 10 3-34
1 0FF-SITE RECFPTORS (REAL TIME) 0- if45 it-CCT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 91 11 6.0 188.3 .10 .15 2.59E-02 3.74E-02 3.58E-03 157 19 7.0 188.7 .13 .28 3.23E-02 6.92E-02 .43.
'THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT
.-O lj ; ENTER (i=page one, LINE FEED =page forward, B=page back, H= menu) : E L
./
3-35
O PLUME DISPLAY > (REAL TIME) 0- 1: 0 ti-00T-?0 0 13:52 g 237.5 i 15.5 e - - _ .i 315 IB
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.N./^M,3' / W.E0dy C. Thy.
f 1 .5(g. i.3.113.3) mile,dfei) 3.iE+00 .1.EE+0i
' W5 (mph) 6.4 D- I ~
EMl( 2.2.137.5) 6 !E-01 4.6E+00 WD (deg) 32?.E SV A Sh G SM ( 5.0,1E0,7) 2.4E-01 1.5E+00 10M.( .0, .0) 0,0E-Oi 0.0E-01 0 3-36
I) 0FF-SITE RECEPTORS (REAL TIME) 0- 2: 0
'~' ii-0CT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM)
Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 2 1 1.5 222.6 0.00E-01 0.00E-Oi .40 .60 .72 3 1 2.0 201.2 0.00E-Oi 0.00E-Oi 3.4 9.1 59, 4 i .8 221.3 0.00E-Oi 0.00E-Oi .38 .62 1.2 5 i 1.0 206.6 0.00E-01 0.00E-01 .31 .43 4.45E-02 7 i 1.0 173.6 0.00E-Oi 0.00E-01 1.4 2.0 2.0 8 i 1.7 169.0 0.00E-01 0.00E-01 .20 .28 4.70E-02 9 i 1.1 153.7 0.00E-01 0.00E-01 .58 .85 .53 10 i 1.0 128.8 0.00E-01 0.00E-01 1.3 2.4 6.0 11 i 1.2 135.2 0.00E-01 0.00E-Oi .70 1.1 1.7 Iv ;Et4TER (i=page one, LIi4E FEED =page forward, B=page back, H= menu) : 3 l 3-37 i
3 O OFF-SITE RECEPiORS (REAL TIME) 0- 2: 0 11-00T-90 ERPA Receptor Dose Rate (mR/hr) Cumulative base (MREM) 4 Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 12 1 2.0 151.6 0.00E-Oi 0.00E-Oi .19 .31 39 13 i 1.3 117.5 2.7 3.8 .67 .94 8.18E-06 15 1 2.2 140.2 .60 .87 .15 .22 .11 17 2 1.8 151.9 0.00E-Oi 0.00E-Oi .17 .24 5.6EE-04 24 3 3.0 209.5 0.00E-Oi 0.00E-01 1.4 4.2 33, 25 3 2.9 208.2 0.00E-01 0.00E-01 .77 2.1 16. 27 3 1.9 205.2 0.00E-Oi 0.00E-01 .85 1.7 7.4 28 3 3.9 188.9 0.00E-01 0.00E-01 7.28E-02 .10 1.07E-02
- 30. 3 2.6 184.9 0.00E-Oi 0.00E-01 .13 .20 - . 33 31 3 2.0 '182.3 0.00E-Oi 0.00E-Oi .17 .24 .17 ENTER (i=page one, LINE FEED =page forward, B=page back,.M= menu) : .
O 3-38
. = . - . . - - - . . - - - _ _ . . . - . - . - . . . . - - . - . .- ,- . - . - - . . ,
J M G M e.py w w. O 0FF-SITE RECEPT 0RS (REAL TIME) 0- 2: 0 ti-0CT-90 ERPA Receptor Dose Rate (mR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 45 5 4.0 186.8 0.00E-01 0.00E-01 8.74E-02 .16 .54 47 5 4.0 183.2 0.00E-Oi 0.00E-Oi 8.43E-02 .13 .19 48 5 6.2 181.4 0.00E-01 0.00E-Oi 3.01E-02 4.44E-02 1.96E-02 49 5 2.7 162.6 0.00E-Oi 0.00E-01 .15 .20 1.86E-02 50 5 3.8 166.6 0.00E-Oi 0.00E-01 9.63E-02 .15 .iB 51 5 3.1 163.3 0.00E-Oi 0.00E-01 .13 .23 .71 52 5 3.6 164.7 0.00E-Oi 0.00E-01 9.91E-02 .14 8.97E-02 53 5 2.8 143.8 .57 1.0 .14 .26 .78 59 6 3.7 168.4 0.00E-Oi 0.00E-Oi .11 .19 .54 79 10 5.8 180.2 0.00E-Oi 0.00E-01 3.64E-02 6.14E-02 .15 OENTER (i=page one, LINE FEED =page forward, B=page back, H= menu) : E O 3-39
i 1 i () 0FF-SITE RECEPTORS (REAL TIME) 0- 2: 0 ti-0CT-90 ERPA Receptor Dose Rate (nR/hr) Cumulative Dose (MREM)
..............----- .................. ------------.................-- l Distance Direction Gamma Skin Whole Skin Child l (Miles) (Degree) Body Thyroid i 82 10 5.1 165.4 .16 .23 3.98E-02 5.71E-02 4.38E-03
- 83 10 4.9 164.0 .17 .25 4.37E-02 6.26E-02 6.70E-03 84 10 6.1 166.0 .13 .31 3.13E-02 7.76E-02 .54 85 10 7.2 165.8 7.95E-02 .18 1.99E-02 4.55E-02 .30 87 11 6.2 204.0 0.00E-01 0.00E-01 2.47E-02 3.68E-02 2.56E-02 88 11 4.9 210.5 0.00E-Oi 0.00E-Oi 3.72E-02 5.37E-02 6.23E-03 89 11 6.0 204.1 0.00E-Oi 0.00E-01 2.59E-02 3.75E-02 6.56E-03 91 11 6.0 188.3 0.00E-01 0.00E-Oi 2.59E-02 3.74E-02 3.58E-03
- 157 19 7.0 188.7- 0.00E-Oi 0.00E-01 3.23E-02 6.92E-02 .43 158 19 8.2 179.6 5.85E-02 8.52E-02 1.46E-02 2.13E-02 1.19E-02 O
(_-ENTER (i=pageone, LINEFEED =pageforward,B=pageback,H= menu) : " _ i F I l ' l l O 3-40
i O 0FF-SITE RECEPTORS (REAL TIME) 0- 2: 0 ti-0CT-90 Receptor Dose Rate (mR/hr) ERPA Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 159 19 7.1 166.4 .12 .28. 2.92E-02 7.07E .50 THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR MINUS 100.0 PERCENT O ENTER (i=page one, LINE FEED =page forward, B=page back, M= menu) : E
- O 3-41
($3) ON-SITE RECEPTORS (REAL TIME) 0- 2: 0 1 ii-0CT-90 ERPA Receptor Dose Rate (nR/hr) Cumulative Dose (MREM) Distance Direction Gamma Skin Whole Skin Child (Miles) (Degree) Body Thyroid 1 i .5 197.6 0.00E-01 0.00E-01 .88 1.8 7.1 4 2 i .6 209.2 0.00E-01 0.00E-Oi .66 .93 9.70E-02 3 i .6 224.4 0.00E-Oi 0.00E-01 .65 1.4 6.3 4 i .7 232.8 0.00E-01 0.00E-Oi .45 .62 1.63E-02
- 18. i 1.2 136.2 0.00E-Oi 0.00E-01 .65 .95 .47 THE GAMMA DOSE RATE IS ACCURATE WITHIN PLUS OR HINUS 100.0 PERCENT
-O ENTER (i=page one, LINE FEED =page forward, B=page back, H= menu) : E NO MORE DATA IN TABLES O 3-42
......e.. , .-,m . - , . . - .<, _
__% .- ..-.s. . ..r , n.-
i g SECTION 3 b# James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 METEOROLOGICAL FORECAST The attached meteorological forecast information should be completed for the exercise. Actual meteorological forecasting should be performed. O 3-43 l
1 SECTION 3 I James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 WEATHER DESCRIPTION AND FORECAST CURRENT DATE FORECAST LEVEL (FEET): CURRENT TIME: FORECASTER'S INITIALS: GENERAL WEATHER DESCRIPTION: FORECAST WIND WIND STABILITY TEMPERATURE PRECIPITATION TIME SPEED DESCRIPTION CLASS 'F (TYPF., QUANTITY)
, (LOCAL) (MPH) (FROM) u l
l l l 3-44 i
. _ . _ . _ _ _ . _ . . _ . . _ . _ _ _ _ _ _ _ _ _ . _ _ . - - - _ _ . _ _ . _ _ ~ _--. - - -- -__. _ . _ . _~
1 I l 1 r 4 SECTION 4 l i James A. FitzPatrick Nuclear Power Plant
- . 1990-Partial Scale Emergency Exercise i
December 19, 1990 MEETINGS n i i 1 J J d d' 4-1 rwe- , +*ww- -<m'a --e='e-*- - - - -e ww - - e=- +- *w--w - a + -w w . e -,e- ' ' - * -----===== ewe e*'=,--~*-==----'------------e - - - * = .- --'> -== -
. . . - - - _ . . . _ . - -. - - - . . - - . - - _ . ~ ~ . - - . - - .. ._- - . -
SECTION 4 O James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 MEETINGS December 18. 1990 1300 to 1500 NYPA, State, NRC Controller / Observer Briefing (Training Building) 1500 to 1700 NRC Training and' Badging (Training Building) December 19. 1990
-0700 to 1230 NRC Observed Partial Deale Emergency Exercise December 20, 1990 -f 0900 to 1030 Observer Debrief (Training Building - Classroom 3) 1030 to-1130- NYPA Exercise Critique- (Training Building -
Classroom 3) 1145' to 1215 NRC Exercise Critique (Training Building -
-Classroom 3) is s
i 4-2
SECTION 5 O James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exorcise December 19, 1990 TIMELINE O 5-1
i SECTION 6 4 4 James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise I December 19, 1990 EXERCISE / CONTINGENCY MESSAGES I. Controller Sheets II. Message Sheets , III. Plant'SPDS and Parameter Sheets - Sequentially - (optionti distribution) , .L O f h 6-1
,- m ,
(. I U) t v (v) FORM SAP 1.3 CONTROT.TIR SHEET Page O of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0630 N/A Initial See attached Daily Schedule Plant Briefing i Partici-pants l l
DATE December 19, 1990 Pact i
- I AcTfvity No. nrpt.
o fMP-30-1 nPard ErnN atAPt in ppm. [ Mfc Prn-Mananr M2/07 Ana ggf cal
\_ YSP-3-4 Rameter faval i n s t rumdr.~ se TEP-3-E Reacter faval MoniterJc,3 f r:a t rums._ .t a
?MP-23-1 PMW fnet calm _
PM Dutage PM Planninn PM 42TE-112L caustic Diach Le Temn Sw j PM 421T-102 caustic Sterace Tank faval Ymitter PM cYsek Can PM Walk-Thru of New Warahnuma w/farurftv PnN 99/91f4% SAE Deer Iatch inen
/65227 Refumi Aridna Headnat 00/71692 Refumi Piner Pamnta camera Mvatam
/FE409 70RfR. ci-113. 112 e E a'a t a Damnn Out Ennd 76/74930 FI-103 New Fire Pume Tant Plow Ind 76/73E41 SD-430 fene 79 Emeka Detecter 07/A0937 R1194. tPRM 28-23B. 2R-DEA 13/P0077 MTU-2R4 Mcfc Mta.m Pinw innut can
/EE111 RM-463A PW Rids Hieh Ranea~ Rad Mhniter
/73602 Ann RV-EA-12 c5hi. Em Pan ~ 4A No Plow 39/500RE9 2MD-ME Run in Pnekinn en R A-c 42/P07EE Raneir Pinheim Leak en d' f. i na Diach of 12P-11ACR 76/730ER PPM-114 PackinN f.m a k 76/73042 check Valve Devnetream et PPS-313 Mtuck onen
_,46/74101 Raelace 4EMWS-707 72/74291 72cR-11 cend Unit ciman L." mint 72/74P92 72cR-1R cond Unit clea'n & , int gNg 71/71437 JMD-EL 710PE-E - Raelaca Mattmev dB ( / 71/73311 71UPS-E - clean A1) calla 71/10676 17P-16R cramme Haarings - Pv Rut 1d yant i Mnnitnr *R* Mampla Pump __ Met n r l 71/9210 Mcc-263-Oc4 PM centre 11er fgg_2fjHU-30R _ ( 76/91252 7BP-EAfMi check Out f.av a l switgb on Pumn in En. Tank Pit,- condannata Tank *A* 71/E01140 Mwitchvard - We a k1_v
,J g QE29 EOD-32 Turb Rida Done Won't O~an 71/7E29E Haat Traea JoPE Jcs Warahnuam Encurity T.be ka r Pnne Rahab Pamave Meaffniding in crescant s
l l l t l l
f ] j I Plant status:
.O -
100% power. s 115KV Line #4 out of service due to maintenance being done by Niagara Mohawk. Estimated return to service at 0800 tomorrow. ST-1D "MSIVS and MSLDV and RWSV LFT" and ST-20C " Control Rod Operability Test" are in progress. i i I e j. O 4 1 i s l
.Q- ,
i 6-2 r
.~.._..,.-,,_._,._.___,__,_..~....____-..,_._.__,_.,_,,-,__.____.,.,m._...___...___.,_.,c ,1,-...___,._,.a..._.. , _ . . ..,;
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i-i FORM SAP 1.3 + j CONTROr.TRR SHEET Page 1 of 41 6 i MESSAGE- ANTICIPATED RESULTS AND EM M ENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION . I I i 0700 1 -Control Plant is operating at None None ! j Room 100% power. f I i ! - Annunciator 09-8-6-15 ' NMP-FITZ 115KV Line 4 BKR 10012 TRIP is sealed in due to maintenance on
- the line. NiMo r estimates return to l l service-for the #4 line i i to be 0800 tomorrow.- ;
! I j - Completion of ST-20C and j AOP-24 have identified :
i control rod 30-35 to l be stuck in the fully i withdrawn position.
, - Inboard main steam line t
', drain isolation valve r ! 29MOV-74 has failed to l close during performance ; of surveillance testing.
> t j - Plant parameters as indicated on SPDS -
display. CONTROLLER'S NOTE: Control rod 30-35 is.a member of RNM Group 1 and will not move. ! In accordance with Technical Specification 3.3.A.2.a, the reactor i must be in Cold Shutdown within 24 hours. ! k i 1 4 a
< r i l FORM SAP 1.3 t ! CONTROLLER SHEET Page 2 of 41 ! 1 > t i- MESSAGE ANTICIPATED RESULTS AND EMERGENCY j TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION I :; 0705 2 Control . Plant parameters as Continue attempts to None . Room indicated on SPDS display. free control rod. l 4 I i i i
?
l t ! I i i CONTROLLER'S NOTE: Recirc run back has reduced power to 65% and flow to 50%. f t b - t { I 1 1 ! i
k .4
~
l - i l t + t FORM SAP 1.3 { t t . CONTROLLER SHEET Page 3' of 41 -!
.i i MESSAGE -
' ' ANTICIPATED RESULTS AND EMERGENCY -
l TIME : NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS C0f9fENTS CLASSIFICATION I r i j' , Plant parameters as 0715 3 Control - Commence reactor Unusual Event ! ! Room indicated on SPDS' display. ' shutdown due to * . stuck control rod. i j - Initiate j' notifications of } l Unusual Event : classification due l to 24-hour LCO. i 5 I f l 4 5 I r i t
+
i I I r 1 ~ i r
_m _ .._ _- , O ' O
?
FORM SAP'1.3 CONTROLLER SHEET Page 4 of 41 . v MESSAGE ANTICIPATED RESULTS AND EMERGENCY , TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION i j 0730 4 Control The following annunciators - Contact Niagara Unusual Event Room alarm: Mohawk to determine l' cause for trip on j 09-8-6-10 LHH-Fitz 115KV 115KV line. i ! Line 3 Bkr 10022 ; , Trip - Discuss requirements ! for continuing plant 09-8-6-14 115KV SYS VOLT shutdown in lieu of i IDSS loss of 115KV reserve power. !
- Plant parameters as !
, indicated on SPDS ' display. [ s 4 i CONTROLLER'S NOTE: Niagara Mohawk Central regional controller informs the Control Room of a fault on the line. Maintenance crews have been dispatched in an attempt to locate the problem. l If operability of EDG's are to be demonstrated due to loss of reserve power, the "A" diesel starts but its speed ,
- oscillates excessively. t The' plant is at 50% power and 50% flow. t i
! -j , r J
A
< a .-mi -
O
~'
O t i FORM SAP 1.3 , r CONTROT.TIR SHEET - Page 5 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY ! TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION i t
- 0745 5 Control Plant parameters as Continue investigating Unusual Event Room indicated on SPDS display. problems with offsite power.
I . i i I l i . l I i f 4 t f CONTROILER'S NOTE: NiMo has suspended maintenance on the #4 line. A temporary fix for emergency restoration of power will be completed within two hours. , If necessary, the Emergency Director will be prompted to
- maintain power at 45% due to loss of offsite reserve power. '
e j
U Uy 4 FORM SAP 1.3 i i CONTROLLER SHEET Page 6 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER. ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION i 0800 6 Control The following annunciators - Determine cause of Unusual Event Room alarm: scram. 09-3-1-9 Fuel Pool Cool & - Take actions in Cln Up Trouble accordance with 09-3-1-10' Core Spray A or AOP's for loss of , B Disch Line Not power. Full 09-3-1-18 RHR A or B Disch - Review-i Line Not Full classifications and 09-3-1-19 ARM Downscale consider activating , 09-3-1-20 Refuel Area ARM emergency ' Rad Hi facilities. ! 09-3-1-29 New Fuel Storage l
- ARM Rad Hi )
09-3-1-30 Radw Bldg ARM Rad Hi I 09-3-1-39 Turb Bldg ARM Rad Hi 09-3-1-40 Rx Bldg ARM Rad , Hi i 09-3-2-7 Off Gas Supl !
- Flow Hi or Lo i
, 09-3-2-10 Off Gas Timer I Initiated , 09-3-2-17 Off Gas Rad Mon Downscale or Inop ' i
O O O FORM SAP 1.3 CONTROLLER SHEET Page 7 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY : TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION l 0800 6 Control Annunciators continued: Unusual Event I (cont'd) Room 09-3-2-19 Rx Bldg Vent Rad Mon Downscale i 09-3-3-11 Main Stu Rad Mon Downscale 09-3-3-22 HPCI Stm Leak Det Logic Pwr Fail 09-4-0-1 Cont Hi Range Rad Mon A Fail ' or Pwr Ioss 09-4-0-4 Cont Hi Range Rad Mon B Fail or Pwr Loss 09-4-0-21 PASS Gas Supl Ht ( Trace A Trouble 09-4-0-22 PASS Gas Supl Ht 1 Trace B Trouble 09-4-0-23 PASS Exh Fan Trouble l 09-4-1-16 SRV Leaking
.09-4-1-19 Rx Bldg Equip Sump A Temp Hi ,
09-4-1-20 Rx Bldg Equio Sump B Temp Si i i
O O O , s FORM SAP 1.3 CONTROLLER SHEET Page 8 of 41 i I MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION 0800 6 Control Annunciators continued: Unusual Event ,. (cont'd) Room 09-4-2-1 DW Equip Drn ! Isol V1v Closed 09-4-2-2 DW Floor Drn Isol V1v Closed 09-4-2-3 PCIS Sys A Vlv Overload or Pwr Loss 09-4-2-6 SRV Sonic Mon 1 Alarm Hi 09-4-2-11 DW Equip Sump ; Temp Hi or Cool
.Wtr Flow Lo ;
09-4-2-13 PCIS Sys B Vlv , Overload or Pwr Loss ; 09-4-2-20 RWR MG A Drv Mtr Bkr Trip i 09-4-2-21 DW Equip Sump i HI-HI or ID-ID 09-4-2-36 TIP ARM Rad H1
' 09-4-2-37 RWR.MG A Oil Mist Elia Diff '.
Press Hi - , 09-4-3-1 RWR MG A Gen i Lockout ' q i f .
L O O O i FORM SAP 1.3 CONTROT.T.RR SHEET Page 9 of 41 l 1 MESSAGE ANTICIPATED RESULTS AND EMERGENCY-TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION
. 0800 6 Control . Annunciators continued: Unusual Event j' (cont'd) Room i .
09-4-3-2 RWR Loop A Out
! of Serv 09-4-3-5 RWR Loop B Out of Serv 09-4-3-10 RWR MG B Gen I Lockout 09-4-3-11 RWR.MG A Scoop Tube Lock 09-4-3-19 RWR MG B Drv Mtr Bkr Trip 09-4-3-20 RWR MG B Scoop
' Tube Lock ; 4 09-4-3-21 RWR MG A Gen Aux Lockout
- 09-4-3-30 RWR MG B Gen Aux Lockout 09-4-3-31 RWR MG A Speed Cntrl Sig Failed 09-4-3-36 RWR MG B Oil l l; Mist Elim Diff Press Hi
- 09-4-3-40 RWR MG B Speed I Cntrl Sig Failed
- 09-5-1-1 SDIV A or B Hi Lvl Trip
?
i >
O O O FORM SAP 1.3 CONTROLLER SHEET Page 10 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIJLSSIFICATION 0800 6 Control Annunciators continued: Unusual Event , (cont'd) . Room 09-5-1-2 MSIVS Not Full Open Trip 09-5-1-3 RPS A Auto Scram , 09-5-1-4 RPS B Auto Scram l 09-5-1-5 RPS MG A Trouble 09-5-1-6 PCIS Sys A Rx Lvl ID-ID-ID 09-5-1-7 PCIS Sys B Rx Lvl ID-ID-ID 09-5-1-9 CRD Charging Wtr
- Press Lo ,
09-5-1-10 CRD Drv Wtr Filter Diff ; Press Hi 09-5-1-13 RPS A Man Scram ' 09-5-1-14 RPS B Man Scram . 09-5-1-15 RPS Mg B Trouble !
+
09-5-1-16 PCIS Sys A Stu i Tun Temp Hi ,
- 09-5-1-17 PCIS Sys B Stu ;
Tun Temp Hi 09-5-1-21 RPS Hi DW Press , . Trip 09-5-1-22 RPS Hi Rx Press Trip ; o I I i i L
=-' - ~-
,- y-~
.(.
t - Q i i l FORM SAP 1.3 CONTROLLER SHEET Page 11 of 41 i.' MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS. COMMENTS CIASSIFICATION l l 0800 6 Control Annunciators continued: Unusual Event (cont'd)- Room i' 09-5-1-24 Fdtwr Cntrl Lo i Flow Vlv Elect i Sig. Fail 09-5-1-26 PCIS Sys A Main Stm Line Flow Hi !- 09-5-1-27 PCIS Sys B Main Stm Line Flow Hi ' 09-5-1-28 Rx Wtr Lv1 Alarm i Hi or Lo ! 09-5-1-31 RPS Rx Vessel Io Lvl Trip . 09-5-1-32 RPS Main Sta l Line Hi Rad Trip l 09-5-1-36 Sys A Stu Line ! Press Lo i 09-5-1-37 Sys B Stm Line Press Io 09-5-1-41 Neutron Mon Sys ! Trip l 09-5-1-43 CRD.Accum Press Lo or Lvl Hi
- .09-5-1-44 SDIV A or B Not Drained 09-5-1-51 TCV Fast Closure Trip i I
O O . O k 't 4 FORM SAP 1.3 i
- CONTROr.T.ER SHEET Page 12 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE' CONTENTS COMMENTS CLASSIFICATION > 0800 -6 Control Annunciators continued: Unusual Event (cont'd) Room i 09-5-1-53 TSV Closure Trip 09-5-1-54 Scram Air Hdr ' Press Hi or Lo 09-5-1-55 PCIS Sys A Group I Isol 09-5-1-56 PCIS Sys B Group ' I Isol ; 09-5-1-58 Interposing Relay Sys on DC - Pwr I 09-5-2-2 Rod Withdrawal i Block 09-5-2-3 Rod Drift f 09-5-2-6 EHC Lo Press l Trip ]' 09-5-2-9 Main Turb Trip ' 09-5-2-16 Main Turb Exh Hood Hi Temp j; Trip ! 09-5-2-20 Main Turb Exh , l Hood-Temp Hi ! 09-5-2-22 RSCS In Serv 09-5-2-25 Flow Ref Off Norm ! 4 b 4 w 4 , . . ~- . . -...nw...+ - , p . ,_ -, - . _ .-
O O O FORM SAP 1.3 _ Page 13 of 41 CONTROLLER SHEET ANTICIPATED RESULTS AND EMERGENCY MESSAGE CLASSIFICATION ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS TIME NUMBER Unusual Event 0800 6 Control Annunciators continued: (cont'd) Room 09-5-2-26 Main Turb Lo Vac Trip 09-5-2-27 Main Turb Loss of Stator Coolant Trip 09-5-2-30 Main Turb Bellows Fail or Lo Vac Trip 09-5-2-32 IRM Downscale 09-5-2-34 APRM Downscale 09-5-2-35 RBM Downscale 09-5-2-36 Main Turb Hi Vib Trip 09-5-2-44 APRM Upscale 09-5-2-45 RBM Upscale or Inop 09-5-2-54 APRM Trip Sys A Inop or Upscale Hi 09-5-2-55 APRM Trip Sys B Inop or Upscale Trip 09-5-2-57 ATIS RPS Div Al or A2 Pwr Supp Fail or TU Out f of File
. gw 3
v J FORM SAP 1.3
' CONTROLLER SHEET _ Page 14 of . 41' MESSAGE . .
ANTICIPATED RESULTS AND EMERGFNCY-TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMPCNTS CLASSIFIGTION 0800- '6' Control Annunciators continued: Unusual Event (cont'd) Room
~
09-5-2-58 ATTS RPS Div Al-or A2 Gross' Fail or TU Inop 09-5-2-59 ATTS RPS Div B1 ; or B2 Pwr Supp Fail or TU Out of File 09-5-2-60 ATTS RPS Div B1 or B2 Gross Fall or TU Inop 09-6-1-3 Circ Wtr Pap 36P-1A Overload or Trip 09-6-1-10 Screen Wash Bstr Pmp 46P-6A or 6B Trip or~Cntrl' Pwr Loss 09-6-1-11 Circ Wtr Pmp 36P-1B Overload or Trip 09-6-1-14 Perimeter Drn Pap Trouble 09-6-1-18 Trvig Wtr. Screen Trip or'Cntrl Pwr Loss
. . _ . . , . _.m.. .e_, ~ . . - .
- c. .w.o-.u. ..w_ .
' 4 FORM.' SAP 1.3 CONTROLLER SHEET Page 15 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION , 0800 6' Control Annunciators continued: Unusral. Event '
.(cont'd) Room 09-6-1-19 Circ Wtr Pap -
36P-1C Overload or Trip-09-6-1-24 Stack Dilution , Fan 26FN-2A or 2B Fail-09-6-1-29 CNDSR Vac Lo i 09-6-1 SJAE Stm Press Lo 09-6-1-31 Serv' Air Hdr Press Lo 09-6-2-2. RBC Hx Disch Temp Hi~or Lo 09-6-2-9 Cond Xfer Pap. 33P-13A Lockout or.. Trip 09-6-2-12 RBC Conduct Hi i 09-6-2-19 Cond Xfer Pap. 33P-13B Lockout ! or Trip , 09-6-2-22 RBC Makeup Tk
-Lvl Hi or Lo 09-6-2-29 Cond Xfer Hdr -
Press Lo
-. -, - -. .- . - -.- - . , . . . . . ~
O O O FORM SAP 1.3 Page 16 of 41 CONTROLLER SHEET
~
ANTICIPATED RESULTS AND EMERGENCY MESSAGE COMMENTS CIASSIFICATION TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS Unusual Event 0800 6 Control Annunciators continued: (cont'd) Room 09-6-2-30 CNDSR Hotwell Lvl Hi or Lo 09-6-2-31 RBC Hdr Press Lo 09-6-2-32 RBC Hdr Press ID-ID 09-6-2-34 Serv Wtr Hdr Press Io 09-6-2-36 TBC Hdr Press lo 09-6-2-38 Breathing Air Hdr Press Lo 09-6-2-39 Serv Air Hdr Isol Vlv Closed 09-6-2-40 Breathing Air Hdr Isol Vlv Cls 09-6-3-20 RFP A & B Seal Wtr Diff Press Lo 09-o-3-30 SJAE or SPE Drn Tk Lvl Hi or Lo 09-6-3-31 Cond Pmp Disch Hdr Press Lo 09-6-3-32 Cond Demin Sys Trouble 09-6-4-1 .RFPT A Vac Lo 09-6-4-2 RFPT A Trip
~
~=
l FORM SAP 1.3 i CONTROLLER SHEET Page 17 of 41 [' MESSAGE ANTICIPATED RESULTS AND - EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION 0800 6 Control Antunciators continued: Unusual Event i (cont'd) Room . 09-6-4-3 RFPT A Oil Clr . Disch Oil Temp , Hi 6-4-4 RFPT A or B Aux Oil Pap Trouble 09-6-4-6 RFPT A or B Turning Gear , Trouble-09-6-4-8 RFPT B Vac Lo ' 09-6-4-9 RFPT B Trip 09-6-4-10 RFPT B Oil Clr Disch Oil Temp Hi 09-6-4-15 RFPT A or B Esecg Brg Oil. Pep Running , 09-7-1-3 Main Gen Auto i Reg Trip to Man ' 09-7-1-5 Unit Prim Lockout ! 09-7-1-15 Main XSFMR T-18 Temp Hi 09-7-1-26 Main Gen Exciter Filed Bkr Trip
. . - - . , . - . - . , - . - ~. - . . ~- - . .
s ,
) .
FORM SAP 1.3 CONTROLLER SHEET Page 18 of 41 MESSAGE . ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS ' CLASSIFICATION 0800 6 Control Annunciators continued: Unusual Event (cont'd) Room 09-7-1-28 Main Gen Field Grd Will Alarm only 09-7-1 Main XSFMR T-18 Trouble 09-7-2-1 Main Gen Disc 10031 Open 09-7-2-3 Fitz-Edic 345KV Line 1 Bkr 10052 Trip 09-7-2 Fitz-Scriba 345KV Line 10 ' Bkr 10042 Trip 09-7-2-8 Main Turb Brg Oil Vapor Extractor Trouble 09-7-2-10 Reboiler Lvl Cntrl Trouble 09-7-2-16 EHC Fluid Pwr Unit'Tk Trouble 09-7-2-18 Reboiler Trouble 09-7-2-21 345KV Bkr 10042-Ext Dry Time or Loss of AC for Htrs _ =- -- _ _ ~ , - _ _ ._1 _ . -
r m ,-<. .I '
}
.. : v
' FORM SAP 1.3 CONTROLLER. SHEET Page 19 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY' TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0800 6 Control Annunciators continued: Unusual Event (cont'd) Room 09-7-2-32 Main Gen Core Mon Trouble 09-7-3-1. Main Turb Brg 3 Lift Pap Trouble 09-7-3-2 Main Turb Brg 4 Lift Pap Trouble 09-7-3-3 Main Turb Mtr Drvn Suct Oil Pap Trouble 09-7-3-8 Main Gen Stator Wtr Sys Trouble 09-7-3-13 Main Turb Brg 5 Lift Pap Trouble 09-7-3-14 Main Turb'Brg 6 Lift Pmp Trouble 09-7-3-19 Main Gen Emerg
~
Seal Oil Pap Running 09-7-3-22 Moist Sep Drn Tk 2A Lvl Lo 09-7-3-24 2nd Stage RHTR , Drn Tk 4A Lvl Lo 09-7-3-25 Main Turb Brg 7 Lift _ Pap Trouble
4 ,s 7 s_ j .- FORM SAP 1.3 CONTROLLER SHEET. Page 20 of - '4 1 MESSAGE ANTICIPATED RESULTS AND. EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0800 6 Control Annunciators continued: Unusual Event (cont'd) Room 09-7-3-26 Main Turb Brg 8
~ Lift Pmp' Trouble 09-7-3-29 EHC Pap A or B Trip or Cntrl Pwr Loss 09-7-3-32 SPE Fan Overload Cntrl Volts Lo 09-7-3-38 Main Turb Turning Gear Oil Pmp Running 09-7-3-40 Main Stm Leads '
Drn Pot Lvl Hi 09-7-3-43 SPE Vac Lo 09-7-3-44 Seal Stm Hdr Press Lo 09-7-3-46 Moist Sep Drn Tk ' 28 Lvl Lo 09-7-3-48 2nd Stage RHTR-Drn Tk 48 Lvl Lo 09-8-1-4 Computer Cntrl Volt' Trouble 09-8-1-8 UPS'on DC Drive .. 09-8-2 EDG C Load Bkr 10512 Closed
FORM SAP-1.3 CONTROLLER SHEET Page 21 of 41-
-MESSAGE ' ANTICIPATED RESULTS AND EMERGENCY-TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0800 6 Control Annunciators continued:. Unusual Event (cont'd) Room ~ 09-8-2-8 Bus 10300-10500 Tie Bkr 10514 Trip or Cntrl Pwr Loss 09-8-2-9 EDG A Eng Trouble or Shutdown 09-8-3 10100 or 10200 or 10300 or 10400 Prolong UV Trip 09-8-3-17 Bus 10300-10500 4KV Tie Bkr 10304 Trip 09-8-3-18 L13 L23 L33 L43 > 4KV Supp Fdr Bkr 10340 Trip 09-8-3-23 L14 L24 L34 L44 I 4KV Supp Fdr Bkr 10440 Trip 09-8-3-24 4160V Bus 10500 Degraded Voltage ~ Timer Initiated 09-8-3-26. Bus-10300 Norm Supp Bkr 10302 Trip.
.w.. ...<<,-.a.-. - .a
- g. e .- -- . . . - - - - , , .
- p. ,3 _ _
1 I FORM SAP 1.3
- CONTROLLER SHEET Page 22 of 41' ..,
l MESSAGE .
. ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION. 0800 6 Control Annunciators continued: Unusual Event'~ -
'(cont'd) Room 09-8-3-32 Bus 10400 Norm Supp Bkr 10402
. Trip 09-8-4-1 Bus 10400-10600 Tie Bkr 10614
Trip or Cntrl Pwr Loss 09-8-4-3 EDG B Load Bkr 10602 Closed 09-8-4-6 EDG D Load Bkr 10612 Closed. 09-8-4-11 EDG B Eng Trouble or Shutdown 09-8-4 EDG D Eng Trouble or Shutdown 09-8-5-3 Bus 10100 Norm Supp Bkr 10102 Trip-09-8-5-13 Bus 10700 Supp Bkr 10702 Trip 09-8-5-15 Bus 10200 Norm Supp Bkr 10202 Trip
l p- ,m .s. 1 I
- FORM SAP.1.3 CONTROLLER SHEET Page 23 of 41 MESSAGE' _
ANTICIPATED RESULTS'AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS' CCMIENTS CLASSIFICATION. 0800 6 Control Annunciators. continued: Unusual Event (cont'd) Room 09-8-6-1 IRH-Fitz' 115KV Line 3 Prim Relay Trip 09-8-6-10 IRH-Fitz 115KV Line 3 Bkr 10022 Air Lo or AC Pwr Loss 09-8-6-14 115KV SYS Volt Loss 09-8-6-15 NMP-Fitz 115KV Line 4 Bkr 10012 Trip
- HPCI/RCIC auto initiate
.and control level.
"B", "C" and "D" EDG's start and load the 10500 and 10600 buses. .
- Plant parameters as indicated on SPDS display.
O O O FORM SAP .3 CONTROLLER SHEET Page 24 of 41 ANTICIPATED RESULTS AND EMERGENCY MESSAGE CLASSIFICATION TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS 6 Control Unusual Event 0800 (cont'd) Room CONTROLLER'S NOTE: Main turbine #8 bearing vibration jumped to 10.0 mils, causing turbine' trip and subsequent scram. Steam tunnel temperatures are not available until RPS is i After RPS restoration, temperature indications of l restored. 200*F near the break and 160*F further down the tunnel are available. Only 10500 and 10600 emergency bus loads remain powered (see attached list). Drywell temperatures increase until ESW is lined-up to coolers. HPCI and RCIC are in manual control.
NEW YORK POWER AUTHORITY
/ JAMR$ A. FITZPATRICK NUCLEAR .WER PIANT t,g] ABNORMAL OPERATING PROCEDLRE l
TITLE: 1455 0F 10500 BUS
- NO. F.AOP 18
- 16. Upon restoring 10500 bus to service:
- a. Restore isolated systems to service in accordance with F.
AOP 15, Recovery from Isolations,
- b. Place LPCI A, 24 VDC A, and Station A Batteries on float or equalize charge as necessary,
- c. Restore to service equipment isolated to minimize battery loads.
- D. sinounY OF TMPORTANT 10500 RUs inAns:
- 1. RHR A and RHRSV A Systems
- 2. Core Spray System A -
- 3. CRD Pump A
[ 4. SCT System A
- 5. Drywell Sump Isolation Valves -20HOV 82 and 94 fail "as is"
- 6. Drywell Cooler Fans 68FN-2A, 2C, 4A, and 4D.
7 SLC Pump A and SLC Heaters
- 8. LPCI MOV Independent Power Supply A
- 9. Drywell Radiation and Atmosphere Monitors A
- 10. RCIC Tast Power
- 11. CAD System A l 12. 178 System A.
- 13. RFP Turning Gear A
- 14. Station Battery A Charger and Battery Ventilation Rev No. 5 Date 02-14-90 5 of 6 PaBe f
i
m i NEW YORK POWER /UTHORITY [ JAMES A. FITZPATRICK NUCLEAR POWER FIANT ABNORMAL OPERATING PROCEDURE i TITLE: 14SS OF 10500 BUS
- No. F.AOP 18 j
'15. UPS Alternate Supply
- 16. ESW System A
- 17. Main Turbine Lift Pumps 4A, 4C and 4E
- 18. Inboard Drywell Vent and Purge A0Vs
- 19. EPIC normal supply LO l-
-Rev. No. 3 Date 30/21/89 Page 6 of 6 O
NEW YORK POWER AUTHORITY
/ JAMES A. FITZPATRICK NUCLEAR POVER PLANT I
ABNORMAL OPERATING PROCEDURE TITLE: - 14SS OF 10600 BUS
- NO. F.AOP 19
+4
- c. Restore to service equipment isolated to minimize battery loads.
D, StMMARY OF IMPORTANT 10600 BUS IDADS :
- 1. RHR B and RHRSV B Systems
- 2. Core Spray System B
- 3. CRD Pustp B
- 4. SCT System B
- 5. Drywell Sump Isolation Valves 20A0V 83 and 95
- 6. Drywell Cooler Fans 68PN 25, 2D, 45, and 4D '
- 7. SLC Pump B and SLC Heaters
- 8. LPCI Independent Power Supply B
- 9. Drywell Radiation and Atmosphere Monitors B
- 10. Main Turbine Turning Gear 011 Pump and Turning Gear
- 11. CAD System B
- 12. RPS System B
- 13. RTP B Turning Cear
- 14. Station Battery B Charger and Battery Ventilation
- 15. UPS Normal AC Supply-
- 16. ESW System B
- 17. Main Turbine Lift Pumps 94P 48, 4D, and 4F, i
I Rev. No. 3 Date 06/14/89 Page 5 of 6 O
.y NEW YORK POWER AUTHORITY-( JAMES A. FITZPATRICK NUCLEAR POWER PLANT ..
ABNORMAL OPERATING PROCEDURE : i. t'" TITLE: 1458 0F 10600 BUS
- No.'F.AOP 19 '
- 18. Outboard Drywell Vent and Purge A0Vs
- 19. Crescent and Reactor Building Smoke Detectors
- 20. HPCI Test.. Power F
~f b
( t p i LRev No. 3 Date 06/14/89 p86e 6 of 6' ' O .
4 FORM SAP 1.3' t CONTROLLER SHEET Page 25 of 41' MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER- ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION ~ 0801 '7 Control _ The following annunciators - Recognize steam leak Site Area Room are sealed'in: without isolation. Emergency' 09-3-3-2 Div I Ambient - Classify Site Area Temp'Hi Emergency. 09-3-3-12 Div II Ambient Temp Hi - Activate TSC, OSC 09-5-1-16 PCIS Sys A Stu and EOF. Tun Temp Hi 09-5-1-17 PCIS Sys B Stn Tun Temp Hi 4 panel dual posit. ion indications for 29MO'/- 74, -77 and -79. CONTROLLER'S NOTE: Once RPS is restored, all associated annunciators clear except those listed above.
.. - . ,~,-
% . --r')(ns . -(~ J)
; FORM SAP 1.3 CONTROLLER SHEET .Page 26 of 4'1' MESSAGE _ .. ANTICIPATED RESULTS AND EMERGENCY.
TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION 0815 8 Control Plant. parameters as ~
- Continue activation Site Area Room indicated on SPDS display. of emergency Emergency facilities.
- Assemble non-essential staff in l Training Building. 'l t
t t t 4
Pg l/^N /~~' D (/ ~ (_))-. FORM SAP 1.3 CONTROLLER SHEET Page '27 of ' 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY ~ TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0830 9 Control The following ' - Monitor hydrogen Site Area Room annunciator alarms: ' pressure. Emergency' ' 09-7-3-42 Hydrogen Seal - Take actions in Oil Trouble accordance with AOP-48 for loss of
- Plant parameters as generator hydrogen.
indicated on SPDS display. - Maintain contact , with Niagara Mohawk for restoration of offsite power. CONTROLLER'S NOTE: Main generator hydrogen pressure should be decreasing at a rate which will be zero pressure by 0900.
-If the Emergency Director is not in the process of having declared a' Site Area Emergency, this must be prompted. -
/"' _ (") %.
L)- U .
;V FORM SAP 1.3 ,
CONTROLLER SHEET Page 28 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION. 0845 10~ Control- Plant parameters as Continue actions for Site Area Room indicated on SPDS display. restoring plant Emergency stability. P a
- + ...e...-~ . . . L, , n. .
O O O i FORM SAP 1.3 CONTROLLER-SHEET Page 29 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CIASSIFICATION 0900 11 Control' . Plant parameters as. Continue plant. . Site Arca Room indicated'on SPDS display.- assessment Emergency activities. CONTROLLER'S NOTE: Main generator hydrogen pressure is zero. 4 _ . . . - m .- _.u. .- .,
- ~ .
FORM' SAP 1.3 CONTROLLER SHEET Page '30 'of 41 I
' MESSAGE- . .
ANTICIPATED RESULTS AND EMERGENCY' TIME NUMBER ISSUED TO
SUMMARY
.OF MESSAGE CONTENTS COMMENTS CLASSIFICATION-0915 12 Control - NMP Line:f4 is restored - Close 10012 and Site Area-Room and.T-3 transformer can- 10022 breakers. Emergency be placed back in service. t i
- Plant parameters as indicated on SPDS display. '
h e i t i b b 5 4
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.\j h .O l
l l l FORM SAP 1.3' j CONTROT.TIR SHEET Page 31 of 41 l l l MESSAGE ANTICIPATED RESULTS AND EMERGENCY ! TIME NUMBER ISSUED TO
SUMMARY
-OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0930 13 Control - An explosion is heard Site Area-Room coming from the' Turbine Emergency Building.
- Plant parameters as indicated on SPDS display.
CONTROLLER'S-NOTE: At 0930, an explosion is heard coming from the Turbine Building. The explosion occurred from the ignition of a pocket of hydrogen during unisolation of the ventilation , system.
.- ..- .a
l-FORM SAP 1.3' CONTROLLER SHEET Page 32- of ~41' MESSAGE- ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS- COMMENTS CLASSIFICATION 0945 14 . Control ' Plant parameters as l Site Area Room . indicated on SPDS display. Emergency t [
. . . . -.n_ .- . . . . . - . . - , - ~ - . - - - ~
FORM SAP 1.3 CONTROLLER SHEET Page 33 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO .
SUMMARY
.OF MESSAGE CONTENTS COMMENTS .CIASSIFICATION 1000 '15 Control Plant' parameters as Site Area
' Room indicated on SPDS display. Emergency l
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FORM SAP 1.3 CONTROLLER SHEET Page 34 of 41' MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1015 16 Control The.following annunciators Site Area Room alarm: Emergency 09-8-1-20 125VDC Batt Chgr A Current or output To . t
- Plant parameters as indicated on SPDS display.
CONTROLLERi S NOTE: If Operations attempts to shift UPS back to AC-Drive, the MG-Set trips and failover to the alternate feeder occurs. ,
.LJ V V ,
FORM SAP 1.3 CONTROLLER SHEET Page. 35 of ' 41' MESSAGE ANTICIPATED RESULTS AND EMERGENCY -' . TIME NUMBER .' ISSUED TO '
SUMMARY
OF MESSAGE CONTENTS LOMMENTS CIASSIFICATION. 1030 17 ' Control' .' Plant parameters as Site. Area i Room indicated on SPDS display. Emergency. I ' s i t I
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T '" [m/ ({)\ k.jY u. FORM SAP 1.3 CONTROTLER SHEET . Page 36- $" _ .{1 MESSAGE ANTICIPATED RESULTS AND' EMERGENCY" TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE. CONTENTS- COMMENTS CLASSIFICATION 1045 18- _ Control Plant parameters as Site Area Room. indicated on SPDS display. Emergency b 1 1 'l L i
. . ~ . . ~ . . - ,_ -. .. -. - . . -
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i i FORM SAP _1.3 CONTROLLER SHEET Page 37 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY , TIME NLitBER ISSUED TO
SUMMARY
OF MESSAGE. CONTENTS COIWEENTS CLASSIFICATION 1100 19 Control Plant parasmeters as Site Area Room- indicated on SPDS display.' Emergency I i-i I l l l
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O O i b 1 l E k FORM SAP 1.3 [ CONTROr.T.ER SHEET Page 39 of 41 MESSAGE ANTICIPATED RESULTS AND EMERGENCY !- TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COISEENTS CIASSIFICATION i 4 1130 21 Control Plant parameters as Site Area . Room indicated on SPDS display. Emergency i i I ,' i S
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i FORM SAP 1.3 ! CONTROTJRR SHEET Page 40 of 41 i* l MESSAGE ANTICIPATED RESULTS AND EMERGENCY ' TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COIWfENTS CIASSIFICATION > i 1145 22 Control Plant parameters as- Site Area ; Room indicated on SPDS display. Emergency [ i ! i t : 1 i r h I i, i t t i i
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9 I-t I FORM SAP 1.3 i CONTROr.T.ER SHEET Page 41 of 41 MESSAGE ANTICIPATED RESULTS AND ENERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COISEENTS CLASSIFICATION , I 4 r , 1200 23 Emer- Plant is stable. Commmence
- gency discussions on terminating t Facil- the energency and entering
- ity recovery.
Mana- ; gets i c + i = i i 3 t
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FORM SAP 1.4 Page 1 of 28 MESSAGE SHEET MESSAGE NO. 1 Exercise Times 0700 Issued To Control Room Issued By: Land controller MESSAGE Plant is operating at 100% power. Annunciator 09-8-6-15 NMP-FITZ 115KV Line 4 BKR 10012 TRIP is sealed in due to maintenance on the line. NiMo estimates return to service for the #4 line to be 0800 tomorrow. Completion of ST-20C and AOP-24 have identified control rod 30-35 to be stuck in the fully withdrawn position. , Inboard main' steam line drain-isolation valve 29MOV-74 has failed to close during performance of surveillance testing. Plant parameters as indicated on SPDS display. O
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- a. FItreatridt Muclear Power III - Plant Paraneters PIarit Seguencm No. _
a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 99.98 % fyget HDICItst P0hER % 3.999 O'S 1951 flDETWt Pelst 9.9888E+416 Iricf. Tff" SWI 3EFETWt POIER 291.8 ft.B 45t 5tx WWWVBtFung IDEL 18.34 W tt 8.9895E+99 PSIG IEIC tees. EPft gEyE19t PRE 335E 9.9888E+98
.py cI Ft.333 8.908EE*e8 EFff
' IfCT A FIDig 8.980eE+e9 EFft e tt IfCI B F1.Dif 8.88esE+ee EPfl T CINE SPlutr FIEis 9.8888E+ee Irw i 15.98 T CINE SP9WWF FtElf IEI'5ec i
' EtYesli MBFLBEL 73.98 (EI/sec STRIX GIS IWW. 19.se (EI/sec
' Itx m nr. User 353 2.888 (EI'sec IIFIEL FUt DGE 8153. 9.988 tEI/sec T5itE.EG MENT IWW. 2.see tEI/8tl gas gLEG Upgf IWW. 8.138E-4B5 8.2819 CI/sec SDtUlm URtUt 555. CI/sec STUDC HI IWWEE 853. 8.EF99EE+es 8.990eE+99 CI/see i
' TB IE.B HI IWWEE Itfe. v4RM gaf EN 3 HI IWWEE IlfW. 14.98 l tyTuts Elfe. 8.999 RM Ntynsie afW . 1589. MM I.9ee PSIG NIGEST M!E. 315W IM Beg F Eftvasia PflE351.5tE 129.e Beg F EftytE11 TDFDum31E 76.99 TUlits URtst HUG TfF 13.91 FT 7tNils WTTet LEUEL 0.3000 % IBMEli H2 C0HC 1.888 Irtcf. MtYtEIL 02 CfDE 250.9 CST l.EUEL O TIVE: _ Energency Birector firpe,owal:
FORM SAP 1.4 Page 2 of 28
,h (V MESSAGE SHEET MESSAGE NO. 2 Exercise Time: 0705 Issued To: control neem Issued By: Iend controller MESSAGE Plant parameters as indicated on SPDS display.
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96:22:18 I?ItE-463 0.000 IR4R // 96:22-18 1711E-434 0.000 tst4R Forn DP-I.I.3 ) James it. Fitzpatrid Detselear- Pouer PIarit
- PfttT III - PIarit Parameters h + Mo.
, WIin IIERCTER PSER 61.93 % IEWI IERCTtR PGRER 5.988 % Set IEfETER peter 9.9998E+96 (FS ftK IWHER LBEI. 291.9 Iricf TVF FWlapHUt FLaf 7.923 IRB49t SEIC FLAI 8.9998E+98 WH EERCTEWt Puritsaw lege. PSIG WCI FLmf 0.9888E+98 e tt , LPCI ft Flmf 9.9999E+99 WH ' t.FCI B FLDit 0.9988E+98 EiFH "ft" WWWF FLDif 9.9088E+98 EiPH
*1B" WWfr FLmf B.9998E+98 WH Etyssa I SSfP LE4EL 15.98 IrirA STREK EifE IWW. 75.98 tEI/sec ItX 35 EE tEIgr WW. 19.99 (EI/sec !
8FIEL FLR DGE IWW. 2.988 IEI/sec ' 1B ELEE tlENT WW. 9.999 IEI/sec 510f ELB6 tEHF IWW. 2.999 tEI/see SERUIE tuffER IWW. 8.1599E-95 tEI/sel i STR0K HI SWWEE Ilfe. e.2819 CI/sec TB ELD MI IWWEE IWW. 0.90eeE+98 CI/sec ! 558 EKD MI SWWWE IWW. 0.0088E+00 CI/sec WHiUE IWW. 14.98 setMer ' EtytR I IWW. 8.998 RM HIGEST BE 553 IEN 1500. edtMer Eftverai PUE3585lE I.999 PSIG 2 NtVen i 1DW'UWmplE 129.0 1 Beg F i TEWitE tuffUt ftUG TfF 76.00 Beg F 7ttits tWHUt LDIEL 13.91 FT NmELL H2 CODE 0.7000 t NMELL G2 CSE 1.800 0% ! CST LBEL 250.9 Irttis t I Eriergericw Birector Ryyrovat: TIfE: t i _______________ _.____________________-___--______ t
FORM SAP 1.4 Page 3 of 28 V MESSAGE SHEET MESSAGE No. 3 Exercise Times 0715 Issued To control Room Issued By: Lead controller MESSAGE Plant parameters as indicated on SPDS display. m
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7-~ FORM SAP 1.4 Page __4 of 28
\'-
MESSAGE SHEET MESSAGE No. 4 Exercise Times 0730 Issued To: Control Room Issued By: Lead Controller MESSAGE The following annunciators alarm: 09-0-6-10 LHH-Fitz 115KV Line 3 Bkr 10022 Trip 09-8-6-14 115KV SYS VOLT LOSS Plant parameters as indicated on SPDS display. (% G - a m'-
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I j 1 l l 7 . FORM SAP 1.4 Page _ 5 of 28 l
's MESSAGE SHEET l l
1 MESSAGE NO. 5 i Exercise Time 0745 Issued To: control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display. (~ l x e
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96:22:18 17RE-463 9.999 Istost // 96:22:1817RE-434 9.999 tst45? Forn DP-1.I.3 Jaries R. FE tzpatrid Eclear Power PIarit Pf5tT III - PIarit Parameters Segtseruce h. fWWI IE]ETGt PEREEt 43.99 % IINE BENEftBt P9tEEt 5.999 % WWI M3EftR F4EER 9.999EE+96 CPS RNIWHER REEL 291.9 Ientf. TfF FEEBINHDt FLfRf 5.959 f5.5462 UEIC FLSIf 9.959EE+99 EFM IEEETER RESStBE 1999. PSIG IFCI RERf 9.990sE+99 EiPM IMI R FURf 9.99BIE*99 EiFH EKI B FLSf 0.999EE+99 EiPH T CINE W95W FLElf 9.999fE*99 EiRI T CINE W95W RDif 0.999EE*99 tiPM 4 5tW51I SISP IEEL 15.99 Iruf. ' S:TEK G45 IWW. 75.99 (EI/sec ItX ELEG UDfr IWW. 19.99 IEI/sec IIFIEL FLR Det IWW. 2.999 tEI/sec 9.999 tEI/sec l TB ELEG sJDK IWW. l 515f IILEG UDW IWW. 2.999 (EI/sec SUtUICE tWTTDt 555. 9.139eE-4t3 (EI/ml . STTEK HI SIf95E IWEB. 9.2819 CI/sec TB ELB HI Ilf9EE 553. 9.9A9fE+99 CI/sec Inf IR.B HI IWWEEiE IWW. 9.sesEE+99 CI/sec (FTUSIWW. 14.99 estoir Etyisa5 IWW. 8.999 R/Hr-HIGE3T IM_ 5WW FEDE 1399. estotr-MtWELt_ RIE35tBE 1.999 FSIG WEVIE11 TUTUIRTIDE 129.9 Beg F TUIR E MRf Dt fW G TfF 76.99 Beg F T1311E 45MUt LEUEL 13.91 FT NtWEI.L M2 CDE B.39Pe T. NEVts1I G2 UEE 1.999 % CST LEUU_ 259.9 Irwf. O 6 w _9 Birector ~,,. w l: TIfE:
l l FORM SAP 1.4 Page 6 of 28 i ( l
\ MESSAGE SHEET MESSAGE NO. 6
.L Exercise Times 0800 F Issued To Control Room Issued By: Lead controller MESSAGE The following annunciators alarm: 09-3-1-9 Fuel Pool Cool & Cln Up Trouble 09-3-1-10 Core Spray A or B Disch Line Not Full 09-3-1-18 RHR A or B Disch Line Not Full 09-3-1-19 ARM Downscale 09-3-1-20 Refuel Area ARM Rad Hi 09-3-1-29 New Fuel Storage ARM Rad Hi 09-3-1-30 Radw Bldg ARM Rad Hi 09-3-1-39 Turb Bldg ARM Rad Hi 09-3-1-40 Rx Bldg ARM Rad Hi
.f 09-3-2-7 Off Gas Smpl Flow Hi or Lo 5
5 09-3-2-10 Off Gas Timer Initiated 09-3-2-17 Off Gas Rad Mon Downscale or Inop 09-3-2-19 Rx Bldg Vent Rad Mon Downscale 09-3-3-11 Main Stm Rad Mon Downscale 09-3-3-22 HPCI Stm Leak Det Logic Pwr Fall 09-4-0-1 Cont Hi Range Rad Mon A Fall or Pwr Loss 09-4-0-4 Cont Hi Range Rad Mon B Fail or Pwr Loss 09-4-0-21 PASS Gas Smpl Ht Trace A Trouble < 09-4-0-22 PASS Gas Sap 1 Ht Trace B Trouble 09-4-0-23 PASS Exh Fan Trouble 2 09-4-1 SRV Leaking 09-4-1-19 Rx Bldg Equip Sump A Temp Hi-09-4-1-20 Rx Bldg Equip Sump B Temp Hi 09-4-2-1 DW Equip Drn Isol Viv Closed 09-4-2-2 DW Floor Drn Isol Viv Closed 09-4-2-3 PCIS Sys A Viv Overload or Pwr Loss 09-4-2-6 SRV Sonic Mon Alarm Hi 09-4-2-11 DW Equip Sump Temp Hi or Cool Wtr Flow Lo 09-4-2-13 PCIS Sys B Vlv Overload or Pwr_ Loss 09-4-2-20 RWR MG A Drv Mtr Bkr Trip 09-4-2-21 DW Equip Sump HI-HI or LO-LO 09-4-2-36 TIP ARM Rad Hi 09-4-2-37 RWR MG A Oil Mist Elim Diff Press Hi 09-4-3-1 RWR MG A Gen Lockout 09-4-3-2 RWR Loop A Out of Serv 09-4-3-5 RWR Loop B Out of Serv O
_ . _ _ _ _ _ _ . . _ _ . . ~ _ __ FORM SAP 1.4 Page 7 of 28 i MESSAGE SHEET , I MESSAGE No. 6 i Exercise Time: 0800 (cont) l Issued To: Control Room I Issued By: Lead controller MESSAGE Annunciators continued: 09-4-3-10 RWR MG B Gen Lockout 09-4-3-11 RWR MG A Scoop Tube Lock 09-4-3-19 RWR MG B Drv Mtr Bkr Trip 09-4-3-20 RWR MG S Scoop Tube Lock 09-4-3-21 RWR MG A Gen Aux Lockout 09-4-3-30 RWR MG B Gen Aux Lockout 09-4-3 RWR MG A Speed Cntrl Sig Failed 09-4-3-36 RWR MG B Oil Mist Elim Diff Press Hi 09-4-3-40 RRR MG B Speed Cntrl Sig Failed
/ 09-5-1-1 SDIU A or B Hi Lvl Trip 's 09-5-1-2 MSIVS Not Full Open Trip 09-5-1-3 RPS L Auto Scram 09-5-1-4 RPS B Auto Scram 09-5-1-5 RPS M.G A Trouble 09-5-1-6 PCIG Sys A Rx Lvl LO-LO-LO 09-5-1-7 PCIS Sys B Rx Lvl LO-LO-LO 09-5-1-9 CRD Charging Wtr Press Lo 09-5-1-10 CRD Dry Wtr Filter Diff Press Hi 09-5-1-13 RPJ A Man Scram 09-5-1-14 RPS B Man Scram 09-5-1-15 RPS Mg B Trouble 09-5-1-16-PCIS Sys A Stm Tun Temp Hi.
09-5-1-17 PCIS Sys B Stm Tun Temp Hi 09-5-1-21.RPS Hi DW Press Trip 09-5-1-22 RPS Hi Rx Press Trip 09-5-1-24 Fdtwr Cntrl Lo Flow Viv Elect Sig Fall l 09-5-1 PCIS Sys-A Main Stm Line Flow Hi l 09-5-1-27 PCIS Sys B Main Stm Line Flow Hi L 09-5-1-28 Rx Wtr Lvl Alarm Hi or Lo 09-5-1 RPS Rx Vessel Lo Lvl Trip l 09-5-1-32 RPS Main Stm Line Hi Rad Trip 09-5-1-36 Sys A Stm Line Press Lo 09-5-1-37 Sys B Stm Line Press Lo 09-5-1-41 Neutron Mon Sys Trip 09-5-1-43 CRD Accum Press Lo or Lvl Hi
,/~%.3 09-5-1-44 SDIV A or B Not Drained V
.. _ . .. _ ._ _ ___._______.___m _ _. _ . . _ _ _ _ _ _ . . . - _ _ _
/' FORM SAP 1.4 Page 8 of 28 l MESSAGE SHEET l l
MESSAGE NO. 6 Exercise Times 0800 (cont) Issued To: Control Room Issued By: Lead Controller MESSAGE Annunciators continued: 09-5-1-51 TCV Fast Closure Trip 09-5-1~53 TSV Closure Trip 09-5-1-54 Scram Air Hdr Press Hi or Lo 09-5-1-55 PCIS Sys A Group I Isol 09-5-1-56 PCIS Sys B Group I Isol 09-5-1-58. Interposing Relay Sys on DC Pwr 09-5-2 Rod Withdrawal Block 09-5-2-3 Rod'Orift 09-5-2-6' EHC Lo Press Trip- '
.("N 09-5-2-9 Main Turb Trip s
09-5-2-16 Main Turb Exh Hood Hi Temp Trip 09-5-2-20 Main Turb-Exh Hood Temp Hi 09-5-2-22 RSCS In Serv 09-5-2-25 Flow Ref,Off Norm 09-5-2-26 Main Turb Lo_Vac Trip-
- 09-5-2-27. Main Turb Loss of Stator Coolant Trip 09-5-2-30 Main Turb Bellows Fail or Lo Vac Trip 09-5-2-32-IRM Downscale 09-5-2-34 APRM Downscale 09-5-2-35 RBM Downscale 09-5-2-36 Main Turb Hi Vib Trip 09-5-2-44*APRM Upscale 09-5-2-45.RBM Upscale or-Inop 09-5-2-54 APRM> Trip Sys A Inop or Upscale Hi 09-5-2-55 APRM Trip Sys B Inop or Upscale Trip 09-5-2-57 ' ATTS RPS' Div Al or A2 Pwr Supp Fail or TU Out of File 09-5-2-58 ATTS RPS Div Al or A2 Gross Fail or TU Inop 09-5-2-59 ATTS RPS Div B1 or B2 Pwr-Supp Fall or TU Out of File 09-5-2-60'ATTS RPS Div B1 or B2 Gross Fail or TU Inop-09-6-1-3 Circ Wtr Pmp 36P-1A Overload or Trip o 09-6-1-10 Screen Wash Betr' Pap 46P-6A or 6B Trip or Cntrl Pwr Loss L '09-6-1-11" Circ Wtr: Pap 36P-1B Overload or Trip ,
09-6-1 Perimeter Drn Pmp Trouble
'09-6-1-18 Trvig Wtr Screen Trip or Cntrl Pwr Loss 09-6-1-19' Circ Wtr Pmp 36P-1C Overload or Trip <
09-6-1-24 Stack Dilution Fan 26FN-2A or 2B Fail
-,,m.,-. --e-,- , ,r-, ,-, ,,--,,,,,--m in---,. -- . ,w + - ~ , , . , - - - , - - . w t-,
~. FORM SAP 1.4 Page 9 o f __2 8
\~- MESSAGE SHEET MESSAGE No. 6 Exercise Time: 0800 (cont) Issued To: Control Room Issued By: Lead Controller MESSAGE Annunciators continued: 09-6-1-29 CNDSR Vac Lo 09-6-1-30 SJAE Stm Press Lo 09-6-1-31 Serv Air Hdr Press Lo 09-6-2-2 RBC Hx Disch Temp Hi or Lo 09-6-2-9 Cond Xfer Pmp 33P-13A Lockout or Trip 09-6-2-12 RBC Conduct Hi 09-6-2-19 Cond Xfer Pmp 33P-13B Lockout or Trip 09-6-2-22 RBC Makeup Tk Lvl Hi or Lo 09-6-2-29 Cond Xfer Hdr Press Lo /~~N 09-6-2-30 CNDSR Hotwell Lvl Hi 'or Lo (_j/ 09-6-2-31 RBC Hdr Press Lo 09-6-2-32 RBC Hdr Press LO-LO. 09-6-2-34 Serv Wtr Hdr Press Lo 09-6-2-36 TBC Mdr Press Lo s 09-6-2-38 Breathing Air Hdr Pre'ss Lo 09-6-2-39 Serv Air Hdr Isol Viv Closed 09-6-2-40 Breathing Air Hdr Isol Viv Closed 09-6-3-20 RFP A & B Seal Wtr Diff Press Lo 09-6-3-30 SJAE or SPE Drn Tk Lvl Hi or Lo 09-6-3-31 Cond Pmp Disch Hdr Press Lo 09-6-3-32 Cond Demin Sys Trouble 09-6-4-1 RFPT A V&c Lo
- 09-6-4-2 RFPT A Trip 09-6-4-3 RFPT A 011 Clr Disch oil Temp Hi 09-6-4-4 RFPT A or B Aux 011 Pmp Trouble 09-6-4-6' RFPT'A or B Turning Gear Trouble 09-6-4-8 RFPT B Vac Lo 09-6-4-9 RFPT B Trip 09-6-4-10 RFPT B Oil Clr Disch oil Temp Hi 09-6-4-15 RFPT A or B Emerg Brg Oil Pmp Running 09-7-1-3 Main Gen Auto Reg Trip to Man 09-7-1-5 Unit Prim Lockout 09-7-1-15 Main XSFMR T-18 Temp Hi 09-7-1-26 Main Gen Exciter Filed Bkr Trip 09-7-1-28 Main Gen Field Grd Will Alarm Only
(-] 09-7-1-31 Main XSFMR T-18 Trouble LJ
FORM SAP 1.4 Page 10 of 28 MESSAGE SHEET MESSAGE NO. 6 Exercise Time 0800 (cont) Issued To: Control Room Issued By: Lead Controller MESSAGE Annunciators continued: 09-7-2-1 Main Gen Disc 10031 Open 09-7-2-3 Fitz-Edic 345KV Line 1 Bkr 10052 Trip 09-7-2-7 Fitz-Scriba 345KV Line 10 Bkr 10042 Trip 09-7-2-8 Main Turb Brg 011 Vapor Extractor Trouble 09-7-2-10 Reboiler Lvl Cntrl-Trouble 09-7-2-16-EHC Fluid Pwr Unit Tk Trouble-09-7-2-18 Reboiler Trouble 09-7-2-21 345KV Bkr 10042 Ext Dry Time or Loss of AC for Htra 09-7-2-32 Main Gen Core Mon Trouble 09-7-3-1 Main Turb Brg 3 Lift' Pup Trouble s 09-7-3-2 Main Turb Brg 4 Lift Pmp Trouble 09-7-3-3 Main Turb Mtr Drvn Suct Oil: Pap Trouble l 09-7-3-8 Main Gen Stator Wtr Sys Trouble , 09-7-3-13 Main Turb Brg 5 Lift Pmp Trouble 09-7-3-14 Main Turb Brg 6 Lift Pmp Trouble 09-7-3-19 Main Gen Emerg Seal Oil Pmp Running 09-7-3-22 Moist Sep Drn Tk 2A Lvl Lo 09-7-3-24 2nd Stage RHTR Drn Tk 4A Lvl Lo 09-7-3-25 Main Turb Brg 7 Lift Pmp Trouble 09-7-3-26 Main T, urb Brg 8 Lift.Rmp Trouble 09-7-3-29 EHC Pmp A or' B Trip 'or Cntrl Pwr Loss 09-7-3-32 SPE' Fan Overleat Ontrl Ytits Lo 09-7-3-38 Main Turb Turning Gear 011 Pmp Running L 09-7-3-40 Main Stm Leads Drn Pot Lyl Hi 09-7-3-43 SPE Vac Lo 09-7-3-44 Seal Stm Hdr' Press Lo
.09-7-3-46 Moist Sep Drn Tk 28 Lvl Lo 09-7-3-48 2nd Stage RHTR Drn Tk 48 Lvl Lo
- 09-8-1 Computer Cntrl Volt Trouble L 09-8-1-8 UPS on DC Drive 09-8-2-4 EDG C Load Bkr 10512 Closed 09-8-2-8 Bus 10300-10500 Tie Bkr 10514 Trip or Cntrl Pwr Loss l09-8-2-9 EDG A Eng Trouble or Shutdown 09-8-3-9 10100 or 10200 or 10300 or 10400 Prolong UV Trip 09-8-3-17 Bus 10300-10500 4KV Tie Bkr 10304 Trip 09-8-3-18 L13 L23 L33 L43 4KV Supp Fdr Bkr 10340 Trip I
,c - e-, . - - , - -- , , - ~ - - . - - - - - - - - - , - - - - - , - ~ . - - - ,
FORM SAP 1.4 Page 11 of 28
> MESSAGE SHEET MESSAGE No. 6 Exercise Time: 0800 (cont)
Issued To Control Room Issued By: Lead Controller MESSAGE Annunciators continued: 09-8-3-23 L14 L24 L34 L44 4KV Supp Fdr Bkr 10440 Trip 09-8-3-24 4160V Bus 10500 Degraded Voltage Tih9r Initiated 09-8-3-26 Bus _10300 Norm Supp Bkr 10302 Trip 09-8-3-32 Bus 10400 Norm Supp Bkr 10402 Trip 09-8-4-1 Bus 10400-10600 Tie Bkr 10614 Trip or Cntrl Fw'r Ic s 09-8-4-3 EDG B Load Bkr 10602 Closed 09-8-4-6 EDG D Load Bkr 10612 Closed 09-8-4-11 EDG B Eng Trouble or Shutdown
, 09-8-4-14 EDG D Eng Trouble or Shutdown , j
, 09-8-5-3 Bus 10100 Norm Supp Ekr 10102 Trip" ' s 09-8-5-13 Bus 10700 Supp Bkr 10702 Trip i 09-8-5-15 Bus 10200NormSuppBkr10202Tripi 1 09-8-6-1 LHH-Fitz 115KV Line 3 Prim Relay Tt4p 09-8-6-10 LHH-Fitz 115KV Line 3 Bkr 10022 Air.Ioner AC Pwr Loss 09-8-6-14 115KV SYS Volt Loss . ed^ 09-8-6-15 NMP-Fitz 115KV Line 4 Bkr'10012 Trip p - HPCI/RCIC auto initia6e'and'co'htrol' levels -
. --g "B", "C" and "D" EDG's start and load.the A0500 and 10600 buses.
Plant parameters as ind cated on SPDS disp ay. L l l O
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s .; FORM SAP 1,4 Page; ~12 of 28 MESSAGE SHEET MESSAGE NO. -7 Exercise' Time: __0801 Issued'To: -Control Room
.- Issued By: Lead Controller MESSAGE- .
The=following annunciators are sealed in: 09-3-3-2 DIV I' Ambient Temp Hi 09-3-3-12 DivLII Ambient Temp Hi 09-5-1-16' PCIS Sys:A Stm Tun Temp Hi 09-5-1-17 PCIS Sys B Stm Tun Temp Hi 09-4 panel dual 1 position indicationsLfor 29MOV-74, -77 and -79. 2 W~ g . M -
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- = .- . - -. .- - ._ _
FORM SAP 1.4 Page 13 of 28 O MESSAGE SHEET MESSAGE No. 8 Exercise Time 0815 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parametors as indicated on SPDS display.
~
I y** .see .>en e t~* . ns
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._,. FORM SAP 1.4 Page 14 of 28
- ~ R. ,
i ~
+Q MESSAGE SHEET-M"SSAGE NO. 9
. Exercise' Time: 0830 ;
Issued To: Control Room 2
' Issued By: Lead controller ;
I MESSAGE p The-following annunciators alarm-h9-7-3-42 Hydrogen Seal Oil Trouble i
?
Plant parameters as.. indicated on SPDS display. .. 1 - , . O h l\ _. . .
- 4. Y ":r.' -
! 1
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FORM SAP 1.4 Page 15 of 28 MESSAGE SHEET MESSAGE NO. 10 Exercise Time: 0845 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display. O
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FORM SAP 1.4 Page 16 of _ 28 O MESSAGE SHEET MESSAGE NO. 11 Exercise Time: 0900 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display. O .
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5 FORM SAP 1.4 Page -17 -of- 28 I MESSAGE SHEET MESSAGE NO. 12 Exercise Time 0915 Issued To: Control Room 4 Issued By: -Lead controller-l MESSAGE NMP Line-#4-is restored and T-3 transformer can be placed back in service. Plant parameters'as indicated on SPDS display.
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. _ __ - .-_ __ ... . - . - - _ . . . _. - _ . . . . . ~ . _., _ _ . _ . . _ _ . _ - .
f c FORM SAP 1.4 Page 18 of 28-g ' MESSAGE SHEET MESSAGE..NO. 13 !
~ Exercise: Time: 0930 Is0Jed'To: Control Room Issued By: Lead Controller MESSAGE
~An explosion is heard coming from the Turbine Building. ,
-Plant parameters'as indicated on SPDS display.
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i l' ~ , I 99:31.'"iB 18RtHR21-22 .. 35t452 // 99:31:581EBitHt21-97 ISt4R l l Fern EIP-1.1.3 i Janes R. Fatzpatridt Hisclear Power Plant PfWtf III - Plant Paranaters Sequuence No. frilft IIERCTUt POER 9.9888E+98 % ' IIst IIERCTGt PUlER 9.988EE+98 % GW1 EERCTUt PGER 9.988EE+98 CPS ItX IEffER LEUEL 291.9 Irwh TIF ETmBUIER FIDf 8.m ISB45t IICIC FIDS 388.9 EiPft i IEEE1Gt PIIF1MBHE 493.6 PSIG DFCI FIAf 9.81mRIIF+98 EFft LPCI R FLDid 9.9888E+98 EiPft LPCI B FIDf 9.mansur+99 Erst
*ft" CGE W51RY Flmf 9.988E+98 GT1
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lesEREG4ENTIWW. M 2.889 IEI/sec tEI/sec MMUICE'45ffER 553. 9.1w-95 tEI/h1 STREK HI IWWEE 51f3. 9.2819 CI/sec TB tlLB HI BifBEE 5159. CI/sec IlW EEE HI fifBEE ElfB. 8. +98 CI/sec GTHIS553. 1.889 mit44r - WPYlFII 515 3 . 5.3G8 RM - HIGEST 315 ElfB IEB4 4329. sdt/Hr < EtTREl i P5lE5515lE 1.988 PSIG Etvl51 I TEfrDiffttEIE 126.9 Beg F i Twits istfER RUG ltF 78.26 Beg F 191t35 45ffDt LBEL 13.99 FT l EtYl511 H2 CGEC 0.3889 % ! EtVLFI 9 G2 CEDE 1.888 % 2 CST LEUEL 239.9 IrwA C Ees Director Approual: TITE: l
FORM SAP 1.4 Page 19 of 28
\ 'ul MESSAGE SHEET MESSAGE NO. 14 Exercise Time: 0945 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display.
l em v l l l 9 4 s . A . I
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fem Ho. i Encme ,9uoe 9.9 E.9. 2 IEWt IEIM'TTEt PEMBt 9.AAAAFe99 %
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*B" GEE WIlfW FUM5 9.988EE*99 GPft i EtYtE11 MSF IBJEL 15.98 Inch STVEBC EEIS IIIB. 75.89 IEI/sec !
ItX ELEG tBIT 5153. 19.98 IEI/sec IIFIEL FUt DSI IlfW. 2.988 LEI /sec TB fu E 4ENT IlfB. M LEI /sec sins a K TENT IlfW. 2.999 IEI/sec liUtt# ICE I5ITUt IWW. 9.1598E-85 tEI/vil STIE3C HI IlfBE E 5113. 9.2819 CI/sec TB W.B HI IIGBEE IlfW. Inf ELB HI IlftEiE IIIW. M CI/sec I 9.998E+98 CI/sec WFBISIlfB. 1.889 edtotr MtYtFII IlfB. 4.914 RM MIGEST IER. IlfB IEBt 4895. N Btvtsti MESStalE 1.999 PSIG Mt1551 i TENUIRTINEE 125.7 Beg F 7tEltE WITEEt RUG TTP 78.64 Beg F tGitIS 45tTElt LEtEL 13.99 FT 15tYtEI.I. H2 CIDE 0.3900 % mtvasi t 02 CINE 1.888 % CST LEEI. 238.9 Inti O t. Energeracy Birector Ryyroval: TIVE: b
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- - FORM SAP 1.4 Page- 20 'of 28
~
MESSAGE SHEET 1 - MESSAGE No. -15 Exercise Time:- 1000-
. Issued-To: Control-Room R 1
I
. Issued By: Lead Controller l
i MESSAGE l 1 Plant parameters as' indicated on SPDS display. i 1 I
- 4 'l 4-I v .ai3% , - * -p . ,
g# ~ , :.:2 i'
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* .s m;D , 4 .. . . ,
- . . . . . . _ __ . , . _ . . _ . . . . ~ . , ._,,.... -. . . . - , , _ ~ , , _ _ . - . , _ _ _ , , , . . . . _ .
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Y FORM SAP;1.4 Page 21 of 28-MESSAGE-SHEET ;
. .i!
MESSAGE No. 16 w Exercise Time: 1015: Issued To: ' Control-Room e Issued By: Lead Controller , N o MESSAGE :
-The following. annunciators alarm: -g. .
09-8-1-20.125VDC Batt Chgr A Current or output Lo l' . Plant parameters as indicated on SPDS-display.
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. 2 L ^ $ i ?- , ,1
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FORM SAP 1.4 Page 22 of 28 MESSAGE SHEET MESSAGE NO. 17 ___ Exercise Time: 1030 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display. O . 9 4
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-I MESSAGE SHEET MESSAGE No. 21 Exercise Time: 1130 Issued To: Control Room Issued By: Lead controller MESSAGE Plant parameters as indicated on SPDS display.
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I i FORM SAP 1.4 Page 27 of 28 MESSAGE SHEET MESSAGE No. 22 Exercise Time 1145 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant parameters as indicated on SPDS display. O O
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,-~ FORM SAP 1.4 Page 28 of 28 l \. -) MESSAGE SHEET MESSAGE No. 23 Exercise Time: 1200 Issued To: Control Room Issued By: Lead Controller MESSAGE Plant is stable. Commence discussions on terminating the emergency and entering recovery, r ~ x.
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SECTION 7 ( James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emerg2ncy Exercise December 19, 1990 DATA I. Plant Process Computer Data I' ARMS and In-Plant Maps Chemistry Data Offsite Radiological Data i b i l l ! V 7-1 l-i
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I l 1 SECTION 7 O James A. FitzPatrick Nuclear Power Plant { 1990 Partial Scale Emergency Exercise i l December 19, 1990 4 Plant Process Comeuter (SPDS) Data l The following displays are examples of process computer logs and the SPDS displays that are available in the emergency facilities for personnel to obtain plant data information. These process computer logs are updated on a one minute basis and SPDS is a real-time display. Process Computer Logs 4, 6 and 7 (ERDS/NYS Part-III-Data) and the SPDS Plant,-RRC, SCR and TBRWRD displays are the only ones which. will contain actual scenario data during the course of the training drill. This data is the same that can be found in Section 6 of this package on the.Part III forms and SPDS displays. , a o L N 72
iO Fit: Patrick Nuclear Plant EOFr~~ dient Status Loss Master Menu ---- (1) Eles#1 - General Plant Status (2) Elos#2 - Containment Temp / Pressure (3) Elog#3 - Power & Steam Systems (4) Elose4 - Area Rad Monitors (5) Elas#5 - Vessel /RCS Inteselty (6) Elos#6 - Ventilation Rad Monitors (7) NYS Part-lli Data Sheet (8) One-hour Trends (9) 15-Minute Met Data (q) Quit and Exit System. Enter 1:2 3,4,5,6,7,8 or mi O O >->
_ . . ._ . . . _ . . . _ _ _ -__ . . _ _ . _ _ _ _ ~ . . . .._. _ _ _ . - . _ 1 I I l l Fitzpatrick Plant Eles #1 i Data at Times 15:40 CORE THERMAL POWER MUTH- -22.581 GROSS GEN POWER (MW)- 0.000 GROSS GEN POWER % RATED- 0.000 TOTAL CORE FLOW M#/HR- 27.913 TOTAL CORE FLOW % RATED- 36.361 RX TEMP /RECIRC A DELTA T- -0.078 CNOSR 33C-10A VAC IN HG- 24.584 CONO-!NLT/DISCH TUNNL 07- 4.557 REACTOR PRESSURE PSIG- 143.171 RX WATER LEVEL i nch TAF- 204.082 CLNUP SYS INLT TEMP DEGF- 333.599 RX WTR CUT NONREGEN HX T- 81.535 RB CLG WTR HX OUT DEGF- 73.678 ORYWELL PRESSURE PSIG- 0.155 SUPR POOL PRESSURE PS!G- 0.178 ORYWELL TO TORUS 0 ELTA P- -0.015.
- TORUS WATER LEVEL FEET- 13.887 '
SUPR POOL AIR TEMP DEG F- 84.926
' OWLL OXYGEN (A) 0/30 Y.VOL- 21.997 STACK HI RANGE. RAD mR/He- 0.176 Press (RETURN) for Main Menu CTABs7]s l.
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Fitzpatrick Plant Eles #2 Data at Times 15: 41 ORYWELL PRESSURE PSIG- 0.154 OWLL AREA 0(RTO-101)DEGF- 93.91 O' SUPR POOL PRESSURE PSIG-ORYWELL TO TORUS DELTA P-0.176
-0.016 OWLL AREA 0(RTO-120)DEGF-OWLL AREA 1(RTO-119)DEGF-89.84 89.04 ORYWELL TEMPERATURE DegF- 97.817 OWLL AREA 1(RTO-102)DEGF- 94.67 SUPR POOL AIR TEMP DEG F- 84.964 OWLL AREA 2(RTO-103)DEGF- 97.97" TORUS WATER LEVEL FT - 13.900 OWLL AREA 2(RTO-104)DEGF- 97.6C TORUS WATER AVG TMP DesF- 75.644 DULL AREA 3(RTO-105)DEGF- 98.66 ORYWELL SUMP LEVEL Inch- 15.000 OWLL AREA 3(RTO-106)DEGF- 108.37 ORYWELL RAD Monitor R/Hr- 1.925 OWLL AREA 4(RTO-107)DEGF- 107.39 ORYWELL H2 CONC %- 0.354 OWLL AREA 4(RTO-108)DEGF- 112.47 ORYWELL 02 CONC 7. - 23.957 OWLL AREA 5(RTO-109)DEGF- 98.35 TORUS H2 CONC Y. - 0.000 OWLL AREA 5(RTO-117)DEGF- 109.59 TORUS O2 CONC %- 21.997 OWLL AREA 6(RTO-110)DEGF- 108.75 OWLL AREA 6(RTO-111)DEGF- 108.31 OWLL AREA 7(RTO-118)DEGF- 86.12 OWLL AREA 8(RTO-113)DEGF- 84.11 OWLL AREA 8(RTO-114)DEGF- 85.8C DRYWELL WGTO AVG TEMP- 97.81 Press (RETURN) for Main Menu [TABe?]s Fitzpatrick Plant Eles #3 Data at Times 15: 41 APRM A FLUX LEVEL -
6.391 CRO ORIVE WATER FLO MW/H- 0.03 APRM B FLUX LEVEL - 5.038 F0WTR LOOP A FLOW M#/HR- 0.48 APRM C FLUX LEVEL - 5.618 FOUTR LOOP B FLOW M#/HR- 0.48 O' APRM 0 FLUX LEVEL APRM E FLUX LEVEL 4.127 CLNUP SYS A FLOW M#/HR- 0.04 3.428 CLNUP SYS B FLOW M#/HR- 0.04 APRM F FLUX LEVEL - 5.817 CLNUP SYS INLT TEMP DEGF- 333.96 RX TEMP /RECIRC A DELTA T- -0.341 CLNUP SYS OUTL TEMP OEGF- 293.45 TBCLCU CLR OUTLET DEG F- 74.852 RELIEF VALVE RV-2-11A T- 169.15 CNOSR 33C-10A VAC IN HG- 24.608 RELIEF VALVE RV-2-71B T- 150.04 TOTAL CORE FLOW M#/HR- 27.882 RELIEF V,ALVE RV-2-71C T- 140.47 CORE O!FFERENTIAL PRESS - 1.951 RELIEF VALVE RV-2-710 T- 121.62 RECIRC PMP MTR A PWR MW- 0.057 RELIEF VALVE RV-2-71E T- 181.01 RECIRC PMP MTR B PWR MW- 0.067 RELIEF VALVE RV-2-71F T- 133.04 TOTAL STEAM FLOW Mw/HR- 0.534 RELIEF VALVE RV-2-71G T- 118.50 REACTOR PRESSURE PSIG- 142.804 RELIEF VALVE RV-2-71H T- 127.70 MAIN STEAM PRESSURE - 0.000 RELIEF VALVE RV-2-71J T- 128,12 MAIN STEAM PRESSURE - 1200.000 RELIEF VALVE RV-2-71K T- 137.93 CONO INLT/DISCH TUNNL OT- 4.$57 RELIEF VALVE RV-2-71L T- 202.30 CONO PPS DISCH HOR PRESS- 240.741 RECIRC A1 INLT TEMP DEGF- 362.49 CONO BSTR FMP SUCTN PSIG- 193.079 RECIRC B1 INLT TEMP OEGF- 363.82 Press (RETURN) for Main Menu CTABs73: 7-5
. . _ - - - .- -.. . . - - . _ - - . _ . - . _ ~ - - . . . . - - . - . . . - . - -
i Fitzpatrick Plant Eles #4 Data at Times 15: 41 12 SPENT FUEL POOL mR/He- 0.546 01 CHEMISTRY LAB mR/Hr- 0.05 g s 14 NEW FUEL VAULT mR/Hr- 1.043 02 CLOTHNG CHG AREAmR/Hr- 0.03 30 SOUTH REFUEL FLRmR/Hr- 188.646 03 CONTROL ROOM R/He- 0.01 13 RXBLD 344' SOUTH mR/Hr- 2.405 04 TB 300 HP-END mR/Hr- 0.57 15 RXCU PREC0AT TNKmR/Hr- 8.029 05 TB 300 LP-END mR/Hr- 0.38 17 FUEL POOL PUMP mR/Hr- 74.957 06 TB 252 HOGG PUMPmR/He- 0.1C 18 CONTAM EQPT STORmR/Hr- 2.519 07 RX FEEOPUMP AREAmR/Hr- 0.48 16 RWCU HX ROOM mR/Hr- 1.955 08 R0WST CONTROL RMmR/He- 0.34 20 RX SAMPLE AREA mR/Hr- 7.559 09 RW286 FILTR/VLV mR/He- 6.6( 19 RWCU PUMP AREA mR/Hr- 1.720 10 RW272 ORUM STOREmR/He- 1. 7( 21 RBCLC HX AREA mR/Hr- 0.408 11 RW252 R0WST PUMPmR/He- 12.21 23 RX BLOG EL 2728 mR/Hr- 1.097 22 CONO DEMIN VALVEmR/Hr- 0.61 24 T!P DRIVE PLATF mR/Hr- 2.637 25 EAST CR0 HCV mR/He- 0.897 28 CR0 REMOVL HATCHmR/Hr- 4.981 26 WEST CR0 HCV mR/He- 1.456 27 EAST CRES EL227d mR/Hr- 12.778 l 29 WEST CRES EL227'mR/Hr- 6.854 l Press (RETURN) for Main Menu CTABs73: l l Fitzpatrick Plant Elce #5 Data at Timei 15:41 APRM REACTOR POWER %- -0.923
- RX WATER LEVEL Inch TAF- 204.132 REACTOR PRESSURE PS!G- 143.144 l
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\-- RX TEMP VIA STEAM TABLES- 362.152 FEEDWATER FLOW MLB/HR- 0.959 HPCI PUMP FLOW GPM- 1.406 LPC1 A FLOW GPM- -0.375 LPCI B FLOW . GPM- -3.124 LOWER CORESPRAY FLOW GPM- 0.000 UPPER CORESPRAY FLOW GPM- 0.000 ORYWELL SUMP LEVEL Inch- 15.000 SUPR POOL AIR TEMP OEG F- 84,964 SUPR POOL PRESSURE PSIG- 0.176 TORUS WATER LEVEL FT - 13.900 TORUS WATER AVG TMP DesF ' 75.644 ORYWELL TEMPERATURE DesF- 97.817 ORYWELL. PRESSURE PSIG- 0.154 PRIMARY CONT. H2 CONC % - 0.354 PRIMARY CONT. 02 CONC % - 23.957 Press (RETURN) for Main Menu CTABs738 bl
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Fitzpatrick Plant Eles #6 Data at Times 15 41 g-~ STACK HI RANGE RAD mR/He- 0.182 MAIN STEAM RAD A mR/He- 7.3 i T-BLOG HI RNGE RAD mR/Hr- 0.244 MAIN STEAM RAD B mR/He- S.1 RDWST H! RANGE RAD mR/Hr- 0.100 MAIN STEAM RAD C mR/Hr- 7.8 DWLL HI RNGE RA0(A) R/HR- 1.523 MAIN STEAM RAD 0 mR/Hr- 7,8 OWLL HI RNGE RA0(B) R/HR- 1.925 RA0 WASTE EFFLUENT CPS- 131.4 A XHST BELOW RFL FLR CPM- 41.017 SERV WTR DISCHARGE CPS- 3.5 B XHST BELOW RFL FLR CPM- 173.776 INTAKE WATER-TEMP Dog F- 59.0 RFEUL FLR VENT A RAD CPM- 68.122 RFEUL FLR VENT B RAD CPM- 39.S70
-T-BLOG XHST A RAD CPM- 32.347 T-BLOG XHST B RAD CPM- 34.198 RDWST BLO XHST RAD A CPM- 27.372 ROWST BLO XHST RAD B CPM- 31.221 STACK MON A RAD CPS- 5.601 STACK MON B RAD CPS- 33.564 RX BLOG EXHAUST FLOW CFM- 54153.406 TB BLOG EXHAUST FLOW CFM- 58993.675 RW BLOG EXHAUST FLOW CFM- 30132.855 SBGT FLOW CFM- 6198.150 Press (RETURN) for Main Menu [TABe73:
Fitzpatrick Plant NYS Part 111 Data at Times 15: 41 APRM REACTOR POWER %- -0.923 TB BLOG VENT RAD. uCl/ml- 3.42t IRM REACTOR POWER %- 17.763 RW BLOG VENT RAD. wCi/mi- 1.40!
/ SRM REACTOR POWER CPS- 823.658 STACK HI RANGE RAD Ci/s- 0.461 \ RX WATER LEVEL inch TAF- 204.132 TB BLO H1 RANGE RAD. Cl/s- 5.51; FEE 0 WATER FLOW MLB/HR- 0.959 RU BLO H! RANGE RAD. Cl/s- 0.68!
RCIC FLOW GPM- 0.000 SERVICEWATER RAD. uCi/mi- 0.00t REACTOR PRESSURE PSIG- 143.144 0FFGAS RAD. mR/Hr- 4.033 HPCI PUMP FLOW GPM- 1.406 ORYWELL RAD Monitor R/Hr- 1.925 LPCI A FLOW GPM- -0.375 HIGEST MSL RAD MON mR/Hr- 8.165 LPCI B FLOW GPM- '-3.124 ORYWELL PRESSURE PSIG- 0.154 UPPER CORESPRAY FLOW GPM- 0.000 ORYWELL TEMPERATURE DesF- 97.81". LOWER CORESPRAY FLOW GPM- 0.000 TORUS WATER AVG TMP DesF- 75.644 15.000 13.90C. ORYWELL SUMP LEVEL Inch- TORUS WATER LEVEL FT - STACK GAS RAD. uCi/mi- 83.911 ORYWELL H2 CONC %- 0.354 RX BLOG VENT RAD. uCl/ml- 17.378 ORYWELL 02 CONC %- 23.95~ RFUELFLR EXH RAD. uCi/mi- 1.703 CS TANK LEVEL Inch- 310.344 Press (RETURN) to Continue... P to Print O 7-7
James A. FitzPatrick Nuclear Plant l Part !!! - Plant Farameters Form EAP-1.1.3 Description Units Value APRM REACTOR POWER %- -0.923 1RM REACTOR POWER %- 17.763 SRM REACTOR POWER CPS- 823.658 RX WATER LEVEL Inch TAF- 204.132 FEE 0 WATER FLOW MLB/HR- 0.959 RCIC FLOW GPM- 0.000 REACTOR PRESSURE PSIG- 143.144 HPCI PUMP FLOW GPM- 1.406 LPCI A FLOW GPM- -0.375 LPCI B FLOW GPM- -3.124 UPPER CORESPRAY FLOW GPM- 0.000 LOWER CORESPRAY FLOW GPM- 0.000 ORYWELL SUMP LEVEL Inch- 15.000 STACK GAS RAD. uCl/mi- 83.911 RX BLOG VENT RAO. uCl/mi- 17.378 RFUELFLR EXH RAD. uCi/ml- 1.703 TB BLOG VENT RAD. uCi/mi- 3.420 RW BLOG VENT RAD. uCl/mi- 1.405 STACK H! RANGE RAD. Cl/s- 0.461 TB BLO HIRANGE RAD. Cl/s- 5.513 RW BLO HlRANGE RAO. Cl/s- 0.685 SERVICEWATER RAO. uCl/mi- 0.000 O OFFGAS RAO. mR/Hr-DRYWELL RAD Monitor R/Hr-4.031 1.925 HIGEST MSL RAD MON mR/He- 8.165 ORYWELL PRESSURE PSIG- 0.154 ORYWELL TEMPERATURE DegF- 97.817 TORUS WATER AVG TMP DesF- 75.644 TORUS WATER LEVEL FT - 13.900 ORYWELL H2 CONC %- 0.354 ORYWELL 02 CONC %- 23.957 CS TANK LEVEL Inch- 310.344 Emergency Olrector Approvals ______________________ TIME 15: 41 i
Trending - One (1) Hour History
\- A. Core Thermal Power MW Thermal B. Gross Gen. Power 7. Rated C. Gross Gen. Power MWatt O. Cond Inlet /Osch Tunnel OT Des F E. Cinus Sys Inlet Temp. Des F F. Reactor Pressure PSIG G. Reactor Water Level Inches TAF H. Conder 33C-10A Vacuum inches Hg
- 1. RBCLC Water HX Outlet Dog F.
J. TBCLW Clr Outlet Temp. Des F. K. Drywell Pressure PSIG L. Torus Pressure PSIG M. Torus Utr Lvl Feet N. Torus Wtr Temp Des F. O. Drywell Oxygen (0/30%) % Volume P. Main Steam Pressure PSIG Q. Vessel Bottom Orain T. Dog F. R. Stack Hi Range Rad, mR/He S. T-Blde HI Range Rad, mR/He T. Rdwet HI Range Rad. mR/Hr. Enter Choice CA-TL or 0 to Quits 204.500+ G. Reactor Water Level Inches TAF I i
/~N 204.400+ +
(-) 204.300+ l
+
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l 1 203.900+ + l i 203.800+ + l I 203.700+ + l i 203.600+ + l 1 203.500++----+----+----+----+----+----+----+----+----+----+----+---++ 6J 55 50 45 40 35 -30 25 20 15 10 5 1
<-- Minutes Ago Press Any-Key...
High = 204.182 Lou = 203.984 Last . 204.044 7-9
=== 15-Minute Average Met Data ===== /'
Dates 6/21/90 Times 13:45
'\ =======u== Main Tower ==============
30 ft wind speed (mph) = 1.7 ! 30 ft wind direction (des) = 348. 30 ft sisma-theta (des) = 27.3 30 ft temperature (des f) = 65.4 100 ft wind speed (mph) m 0.0 100 ft wind direction (des) = 0. 100 ft delta t (des f) = 0.0 200 ft wind speed (mph) = 4.0 200 ft wind direction (des) = 315. 200 ft sigma-theta (des) = 5.7 200 ft detta t (des f) = 2.2 m=ammessen Backyp Tower numamens 96 ft wind speed (mph) = 5.0 96 ft wind direction (des) = 328. ammmmmmmmme jnlgnd TQwgr mem=musamme . 30 ft wind speed (mph) = 0.0 ' 30 ft wind direction (des) = 0, 30 ft sisma-theta (des) = 0.0 i Press RETURN for Main Menus O
SECTION 7 James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 ARMS and In-Plant Maos Timeline of exercise ARM readings are attached. These values are for controllers use only. Also attached are in-plant maps which may be used for reference when repair teams are dispatched into the plant. These in-plant maps are to be used when providing all in-plant radiological data. The controllers shall provide all non-radiological data (i.e. status of repairs, valve indications, pressure readings, etc.) to drill participants in accordance with Section 6 of this scenario
. package and the damage repair reports.
Any area that is entered which does not appear on these in-plant maps shall have radiological conditions which are normal to that area under operating conditions.
~h Any area that is entered at a time which does not appear on these (d
in-plant maps shall also have radiological conditions which are normal to that area under operating conditions. O 7-11
m SECTION 7 IL.)T AREA RADIATION MONITORS DATA SHEET (All readings are mR/hr)
. ARM 0700 to 0815 to 0900 to 1100 to 1130 to
# ARM Location 0815 0900 1100 1130 1200 1 AB 272' Chem Lab Normal Normal Normal Normal Normal 2 AB Change Area Normal Normal Normal Normal Normal 3 AB CR Normal Normal Normal Normal Normal 4 TB 300' HP End Normal 145 Upscale Hi 195 150 5 TB 300' LP End Normal 118 Upscale Hi 138 110 6 TB 252' Hogging Normal 85 Upscale Hi 105 100
_. 7 TB 252' Feed Pump Normal 150 Upscale Hi 150 120 8 RW CR 284' Normal Normal Normal Normal Normal 9 RW Filter /Vlv 279' Normal Normal Normal Normal Normal 10 RW Drum Area 272i ~ Normal Normal Normal Normal Normal 11 RW Pmp Rm 252' Normal Normal Normal Normal Normal 12 RxB 369' Fuel Pool Normal Normal Normal Normal Normal 13 RxB 344' S. End Normal Normal Normal Normal- Normal 14 369' Fuel Vault Normal Normal Normal Normal Normal 15 326' Cleanup Tank Normal Normal Normal Normal Normal
- O 16 300' Clnup Hx Normal Normal Normal Normal Normal U 17 326' Pool Pmps Normal Normal Normal Normal Normal 18 326' Decon Storage Normal Normal Normal Normal Normal 19 300' Rx Clnup Pmp Normal Normal Normal Normal Normal 20 300' Rx Sample Sta Normal Normal Normal Normal Normal 21 300' CLCW Hx Normal Normal Normal Normal Normal 22 TB 252' Demin Vlv Normal 160 Upscale Hi 180 150 23 RB 272' Access Normal Normal Normal Normal Normal 24 RB 284' TIP Normal Normal Normal Normal Normal 25 272' East CRD Normal Normal Normal Normal Normal 26 272' West CRD Normal Normal Normal Normal Normal 27 227' Equip Sump Normal Normal Normal Normal Normal 28 272' CRD Hatch Normal Normal Normal Normal Normal 29 227' West Sump Normal Normal Normal Normal Normal 30 369' S. Fuel F1 Normal Normal Normal Normal Normal 7-12
SECTION 7 (~} L.) INPLANT AIR SAMPLE DATA (Field Readings in R/hr) (Concentrations in pCi/cc) NUCLIDE 0-1 1.1-10.0 10.1-20.0 20.1-50.0 50.1-100 (R/hr) Kr-85 8.4E-06 8.4E-05 2.5E-04 4.0E-04 1.2E-03 Kr-85m 8.4E-05 8.4E-04 2.5E-03 4.0E-03 1.2E-02 Kr-87 1.5E-04 1.5E-03 4.3E-03 7.0E-03 2.1E-02 Kr-88 2.1E-04 2.1E-03 6.2E-03 1.0E-02 3.0E-02 Xe-131m 2.5E-04 2.5E-03 7.4E-03 1.2E-02 3.6E-02 Xe-133 7.8E-04 7.8E-03 2.3E-02 3.7E-02 1.1E-01 Xe-133m 1.1E-04 1.0E-03 3. E-03 5.0E-03 1.5E-02 Xe-135 8.4E-05 8.4E-04 2.5E-03 4.0E-03 1.2E-02 Xe-135m 1.3E-04 1.3E-03 3.7E-03 6.0E-03 1.8E-02 I-131 8.4E-08 8.4E-07 2.5E-06 4.0E-06 1.2E-05 I-133 1.2E-07 1.2E-06 3.5E-06 5.7E-06 1.7E-05 I-135 7.1E-08 7.1E-07 2.1E-06 3.4E-06 1.0E-05 l - TOT. CONC. 1.8E-03 1.8E-02 5.29E-02 8.54E-02 2.55E-01 (pCi/cc)
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l NOTE: Information on this sheet is for controller use only. This page will not be handed to drill players. l l f) / 5 x' 7-13
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SECTION 7 James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 Chemistry Data O O 7-41
1 I i
,. SECTION 7
$s Table 1 ) SMALL VOLUME I REACTOR WATER RADIATION LEVELS (1) l l Time Dose Rates (mR/hr) Normal Sink Entire Contacts 30 Drill P 1 ft.: 5 3 2 ft.: 2 0 3 ft.: 1 (1) Data to be provided to Sample Team Member if the sink is operated. a m 7-42
SECTION 7 Table 2 REACTOR C001 ANT ACTIVITY DATA (pC1/g) (Entire Exercise) I-131 4.8E-2 I-132 8.5E-3 I-133 7.1E-3 I-134 1.1E-2 I-135 1.2E-2 Kr-83m 8.2E-1 Kr-85 1.7E-1 Kr-85m 3.1E+0 Kr-87 1.2E+0 Kr-88 8.4E+0 Xe-131- 1.1E-3 Xe-133 3.1E-1 Xe-133m 1.1E-2 Xe-135 6.1E-2 Xe-135m 4.2E-2 Xe-138 1.2E-3
- ,-- .Cs-137 3.1E-2 e
J-1 i: l l. O 7-43
- . - . . . . . . . _ . . . . - - . ~ . _ . - . - . - - - - -
- . - . . - . . . ~ . , - _ . . - , - _ . , . . _ , . - , - . , - - - .
._ _ . . _ - . . . ~ . . . - - . . . - . . - . - . -. . . - . - - - . - . _ . . . ~.. ._... - ... .._-- -
SECTION 7 James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise I l December 19, 1990 Offsite Radioloaical Data The following Turbine Building Vent Radiation Monitor readings and
-dose rate maps are based on a simulated atmospheric release of approximately 4 Ci/sec out the Turbine Building vent. l On the day of the exercise, actual meteorology will be used. An l example of a similar release under real time meteorology can be ,
seen in Section 3 of this scenario. ; l l I l l l l 1 I n 7-44
...a , . +. . --
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SEOTION 7 TURBINE BUILDING VENT RADIATION MONITORS Monitor Reading Iing Vent Flow Lgw Rance Hiah Rance 0700 70,000 cfm 70 cpm 0 mR/hr 0715 70,000 cfm 70 cpm 0 mR/hr 0730 70,000 cfm 70 cpm 0 mP/hr 0745 70,000 cfm 70 cpm 0 mR/hr 0800 70,000 cfm 70 cpm o mR/hr 0815 0 70 cpm 0 mR/hr 0830 0 70 cpm 0 mR/hr 0845 0 70 cpm 0.1 mR/hr 0900 0 70 cpm 0.2 mR/hr 0915 0 70 cpm 0.25 mR/hr 0930 70,000 cfm* Offscale 0.27 mR/hr 0945 70,000 cfm Offscale 0.26 mR/hr 1000 70,000 cfm Offscale 0.27 mR/hr 1015 70,000 cfm Offscale 0.27 mR/hr 1030 70,000 cfm Offscale 0.25 mR/hr 1045 70,000 cfm Offscale 0.26 mR/hr 1100 70,000 cfm Offscale 0.26 mR/hr 1115 70,000 cfm Offscale 0.23 mR/hr O 1130 1145 70,000 70,000 cfm cfm Offscale 600,000 cpm 0.20 mR/hr 0.1 mR/hr 1200 70,000 cfm 50,000 cpm 0 mR/hr
- Assuming building ventilation unisolated and exhaust fans started.
7-45
i SECTION 7
%)
OFFSITE AIR SAMPLE DATA Conc. (sci /cc) for Various Dose Rate Readings (mR/hr) NUCLIDE 1-10 11-20 21-50 51-100 101-200 l Kr-85 8.4E-09 8.4E-08 2.5E-07 4.0E-07 1.2E-06 Kr-85m 8.4E-08 8.4E-07 2.5E-06 4.0E-06 1.2E-05 Kr-87 1.5E-07 1.5E-06 4.3E-06 7.0E-06 2.1E-05 Kr-88~ 2.1E-07 2.1E-06 6.2E-06 1.0E-05 3.0E-05 Xe-131m 2.5E-07 2.5E-06 7.4E-06 1.2E-05 3.0E-05 Xe-133 7.8E-07 7.8E-06 2.3E-08 3.7E-05 3.6E-05 Xe-133m 1.1E-07 1.0E-06 3.1E-09 5.0E-06 1.1E-04 Xe-135 -8.4E-08 8.4E-07 2.5E-09 4.0E-09 1.5E-05 Xe-135m 1.3E-07 1.3E-06 3.7E-09 6.0E-09 1.3E-05 I-131 8.4E-11 .8.4E-10 2.5E-09 4.0E-09 1.8E-08 I-133 1.2E-10 1.2E-09 3.5E-09 5.7E-09 1.7E-08 I-135 7.1E-11 7.1E-10 2.1E-09 3.4E-09 1.0E-08 TOT. CONC. 1.8E-06 1.8E-05 5.3E-05 8.5E-5 2.6E-04
.i i .Part. . .
[ Count Rate (cpm) 0 5 15 20 75' 1 I Count Rate (cpm) 5 45 135 210 750 NOTES Information on this sheet is for controller use only. This page will not be handed to drill players. Deposition increase due to precipitation.
.1 Light rain, drizzle or. snow flurries = no change in data 2 - Moderate rain or snow = multiply data by 1.1 3 - Heavy rain or. snow = multiply data by 1.3 Reference Slade, D.H. " Meteorology and Atomic Energy," 1968.
7-46
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t d SECTION 8 j James A. FitzPatrick Nuclear Power Plant 1990 Partial ~ Scale Emergency Exercise l December 19, 1990 i 1
. 1 1
ANTICIPATED ACTIONS I. Control Room II.. Technical Support Center III. Operational Support Center IV. Emergency Operations Facility 1 l O l l s n ll l O 8-1
? - ,-..,,c-._-.....m.,,-.--;__-_,-_.,,, ..---,...-4.,. . . . . . . . - , - . . . . - . . . ..
Tech. Support Ctr. Oper. Support Ctr. Emere. Ops. Fac. Event Time Control Roo:n None None None
- 1. Stuck 0700 1. Actions in control rod to accordance 0730 with AOP-24.
- 2. Recognize 24-hour 140 requirement.
- 3. Classify m UNUSUAL EVENT.
E None None None
- 2. Loss of 0730 1. Contact 115KV to Niagara l reserve 0930 Mohawk and i power request emergency restoration of power.
- 2. Actions in accordance with AOP's.
f l l l
.g -
s ] ,. ( 1 s - i j i 4-l [ Event- Time . Control Room Tech. Support Ctr. _ Oper. Support Ctr. Emerr. Ops. Fac. !
- 3. Scram with- -
0800 1. ' Actions in -1. Determine 1. ' Work with 1. Perform dose [ break in- accordance. source of . engineers on proj ee.tions. ! Main Steam. with EOP's break and implementing , Line Drain and AOP's to rate of corrective 2. Recommend ! Pipe _ stabilize leakage. actions. protective !
. plant. actions. !
- 2. Determine i j.
- 2. Classify- appropriate 3. Relieve TSC. f SITE AREA mitigating of offsite !
ENERGENCY actions. comum_=nica- ? based on ' tions. [ steam line ' 4
, break. j s r u 3. Notify '
- offsite .
j agencies. [ 4 Hydrogen 0930 'l.- Actions in 1. Assess 1. Work with 1. Perform dose a Explosion accordance potential engineers on projections. $ with E0P's dansge due to implementing * ] and AOP's to explosion. corrective 2. Recommend 3 stabilize actions. protective -)
- - plant. 2. Continue actions. >
j- efforts to ! l mitigate 3. Relieve TSC ) l accident of offsite : consequences. communica- I j- tions. j t !~ l j t i .[>
SECTION 9 James A. FitzPatrick Nuclear Power Plant 1990 Partial Scale Emergency Exercise December 19, 1990 METHOD OF EVALUATION I. SAP-6 " Drill / Exercise Conduct" O l l l l 9-1
NEW YORK POWER AUTHORITY Pg JAMES A. FITZPATRICK NUCLEAR POWER PLANT tJ EMERGENCY PLAN IMPLEMENTING PROCEDURE EMERGENCY PLAN VOLUME 3 I PROCEDURE NO.: SAP-6 TITLE: DRILL / EXERCISE CONDUCT
- PORC REVIEW NO. Meeting No. 89-48 Date 8-16-89 APPROVED BY: h -
Resident . nager APPROVED BY: _^ EmergencyPlan[ingCoordinator PAGE NO. 1 2 3 4 5 6 7 8 9 10 REV. NO. 3 0 4 3 4 0 3 0 0 4 PAGE NO. 11 12 13 14 15 16 17 18 19 20 REV. NO. 4 0 4 4 4 4 4 4 4 4 PAGE NO. 21 22 23 24 25 26 27 28 29 30 REV. NO. 4 4 4 4 4 4 4 4 4 4 PAGE NO. 31 32 33 34 35 36 37 38 39 40 REV. NO. 4 4 4 4 4 4 4 4 4 4 PAGE NO. 41 42 43 44 45 46 47 48 49 50 REV. No. 4 4 4 4 4 4 4 4 4 4 PAGE NO. 51 52 53 54 55 56 :57 58 59 60
- REV. No. 4 4 4 4 4 4 4 4 4 4 1
l. PAGE NO. 61- 62 63 64 65 66 67 68 69 70
.REV..NO.. 4 4 4 4 4 4 4 4 4 4 PAGE NO. 71 i-72 73 74 75 76 REV. NO. 4' 4 -4 4 4 4 1 Rev. No. 4
'Date: -08/89
_ . _ _ _ - _ _ _ . . _ _ _ . _ _ . _ . _ - _ _ . _ _ . _ . _ _ . _ _ . - . ~ _ _ . _ _ EMERGENCY PLAN IMPLEMENTING PROCEDURE SAP-6 DRILL / EXERCISE CONDUCT
- 1.0 PURPOSE i
To establish a procedure for the conduct and evaluation of all Emergency Plan Drills and Exercises at JAFNPP. This procedure also outlines the management controls used to ensure that corrective actions are implemented.
2.0 REFERENCES
2.1 NUREG-0654 ation of -_ " Criteria for the Preparation and Evalu-Radiological 4 Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". 2.2 JAFNPP Emergency Plan and -Implementing Procedures, Volumes 1, 2 and 3. 2.3 SAP-1 MAINTAINING EMERGENCY PREPAREDNESS
- 2.4 Administrative
)ISTRIUUTION OF Procedure THE EMERGENCY6.2 PROCEDUREPLAN &
FOR CONTRO
- >ROCEDtRES* IMPLEMENTING 3.0 INITIATING EVENTS Not Applicable.
4.O PROCEDURE 4.1-Drill Conduct cedure. is discussed in Section 5 of this -pro-activity for a drill at JAFNPP.This section delineates the minimu 4.2 Exercise procedure. Conduct is discussed in Section 6 of this ceptable activity Thisfor section delineates an exercise at JAFNPP. the minimum ac-4.3 ' Observer procedure. ConductThis section is discussed specifies in Section 7 of this the minimum ac-captable, preparation, training and response required for an observer of a JAFNPP drill or exercise.- l 4.4 Critiques and Corrective Actions ar's Section 8 of this procedure. discussed in This section specifies the method in which problems with Emergency Prepared-ness at JAFNPP are handled. O Rev. No. 3 Date 12/87 Page 1 SAP-6 of
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- ~.. - _ - - .- - _ _ . - - . . - - . - - - . . - - - - - - .
- 5. 0. DRILL CONDUCT 5.1 -Drills shall be directed with the frequency established by SAP MAINTAINING EMERGENCY PREPLREDNESS.
e 5.2 Drills shall be directed by a Lead Controller who shall i' be responsible for conducting the drill in accordance
- with the drill scenario and the drill report.
5.2.1 The Imad controller may conduct a briefing with ^ drill participants. The intent of such a briefing would be to insure that drill participants under-stand their function and purpose in the drill. The Lead controller may delegate controller res-5.2.2 ponsibilities to other individuals. Controllers n t.nd observers can be used for this purpose. A controller shall be called such when that indiv-iduals sole responsibility is to assist in the conduct of a drill. An observer can function as a-
. controller when assigned the task of providing information or instruction during a certain aspect of a drill.
L _ 5. 2. 3 - The. Lead Controller shall-insure that plant safety is not compromised by a drill, and may stop a
- drill at any time if in his opinion plant safety may be affected.
'5.2.4 The_ Imad controller shall attempt to collect the signatures of as many participants as possible'for training documentation. This responsibility can be' delegated to other controllers,.or observers.
.5.2.5
.The Imad Controller _ shall commence and and the Drill, upon approval from the JAFNPP Resident Manager..
5.2.6 The Lead Controller shall' ensure that drill ob- -3 servers are stationed to properly observe the drill. 5.3 During a ' drill, when (public address system) ..announce-: ments are made, those announcements shall be prefaced or_followed by the'words "This is:a Drill". 5.4- During a' drill when contacting ~any'offsite or non-NYPA, institution, the individual shall insure that the
- organisation- fully realizes. that no' emergency exists onsite and that- it is a test of the JAFNPP Emergency
-Plan.-
t O
-Rev. No. O Date 04/83 Page 2 of SAP-6
;_ _ . _ _ _. __ . _ - - . _ .~_._.-.,u - , - _ . u
I 5.5 Drills shell be conducted using the guidance estab-lished by Form SAP-6.1 " Drill Conduct Checklist". 5.6 The Emergency Planning Coordinator shall conduct an observer meeting prior to a drill. The meeting shall be to inform the observers of their specific tasks. 6.0 EXERCISE CONDUCT An Exercise shall include all items specified for a drill with the following differences: 6.1 Exercises shall be conducted with the frequency estab-lished by SAP MAINTAINING EMERGENCY PREPAREDNESS. 6.2 A Lead Controller stationed in the Control Room shall be responsible for conducting the exercise in accord-ance with the written scenario. As a minimum, con-trollers shall also be present in the Technical Support Center, Operational Support Center, and the Emergency Operations Facility. 6.3 Every attempt should be made to include Federal, State and local input into the davelopment of the exercise scenario. 6.3.1 The Exercise scenario shall be developed by a committee headed and organized by the Emergency Planning Coordinator at JAFNPP. 7.0 OBSERVER CONDUCT 7.1 Observers shall be used to record all significant events and the time at which they occur during a drill or exercise using Form SAP-6.2 " Evaluation Form". The l drill or exercise scenario shall state the objectives of the drill or exercise which will determine the major areas for the observers to concentrate their observa-tion. Actions to be observed includes the ability to control the emergency, timely and proper notification, availability and use of equipment and _ personnel for control and recovery, assessment of consequences of the emergency actions taken by emergency personnel, and the necessity for off-shift notifications. 7.2 Observers Superintendent of Power. shall be selected with the concurrence of the Rev. No. 4 l Date 03/89 _ _ Page 3 of SAP-6 _ _ _ - _ _ - - - - . - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - ~ - - - ~
7.3 There shall be enough observers to match all points
,.C specified in the drill / exercise scenario or drill form (SAP-1.2). The degree of observation shall be made based on the extent of the drill or scenario. As a general rule, however, observers shall be stationed to observe all expected major actions of the drill ex-pected and as listed in objectives statement of the I
drill or exercise scenario. As a general rule of thumb, an observer shall be available at a ratio of one observer to each five participants. (With the excep-tit,n of Plant accountability drills. ) At least two observers eight observersmust forbe anavailable exercise. for drills and at least 7.4 In plant observers shall be badged following normal plant badging procedures, and are required to , contact security during any accountability drills or exercises to identify themselves and their location. 7.5 Observers shall be visibly identified as observers, and they should take no part in the action of the drill or exercise except tot ' 7.5.1 Indicate simulated conditions drill participants, (e.g., to the exercise or survey meter readings, contamination levels, etc.), but only after instructions by the lead controller or individual { x acting on behalf of lead controller. 7.5.2 Observe poor communication techniques and pro-cedures they occur. and note / correct such occurrences when 7.5.3 Prevent the communication of simulated emergency ! conditions as actual conditions outside of the l exercise or drill area and to ensure that radio or l telephone messages are periodically preceded and ended by the statement "This is a Drill". 7.5.4 Prevent actions which might create a hazard to ! personnel or eruipment. In such cases, observers i shall require personnel participating in the L l exercise or drill to indicate the action verbally. l 7.6 Observers the shall be briefed as to their duties prior to j commencement of the drill or exercise. Drill observers should be briefed within 24-hours of the commencement of a drill. Exercise observers should be
-briefed exercisewithin 24 hours and written aids of the andcommencement procedures shall of bean provided for use by the observers. This 24-hour time frame may be adjusted to compensate for un. announced exercises.
O Rev. No. 3 Date _ 12/87 Page 4 of SAP-6
7.7 Training shall be provided to observen by the JAFNPP l Training Department. The training provided for ob-servers will entail the briefing listed in Section 7.6. The briefing shall include a review of the drill or exercise scenario, the observer duties with regard to the assigned areas of observation, and the key points to be noted. The Emergency Planning Coordinator shall provide the JATNPP Training Department with a list of observers to be trained seven drill or exercisa. Exceptions (7) daysqualified to the in advanceob- of server list may be made by the Emergency Planning Coordinator. The exception shall be noted in a mem-orandum detailing why the exception war being made. 7.8 At the conclusion of the drill or axercise, the Emer-gency Planning Coordinator or thd Fire Protection Supervisor shall collect the cr.,wpleted " Evaluation Forms" (SAP-6.2), compile a list of participants and l conduct a critique with the observers. l 7.9 Observers shall familiarize themselves with the duties and action requirements of the personnel they are monitoring. The Drill Report SAP-i.2 shall list Observers' Name, organization, Area of Responsibility, , and Reference Procedures. Observers shall review referenced procedures. observers shall use the follow-ing as guidelines. 7.9.1 Control Room The observer shall observe the action of personnel assigned to the control Room and personnel who report to the Control Room for assignment. In i addition, special attention will be given to the following. Use of map and overlays. Notifications to onsite personnel and offsite agencies. Request for the call-in of off duty person-nel. operations handling of accident conditions. Instructions given to Search and Rescue, Repair and Corrective Action Teams and H.P. Tech's by the Shift Supervisor (SS), as ap-l plicable. Does the SS handle the emergency by directing L people or by trying to do the work himself? lO I Rev. No. 4 Date 08/89 Page 5 of SAP-6 l
7 - Are the time frames of actions by the SS V) r reasonable enough? Actions of personnel in the Control Room. Communications with the EOF. Communications with the TSC. Actions of the STA. 7.9.2 Control Point It is to be noted that all normal practices such as sign out and use of frisker and the portal monitor are to be accomplished unless the H.P. Technician gives other directions because of radiological conditions. The observer will pay special following. attention to the above along with the No one is wearing radiological protection clothing when leaving. All alarms from monitoring equipment are acknowledged. 7.9.3 Assembly Area observe the following for assembly area personnel: They seek out their assembly area, generally stay together as a group and remain orderly. Time of assembly and comple:ed accountabil-ity. l 7.9.4 Emergency Operation Facility This is the command post for the Emergency and it L should seem so to the observer. Look for the following things The . Emergency Director is in command of the EOF. Any extra personnel, spectators and those awaiting orders, are quietly standing out of the way. The Emergency Director has assigned personnel I to various functions, i.e., Communications, L Radiological Assessment. l Rev. No. O Date 04/83 Page 6 of SAP-6
Has the -Emergency Director contacted the Operations Coordinator? The Radiation Protection or Support Personnel are performing duties in _an efficient manner and reporting results to the Director. Emergency Instrumentation deployed in the EOF is placed in an non-interfering position. How problems with the radio and telephone are handled.. Using time as criteria, release rates and thyroid and whole body exposures to the offsite population are calculated quickly af ter the receipt of data from the Control . Room or.the Offsite Monitoring Team (s). I The and time frame of updates to offsite agencies. the re porting .of exposure' data and
' changes to s:.te meteorological conditions, to
'those same agencies.
The Emergency Director assigns, where possi-ble, the duty of making routine calls to
/3-
-() someone else thereby leaving.himself free to command the action.
. Assessment Teams methods to make protective actions to offsite populations.
7.9.5 Off-Site Monitoring Teams ' The observers shall observe the following items: 3 Received KI dose,-if necessary.
. Operational check performed on survey in-struments, sample counter- and sample pump before leaving the site.
Equipment ~ check off performed.
. Assignment of TLD's and' dosimeters before '
leaving the site.
. Silver Zeolite Cartridges made available before leaving the-site.
Survey instrument operationally checked out and turned on prior to leaving to take field readings. O Rev. No.- 3 Date 12/87 Page 7 of SAP-6 w -
Radio check out by communicating to eof or
=
TSC before leaving. Beta and gamma field surveys performed on the way to sample point. Sampling and field surveys performed at sample location. Instrument calibration performed and samples counted. Work performed in a professional manner. 7.9.6 on-Site Monitoring Team on-site monitoring teams may be assigned field survey work along the perimeter of the site. Check on the following items: Where do they receive their instructions? Dosimeter and film badge are being worn. What type of survey instruments used. Do they pick up a portable radio with survey kit? Radio check performed. Field readings taken along the route to the designated area. Work performed in a professional manner. 7.9.7 Security Force Are all security personnel accounted for? Does security direct people to the nearest assembly area for accountability? Are access and egress roads blocked off? 7.9.8 Technical Support Center The area maintained as a controlled area. Are communications initiated? Are H.P. Surveys performed and by whom? O - Rev. No. O Date 04/83 Page 8 of SAP-6
7.9.9 Operations Support Center How is it staffed? What and how many teams are brought to the OSC? Are phones continuously manned? Are H.P. Surveys performed and by whom? 7.9.10 Radiation Protection Office Do they report to the Radiation Protection office when an Evacuation Alarm Sounds? Do they receive instructions from whom? Are accurate protective measures taken if an entry into the controlled area is required? Who are survey results reported to? (CR and/or EOF) 7.9.11' Fire Brigade Do they receive instructions and from whom? Are protective measures taken if an entry into a controlled are is required? ' Are Fire preplans consulted? Is assistance requested from. local support fire departments? 8.0 CRITIQUES AND CORRECTIVE ACTIONS 8.1 Critique A post exercise / drill critique should be held for. ob-servers and plant supervision by the Emergency Planning Coordinator. The critique should be held within 24 hours 'of the drill / exercise, at a time and place specified by the Emergency Planning Coordinator. This meeting shall be held to help resolve questions raised by 'various observers and plant supervisors and' to develop a list of corrective actions as necessary. The
. observations'should include those actions noted by the observers which were not in accordance with approved procedures. In addition, the exercise drill observers should identify any areas which require clarification, 0 development or revision of procedures.
-Q Rev. No. O Date 04/83 Page 9 of SAP-6
8.2 Emergency Plan Corrective Action Report l Following the critique, the Emergency Planning Co-ordinator shall develop a list of required Corrective Actions as identified at this critique. Corrective Actions shall be documented The required on SAP-6.3 l
" Emergency Plan Corrective Action Report". In addition to the items requiring corrective action identified at the critique, SAP-6.2 any additional items as identified on the
" Evaluation Form" or through routine nurveill-ances shall be detailed on SAP-6.3.
8.3 Review Following the preparation of the Emergency Plan Cor-rective Action Reports, the Superintendent of Power shall review the contents of the reports. 8.3.1 The Superintendent of Power shall review and approve the final recommended corrective action to be taken, the individual assigned responsibility to complete the recommended correctiver action, and the recommended completion dates. 8.3.2 Upon approval of the recommendations, included in the Emergency Plan Corrective Action Report, the approved Planning Coordinator. report shall be returned to the Emergency The EPC shall then prepare SAP-6.4 This log
" Emergency Plan Corrective Action Log". l shall be used for work tracking associated with the Emergency Plan Corrective Actions.
8.4 Close Out 8.4.1 Each individual assigned responsibility to com-plate the recommended corrective action shall be sent a copy of each form SAP-6. 3 that has been assigned to that individual. The action addresses l shall resolve the problem, indicate on the form the it, final corrective action taken, sign and date coordinator. and forward it to the Emergency Planning 8.4.2 In the event that an action addressee cannot complete the final corrective actions by the date specified on form SAP-6.3, a formal request for an extension (by memo::andum) shall be presented to the Superintendent of Power. The request shall include the circumstances or reasons that necessi-tate the extension and an estimated completion date. The Superintendent of Power upon receipt of an extension request, shall review its justifica-tions and, either approve or reject the request. Rev. No. 4 Date 08/89 Page 10 of SAP-6
_ . . - . . . . - - . - - . . . . . . _ . . . - . . . . . - ~ ~ - .. - -.- -. t 1 8.4.3 For' approved extensions, the Superintendent of Power shall assign a revised completion data, and inform the action Furthermore, addressee _of the extension. the Emergency Planning Coordinator
-shall be directed to update the Emergency _. Plan Corrective Action Log, and file the request for extension. For rejected extensions, theaction addressee 'shall be informed - and the request forwarded to the Emergency Planning Coordinator.
8.4.4 The Emergency Planning Coordinator shall, after the preparation and review of an Emergency Plan Corrective Action. Report,.present the report (s) to the Plant operating Review Committee (PORC). The PORC shall review the report (s). This review shall- be incorporated into the PORC meeting minutes. The Emergency. Planning Coordinator shall mainthin the active file on Emergency Plan Correc-tive Action Reports.- The JAFNPP Training Depart-ment'shall maintain the file on training reports. 9.0 FIGURES; FORMS AND ATTACHMENTS '
- 9 .1- FORM SAP-6.1 Drill or Exercise Conduct Checklist' 9.2' FORM SAP-6.2 Evaluation Form
- 9. 3 - FORM SAP-6.3 Emergency Plan Corrective Action Report 9.5 FORM SAP-6.4 Emerge.. Plan Corrective' Action Log i
[L l. L L i; l6 t O Rev. No. 4 -Date 08/89 Page 11 of SAP-6 f
,-g FORM SAP 6.1 DRILL OR EXERCISE CONDUCT CHECKLIST
- 1. Prepare a drill or exercise scenario.
- 2. Prepara a drill or exercise report.
3. Present the drill or exercise to the Plant Operating Review Committee Representative for approval. 4. Brief observers on the entire drill or exercise. '
- 5. Brief the individual observers on specified l tasks.
6. Issue Observer Aids and Drill / Exercise Observation Sheet.
- 7. Initiate the drill or exercise.
- 8. 2nsure the " flow" of activity throughe At the drill or exercise.
- 9. !
Terminate the drill or exercise when it's purpose is accomplished.
- 10. Conduct a critique with participants or observers, j
11. Collect Drill / Exercise observation Sheets.
- 12. Complete Emergency Plan Corrective Action Report, list all deficiencies and recommendations.
- 13. Present the Emergency Plan Corrective Action Report to PORC.
- 14. Complete action required on deficiencies.
Rev. No. O Date 04/83 Page 12 of SAP-6 V
O O O EVALUATION FORM OBSERVER CONTROLLER- LOCATION '. DATE REFERENCE PROCEDURES y a' f O!LIECTIVE 1: EMERCENCY CIASSIFICATION LEVELS
- Demonstrate the ability to monitor, understand and use emergency classification levels (ECL) through the appropriate implementation of emergency functions and activities corresponding to ECL's as required by the scenario. The four ECL's' ara: Notification of Unusual Event, Alert, Site Area Emergency and General Emergency.
i NUREO REF- . POINTS OF REVIEW
.o .YES NO -N/A N/O. $ D.3 'l.
Did the~ organization declare appropriate emergency classification levels? o D.3 2. Were staff notified of ECL's? D D.3 rn
- 3. When was your location notified of the following ECL's?
[Specify the time staff were notified and not the time $ that the ECL was declared by the utility. Also, specify 1 if these notifications were verified (if required).] g. EG.L TIME NOTIFIED UERE NOTIFICATIONS VERIFIED 7 (IF REOUTnEn) , j Notification of Unusual Event , Alert ea . u Site Area Emergency _ General Emergency . ' O D.3 4. Were,the ECL's prominently displayed?
" D.4 _
D.3 5. Were the staff aware of. the current ECL? - 4 os 1.1 ,
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EVALUATION FORM OBSERVER CONTROLLER LOCATION DATE
- o REFERENCE PROCEDURES e
z o l OBJECTIVE 1: EMERGENCY CIASSIFICATION LEVEIS NUREG REF POINTS OF REVIEU l YES NO N/A D.3 N/O 6. D.4 Were the relevant functions and activities implemented in a manner that is consistent with the organization's emergency plan and procedures? E If not,
$ plan and explain why the organization did not follow its emergency procedures.
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EVAIEATION FDRM OBSERVER-CONTROU M_~ M. 'IDCATION DATE ' e REFERENCE PROCEDURES f OBJECTIVE 2: . MOBILIZATION OF EMERGENCY PERSONNEL
- Demonstrate the ability to fully alert, emergency functions.
mobilize and activate personnel.for both facility and field --_- h- _-- ' I NUREC REF , POINTS OF REVIEW __
$ E.1 '1. YES NO. N/A N/O g During what time period were calls / contacts made tooffsite notify response organizations as required by the plan?
Start: O __ Completed: m m Who made-the calls / contacts?
- E.1 '2.
What' method (s) was used to notify organizations? en g, - numbers current and correct?If a written call-list wase used, were staff names and telephon . e
@ E.2 3. -
i, # Were required' staff alerted in a timely manner? - _ E.2 4.
' During what- tiw period were facility staff acti _ _
vated/ deployed? g m Start: __ Completed: E.2 5. List all , staff who were preser t' at your location: O-m _ t 2.1
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- a. 'NUREC REF
' POINTS OF REVIEW i c E.1 6. YES- . NO ~N/A, N/O ~ E.2 Were staff dispatched to.other ~ facilities or locations . : O if-required?' _ _
.o IIf so, list these staff. members and their time of dispatch n STAFF ' .
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EVALUATION FORM OBSERVER CONTROL.LER LDCATION DATE
- o REFERENCE PROCEDURES e
OBJECTIVE 3: DIRECTION AND CONTROL A Demonstrate the ability to direct, coordinate and control emergency activities. NUREC REF POINTS OF REVIEW YES NO N/A N/0 A.I.d 1. a Was an individual effectively in charge of the emergency response 7 y A.l.d 2. If so, name this individual: t o e A.l.h 3. oo A.2.a Were periodic briefings held, to update staff on situation 7 e y A.l.b m
- 4. f A.2.a Were staff (as appropriate) involved in decision making? os u
A.1.b 5. Was a copy of the plan available for reference? A.2.a d2 - e A.2.a 6. Were message logs kept for all incoming and outgoing messages and transmissions? w e Were message reproduced and distributed, if appropriate? I A.2.a 7. Did the facility use an internal message-handling system?
- o m If so, was information provided to staff in a prompt manner 7 If so,
} $ was a record kept of internal messages through logs or file copies?
'd s _ _
os A.l.d 8. Were protective action decisions and implementation of these decisions coordinated effectively with all appropriate organizations? 3.1
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' OBSERVER CONTROLLER IDCATION DATE REFERENCE PROCEDURES lc a
l ,h OBJECTIVE 3: DIRECTION AND CONTROL 1 NUREC REF POINTS OF REVIEli YES NO N/A N/O A A.l.a 9. Were the relevant functions and activities implemented in a l A.l.b manner that is consistent with the organization's emergency A.l.d plan and procedures? A.2.a E If not, explain why the organization did not follow its y emergency plan and procedures: I o Un m >
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0~. 7 ~, b,U - EVAIJJATION FDRM - OBSERVER CONTROLI m-mi IDCATION e DATE 4 -REFERENCE PROCEDURES
- f. OfuECTIVE 4: COMMUNICATIONS- _I.
Demonstrate ability to communicate with all appropriate a loc ti ons, organizations, and field personnel. NUREG REF POINTS OF REVIEW F.1.b 1. Identify c YES NO N/A N/O a F.1.d g mications' systems demonstrated during the e xercise: 1 F. 2 Commercial telephone. Conferencing capabilitySpecify number of lines available: Cellular-telephone in vehicle N [Radiosystem. Specify type of systems: m e -- Computer link. Describe system: r Facsimile machine > <
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Other (specify)
- 4
.o a F.1.b 2.
j F.1.d Identify with: organizations that this facility had communicatio ' F.2 n links u u F.1.b 3. .___ i Were. primary communications systems able to handle 1 flow without undue delays? communication o F.1.b 4. rs - _ What was the average de'.ay for the primary communicati _ ons system? g System
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f) Q EVAlllATION EURM OBSERVER CONTROLLER- IDCATION DATE lc REFERENCE PROCEDURES m f OBJECTIVE 4: COMMUNICATIONS NUREG REF POINTS OF REVIEW YES NO N/A N/O F.1.b 5. Were backup systems demonstrated? F.1.d [ If so, did they function properly? E F.1.b 6. Did any of the communications systems break down? y F.1.d If so, describe the break downs with respect to what occurred; a the primary or backup system; the length of time; impact on m organizational functioning; steps taken to correct problem, and any use of a backup system: as y ao ' i u
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j F.1.b 7. F.1.d Were ti;e relevant functions and activities implemented it. a manner that F.2 is consistent plan and procedures 7 with the organization's emergency u u If not, 1 plan andexplain why the organization did not follow its emergency procedures: O es U)
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OBJECTIVE 5: FACILITIES, EQUIPMENT AND DISPLAYS Demonstrate the adequacy of facilities, equipment, displays and other materials to support emergency operations. NUREG REF POMS OF REVIEW YES NO N/A N/O H.3 1. Were the following facility components sufficient to support O emergency operations? Sufficient rt o
- a. Space
- b. Furnishings o c. Lighting m d. Rest rooms y m e. Ventilation .o
- f. Backup power (if required per plan) i
- g. Other (specify) -
H.3 2. Was the following equipment available (check if it was) and a 2 sufficient to support emergency operations 7 Available Eaulement Sufficient u Typewriter - a Computer / word processor - Copier - Kitchen supplies Cots _ _ o Other (specify) _ l
$ If not, identify needs: 'E _ _ _
e _ _ _ __ 5.1
m - EVALUATION FORM OBSERVER CONTROLLER LDCATION DATE REFERENCE PROCEDURES A o I h OBJECTIVE 5: FACILITIES, EQUIPMENT AND DISPIAYS NUREC REF POINTS OF REVIEW YES NO N/A N/O a H.3 3. Was access to the facility controlled? H.3 4. Identify maps which were used: O Maps Provided et O Plume EPZ with appropriate planning areas labeled Evacuation Routes c) Plume EPZ population by planning areas ao Relocation Centers y a2 Radiological monitoring points v
- Ingestion EPZ for agricultural information d Other (specify) _ _ ,
- 11. 3 5. Were status boards used and positioned for viewing by staff?
jj If so, identify information placed on status boards: Provided on Status Boards Emergency classification levels l g, Protective action decisions m Weather data (actual and forecast) Other (specify) _ i I j o H.3 6. Were status boards and displays updated in a timely
"* manner (i.e., were they updated within 10 minutes of notification of status changes)7 ___
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7 ~s :_ V O. .V EVAIEATIC3 FORM ! OBSERVER CONTROLLER IACATION- DATE REFERENCE PROCEDURES l0 . O f OBJECTIVE 5: FACILITIES, EQUIPMENT AND DISPIAYS. NUREG REF POINTS OF REVIEW YES NO N/A N/0 H.3 7. Were the relevant functions anduactivic'ies addressed'above J.10.a implemented-in a manner'that is consistent.with the organ-J.10.b ization's emergency plan and procedures? J.11 E If not, explain why the organization did not follow its emergency y plan and procedures: o to y i M
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EVALUATION FDRM OBSERVER- CONTROLLER IDCATION DATE' REFERENCE PROCEDURES W o OBJECTIVE 6: EMERGENCY UORKER EXPOSURE CONTROL f
- Demonstrate the ability to continuously monitor and control emergency worker exposure.
NUREG REF POINTS OF REVIEW YES NO N/A N/O K.3.a 1. Did each emergency worker who entered the plume EPZ have a g ce non self-reading permanent record dosimeter? O If not, identify the reason why a periaanent record dosimeter was not available to each emerge- ::y worker: O e N tn m F. e 9 e os K.3.a 2. Did each emergency worker who entered the plume EPZ have: u. (a) Two direct reading. dosimeters with different ranges? ts
$ List' the ranges of :the two dosimeters:
el #2 I u OR: e (b) One direct reading dosimeter? List the range of the dosimeter: ,
'e o
" 3.
K.3.a Did each ' team or: group have access to a charger for.the ' direct reading. dosimeter? 9 K.3.b 4. Did each worker have an exposure record? _ _ 6.1 ,
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NUREG REF a POINTS OF REVIEW K.3.b S. YES NO N/A N/O Were appropriate instructions issued? K.3.b 6. _ _ Were the dosimeters zeroed 'or the initial readings recorded? E K.3.b 7. y Were the dosimeters emergency worker? read and the exposure recorded for each K.4 8 _ o What exposure was authorized for the mission?
<n K.4 9. .
A Did the emergency workers know who to contact for authorization . to incur limit? exposures in excess of the authorized missio n exposure .to K.3.b $.
- 10. exposure Did'eachhigher emergency worker know what to do if they received than authorized? n a
3 K.3.a _ j 11. Wem the relevant functions and activities implemented in a manner plan and that is consistent with the organization's emergency procedures? u If not, _ o plan and procedures: explain why the organization did not follow its emergency O . tt CO
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- OIUECTIVE 7: FIELD RADIDIDGICAL MONITORING - AMBIENT RADIATION MONITORING
- s. Demonstrate-the appropriate equipment and procedures for-determining field radiation measurements.
NUREG REF POINTS OF REVIEW YES .NO N/A N/O I.8 1. Did the team have a survey instrument? O I.11 g Was it the. instrument specified in the plan? If not, was it equivalent? o m 1.8 2. Did the team have a high-range (greater than 0.05 res/hourf y m 1.11 survey instrument?' to ao e os Was it the instrument.specified in the plan?
- u If not, was it equivalent?
E I.8 3. Did the team have access to equipment spares? y 1.11 I.8 4. Did they perform battery checks and' source checks? u 1.11 m Was there evidence that the instruments were within their calibration period? I.8 5. Were Ca-a-only. and Beta + Cama readings made at both'about " o 1.11 1 meter (waist level) and about 2 cm (near ground level)?- es 1.8 6. Did the team avoid contaminating instruments?'
'o 1.11 s
os I.8 7 Were readings logged along with location, time and date? _ I.11 7.1
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1EVA1EATION RMtM OSSERVER : CONTROLLER lIDCATION- . DATE'-. REFERENCE ' PROCEDLRES f' . OBJECTIVE 7:- l FIEID RADIOIDGICAL MONITORING'-I ANBIENT RADIA' TION' MUNITORING NUREG REF POINTS OF REVIEW YES :NO N/A N/O 1.8 8. Was the team able to find and arrive'at' monitoring location-I.11 - promptly?.
.I.8 9. - Did the staff. in general, display adequate ' training and :
;gp- - 1.11. : knowledge? .
et
- O I.8 10.~Did the team transmit-field readings to the appropriate I.11 location promptly?
o e 1.8 11. Were.the relevant functions ~and activities. implemented In U2 e 1.11 . a manner.that'is consistent with'the organization's H.?? emergency plan'and procedures? ' If not, explain why the organization did not follow its emergency- -%. plan and procedures:-
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ORJECTIVE 8: FIELD RADIDIDGICAL MONITORING - AIRBORNE IODINE MONITDRING I d a' Demonstrate +he appropriate equipment and procedures for the measurement of airbor' radiotodine concentrations as low as 10.(.0000001) nicrocuries per cc in the presence of noble gases. NUREG REF POINTS OF REVIEW YES NO N/A N/O t l' S I.8 1. Did the field team use monitoring equipment identified in the ,
<t I.9 o organization's plan 7
-If not, was it equivalent 7 r
i
$ 1.8 2. Did the field team have power to operate the air sampler (pump),
)
e 1.9 either a 12 volt vehicle source or portable generator for en 120 volt systems? $ e
)
1.8 3. . Was a silver-based adsorber available? (A charcoal adsorber is I.9 acceptable for exercise demonstrations if silver media is available.) , t
@ 1.8 4.
da I.9 Were air samples taken using the proper flow rate and sample u duration, as specified in plan and procedures? " I.8 5. ! Were. samples / components properly bagged and labeled with time, 1.9 date. location and identification of person who took them7 ! i un I.8 6. Did the field team leave the plume and travel to a low-background 1.9 area before attempting to count the air sample media 7 [ g I.8 7. Was the instrument used to count the air sample media within m I.9 calibration date7 , y I.8. 8. Was a fixed (reproducible) geometry used to count the air sample
*c I.9 media? [
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. ,o O U ECTIVE 8: FIELD RADIOIDGICAL MONITORING - AIRBORNE IODINE MONITORING !
t t j NUREG REF ,
- POINTS OF REVIEW ;
1 YES NO N/A N/0 t l I.8 9. Wre the count rates of air sample media transmitted to the ' I.9 proper location promptly? !
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- 10. Wre the relevant' functions and activities implemented in I.9 4
a menner that is consistent with the organization's ; } 2
$' emergency plan and procedures?
- o If not. explain why the organization did not foIIow its emergency plan and procedures:
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O O O EVATEATION IVRM OBSERVER CONTROLLER IDCATION DATE REFERENCE FROCEDURES lc U h OBJECTIVE 9: FIEIR RADIOIDGICAL MONITORING - PARTICUIATE ACTIVITY Demonstrate the ability to obtain samples of particulate activity in the airborne plume and promptly
- perform laboratory analyses.
NUP"; REF POINTS OF REVIEW YES NO N/A N/0 3 r 1.10 1. Did a field monitoring team send an iodine particulate filter to a g laboratory for analyser" Answer questions below if answer is yes. I.10 2. Identify field team official who arranged for filter to be sent to o laboratory. vs Y. *
- 1.10 3. When was the filter sent to the laboratory? What was the time d interval between the taking of iodine samples and sending of the u filter to the laboratory 7 i
8 1.10 4 Who took the filter to the laboratory 7 e O Was this person a " runner" who is not part of the field monitoring team 7 _
$ I.10 5. Identify the name and location of this laboratory:
I.10 6. When did the laboratory receive the filter or simulated filter 7 o m I.10 7. Vere established laboratory procedures for analysis of the filter followed? _ ___ ___ _ 8 (D 9.1
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f~ EVAIDATION FURN OBSERVER- CONTRO1.LER .IDCATION DATE REFERENCE FROCEDURES M3 e i f f ' 1 OMECTIVE 9: FIElf RADIOEDCICAL MONITORING PARTICUIATE ACTIVITY NUREG REF POINTS OF REVIEW YES NO N/A N/O
'I.10 8. Describe the results of the laboratory analysis based on a controller inject message provided to laboratory staff:
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e l o I.10 9. When did the laboratory complete its analysis? (Or, when did the i e
- laboratory receive the controller inject message 7 m 4 en :> !
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s' I.10 10. Did the laboratory provide the results of its analysis to other Ef H.12 organizations? ,
/i If so, identify these organizations and the time they were provided. !
e 2 the data: i I e ! Oraanization Time Provided Data I n u . e I i; I.10 11. Were the relevant functions and activities implemented on a manner H.12 that is consistent with the organization's emergency plan and * , o procedures? m j If not, explain why the organization did not follow its emergency
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, l t OBJECTIVE.10: ' PIJJNE DOSE PROJECTION !
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- Demonstrate the ability, i: based on plant and field within data. the plume exposure pathway, to project dosage to the public via plume exposenre .
) t I NUREG REF POINTS OF REVIEW- ! YES NO N/A N/D : 2 I.10 1. Dere primary and backup systems available for dose projection 7 u
. o"
{ I.10 2. Was plant status information promptly.provided so that offsite i
- j. . dose projections could be made? -
o i e 1.10 3. Were new dose projections made, if appropriate, based upon field o e monitoring data? y
=o ;
s ; l Uere new dose projections made as plant status changed? e . I *
, I l' I.10 4
- i. Was the projected plume location plotted and displayed? !
E Plotted Displayed 4 U [ 1.10 5. ! I Were field monitoring teams properly directed so that the plume L could be defined 7 ! s
+-
Was the plume properly defined by field teams? ! l.10 6. Was field monitoring team data compared with projected dose rates 7 i o 1.10 7. Were projected wind shifts considered in the determination of ! the area of concern? r m - o > a i On
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I OBSERVER CONTROLLER iDCATION DATE REFERENCE PROCEDURES
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OMECTIVE 11: PLUME PROTECTIVE ACTION DECISION NAKING s
- Demonstrate the ability to make appropriate protective action decisions, based on projected or actual dosage, EPA PAG's, availability of adequate shelter, evacuation time estimates and other relevant factors.
NUREG REF POINTS OF REVIEW < YES NO N/A N/O S J.9 1. Were the correct PAC's used in consideration of the technical
- g basis for the protective action recommendation? '
J.10.m 2. . Were any preplanned PAR's implemented for special populations 7 1' o e N .If so, were they in accord with the plan? m ' a P
- J.10.m 3. v )
Were factors other than projected dose, i.e. , quality of shelter, j ETE's, etc., considered, if appropriate, in the protective action - decision making process? " ' t If so, specify these factors: i
'.O f* !,
e ' o , , J.9 4 Were new protective action recommendations made as the plant a status 1 changed? , J.9 5. Were protective action recommendations made without undue delay, recognizing that some discussion is appropriate in all o but the fastest-breaking accidents? m i m
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O O O EVAIEATION FORM OBSERVER CONTROLLER IDCATION DATE REFERENCE PROCEDURES
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OILJECTIVE 12: ALEFT, NOTIFICATION AND ENERGENCY INEDRNATION - INITIAL ALERT AND NOTIFICATION
- Demonstrate the ability to initially alert the public within the- IO-mile EPZ and begin dissemination of an
!: Instructional message within 15 minutes of a decision by appropriate State and/or local official (s). I - NUREC REF POINTS OF REVIEW YES NO N/A N/O i l S E.5 1. Did involved organizations demonstrate the capability to disseminate g E.6 an alert signal and initiate and instructional message to the public , within 15 minutes for the plume Emergency Planning Zone? ! g (This demonstration is required for a pre-agreed to alert and ce notification sequence. Also, the timing of the 15-minute sequence m D starts with designated offsite officials making the decision to ! Implement a protective action or notify the public and ends with @ the instructional message being put on the air.) 4 Was this capability actually demonstrated 7 da If not, describe how the capability was simulated: ; o , l y Identify alerting and notification methods used, if actually demonstrated: [ 1 Alert Notification Fixed siren system Siren system with FA system j Mobile stren system EBS
- o Tone alert radios NOAA Weather Radio m [
Route alerting (primary) Tone alert radios Mobile PA alerting units Mobile PA system notification : y- . (e.g. , helicopter, boar units (e.g. , helicopter, boat l
'o or airplane) or airplane)
[ Telephone calls to Telephone calls to individuals or institutions individuals or institutions , Other (specify): Other (specify): ; i
- 12.1 ,
0 O O EVAIEATION FORN , OBSERVER CONTROLIER IDCATION DATE REFERENCE PROCEDURES
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U OBJECTIVE 12: ALERT, NOTIFICATION AND DfERGENCY INFDENATION - INITIAL AIERT AND NOTIFICATION NUREC REF POINTS OF REVIEN YES ND N/A N/0 Identify involved organizations: 0 tes rt O E.5 2. -If primary route alerting was demonstrated, answer the following questions: E.6 - How and when was the route alerting team (s) notified to initiate its functions 7 N (n . as How: >
- 5 e
i When: " What route alerting vehicle (s) (e.g., police car) did you observe 7 e O For each route observed: When did route alerting being and when was it completed? Time Initiated Time Completed Route 1 Route 2 , o , Route 3 ts Was the route alerting completed within 15 minutes (or 45 minutes
'o if for isolated area 5 to 10 miles from the plant)?
e os Route 1 Route 2 Route 3 12.2
._ _. _ _ . _ _ _ . _ _ _ __ _ ._. __ _ _ _ =
I m ( C (U} EVAIEATION FURM OBSERVER CONTROLLER LDCATION DATE REFERD8CE PROCEDURES l 23 l
- l OILJECTIVE 12: AiERT, NOTIFICATION AND EMERCENCY INEDRMATION - INITIAL AIRtT AND NOTIFICATION i
I ! NUREG REF- POINTS OF REVIEW s YES NO N/A N/O l. t j Did route alerting team (s) have route maps 7 Did route alerting team (s) have a written message to read over the O PA system? (If so, secure a copy of the message.) i er
- g Were the centents of the message accurate according to ,
{ recommended protective actions? , J f Was the PA system actually demonstrated? E.5 3. m D Document the times associated with the following steps in the >
- E.6 ao pre-agreed to 15-minute alerting and notification sequence.
' S I bII. u M
- s. Message from utility with PAR 3
e
- b. Decision made by designated offsite officials ;
" c. Alert signal activated
- d. Instructional message begun i
, E.5 4 Did' involved organizations demonstrate the capability to disseminate e E.6 an alert signal and initiate instructional messages to special populations (e.g. extremely rural low-population areas; recreational areas and open water) from 5 to 10 miles from the plant within ~
45 minutes? O m (This demonstration is required for the pre-agreed to alert and m notification sequence. Also, the timing of the 45-minute sequence ! y o starts with the designated offsite officials making the decision to implement a protective action or notify the public and ends with ;
$ the initiation of an instructional message to the public.)
i 12.3 I
O c2 . 0 EVAIJJATION FORM OBSERVER CONTR0llER IDCATION DATE REFERENCE FROCEDURES 21 0 2 OBJECTIVE 12: ALERT, NOTIFICATION AND EMERGENCY INFURMATION - INITIAL AIIRT AND NOTIFICATION
.o NUREG REF POINTS OF REVIEW YES NO N/A N/O
=
Ves this capability actually demonstrated by the involved organizations or simulated? (provide explanation below) i l l l C O ct O Alert Notification Mobile siren system EBS O Tone alert radios NOAA Veather Radio l . m ( g Route alerting (backup) Tone alert radios $: e Mobile PA alerting units Route alerting (backup) (e.g., helicopter, boat Mobile PA system notification . or airplane) units (e.g., helicopter, boat " Telephone calls to or airplane) individuals or institutions Telephone calls to
*ts Other (specify): individuals or institutions $o Other (specify):
Identify involved organizations: on O E.5 2. If backup route alerting was demonstrated, answer the following questions:
$ E.6 Ilow and when was the route alerting team (s) notified to initiate its functions 7 tn $9 Ilow:
o% When: 12.4
O e TION EURM REFERENCE FROCEDURES EVAIEA DATE O CONTROLLER iDCATION NOTIFICA TION N/O INITIAL ALERT AND NO N/A OBSERVER YES INFORMATION EMERGENCY ATION AND observe 7 ALERT, NOTIFIC car) did you / 12: ice OBJECTIVE le(s) (e.g. , pol OF REVIEW POINTS alerting vehic d? y NUREC REF What route s was it complete om observed: - being and when For each route alerting 11mg_$_2E215L UL4 ute _ did ro _ O O y When Route Route 2 1 IIREL.lIll1Lajjtg
,_ve _route maps?
read o ver essage to _ o Rou te 3 alerting team (s) ha writte n m message.) ve a copy _ m
) ha a of the to Did route _
e cure alerting team (s(If so, se a ccording _ ac curate _ Did route m? message the PA syste of theactions? d contentsctive / dem onstrated? the pre-agree Were therecommended prote actuelly sequence. / w wing steps for j Uas the PA systemof the follog and notification1131 es ument the timspecial alertin Doc 6 to, 45-minute f E.5 12.5 /. E.6 Stf2 with PAR ite officiais
/
i a from utilitydesignated offs
- a. Mess ge made by o
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OBSERVER CONTROLLER LDCATION DATE REFERENCE PROCEDGtES 30 0 2;
.o OBJECTIVE 12: ALERT, NOTIFICATION AND ENERCENCY INFOttNATION - INITIAL ALERT AND NOTIFICATION NUREG REF POINTS OF REVIEN -
YES NO N/A N/D E.5 7. Who authorized the 15 and 45-minute alerting and notification? \ q. W E.6
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4.
'O ta y E.5 8. Was the public notification process by the involved organizations E.6 effectively coordinated among involved organizations?
o If not, describe coordination problems: N
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- 9. Obtain copies of all instructional messages and attach to this form "
(Objective 12). N E.7 10. Was;the content appropriate to protective action decisions? e o Identify the scope of the instructional message:
, Plume exposure pathway u Ingestion exposure pathway Re-entry, resettlement and relocation Other (specify) o
" E.5 11. Were the timing of the alert signal and the instructional message E.6 coordinated to ensure that the alert signal came first, followed by
'o the initiation of the instructional message within a few minutes? _ _
E.5 12. Were arrangements made to periodically rebroadcast the instructional message? 12.6
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f p N U - U(3, . EVAIJJATION FDRM OBSERVER CONTROLLER IACATION DATE REFERENCE PROCEDURES l , to e ' OBJECTIVE 12: ALERT, NOTIFICATION AND EMERGENCY INEDRMATION - INITIAL ALERT AND NOTIFICATION NUREC REF POINTS OF REVIEW YES NO N/A N/D What route alerting vehicle (s) (e.g., police car) did you observe?' I 1 t3 For each route observed: m g When did route alerting being and when was it completed? Time Initiated Time Completed o Route 1 m Route 2 D Route 3 fn , e $" e Did route alerting team (s) have route maps? os u > Did route alerting team (s) have a written message to read over the FA system? (If so, secure a copy of the message.) ' a j Uere the contents of the message accurate according to I recommended protective actions? Was the FA system actually demonstrated? l
, E.5 6. Document the times of the following steps for the pre-agreed E.6 to, 45-minute special alerting and notification sequence. i o Step Time i
t
- a. Message from utility with PAR
$ b. Decision made by designated offsite officials y c. Alert signal activated as d. Instructional message begun '
1 5 9 12.5
EVAIEATION MRM CONTROU M IDCATION DATE e REFERENCE FROCEDURES
. l 2:
,o O&JECTIVE 12:
ALERT, NOTIFICATION AND EMERCENCY IN WRMATION - INITIAL ATSnT AND NOTIFICATION NURfC REF. POINTS OF REVIEW E.5 YES NO N/A N/O E.6 13. Were the relevant functions and activities implemented in E.7 a manner that is consistent with t5e organization's emergencyplan and procedures? o g If not, - - e Plan and procedures: explain why the organization did not follow its emergency i o e N to m y '
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EVAllJATION FDRM OBSERVER C = GLI.ER IDCATION DATE REFERENCE PROCEDURES 22 e OBJECTIVE 13: ALERT, NOTIFICATION AND ENERCENCY INFDRNATION - PUBLIC INSTRUCTIONS
- Demonstrate the ability to coordinate the formulation and dissemination of accurate Information to the public in a timely fashion.
NUREG REF POINTS OF REVIEW YES NO F/A N/O S E.5 1. Did staff disseminate information to the public after the first y alert and notification sequence? If so, specify the times when these disseminations were initiated: o - e s1
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#5 u E.5 2. What organization (s) was responsible for this function?
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, E.5' 3. Did the staff have access to current, accurate and timely un .information? "
r E.5 4. Describe how staff secured current information on protective action recommendations: , 4 o i es i m i
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EVA111ATION FORN OBSERVER ! CONTROuER LOCATION
- n DATE e REFERENCE PROCEDURES OBJECTIVE 13:
ALERT, NOTIFICATION AND ENERGENCY INFURNATION - PUBLIC INSTRUCTIONS i NUREC REF POINTS OF REVIEW a YES NO N/A E.7 5. N/O Were pre-scripted messages used? s If not, describe how messages were developed: o e et , e ' I C.4.a 6. m
, Was the formulation and dissemination of the information to the public effectively coordinated by the involved organizations? l N. If not,
'O describe the nature and extent of the coordination problems: o t
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y Did staff provide accurate and timely information to the public7 i j G.4 8. _ t' Who authorized releases of informati in to the public? . t I ,
, E.6 9.
e Was a log maintained of all releases disseminated to the public7 i i Were copies of all releases kept and accessible to all staff 7 . E.6 _ o 10. Did staff monitor radio and television broadcasts to keep track of information provided to the public? es j C.4 _.
$ 11. Was there a retut a flow of information to the EOF ,and so EOC's y that staff been givenattothese locations the media 7 were aware of what information had os i
4 13.2
j i EVALUATION EURM j OBSERVER CONTR01.1.ER IDCATION DATE REFERENCE PROCEDURES
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i o j OMECTIVE 13: ALERT, NOTIFICATION AND EMERGENCY INFURMATION - PUBLIC INSTRUCTIONS 1 NUREG REF POINTS OF REVIEW YES NO N/A N/0 l a G.4 12. Were press releases and results of press interviews exchanged with other spokespersons? How was information exchanged? m et a o o> Did the information management system provide for the effective to D and timely coordination of the formulation and dissemination of $
- emergency information and instructions? _
If not, describe problems:
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e E.5 13. Were the relevant functions and activities implemented in a manner E.6 that is consistent with the organization's emergency plan and E.7 procedures? w C.4 C.4.a If not, explain why the organization did not follow its emergency 7 l G.4.c plan and procedures: O M th
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l 1 Or l EVAIDATION RMLet \ OBSERVER CONTROLTER ' M IDCATION DATE e REFERENCE PROCEDURES l OBJECTIVE 14: ALERT, NOTIFICATION AND EMERGENCY INFDRMATION
- MEDIA Demonstrate the ability to brief the media in an accurate, coordinated and timely manner.
NUREG REF POINTS OF REVIEW C.3.a 1. YES NO m Did staff provide briefings to the " media *7 N/A N/O g If so, _ _ _ I specify the times when briefings were initiated: _ Briefing #1 _ . g
= Briefing #2 ___ Briefing #6 D Briefing #3 ___ _
Briefing #7 _
- Briefing #4 Briefing #8 Briefing #5 Briefing #9 _ !
i i Briefing #10 _ m , C.3.a 2. - g. What organization (s) was responsible for this fu nction? e
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SQ e C.3.a 3. How many staff were utilized for this function? !
, C.3.a 4 e Did the staff have access to current, information? accurate and timely i
C.3.a 5. - _ O Describe on emergencyhow (source response: and method) staffentsecured informationcurr _ 1 4 Us
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EVAIRATION MRM OBSERVER- CONTROL.LER IDCATION DATE REFERENCE PROCEDURES , Oc o OBJECTIVE 14: ALERT, NOTIFICATION AND EMERCENCY IN MRNATION - MEDIA NUREG REF POINTS OF REVIEW YES NO N/A N/O G.3.a 6. Was pre-scripted information used for the media briefings? I G.3.a 7. Did staff provide accurate, responsive information to the media in a prompt manner? O L3 et O G.3.a 8. Who authorized release of information to the media? G.3.a 9. Did staff provide media with accurate information on the protective S action recommendations for the public?
- m e G.3.a 10. Were all protective action decisions described in terms of familiar ao e
landmarks and boundaries for affected planning areas?
- u r C.3.a 11. Did staff avoid use of technical Jargon?
g C.3.a 12. Were maps and other displays effectively used? ! e U G.3.a 13. Were copies of news releases provided to the " media"? Were they provided in a timely manner? ! o (.Obtain copies of news releases and note time released.) f G.3.a 14. Was a log maintained of information provided to the media? ~ o Uere copies of all releases kept and accessible to all staff? m , y G.3.a 15. Did staff maintain sufficient contact with decision makers to y keep. abreast of current events and information? o l 14.2 7
i c O EVAIEATION FORM U n OBSERVER CONTROLLER IDCATION .DATE REFERENCE PROCEDURE 3 .
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Z OBJECTIVE 14: AIIRT, NOTIFICATION AND EMERGENCY INFORMATION - MEDIA
.o NUREG REF POINTS OF REVIEW YES NO N/A N/O s
G.3.a 16. Did staff. monitor radio and television broadcasts to keep track of information provided to the public? , C.3.a 17. Did staff provide kits to the media? O . N If so, describe the types of information contained in the media kits: ' 2 o o oa N C.3.a 18. Were the relevant functions and activities implemented in a manner tn "e that is consistent with the organization's emergency plan and procedures? 7 u If not, explain why the organization did not follow its emergency plan and procedures:
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EVALUATION EDRM OBSERVER' CONTROLLER IDCATION DATE REFEP_ENCE PROCEDURES ltf ~ 'O h, OBJECTIVE 15: USE OF KI '
- Demonstrate the ability to make the' decision to recommend the use of KI to emergency workers based on predetermined criteria : as well as ' to distribute and administer it once tne decision is made, if necessitated by radioiodine releases.
.g. NUREC REF POINTS OF REVIEW YES NO N/A N/O to g J.10.e 1. Did authorizing official (s) make decision to recommend use of Kl? J.10.f What official (s) made the decisions? o m D When was the decision made? e $ When were instructions to use KI transmitted? m ma For what group? c 8 -Emergency. workers? GD J.10.f 2. Was the decision made to use KI based on projected or_ actual dose to thyroid? m Proj ected Actual u Was the decision to use KI made on the basis of FDA PAG's? _ J.10.f 3. Were the affected emergency. workers / institutions informed of this o decision / instructions in a timely manner? .n - For emergency workers? y When?
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l l OMECTIVE' 15: USE OF KI l NUREG REF POINTS OF REVIEW YES NO N/A N/0 l J.10.e S. Did personnel responsible for direct adminir,cration/use of KI i J.10.f follow instructions given them by authorizing official (s)? l For emergency workers? o a er J.10.f 6. Was the KI distributed in sufficient quantities and in a timely manner according to decisions? For emergency workers? _ _ co When? g3 N >
$ J.10.e 7. If the administration (i.e., ingestion) of KI was simulated, *o' e
J.10.f was the date, time and dose for the use of KI for each
- individual recorded? u J.10.e 8. Were the relevant functions and activities implemented in a manner y J.10.f that is consistent with the organization's emergency plan and da procedures?
o If not, explain why the organization did not fo? w its emergency plan and procedures: a e 0 - ts 03
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Q ~0 EVA11IATION FORM si s.. OBSERVER. CONTRO11.ER IDCATION ! DATE REFERENCE PROCEDURES l- :o w OBJECTIVE 16: SUPPLEMENTARY ASSISTANCE-(FEDERAL /OTHER) a Demonstrate the ability to identify.the need for and call upon Federal and other outside agencies' assistance. NUREG REF POINTS OF REVIEW YES ~ NO N/A N/O C.I.a 1. Was Federal assistance requested? O N st e If so, did an authorized official make this request? Identify this official and his/hr organization: O m y C.1.s 2. Which Federal agency (les) was contacted to request assistance? tn e g e m u
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d3 o C.1.a 3. What Federal assistance was requested 4.nd when was it expected to be C.1.b provided? Assistance When Expected m O m C.I.c 4. What actions'and resources were required by the requesting (n organization (s) to support the Federal response?
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0(% O (J' EVALUATION FORM OBSERVER CONTROLISR 21 IDCATION DATE e REFERENCE PROCEDURES 5 Z _.
,o OMECTIVE 16:
SUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER) ! s NUREG REF POINTS OF REVIE'1 YES NO N/A N/0 Were these actions taken and resources provided? If not, why were they not provided? O 2 et e I o C.4 5. m Was other assistance and resources requested from non-Federal a organizations or individuals? y I If so, which organization (s) requested assistance and resources? *o o's l M m 2
$ C.4 6.
From what non-Federal sources was assistance and resources expected 7 os 4 I C.4 7. What assistance was requested from non-Federal sources and when was it expected? o - et Assistance (n When Exoected
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r U' EVAllJATION FORM OBSERVER CONTROLLER II) CATION DATE REFERENCE PROCEDURES lc p OBJECTIVE 16: SUPPLEMENTARY ASSISTANCE (FEDERAL /OTilER) NUREG REF POINTS OF REVIEW s YES NO N/A N/O C.4 8. What actions and resources were required by the requesting organization (s) to support non-Federal response? O 2 et o Were these actions taken and resources provided? o m If not, why were they not provided? N m m O >
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C.I.b 9. Was appropriate assistance and resources requested from Federal
@ and/or non-Federal sources?
! 4 l " l Was this assistance requested in a timely manner? C.I.a 10. Were the relevant functions and activities implemented in a manner
$ C.1.b that is consistent with the organization's emergency plan and C.I.c procedures?
C.4 ~ If not, explain why the organization did not follow ,its emergency o . plan and procedures: es I (A l > o - a m 16.3
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- D REFERENCE PROCEDURES
^ tan f OBJECTIVE 17: EVACUATION OF ONSITE PERSONNEL i
, Demonstrate the ability to coordinate the evacuation of onsite personnel.
NUREC REF POINTS OF REVIEW , YES NO N/A h/O g J.2 1. to Was evacuation of onsite individuals demonstrated? '
$ J.2 2. If so, was it:
Promptly activated? Well organized? O m J.2 3. e Did the licenste contact offsite authorities to coordinate e evacuation of onsite individuals? y i ao J.2 4 Was an evacuation route specified? e-e T u J.2 5. Was monitoring and decontamination provided for, if appropriate? E Were the relevant functions and activities implemented in a manner
$ that is consistent with the organization's emergency plan and procedures?
a If not, O plan andexplain why the organization did not follow its er;ergency procedures: o es ~ (n
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OBJECTIVE 18: OFFSITE RESPONSE ORGANIZATIONS Demonstrate the capability of offsite response organization personnel to interface with through their mobilization A and provision of advice and assistance. NUREG REF POINTS OF REVIEW YES NO N/A N/O y 1. Identify utility offsite response organization liaisons contacted. rt U Liaison Time Notified O V)
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u C.5 2. At what time did the liaisons arrive at their assir,ned duty station? N.1.b y Liaison Time of Arrival d3 O
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C.5 3. Did liaisons provide advice and information to the control cell? ! N.I.b l If yes, indicate the nature of the advice and informa, tion provided. O M Nature of Advice / Assistance tn Y - 18.1 l
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. OBSERVER CONTROLLER- LOCATION _ DATE' REFERENCE PROCEDURES U
OBJECTIVE 18: UTILITY OFFSITE RESPONSE ORGANIZATIONS-NUREG REF POINTS OF REVIW a YES NO N/A N/0 C.5 4. Did the liaisons provide accurate and timely-information, I if appropriate? C.5 5. Were the relevant functions and activities implemented in a manner S N.I.b that is consistent with'.the organization's emergency plan and g procedures? If not, explain why the organization did not follow its emergency plan and procedures: e
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FORM SAP 6.3 EMERGENCY PLAN CORRECTIVE ACTION REPORT i
' Prepared By: Date:
Hame/ Title Approved: Superintendent of Power Individual Assigned to correct Deficiency ' Name/ Title Reviewed: PORC Date TO BE COMPLETED BY INDIVIDUAL PREPARING FORM ITEM DEFICIENCY-DESCRIPTION AND/OR CAUSE- . RECOMMENDED CORRECTIVE ACTION-CORRECTIVE ACTION TO BE COMPLETED BY DATE TO BE COMPLETED BY INDIVIDUAL ASSIGNED TO CORRECT DEFICIENCY RESOLUTION- (Include-Applicable Work Authorization Numbers or Purchase Authorizations) SIGNATURE: DATE: PLEASE RETURN COMPLETED FORM TO THE JAFNPP EMERGENCY PLANNING i COORDINATOR. 1 0
- l. v Rev. No. 4 Date- 08/89 Page 75 of SAP-6
O O . O E FORM SAP 6.4 g o EMERGENCY PLAN CORRECTIVE ACTION IOG I j NO. t DEFICIENCY SCHEDULED PERSON (Include references ACTION TAKEN DATE
^ COMPLETION ASSIGNED to forms, menos, DATE EVAIEATED etc.)
5 l 8 se i 5 2 a e o Pt in I :P 7 EMERGENCY PLANNING COORDINATOR DATE REVIEWED
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