ML20098F770
| ML20098F770 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/01/1984 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8410030355 | |
| Download: ML20098F770 (85) | |
Text
r Pubhc Service O PS G Cornpany Electr c and Gas 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti Gene al Manager Nuclear Assurance and Regulation October 1, 1984 1
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 REVISED DSER OPEN ITEM / QUESTION RESPONSES /FSAR TEXT Pursuant to discussions with the Power System Branch (PSB),
the responses to the DSER open items listed in Attachment I have been revised and are enclosed for your review and approval (See Attachment 2).
Pursuant to discussions with the Licensee Qualifications Branch, enclosed for your review (see Attachment 3) is a copy of revised FSAR Section 13.2 concerning training programs.
The revised FSAR question responses and text are scheduled to be incorporated into Amendment 8 of the HCGF FSAR.
Should you have any questions or require any additional information on these responses, please contact us.
Very truly yours, k
Attachments
- 9 D
' '0\ .
B410030355 841001 PDR ADOCK 05000354 PDR E
The Energy People 954312(3*.')4 84 L__._
Director of Nuclear .
Reactor Regulation 2 10/1/84
~. .
C - D. H.. Wagner USNRC Licensing'. Project Manager E H. Bateman.
USNRC Senior Resident Inspector t
i
-I 4
1 i
j 5
~
r
- MA 19 01/02-d 4
)f I i ,
k E
i
. , - ., , - ----44 .> - , cr ...,,--v-.---.,..,-.w, ..--,-,-e,.,, e,,- . , . - , . . , , , . , , , _ , , , r ,.,m, e .ve..---y,.,.w,~.-w-<..~.w,.,,w,.
s 4
1 Attachment 1 S.
. DSER OPEN ITEMS 259- 8.3.3.'3.4 Use of an inverter as.
an isolation device 260' 8.3.3.3.5 The use of a single breaker tripped by a LOCA signal astan isolation device en*=gne @W4A i
h
/
-9 i
1 J
t l
r.
I 1.
Y Q.
t
l i
Attachment 2
Rev. 3 841 DSER Open Item No. 253 (DSER Section 8.3.3.3.4)
USE OF AN INVERTER AS AN ISOLATION DEVICE By Amendment 4 to the FSAR, the applicant indicated that the non-Class lE public address system distribution panel shown on sheet 2 of Figure 8.3-ll of the FSAR is supplied power f rom the Class lE dc system th, rough an inverter. The applicant further stated that this inverter is an acceptable isolation device per IEEE-384-1981, Section 7.1.2.3. The staff does not agree. Test and analysis to demonstrate the adequacy of an inverter as an isolation device will be pursued with the applicant.
RESPONSE
The response to Question 430.33 has been revised to state that the inverter will be tested as an isolation device. In the event that the tests are not successful, the non class lE loads will be removed or the cables will be re-routed.
S h
I r
k i
i l
l l~
l l
ow.sk;., 430.as DSER Open Item No. 260 (DSER Section 8.3.3.3.5)
TBE USE OF A SINGLE BREAKER TRIPPED BY A LOCA SIGNAL AS AN ISOLATION DEVICE section 8.3.1.1.2 of the FSAR indicates that the Class lE systes provides power to non-Class lE loads. Non-Class IE loads are connected to the class 1E system through a single breaker that is tripped automatically by a LOCA signal. The single breaker tripped by a LOCA signal provides acceptable isolation between Class 12 and non-Class lE circuits, for the design basis accident--
LOCA. However, for other design basis accidents or operating occurrencos that do not generate a LOCA signal (such as loss of of fsite power, de sign basis exposure fire, seismic events, etc.),
it is the staf f concern that a single breaker may not provide ,
acceptable isolation.
By Amendment 4 to the FSAR, the applicant indicated that protect-tive device coordination studies show that the single breake r time overcurrent trip characteristics will trip to clear a fault prior to initiation of a trip of a upstream breaker. Identifi-cation of all non-Class lE circuits being isolated using a single breaker trip by LOCA signal, periodic testing of breaker coordi-nation, and capability of breaker to trip prior to any versus only upstream breaker and for all versus only circuit faults, will l,
be pursued witn'the applicant.
j RESPONSE Re s ponse to Question 430.33 has been revised to provide the requested in fo rmation.
I i
. _ _ _ , . - _ - . - _ - _ _ _ _ _ _ . . _ _ , , _ _ _ _ _ _ . , , , . . . . , _ _ _ _ - . _ . _.-__.,-._,,-._-.-__.--m--r.
g, y 1 MCGS FSAR OUESTION 430.33 (SECTION 8.3.1 and 3.3.2)
Section 8.3.1.1.2 of the FSAR indicatesNon-Class that the Class 1E:]oads IE system are provides power to non-Class IE loads. connected The single breaker to the Cla tripped automatically by a LOCA signal.
' tripped by a LOCA sf gnal provides acceptable isolation between Class 1E and Non-Class 1E circuits for the design basis accident
- LOCA.
However, for other design basis accidents or operating occurrances that do not generate a LOCA signal (su it'is the staff concern that a single Provide breakerinmay an analysis, accordance not provide with' acceptable isolation. 308-1974, that the guidelines of Section 4.9 of IEEE Standard demonstrates that f ailure of anyone or simultanous c four channels of Class 1E power from performing its saf ety function.
(1) capacity and and capability of onsite and of fsite power supplies their associated distribution system to supply power to Class IE loads within their design ratings for all modes of p operation, 384-1981, (3)(2) an analysis of diesel generator loadings for loss of of fsite power similiar to (4) that presented in Tables 8.3-2the failure through 8.3-6 of the FSAR, system that supplies control power,to the subject non Clas loads, and (5) non-Class 1E loads are connected.
RESPONSE
l The following discussion demonstrates the adequacy of employing a single circuit breaker tripped 1E power by a LOCA bus and asignal non-Class as an 1Eisolation load for device between a Clastievent that do not generate LOCA signals.
design ba g shows the two configurations that employ a Figure 430.33-1 circuit breaker tripped by a LOCA signal as an isolation device.
The two configurations ares a.
A Class IE unit substation supplies a non-Class or a motor load through 1E motor control center (MCC)
Class 1E circuit breaker B.
- b. 1A Class 1E motor control center supplies l-panel.
5 The Class 1E circuit breakers B and D are qualified to operate g
for HCGS seismic and environmental parameters for a basis events.
Amendment 4 430.33-1
g66 }
BCGS FSAR respective Class 1E power supply buses from the non-Class IE This applies loads in the whether the event the plant is non-Class supplied from1E anloads offsite fail.
source or an onsite Thus, the failure of the non-Class 1E loads supplied source.
from channels Clas of1E power supply buses will not prevent any of the four Class IE power supplies from performing its safety iunction. 4 gn,y 384-1931 f CDKPL1 ANCE WITH GUIDELINES OF SECTION 7.1.2.1 OF IEEE i i Protective device coordir.etion studies for devices shown in Figure 430.33-1 have shown that the time-overcurrent trip characteristics of circuit breakers A, B, C, and D are such thats a.
Circuit breaker B will trip to clear a fault current prior to initiation of a trip of circuit breaker A.
b.
Circuit breaker D will trip to clear a f ault current f prior to initiation of a trip of circuit breaker C.
l
- Both the onsite and offsite powers supply sources are separately capable of supplying the necessary fault current for suff loads. ,
loss of function of Class IE STANDBY DIESEL GENERATOR LOADINGS FOR LOSS OF OF Table s.3-1 tabulates the loads, their(DBA) KW ratings, and loading and loss of offsite sequences for design basis accidentIt can be verified by ins.pecting scenarios.
power (LOP) Table 8.3-1 that DBA loading of the SDGs is the limiting case with respect to the loading capability of the SDGs. f TAILURE OF TO THE NON-CLASS 1E DC SYSTEM THAT SUP THE SUBJECT NON-CLASS 1E LOADS (described above) the circuit breaker B For configuration (a) supplying a Non-Class IE NCC or a motor load i Class load, IE 125 V de control power supply.a non-Class IE circuit brea /
circuit breakp r B. This non-Class IE circuit breaker (GE-AKR /
typel is controlled by a non-Class 1E 125 V de control power. f GE-AKR type circuit breakers are directthe acting trip devices for I, and do not require external control power supply for trippingthe failure of the d Therefore, electrical fault conditions. control power supply does not/por prevent the cir in response to the f ailure of non-Class 1E motor load.
- Itl5E&T C FM* (%es436 MA6 4
osat opzw ITut JdE6)
Amendment 4 430.33-2
_-y_y.,__v....._,%-,.,.%.r,-..,_,_,.m_,_---.m,. , , , , , . , _ . - , . , - _ .,,-en,e,.
RaJ MGATA
.S"DUrte s ^ ^A Ok t ONDI4 4 (Cw er- SAlet t s
.. . .. . . . h e Cla s s CL H S $4C d t.
===mmend 4kele dlste:builen system are et sagteien+ cepci4y ang fo saff y l power to both Claw Il and non.c(<s, q
'A fr M fl4 y t ords during att piel condifadn s, 2 n 4 f e c.ie n i of < t oc4 4h t. , son- ch ss IL loads arc nat'*m*1%*lly 4riffsi &*m -it e Flass It buses
<n attoM%ee wHh Pos;4lan l". I one Aejal<,'wy ,
k sb L*lS. & A ppo rt orJ, C.$ 8 4.6 5 Faom TME C la c.s -[ E Susas To rdE n/o4~C LA U ,
TS
~Lo ps )) R g pgVTEp j aj m j2,f g;, j p , Cowpv'r s a re. t rznys , wygg my STER L
. .po v ri ve. is ocap , m g ,c , , ,
Lv 17H OTHErz ,,CS c y g gja,g CA $LES $$ .5 0 CI A TED IN Paowm Co~7aot OPetaras Desias c /td~ss f-* idw nr . ra 4s csanic P:"~r 70 Giit t es w effscr 4/I L L CoorA APP /f/0!YG,l1r10p/P'lCA r/0Ns;' AsSaa T}/ar FD TURS RE Q UI n'*H B"' r. ApoiisowlL y; Typ fari Tiw ANT wITH THiS 'M- Pdovipso 4!1 t L 82 k: - ystkl;# Poeur,1per'.s Mffisc.r 7#ts se/Gulssm swr .s", gyp p NOTA T/ost/f 70 _
"'* w . .
l .LNblKT b__ feriod,;e. -les4 *n g o4 AG betAKdt- -fime - evere.orren4 +r .*f , e hA ru e4eris48e s nlil Le (*r0rmd -fo 4%nsbtit -/4d o 4Le t.ireui4 brea rer 4 rig -{anetlen rem <in s out4hin que' red ll='iis.
~TA.6 i e. A M. 'S *'!rI isto,+ i.{ies t%e non - das S I E.- loads .-ffd a rc
$affIled 4hrG ni breAnrs B, A.n A D o.{ fu ueg ASc 55-(,
e trt. ult l l DsER OPEN ITEM M I I 450 W 2A . . . .
---..,-,,-m- ,,ww--,--.--y,_,,n-, ,--n,.--.,_,,w,_-,,, -
ftJ . 3
. HCGS FSAR QUESTION 430.33 Insert "C" ANALYSIS FOR SUPPLYING NON-CLASS lE FROM CLASS lE DC SYSTEMS Figure 8.3.11 shows non-Class lE public address system distribution panel 10J496 supplied from a Class lE de power bus 10D410 through a Class lE inverter in UPS unit 10D496. The inverter is an acceptable isolation. device per IEEE-384-1981, Section 7.1.2.3. Therefore, a failure in'the non-Class lE distribution panel 10J496 will not degrade Class lE de system bus 10D410.
The HCGS UPS system will be tested to demonstrate the adequacy of an invedter being applied as an isolation device. The test will demonstrate that voltage, current, and frequency on the Class lE side of the UPS are not degraded below acceptable levels when maximum credible voltage or current transient it applied on the non-Class lE side of the UPS system. The tests to be performed will simulate all operating modes for which the HCGS UPS system is designed. The tests will include the following types of faults at the UPS output locations
- a. Phase to ground
- b. Neutral to ground
- c. Phase to neutral without ground
- d. Hot short (460 Vac)
A test plan is submitted separately for the staf f's review. The test report and any associated analysis of the test results will be submit.ted in December 1984. z. An analysis has been performed to support the values used for the acceptance criteria for voltages. This analysis shows that the voltages specified will not cause misoperation or loss of any electrical equipment connected to the supply buses. l The results of this analy=ic for the ac systems is stated in FSAR p Section 8.3.1.2.1 and the calculated results are shown in Table l- 8.3-11. The results of the de analysis are contained in FSAR l Section 8.3.2. Those results indicate that the 125 volt de system has an acceptable operating capability with battery voltage variations of 35 volts (140 volts de to 105 volts dc). The test acceptance criterion limits the bus voltage variation to 105-135 volts. In addition, the acceptance values for the test currents are well below the level that would cause the infeed breakers to the UPS supply buses to trip. These values are as follows: Acceptance Infeed breaker ! Circuit Current Setting
'600 ampe res l Normal 480 VAC 0-55 amperes continuous Supply with a maximum peak not Pick-up l
l to exceed 132 amperes and no value above 55 amperes { shall persist for longer l than 10 mS Page 430.33-2B(1)
Insert "C" $f v. 3 Pega two Acceptance Infeed breaker Circuit Current Setting , Back-up 480 VAC 0-78 amperes continuous 600 amperes supply with a maximum peak not Pick-up to exceed 500 amperes and no value above 78 amperes shall persist for longer i than 10 mS Alternate 125 VDC The bus voltage variation 2000 ampere Supply of 105-135 volts will hold fuse for the following cases: (1) With the UPS energized but without load the input current shculd not exceed 56 amperes (2) With the UPS input current at 56 amperes the input current should not exceed the range of 0-56 amperes l (3) With the UPS input current at 158 amperes the input current should not exceed the range of
- of 0-158 amperes
'The fo,llowing is justification that the above acceptance current values'Jo not adversely effect the Class lE buses. The 480 volt ac back-up feed is supplied from a 480 volt Class lE motor control 4 center.which in turn is supplied from a 480 volt Class 1E unit-substation.- The infeed breaker to the MCC is an AKR - 50 which has I a 600 ampere pick-up setting for its time delay trip setpoint.
This allows the largest motor loads on the'MCC, in combination'with , the maximum-acceptable current spike of_the UPS acceptance values
-(500 amperes for not longer than 10 mS), to persist for 25 seconds.
Since.the'500 ampere spike is completed.in 10 mS, the largest motor loads then have 55 seconds to accelerate. This is 48 seconds
-longer than the time delay for the primary protective device for the-largest motor and, therefore, it is not possible for any of the Class lE loads to be disabled. The inrush current of the normal ac feed is 132 amperes for 10 mS which is less than the 480V ac backup supply. - ~ The normal 480V supply breaker is the same type and size
-as the 480V back-up supply' breaker. Therefore the Class lE loads
-on the:MCC's from the normal and backup 480Vac supply are not affected by any short circuits on the output of the inverter.
The alternate 125V de supply full load amperes are already included in thel 125 volt battery load profiles. The maximum current duty on any of the 125 volt Class lE batteries is 4 51.1 ampe re s (battery LAD 411). The impedance of the conductors from the battery to the 125 volt dc bus is such that the voltage drop for the specified - -load profiles does not cause the 125 volt bus to drop below 105 volts.- Page 430.33-2B(2)
)
In ort "C" ktV.3 I Pcgn 3 If the testing can not demonstrate adequacy of the UPS as an isolation device, then an isolation transformer will be added between the inverter and the distribution panel. The test plan for the isolation transformer is also submitted separately for. the ! staff's review.
.In the event of failure of both tests the non-Class lE loads
~
associated with-the UPS system will be removed from the Class lE buses or the cables to these loads will be re-routed so as to be , separated from Class lE cables associated with other Class lE ' channels or an isolation means acceptable to the staf f will be employed. Page 430.33-2B(3)
, , . , . _ . . . - ~ . , . . . . , _ , . _ . , - . . , _ . - . . , , , - , . _ , . . _ . , - ,_ _ . , . , _ , . - . . - . , , , _ . . _ . , _ . _ , .
. ..% (cy,y
- TABLL 4%0.M-1 l Ned-CLASS tt. LD Abs . ceNNMap '
C&h55 IE To etA class IE ndi c Az ugt s aAA ng4 sit . Wese-CLASE IL Lo4D MSCAtPTseAl __ s t- 4 t o t t l . 4.sAb No._ C Sysfem aos4to , l'- Amisfer Assili4ry aelig$ , famp IAttei op4 o ss.4 at4 E* AcAmNLstc 444. 'ervice Ars4 Ntt.t., 104313 l g y s4, s g s.,4gst4 t Air l
, :Agute r seitdios $*tt 3 3 g4adtt $ Unit' tMWSao s 1 - 4 tot t fc64to l
- Aeaafar Aosilkry caeling Sysf aa1 4 Poesp 18F 28$ gg,4wq dr% 4 o 642.o g Aad.Watte and AfrVicf M cC. 10 5 %1,5 tp641O yL,4xgg4 E 5kas4.fAn I
" 4, Acalet b u ll A int 3 I syse t- s t - <soty Surrt y Air la a4s o Keacfer Sall4,'a$
., I t.v rt %
- o 1" 'i
- Hselling Unit l'844" ceafe. ( A*J. Dri<e Pum 7 14P281aos 44 o 51
- H 4 5 ,
c, 4 ret Rel. Delve. Pu mp la P to'f 57.-44814
- q. die sos 446 no Ae,.,fer suitat.$ 14v surety84 e6 144 q(i.9 unit ,os44o gt.44 egg F4% olvitt.
A44da sfc Aru. supply ' ' It i O b A 50 $ 2 - 410 il St A&M She httA MLL. t D615 L sr.-4so 1 A42woft Area, Ep hus4 F.3 04Vso5 los<co 3 (0645'O 5t 41814 E.=tr3enty 2asf rumsof Air Gpressor 14 10 Kin o 8884'*
**~*M if A cr ed er b u Idina) E.vbos4 F4n tevsotT1 d '# 't q ..
i0546o ' ' 4 Asui.e Area. Me.C. tostst, - 86 . 806460 ',- isr. 4 6o84 N I KA a)f t Art'.a Ey3L40St Fan 05V505 5 t7 105470 D St -47al l 8% A*4the hea. MCC.10617L topaq e 5 t. 41s t at 5 ddlarasic Area. Eyhog{ fan egy3e,y 51-41614 i li l 10547a Adiwaste Area. Surr ) Fan e4y3:g 4,a i f %#
- r. ,.., s.,r.4 c,n4, . . <,4 io.4,0 .
u I
----rw, - , , _w-. , , . , , - ,y ,._,m,.,,-,,.,m_ ,,n-_ , , . . , . . . -,--- , , , _ - - , _ , , , . - _ .
. --, a r- 2 A . m _
0 0 T4sts. 430. 33 Rcy.}
~
t.orrtnwasp \ I . ys.4,o i g 3,g4ga A4asier Area Mca sostst. s s. fWI*M 14V34 I I484I* A<asfer 5dildlag EWitWSf F49 ' 23 :": u- :- , w ;1. u nrer <oa hs 5 t -"in) w e,4 s i e.m c u se<.s syas , w <r<<c 2e .o
): 160416, 5 * - 194r.s nor b ra+ar 4..:.l.... M i co,e; ~
I 6, I b " <1I f 10047I ag,7 StwENy System LVardtr 04D41T ies4 i 5 ' d 'J"$
..-+, w< rv e r- is.4.,
, m.
I e a e S i
- h. 98
=
G e ', 6 win o m m a J 6 0 e e os e
**M
- 9 %
q*
' ' + < - - - - - , . - , , _,
~~~""-'~~-m--,n. __
kdb b l l
'FOR MOTOR LOADS,IN ADDITION TO CIRCulT BRE AMER B.
THERE IS NON CLASS-lE CIRCUlT BREAKER DOWNSTREAM OF BR2AKER B. 4.18 KV CLASS lE BUS 4 ,
)A LLL) rr m s
480 V CLASS lE UNIT SUBSTA.
- , a ::
)C ) B TRIPPED BY LOCA
~
>. NON CLASS lE CABLE ,
l 1 P
*NON CLASS lE MOTOR OR, MOTOR CONTROL CENTER l 480 V CLASS lE MCC
) D TRIPPED BY LOCA d 6 NON CLASS lE CABLE 1P i
BACK UP POWER SUPPLY FOR UPS SUPPLY 3NG. NON CLASS-lE DISTRIBUTION PANEL. HOPE CREEK GENERATING STATION FINAL SAFETY ANALYSIS REPORT ISOLATION BETWEEN CLASS lE POWER l SUPPLIES AND NON CLASS lE LOADS-TRIPPING CIRCUlT BREAKER FIGURE 430.33 1 AMENDMENT 4,1/84
NtV. 3
. , l l
l TEST PROCEDURE. ISOLATION VERIFICATION l S/N 9743 1E 20KVA UPS (INSTRUMENTATION AC POWER SUPPLY) l l FOR PUBL'IC SERVICE ELECTRIC & GAS CO. HOPE CREEK GENERATING STATION P0. 10855-E-154 (Q)-AC l 08JECTIVEi. TESTING TO ESTABLISH THE UPS SYSTEM AS A CIRCUIT ISOLATION SYSTEM. , PASS CRITERIA: DEFINITION OF ISOLATION DEVICE OR SYSTEM: A DEVICE OR SYSTEM IS CONSIDERED TO BE A CIRCUIT ISOLATION DEVICE IF IT IS APPLIED SUCH THAT THE MAXIMUM CREDIBLE VOLTAGE OR CURRENT
- TRANSIENT APPLIED TO THE NON CLASS 1E SIDE OF THE DEVICE WILL NOT DEGRADE THE CLASS 1E CIRCUIT ON'THE OTHER SIDE OF THAT DEVICE. ,
CIRCUIT NORMAL VARIATION ALT. DC. SUPPLY 105-116 VDC 1- 0- FULL LOAD ADC NORMAL AC SUPPLY 480+10% V(L-L) 3 PHASE 0-55A 0-132AP FOR 10 MSEC 8ACK UP AC SUPPLY 480+10% V 1 PHASE 0-78A. 0-500AP FOR 10 MSEC ANY VARI ATIONS OUTSIDE OF NORMAL VARIATIONS SPECIFIED. WILL BE ANALYZED ON A CASE BY CASE BASIS. . 5 O e 4 1-
86V. ) FAULT LOCATION AND TYPE FAULTS WILL BE APPLIED TO UPS SYSTEM OUTPUT TERMINALS BY CLOSING A SWITCH AS REQUIRED. f4GLT TYPES:
- 1. PHASE (HOT) TO GROUND
- 2. NEUTRAL TO GROUND
- 3. PHASE TO NEUTRAL W/0 GROUND
- 4. 480VAC APPLIED ACROSS UPS OUTPUT W/0 GP.00ND (HOT SHORT)
THECONDIhl0NOFTHETHREECLASS1ESOURCESWILLBEMONITORED THROUGH SUITABLE SIGNAL CONDITIONERS, BY GOULD INC., 2000W SERIES HIGH FREQUENCY RECORDING SYSTEN. e 4
% e e,
I e l i 4 2
Rev.5 TEST PROCEDURES 1.0 GENERAL NOTES 1.1 BEFORE STARTING TEST DETERMINE AND RECORD ALL SIGNAL CONDITIONER TRANSFER RATION (MULTIPLIER) VALUES. 1.2 NORMAL SYSTEM OPERATION DURING EACH TEST A. CONNECTION PER FIG. 1. B. THE LOAD ON THE UPS SHALL BE ADJUSTED FOR EACH OF THREE SEPARATE TESTS FOR EACH UPS INPUT SOURCE:
-(1) NO LOAD (2) OUTPUT LOAD AT .08 PF TO ACHIEVE 56 AMPERES INPUT CURRENT WHEN FED FROM 125 V0LT DC. LOAD SHOULD REMAIN THE SAME FOR AC INPUTS (3) "TPUT LOAD AT .08 PF TO ACHIEVE 158 AMPERES INPUT C 'ENT WHEN FED FROM 125 VOLT DC. LOAD SHOULD RL .AIN THE SAME FOR AC INPUTS C. UPS POWERED BY " ALTERNATE" DC SOURCE (BATTERY) AND ONE OR BOTH AC SOURCES, " NORMAL" & "BACK-UP" D. STATIC SWITCH IN " PREFERRED" POSITION.
E. ALL BREAKERS & SWITCHES CLOSED, BOTH B.YPASS SWITCHES IN
" NORMAL" POSITION
" TEST" SWITCH - CENTERED
" RETURN MODE" SWITCH - IN "AUT0" POSITION
" ISOLATION" TOGGLE SWITCHES - ON
" SYNC" TOGGLE SWITCH - ON 1.3 TfST INSTRUMENTATION A. GOULD INC. , MODEL 2800W HIGH FREQUENCY RECORDING SYSTEM.
EIGHT CHANNEL, INDEPENDENT SCALE SELECT i.050 TO 1500 VOLTS FULL SCALE. B. POTENTIAL TRANSFORMER 480V, 60HZ PRIMARY 120V SECONDARY (4:1 RATIO). C. CURRENT TRANSFORMER 1000:1 RATIO WITH 10 OHM BURDEN RESISTOR. (.01V/A). D. WIDEBAND DC ISOLATION AMPLIFIER, G0ULD INC. MODEL 13-4615-10 OR EQUIVALENT. 3
Ruf.3 V
\
1.4 TEST FACILITY AND EQUIPMENT A. DC SUPPLY - C&D 4LCW-15 BATTERY (60 CELLS, 80KW FOR 30 MIN.) AND BATTERY CHARGER.
- 8. AC SUPPLY -l480V, 3 PHASE, 4W, 60.HZ, 1200A GROUNDED HEUTRAL.
'C . AC LOAD BANK : 0-30 KW OR 0-30 KV A 9 0.8P F.
D. FAULT APPLICATION DEVICE ,G.E. CIRCUIT BREAKER TJC 36400G 400A, 3P. MAGNETIC ONLY. ., E. HOT FAULT SOURCE - TRANSFORMER,1 PH 480:120V 30KV A OR LARGE,R. . 2.0 TEST PR0'CEDURE 2.1 BASE LINE DATA START UP THE UPS WITH ALL SOURCES AVAILABLE. SET UP " NORMAL OPERATION" PER 1.2 AND ALLOW SYSTEM TO WARM UP FOR AT LEAST 30 MINUTES. A1. METERING AND CONNECTIONS PER FIG. 2 AND " BACKUP SOURCE" BREAKER OPEN. RECORD IN " STORE" MODE AT 20KHZ TIME BASE. COPY MEMORY TO PAPER. , A 2 . '. REPEAT Al EXCEPT USE 500HZ TIME BASE. Bl. WITH METERING AND CONNECTIONS PER FIG. 2 AND " NORMAL SOURCE" BREAKER OPEN. RECORD IN " STORE" MODE AT 20KHZ TlHE BASE. COPY MEMORY T0 PAPER.
- 82. REPEAT B1 EXCEPT STATIC' SWITCH TRANSFERRED TO BACKUP.
S3 REPEAT B1 EXCEPT USE 500HI TIME BASE.
- 84. ' REPEAT 82 EXCEPT USE 500HZ'T,lME BASE.
t h l l l l 4 s
.. . - _ _ . . _ . _ _ , _ _ ,._,,--____,....-_sv.__,..-.. r,--._., ___,4, _ . . _ _ . - . , _ _ _ _ _ _ _ . . - . . . , _ _ - , _ _ _ _ , _ . . , _ _ . _
8EV.3 i 2.2 FAULT TESTING f CO. METERING AND CONNECTIONS PER FIG 2. RECORDER IN MANUAL TRIGGER MODE. APPLY FAULT BY CLOSING " FAULT" CB AND AT THE SAME TIME (OR 0 TO 10 MILLISECONDS BEFORE) TRIGGER THE RECORDER IN " STORE" MODE. REMOVE THE FAULT AND RECORD THE MEMORY TO PAPER. AFTER EACH FAULT APPLICATION CHECK THE UPS FOR DAMAGE. REPAIR THE UPS IF REQUIRED BEFORE PROCEEDING. C1. INSTALL JUMPER " A" TO " FAULT" CB WITH " BACKUP SOURCE" CB 0 PEN WITH RECORDER AT 20KHZ TIME BASE APPLY FAULT PER CO. l C2. ' REPEAT C1 EXCEPT WITH 500HZ TIME BASE. C3. ' OPEN " NORMAL SOURCE" CB AND CLOSE " BACKUP" WITH RECORDER 20KHZ TIME BASE APPLY FAULT PER CO. C4. REPEAT C3 EXCEPT WITH 500HZ TIME BASE. C5. REPEAT C1. C2 C3 & C4 WITH JUMPER "B" INSTEAD OF "A" CONNECTED TO " FAULT" CB. C6. REPEAT C1 C2.- C3, & C4 WITH JUMPER "C" INSTEAD OF "A" CONNECTED TO " FAULT" CB. C7. REPEAT C1. C2 C3..& C4 WITH CONNECTIONS TO HOT FAULT SOURCE (UPS RUNNING AT NO LOAD). 2.3 COMPLETE TEST
SUMMARY
SHEET FOR EACH TEST OR TEST GROUP.
'l' l ."*'1, 1
5
- - - - - - ,--e -, , . , - - - - , , , - - , , , , , - - - - --+,,--n,----,, .,,wd , e- w w , -gn,-,,-,w --m- ,,r---- <----e-~m-- -
7 6
. 4
- 1 s 2 5 ~ g d B s .
- k' ,I
= ky a 5 f gs I f,m u I l
- h. ..
W% $ i ' y 9 s 4.g e {% . l kl 5
,. 3 y't
-x, )f r,-----i 'l L:
g ii! 3 51 - g
. :. ,_._ _ _ _ . _, 3
~
1 ! ; I l
,1 1";
a - n s M
,k 4
y @. , k uei sz _ ,_ g
=
5 II & ' { cy25 l2 *-- 2
.a it 3 ug t ..
3 gow g
<<o oo =o k.
e-sn n I -
- s 1 }3 g g ,_ .
I I
$ gt '
,9 b; f,f1 f4 I__ .J A B 25 3*
** . r o w* un
; s,u E1 -- a-z .v .tYo,'o r~c~nf ~ 'I.*~
U -t : U 31{11t E g ac
..nins. =
f${ b C e n _t
--[
5
. l'lI 1 -
]d, l y Os Li l
) gi r .. .
.u 2 $ 9- g m
s; -
.e 4
31 tt l e e g I b
- p. gj -
o. i Mt .> 6 L q y f E
# dN (8 g
I(AI
!? ,_ 1 4 l !
-r c
.e .
1n :. .; =.' g a* c:~A z .- I"$ n l:! <%-4 -, { ls-j I _ . , ~ n 51 a l G.n....r o o*, . --1 1
~
? .S l' :
w
.. e e n 1c : s t
_64___ F
, am mm un it n s
g
, , . . ~
i i i u
#1 u 1
w 1o A 3 A 3 }l T g g g __ ._ ___... . ...........__.__...._.s g y . %5 1
.....g......
se % .
} .,.... .
g
. g g
i
. ~
C ! i
. E!([ li a < y I .
i 41 1r - i ! sq , , , 17 .d UN b hl dtnY 'i i . 11 J > $ l
.. . ] ', t
-..E,i. ,
i j 7 ) ~su g
;t !
- -- 3.- -
I I, I .f,i~ l
+ ' .,~,,,,, p!
yh
- 4mee
. A's
..= ;
. . , _ .y.,, ._..._,, %,.,,,.,.,,,.,m, - _ , , . . . . _ . . .,,,_.__.~._..,,,,...,...,,,,......,_,e..m,..,%,,m...,.,,.,.r._,.,~,,,
(V* \ TE $ 7" 3 t/ N H 4.2 Y
,ist W CHART W dt/4/rSP110 l I
l d BY Da!C AfA'O i/ A4!(
,~C 3 r D 2 $ C 2 tf 7/0 M :
c> mar sc45,i , CHr.A36E buf.sMS- j7Ee<A x e s u, .rs/.;,, TEST {w,_ast,
/ .
L 3 .. . . _ . . . . - - - YI r'
- c. I ~
7! , 8' ener rme noss CA mmc D P4trs : UPS EstattA TRo!PLO DdAt</G TES T :
$ E C# U U OUn'$ TEA Y E . . . . . . ..
l s u l l l l l __ , i 5 1 1 J T. I -
.r g
( l H - Y - I
- ?- F i- ll 5
. 2 I i ,
1
^ . . . .. -
\ l
.: Ru.3 TEST PROCEDURE, ISOLATION VERIFICATION S/N 9743 IE 20KVA UPS (INSTRUMENTATION AC POWER SUPPLY) IN SERIES WITH A POWER CONVERSION PRODUCTS ISOLATING TRANSFORMER MODEL #
RTF-120/120 FOR PU8LIC SERVICE ELECTRIC & GAS CO. HOPE CREEK GENERATING STATION J PO. 10855-E-154 (Q)-AC i 0BJECTIVE: TESTING TO ESTABLISH THE ISOLATING TRANSFORMER IN SERIES WITH A UPS SYSTEM AS A CIRCUIT ISOLATION SYSTEM. PASS CRITERIA: DEFINITION OF ISOLATION DEVICE OR SYSTEM: A DEVICE OR SYSTEM IS CONSIDERED TO BE A CIRCUIT ISOLATION DEVICE IF IT IS APPLIED SUCH THAT THE MAXIMUM CREDIBLE VOLTAGE OR CURRENT TRANSIENT APPLIED TO THE NON CLASS 1E SIDE OF THE DEVICE WILL NOT DEGRADE THE CLASS 1E CIRCUIT ON THE OTHER SIDE OF THAT DEVICE. CIRCUIT NORMAL VARIATION ALT. DC. SUPPLY lo5-i36 VDC
. 0-FULL LOAD ADC 480+101 V(L-L)
NORMAL AC SUPPLY 3 PHASE l 0-55A, 0-132AP FOR 10 MSEC BACK UP AC SUPPLY 480+101 Y 1 PHASE I. 0-78A, 0-500AP FOR 10 MSEC i ANY VARI ATIONS OUTSIDE OF NORMAL VARIATIONS SPECIFIED, WILL BE ANALYZED ON A CASE BY CASE BASIS. . 1 ( l
RGV} e FAULT LOCATION AND TYPE FAULTS'WILL.8E APPLIED TO ISOLATING TRANSFORMER OUTPUT TERMINALS 8V CLOSING A SWITCH AS REQUIRED. FAULT TYPES:
- 1. PHASE (H0T) TO GROUND
- 2. NEUTRAL TO GROUND
- 3. PHASE 10 NEUTRAL W/0 GROUND
- 4. 480VAC APPLIED ACROSS UPS OUTPUT W/0 GROUND (HOT SHORT)
THE CON $1T10N OF THE THREE CLASS IE SOURCES WILL BE MONITORED THROUGH SUITABLE SIGNAL CONDITIONERS, BY GOULD INC., 2000W SERIES HIGH FREQUENCY RECORDING SYSTEM. e l e L f i 4 ag 2
-em- e - e--, - - - - . . , . _ _ _ . . ,
, j., _ _ _ _ _
Rev. 3 TEST PROCEDURES 1.0 GENERAL NOTES 1.1 BEFORE STARTING TEST DETERMINE AND RECORD ALL SIGNAL CONDITIONER TRANSFER RATION (MULTIPLIER) VALUES. 1.2 NORMAL SYSTEM OPERATION DURING EACH TEST A. C'ONNECTION PER FIG. 1. B. THE LOAD ON THE UPS SHALL BE ADJUSTED FOR EACH OF THREE SEPARATE TESTS FOR EACH UPS INPUT SOURCE:
-(1) NO LOAD
, ( 2) OUTPUT LOAD AT .08 PF TO ACHIEVE 56 AMPERES INPUT CURRENT WHEN FED FROM 125 VOLT DC. LOAD SHOULD REMAIN THE SAME FOR AC INPUTS (3) OUTPUT LOAD AT .08 PF TO ACHIEVE 158 AMPERES INPUT CURRENT WHEN FED FROM 125 VOLT DC. LOAD SHOULD REMAIN THE SAME FOR AC INPUTS C. UPS POWERED BY " ALTERNATE" DC SOURCE (BATTERY) AND ONE OR BOTH AC SOURCES, " NORMAL" & "BACK-UP" D. STATIC SWITCH IN " PREFERRED" POSITION.
E. ALL BREAKERS & SWITCHES CLOSED, BOTH B.YPASS SWITCHES IN
" NORMAL" POSITION -
" TEST" SWITCH - CENTERED
" RETURN MODE" SWITCH - IN "AUT0" POSITION
" ISOLATION" TOGGLE SWITCHES - ON
" SYNC" TOGGLE SWITCH - ON 1.3 TfST INSTRUMENTATION A. GOULD INC., MODEL 2800W HIGH FREQUENCY RECORDING SYSTEM.
EIGHT CHANNEL, INDEPENDENT SCALE SELECT i.050 T0 1500 VOLTS FULL SCALE. B. POTENTIAL TRANSFORMER 480V, 60HZ PRIMARY 120V SECONDARY (4:1 RATIO). C. CURRENT TRANSFORMER 1000:1 RATIO WITH 10 OHM BURDEN RESISTOR. (.01V/A). D. WIDEBAND DC ISOLATION AMPLIFIER, GOULD INC. MODEL 13-4615-10 OR EQUIVALENT. l I t 3
..' { ):
kCV.) 1.4 TEST FACILITY AND EQUIPMENT A. DC SUPPLY - C&D 4LCW-15 BATTERY (80 CELLS. 80KW FOR 30 MIN.) AND BATTERY CHARGER.
- 8. AC SUPPLY - 480V, 3 PNASE 4W. 60 HZ. 1200A GROUNDED NEUTRAL.
'C . AC LOAD BANK 30KW OR 0-30KVA 9 0.8PF.
D. FAULT. APPLICATION DEVICE - G.E. CIRCUIT BREAKER TJC 36400G 400A. 3P. MAGNETIC ONLY. E. NOT FAULT SOURCE - TRANSFORMER. 1 PH 480:120V 30KVA OR LARGER. 2.0 TEST PROCEDURE 2.1 BASE LINE DATA START UP THE UPS WITH ALL SOURCES AVAILABLE. SET UP " NORMAL OPERATION" PER 1.2 AND ALLOW SYSTEM TO WARM UP FOR AT LEAST 30 MINUTES. A1. METERING AND CONNECTIONS PER FIG. 2 AND " BACKUP SOURCE" BREAKER OPEN. RECORD IN " STORE" MODE AT 20KHZ TIME BASE. COPY MEMORY TO PAPER. A2. REPEAT A1 EXCEPT USE 500HZ TIME BASE. 2
- 81. WITH METERING AND CONNECTIONS PER FIG. 2 AND " NORMAL SOURCE" BREAKER OPEN. RECORD IN " STORE" MODE AT 20KHZ TIME BASE.
COPY MEMORY TO PAPER.
- 82. REPEAT B1 EXCEPT STATIC SWITCH TRANSFERRED TO BACKUP.
- 83. REPEAT B1 EXCEPT USE 500HZ TIME BASE.
- 84. , REPEAT 82 EXCEPT USE 500HZ TIME BASE.
4 g 8 4 M 4
.* D$
. . T. > ';-
pv. }
<.:,; . .j 3
, i, 2.2 FAULT TESTING ' il 'I'
)
i . METERING AND CONNECTIONS PER FIG 2. RECORDER IN MANUAL l CO. TRIGGER MODE. APPLY FAULT BY CLOSING " FAULT" CB AND AT THE SAME TIME (0R 0 TO 10 MILLISECONDS BEFORE) TRIGGER THE RECORDER IN " STORE"' MODE. REMOVE THE FAULT AND RECORD THE MEMORY TO PAPER.
- AFTER EACH FAULT APPLICATION CHECK THE UPS FOR DAMAGE.
' REPAIR THE UPS IF REQUIRED BEFORE PROCEEDING.
C1. INSTALL-JUMPER "A" T0 " FAULT" CB WITH " BACKUP SOURCE" CB OPEN WITH RECORDER AT 20KHZ TIME BASE APPLY FAULT PER CO. C 2.., REPEAT C1 EXCEPT WITH 500HZ TIME BASE. C 3.- OPEN " NORMAL SOURCE" C8 AND CLOSE " BACKUP" WITH RECORDER
.- 20KHZ TIME BASE APPLY FAULT PER CO.
C4. REPEAT C3 EXCEPT WITH 500HZ TIME BASE. - C5. REPEAT C1. C2. C3 & C4 WITH JUMPER "B" INSTEAD OF "A" CONNECTED T0 " FAULT" CB. C6. REPEAT C1 C2. C3. & C4 WITH JUMPER "C" INSTEAD OF "A" CONNECTED T0 " FAULT" CB. C7. REPEAT C1. C2 C3, & C4 WITH CONNECTIONS TO HOT FAULT SOURCE (UPS RUNNING.AT NO LOAD). 2.3 COMPLETE TEST
SUMMARY
SHEET FOR EACH TEST OR TEST GROUP.
!, , l I
. i .,
! !. . 3 e, e
, i! ,i s
~ .
4 a 5 .
.y
-( .
-4 0 y .....
i . g G 1 Isj pa y y ..
, I .
f
. j lf,1 E
lIC$
.'i %. Wh-. I$ ' $
(
- g k
L .l,
.L l 9
\s g.
d, f 1 . [ 3 gt u, r)a. sa-
. ~
n t g gw
,., 8.g. . - . . I a d.
I 3
.- ,u 3
3$ T 2 tt WJ j {li C - E 4
.4 lluioA.i{
A
., 'v v' g'
Tl
<v =
_t 0 s1 j
.? g ,
. = I; -
k .t #l G - { h _a , _tX_ 3 de t -
~!
b 0inv'I cl o, u r! 09 0, _ q I ha
% d .
4 I-N g 1= g e- . - - - . . .. , s i t- ,e t$ v tt*i .'- __;.
** n n e l
5A W 1 wh e a N - s I 4 **'" t ce. . . .e ti av
* .g:r g I3 .
.< w., c ~.s 9a 1
e ^^ teRS M99 -
..........,,y ,,
'* *d.
. ,
- g , ,'A;,g ' . . ey .* ,
w g s_ y ,,- M l
---lg,gsl#ta.3 e.
( ! Is
]
1 g y ey'
- . ,..L L
'u .
i
!I -
t y e 5 p' >
-t<
b ,
- ;k
; e Q
s
.L" a -,w .,-; 5e ,t !
m-- .ls _1 g - g;y p- ! ) p, -,.a.. ...i,,. *. a. p j 1
';!r
-I-as . in !
1' w ..- t,<fsj. - lc .: 1
,3
.v n
. t '
.g w ~, e.!
. . ,. 3 =s3 ,
--' "' na h
(
. . i g%h as..-m
( . ... ... it 11
; f -
g
.am swwn m n .
j',
, i .Ii Il I3 l o
i. l g I - e v c :....m,,....f,, g],h,. .. .. p f
. j , d.
- .! g :it e y I .
<! g
- w .r g i i; .:i f.! p
,, l'
- 1r y
'ly J )
a in ". .I
.- 's
,, p -; J I '
~
. . .a i i' j 7} v *.... *~s*s Q
. - - d Ap@ew 4 4, *
- hlq!5 2 ' ' I l-l -
a
+
~~.~
p
.e e gem MEF M e
e 0 9 if'
^ ,
knV.S
. p esu mn
- 76 3 7~ Ju MH4.t y
;"ist d c'MRT d oldJr$PIto ay earc JPNsof wrc
.~csr assenffrved: l
/tr e ,* d a s I C**ar Sc i.e. c u ttuud6
("*_.. ".'" M . E.. _. . .[ * ' t s
-S .. ..
Y5 s' (, ! 7 I '~ _ 8' c,94r r-t sess e CAnaces Mars : 1 , U/3 baeAnca rm!Pt0 Odntdc TEtr : Ws fulE C& C$ A6 D Oud eMC. T4J V ; . . . . _ . . . . , , _ I es s u g 9 I - JT3 3 l l { n,i i n
=
i
~ ,
i S 3 I! . 4 """" j
Attachment 3' Revised Text FSAR. Sections: 13.2.1 13.2.1.1 13.2.1.1.1 13.2.1.1.1.1 13.2.1.1.1.2 13.2.1.1.1.3 13.2.1.1.1.4 13.2.1.1.2
'- Appendix 13C Appendix 13F Appendix 13I Appendix 13J Appendix 13K (new) 630.4 630.7 630.10 L'_.__
1 l l HCGS FSAR 8/84 1 13.2 TRAINING i i 13.2.1 PLANT PERSONNEL TRAINING PROGRAM ,i The training program for Hope Creek Generating Station- (HCGS) 'i:s formulated to develop and maintain an organization qualified to cpaserf-[ assume the responsibility for preoperational testing, operat on, maintenance, and technical considerations for the facility.
-accomplish these objectives and to provide the necessary control (
of the overall plant, tlue following three general training programs will be implemented:
- a. Initial Plant Staff Training Programs - These programs are designed to provide competent, trained personnel in
- all disciplines and at all levels of plant organization. The programs are designed to allow personnel to be placed at various points, according to i their training, experience and intended position. The - training procedures are detailed in the Nuclear . l Department Training Manual.
- b. Requalification Training Program - A requalification program as required by 10 CFR 50.54 (1-1) will be developed to provide continuous training and upgrading of plant personnel and will meet the requirements of 10 CFR 55, Appendix A and NUREG 0737 Enclosure 1. Use f will be made of the Hope Creek specific simulator :
scheduled to be delivered to the facility in the summer of 1984. Therefore, a specific requalification program will not be available until late 1984. Upon formal 1 acceptance of the Hope Creek specific simulator and l establishment of operator shift rotation, the licensed operator requalification program will be implemented to i ensure that all cold license candidates maintain a high q 1evel of knowledge and operator confidence. The
\- requalification program will run on an annual basis i with all program requirements completed during the two year requalification cycle. The requalification program will consist of three areas; pre-planned 1ectures, on-the-job training and requalification 0
examinations. , The pre-planned lectures will cover fundamental review and operational proficiency. Fundamental review training'will be in those areas of heat transfer, fluid ' flow, thermodynamics, mitigation of accidents involving ' 4 a degraded core and these subject areas delineated in 10CFR55, Appendix A. Operational proficiency training 13.2-1 , Amendment 7
,---,---,,---,,,,,,.e--a, --~~-~,n.,,.,m,---,-,+nm.m., , , , - - m,,,w.w,.nw,_w.m . , - -sw-
.I HCGS FSAR 8/84 ,
i will involve lectures that will focus on esse ial ' plant operational guidelines and changes or speriences in.the nuclear industry. d he on-the-job training will ensure th each licensed rator maintains an acceptable leve of skills and fa iliarity associated with plant sy ess, controls and ope tional procedures. This will accomplished i et . thro h reactivity manipulations, ant evolutions and ; opera onal reviews. i Requalifi ation examinations w I be given to determine i the licens operator's knowl dge of the material covered, ar as where additio al training may be required and operationhl pr ficiency. These , i examinations ill consist f a segmented written examination an an oral e amination. l Personnel demonst tin a significant deficiency in a . ! given area of knowl d e and proficiency may be placed L - into an accelerated raining program. This program sill be specificall tructured to upgrade knowledge and skills identif ed eficient. Successful completion of the accelerate trai ing program will be evaluated i by a written an or oral examination. Procedures + describing the ontent a conduct of the ! requalificatio program wi 1 be developed and will be maintained in he Nuclear partment Training Procedure Manual.
- c. Replacemen training - These ograms are designed to provide q lified personnel fo the station !
organiza on. The general mana r - Hope Creek l Operati s, or the designated re resentative, may waive l portio of the training program or individuals based on the e previous experience and/o
,i qualifications.
- 1.
The t aining procedures are detaile in the Nuclear Depa ment Training Manual. i j The Manager.- Nuclear Training is responsible f e implementation .; i of this prog am. Prior to implementation, each ourse, its
. scheduled s acting date, and its duration shall approved by l j the Genera Manager - Hope Creek Operations. j j
The Managey - Nuclear Training will ensure that all individuals M providing instruction are technically qualified to present the j material and that they have demonstrated a knowledge of , 13.2-2 Amendment 7 i
a_=,. -a ._m e4- -s u. a.- - .m..s.-__ 4 aa m m.,_ s - _- ,_.--u. A f la $**<d e a f $ ,
\%%A' wyd aya ys gd & = :s won y ad 4 La+,. rs m f AMMbsu Ayaw g w 1 adnow wAnusp (TA>PO edELb2, g W 4M
%l W+a w s. w7 w go WM.
4 4 l I I . l
-- ,--. .----- - _ - _ - _ _ . . . , . - - . - - - . _ - . - . - - . _ - - . - . - - _ - . - . ---. . - - . . ~ _ . - - - - . - -
~_ _ - .. - - - - . - _ - . . - . - . . - - - __ -_-- . __ _- .
l l HCGS FSAR '8/84 en
- f. will involve lectures that will focus on essential qqrf-plant operational guidelines and changes or experiences i in the nuclear industry, The on-the-job training will ensure that each licensed i' operator maintains an acceptable level of skills and familiarity associated with plant systems, controls and operational procedures. This will be accomplished through reactivity manipulations, plant evolutions and
- operational reviews.
Requalification examinations will be given to determine the licensed operator's knowledge of the material + covered, areas where additional training may be required and operational proficiency. These examinations will consist of a segmented written i . examination and an oral examination. Personnel demonstrating a significant deficiency in a
' given area of knowledge and proficiency may be placed
' into an accelerated training program. This program-tru,ctured to upgrade-knowledge W#illbespecificallykdefi.cientks.Sucetssfulcompletion j ( and skills iden,tified of the accel,erated training program will be evaluated ~ by a written and/or oral examination. Procedures O descriLing the co'ntent and conduct of the , requalification program will be developed and will be
'j maintained in the Nuclear Department Training Procedure Manual.
1 i
) c. Replacement training - These programs are designed to provide qualified presonnel for the station l
,) organization. The @ neral NWnager - Hope Creek Operations, or the designated representative, may waive f portions of the training program for individuals based J on their previous experience and/or qualifications.
i ji Ski-T' raining proceduces are detailed in the Nuclear Department Training Manual. The Manager - Nuclear Training is responsible for implementation
- of this program. Prior to implementation, each course, its i scheduled starting date, and ita duration shall be approved by the General Manager - Hope Creek Operations.
The Manager - Nuclear Training will ensure that all individuals providing instruction are technically qualified to present the j(', material and that they have demonstrated a knowledge of 13.2-2 Amendment 7 1 vm- ---~<vvww.,,+~~n-~m,g,q- am,-,,,s n.-.-- _,.--m-eg,w_-_ne,,m
- ,,-mw,-mmn,--_-mmmm-~,---n-.--
n -- 3 HCGS FSAR 8/84 instructional techniques as required by ANS/ ANSI 3.1-1981, l 4.4.7.2. Individuals providing instruction to license operator candidates will have received all appropriate training and hold or have held an SRO license or certification as required by the H.R. Denton letter of March 28, 1980, Enclosure 1, and . ANS/ ANSI 3.1-1981, 4.4.7.2. These individuals will take an j active part in the license operator shift # training program. Upon completion of the cold license training program and establishment of the operator requalification program, individuals providing specific license training outlined in ANS/ ANSI 3.1-1981, 4.4.7.2.c will participate in the requalification program as specified in ANS/ ANSI 3.1-1981, 5.5.1.5. Figure 13.2-1 shows the present schedule for the various initial plant training program. If significant differences or changes occur in those courses not yet conducted. the appropriate course outlines and descriptions will be revised by Amendment. 13.2.1.1 Operatina Department Trainino Procrams . These programs are designed for individuals who will assume the responsibility for both licensed and nonlicensed plant operating functions, as outlined in job specifications. ctWet s The program is divided into the following E::i: : ;rente: a. hse:12 W.ensed opcAer-WMD r e--eter rune- ::tel: b derOpnAce&msnq
- b. Re :ter St:; tsp L pw 1.nu -
E. Sen(ot- RacAce Opdc buuhg
- d. 6 Shift Technical Advisor Mevinced T c.'.nicali Training
- e. Liernsel opecAcclegrgininguc & a h h a ng
- d. n,r certific;;ien gyrt g _
e, ?" C Id C:rtific tien Training. ,
- f. SiiiR Sugwi. u ovi. Nucl;;r Tr:ining 0 g "c;- Cr :% Oysi.=m= L aining 4
.. c 13.2-2a Amendment 7 9 ,.. . -,--,..,-e, --.,,..,-,-._,,,,._,-,,w,,__,-_-__,-n.--n...,----,.,.__,,___,_,,.,,,,,.n,_ _ --- ,-,.-,- ,n ,n_..- ,, , - -
HCGS FSAR 8/84 u r n,,,< n .
. . . >.- n_,- .s.._
i (al r1 f { e_ ma. - __ _ A,-. . . .. b. T_. ._nt.
. .. .h. er.
.. . _a .n. _{ n.a, pre-woc r_4_.-...- .. . - . . . m- &1..,- .
. . . .a q.. ng i-I I
i l l 13.2-2b Amendment 7
4 1 HCGS FSAR 8/84 assure the experience criteria of ANS 3.1 (1981) is met, as well as the general guidelines of NUREG-0094, additional experience will be provided by a structuredt"L'"'.'- spryatio,n ~ program for all Ifcensed. operator candidates.4 f c4 M dpWOW MG-W0% 15 Shou 3A \A appe8 j( K ed desen l 13.2.1.1.1 Cold License Training Program This program is designed for NRC reactor operator (RO) and senior reactor operator (SRO) cold license candidates of varying backgrounds and experience. Candidates will be factored into the program at various points, depending on their previous experience and training. Testing and screening will be an intimate part of the overall training program. All license candidates who are supervisors will attend the PSE&G Supervisory Skills Training Program and will meet the supervisory training requirements of ANSI /ANS-3.1-1981, Section 5.2.1.8 prior to core load. -
. /
I L . ., . . . s ...-..f:f ^F 'hi= te=t- , ,. 96am that all SRO
,s candidat
- Cffidty u 3u s sem t.x ""r= of eauivalent
/ evel education.
13.2.1.1.1.1 Senior Reactor Operator Training Program The senior reactor operator (SRO) candidates will attend a training program consisting of, but not limited to, the following areas of instructions
- a. Nuclear Reactor Fundamentals
- b. Reactor Startup Experience f c. Advanced technical training i
$ d. Pre-Certification system training . l ^
- e. BWR Cold certification training
.___..,,. u.._,___ m_ ,_i__
eu , m g ' Mha,"4 M Nd3 l i 13.2-3 Amendment 7
.- - - _ . . -- - _ _ _ - - - - - _ - _ _ _ - . = _ _ - - . _. - - - - _ _ --~
I I HCGS FSAR 8/84 l
-g. Hope' Cr:rek Systems training
- h. bMWsc .GKO.mthMcAMSMnc t hd rudT Detailed course descriptions and outlines are shown in Appendices 13A, 138, 13C, 13D, 13E, 13F and 13G3 /.5 z:- and /3 T. 3 l
Y > _mm s It is the intended 4rf this training program thert all SRO candidates % p at least thirty (30) semester hours of equivalent college level educati,on, uM ob%h _.
.uwe -
Following the Hope Creek systems training.the SRO candidates will be assigned to a shift where they will participate in the cold license operator in-plant training program described in Appendix 13I.. ' 13.2.1.1.1.2 Reactor Operator (RO) Training Program The RO candidates will attend a training program consisting of, . but not limited to, the'following
- a. Nuclear Reactor Fundamentals
- b. Reactor Startup Experience
- c. Pre-Certification system training
- d. BWR Cold Certification training l e. Hope Creek system training.
Q. mn- P\ase bo* whet -
- g. ?n.- \(c.tAst exo.mscoMon h=nrshe 46t h.nin9 s Detailed course descriptions and outlines are shown in Appendices 13A, 138, 13D, 13E,and 13G 3 th:c ond ta r, l
#AS&T @W i
13.2-4 Amendment 7 l i . _ - . _ _ _ _ _ , _ _ _ . , _ _ . _ _ - . , _ . - _ , . _ _ . _ , . ._-m_, ,_,,____...___..,_,-_,,______,..__,~,_.,.m. _ . .
O b u wn,s n., p: 7 , sa cons &+ e4 %o sp4(. M % s , Ad m eed
% bntced % inc.$ os dAed. in o,yendlx. t 3 c.
h4 Es-oc wtning e4 cw4dtne 4 to qpodi.x t s F, W adumhe.ckAccd Scdncog p3mm + s u.>as dtqned. & Aou. thdi.uthtds ubo ca. to be. esA &&-4erknlt_cl od.ehoe , te.n' tor- A h.peoisors o r-s,As y%Nm W:r d d M gtAEd b e t M'M % tnin Ae 'tn&ot8ucks A. an Ao be. % 4 g oodors. l l l l \ t L
p( *A b *^-[-l A iM % - M fa4 eaa< : 97 & pro- e f -A
%-wm wp-w k2~ & y , Q s6a.y PW M M. p wac do us -
M ym, nan //a227~/ a SwL qwtan'd & Q y od-
~ & w L Md Gyawl we Awhgs.
I t i
HCGS FSAR 8/84 e l jf Following thf' Hope Creek systems training the RO candidates will be assigned to a shift where they will coma &eee participate in 8 the cold license operator in-plant training program described in Appendix 13I. 13.2.1.1.1.3 Shift Technical Advisor Training Shift technical advisor (STA) training will meet the requiremente outlined in ANSI /ANS-3.1-1981. Training programs will consist of those areas where their prior education did not meet those requirements and will include plant specific thermodynamics, fluid flow, reactor physics, system engineering, transient and
. accident analysis, nuclear instrumentation, process computer, plant response, and duties and' responsibilities. .
The STA training program will consist of, but is not limited to, the following areas of instruction:
- a. Nuclear reactor fundamentals
- b. Reactor startup experience
- c. Advanced technical training
- d. Pre-certification system training
- e. BWR cold certification training
- f. Hope Creek sy, stems training '
$. h- 9\M Mo.mthg Detailed course descriptions and outlines are shown in Appendices 13A, 13B, 13C, 13D, 13E and 13GgLv4 lB r , g 13.2-4a Amendment 7 , - - _ . _ , , . . _ . - _._.m.'
HCGS FSAR __ 8/84 p berc $ ~~r The reactor startup experience and BWR cold certification training may oe waived f:r *hnse individuale 't: ;c- pseviously licensed. They will howaurr ei.ueno a-9WRagLerational review traini an appropriate BWR simulator v6 ih; "Cc< ic simulator when it becomes available. , All STA candidates will be assigned to HCGS staff where they will participate in the cold license operator in-plant training S program as described in Appendix 13I. STA candidates will S cc tin;: te attend training with the SRO candidates. It is not intended at this time to test in lieu of training as stated in ANS/ANS 3.1 1981, 5.2.1.7. Proc res de ing the uct and ding cri of xbr'~ br ta ar nder eve ment and Ib ente int lear epartment ining pr ure man . 13.2.1.1.1.4 BWR Prelicense Refresher Training . Because of the long lead time required for cold license training, a Prelicensing Refresher Course will be conducted. This course JF will be approximately05 weeks in duration and will be scheduled to end about 3 to 6 months prior to initial fuel loading. An [ NRC-type audit examination will be given t th; cr.d ef the 6 uig h refresher training. Further training will be conducted in areas identified by.the audit examination. Appendix 13J provides a detailed description of this program. r l l l 13.2-5 Amendment 7 i m,_-,--.,-m_._,-_--,,..,-,_
i
' ~
HCGS FSAR 8/83 13.2.1.1.2 Nonlicensed Operator Training Program l This program is designed to make equipment operators The knowledgeable of HCGS systems, operations, and procedures. program will cover, but is not limited to, the following material: *
- a. Mathematics Refresher j
' b. Physics and Basic Heat Transfer and Fluid Flow (HTFF) Refresher
- c. Basic Power Plant Equipment (valves, pumps, etc,),
Lubrication, and Job Duties
- d. NSSS
- e. Electrical Systems N *
- f. Auxiliary Systems l
- g. Health Physics
- h. Firefighting .
- i. . Heating Boiler
- j. Procedures (as applicable)
- k. Administrative Functions, Equipment Tagging, and Log Keeping ,
l 1. Technical Specifications (as applicable). It is anticipated that the classroom program, Appendix 13H will 3 last 12 to 14 weeks and will be followed by a period of in-plant training where the equipment operators will complete required 13.2-6 Amendment 1 i
. HCGS FSAR 8/83 i s ,
r ch'ecklists. -?ie;;furer ft:::ibiuv sne uvuduct of s^w== n p699tama r,) F
.er= lec=&-A i the M::1;;- 0;; :treet Tr=!=!=0 "=="=1 13.2.1.1.3 Haintenance Department Training Program {
~
- Maintenance supervisors, electricians, machinists, and boiler
- . repair personnel will generally be selected from other operating i PSE&G facilities (fossi1 and nuclear) or be direct hire, i journeyman level qualified. As such, they will already have ;
j' received training appropriate for their particular skill area. Through their previous experience and selection / testing procedures these personnel will exhibit a high degree of manual l i dexterity and the capability to learn and apply basic job skills in performing maintenance activities. . ! . Maintenance personnel will receive on-the-job training during the preoperational test program by' performing maintenance activities. j Selected personnel will receive specialized vendor training on *
- specific equipment or skills. Personnel promoted to the ,
journeyman or supervisory level will be required to l satisfactorily complete the PSE&G Advanced or Supervisory e t Training Program associated with their particular skill area. .' ~ li Additional training for experienced personnel will include a BWR j Technology Course, appropriate quality assurance training, training on plant specific maintenance procedures, and radiation worker and general employee training, as well as other programs !
; deemed necessary. Procedures for these training programs will be t l'
available in the Nuclear Department Training Manual. ! Personnel below the supervisory and journeyman level, as a I
; minimum, will. complete the various required apprentice level i training programs as their career progresses. These programs will also be detailed in the Nuclear Department Training Manual. )
Training will be conducted by PSEEG and qualified vendor l personnel. , 4 ; j 13.2.1.1.4 Technical Department Training Program l t I The objective of the Technical Department Training Program is to provide highly skilled personnel to effectively support the preoperational testing program and plant power operations. l 13.2-7 Amendment 1 i !
HCGS FSAR 8/83 Procedures _for these training programs will be available in the Nuclear Department Training Manual. 13.2.1.1.4.1 Chemistry Section Training , l Supervisor and technician level personnel will be selected only after meeting applicable experience requirements._ As such, they will generally have completed the appropriate training program Essociated with their respective job pcsition. Procedure for conducting'these programs will be available in the Nuclear Department Training Manual. Experienced personnel who fit that l description will, as a minimum, undergo training in the following general ~ subject areas:
- a. BWR Technology -
- b. Chemistry Practices and Procedures .
- c. Chemistry Equipment and Use
- d. Applicable Administrative Procedures
- e. Special Courses presented by the Nuclear Training Center and/or vendors, as appropriate.
l f. QA Program i
- g. General Employee and Radiation Worker Training.
/
! Personnel promo6ed to the supervisory or technician level will be required to complete the PSE&G Chemistry Technician Advanced l Course or Nuclear Supervisor Course, as appropriate to the respective job position. . Personnel below the supervisory and technician level, as a
- minimum, will complete the various required apprentice level training programs as their career progresses. ,
I 13.2-8 Amendment 1 e-- -, , , . - -
? D-2 HCGS FSAR- 8/83 Chemistry personnel will receive on-the-job training during the preoperational testing program by performing their job associated ; tasks in, support of that testing.
. Training will be conducted by qualified PSEEG and vendor personnel.
13.2.1.1.4.2' Instrumentation and Controls Section Training l i l Supervisory and technician level personnel will be selected only after meeting applicable experience requirements. As such, they will generally have completed the appropriate training program associated with their respective job position. Procedur~e for conducting these programs will be available in the Nuclear Department Training Manual. Experienced personnel who fit that description will, as a minimum, undergo training in the following general subject areas: 4 .
- a. BWR Technology
- b. Instrumentation and Controls Practices and Procedures
- c. Instrumentation and Controls Equipment
- d. Applicable Administrative Procedures l' e. Special Courses presented by the Nuclear Training
? Center and/or vendors, as appropriate. i
- f. QA Program
- g. General Employee and Radiation Worker Training.
Personnel promoted to the supervisory or technician level will be I required to complete the PSEEG Instrumentation and Controls (IEC) Technician Advanced Course or Nuclear Supervisor Course, as
- l. appropriate to the respective job position.
l
. s y
13.2-9 Amendment 1 f - l' 1 .
HCGS FSAR 8/83 l Personnel below the supervisory and technician level, as a minimum, will complete the various required apprentice level training programs as their career progresses. IEC personnel will receive on-the-job training during the preoperational testing program by performing their job associated tasks in support of that testing. Tra,ining will be conducted by qualified PSE&G and vendor personnel. 13.2.1.1.4.3 Reactor Engineering Training Program l
~
Prior to core load, selected reactor engineering personnel will have attended a vendor-offered course typically entitled " Station Nuclear Engineer". Typical subject matter will include reactcr behavior, control rods, shutdown margins, technical - cpecifications and Fuel Warranty Operation Provisions, core flow cnd thermal limit calculati~ons, fuel failure and Preconditioning Interim Operating Management Recommendation and water chemistry, i 13.2.1.1.5 Radiation. Protection Department Training Program l Supervisory and technician level personnel will be selected only afte'r meeting applicable experience requirements. As such, they will generally have completed the appropriate training program escociated with their respective job position. Procedures for conducting these programs will be available in the Nuclear
-Department Training Manual. Experienced personnel who fit that description will, as necessary, undergo training in the following general subject. areas:
i l l
- a. BWR Technolog/
. ,b. Radiation Protection Practices and Procedures .
- c. Radiation Protection Equipment and Use
- d. Applicable Administrative Procedures l
13.2-10 Amendment 1 j l 1
- _ , _ _ _ _ _ . . . - . _ _ . . _ _ - _ _ . _ _ _ _ . . . . _ . ~ . _ _ _ , . . - . _ . _ _ _ , . _ _ . _ . , . - _ - . _ . - . . _
HCGS FSAR 8/83
- e. Special Courses presented by the Nuclear Training Center and/or vendors, as appropriate i f. QA Program
- g. General Employee and Radiation Worker Training.
Personnel promoted to the supervisory or technician level will be required to complete the PSE&G Radiation Protection Technician Course or Nuclear Supervisor Course, as appropriate to the respective job position. Personnel below the supervisory and technician level, as a minimum, will complete the various, programs as their career progresses. . Radiation Protection personnel will receive on-the-job training
- during the pre-operational testing program by performing their job associated tasks.in support of that testing.
Training will be conducted by qualified PSEEG and vendor personnel. 13.2.1.1.6 General Employee Indoctrination l All persons regularly employed at HCGS, including temporary maintenance and service personnel, who are permitted unescorted access shall be given General Employee Indoctrination. This <- training covers the following areas:
- a. Site Description
- b. Emergency Plan .
- c. Security System
- d. Quality Assurance Program 13.2-11 Amendment 1
' HCGS FSAR 8/83 . . _
- e. Radiological Health.
- 1 Personnel will be tested in the above areas to determine the offectiveness of General Employee Indoctrination.
Personnel who will routinely work in radiation and/or contaminated areas will also complete a Radiation Worker Training Program of approximately 12 hours. 13.2.1.2 Refresher Trainino for Nonlicensed Plant Personnel i A retraining program will be provided for all personnel to ensure that they remain proficient in their particular jobs. Retraining in specific areas is provided to the extent necessary for personnel to safely and efficiently carry out their assigned - responsibilities in accordance with established policies and procedures. This includes operating experiences, design changes, revisions to procedures, and new procedure indoctrination. Such training may consist'of vendor presentations, technical training sessions, on-the-job work experience or programmed ; instruction. Personnel are evaluated on an annual basis where individual needs for retraining will be identified. 13.2.1.3 General Employee Indoctrination Recualification All persons regularly employed at HCGS, including temporary
- maintenance and service personnel who are permitted unescorted access, shall requalify in General Employee Indoctrination annually. This is accomplished by attending the requalification class and obtaining a satisfactory score on an examination ~
l covering the areas mentioned in Section 13.2.1.1.6.
-Personnel trained in the Radiation Worker Training Program will requalify annually by attending the Radiation Worker Review l
Program of approximately 4 hours. Satisfactory completion of I that program also meets General Employee Indoctrination Requalification requirements. 13.2-12 Amendment 1 l i
HCGS FSAR 8/84 13.2.1.4 Replacement Training for Nonlicensed Plant Personnel ' Replacement' training is designed to supply qualified personnel at all levels and job positions within the plant organization. Training is carried on at all job levels to qualify that particular individual to effectively perform the required job functions. . Qualified personnel who are promoted to the next job level are placed, as rapidly as possible, into the appropriate training program. It is the general policy of PSEEG to promote from within. In this manner, as an individual progresses, he/she is immediately trained for the new position and capable of supporting and training personnel in the lower classifications. Personnel who are directly hired into job positions above the entry-level will meet or exceed the applicable requirements of . that position. Training programs will be developed for these personnel to familiarize them with appropriate HCGS-specific material. Training will be conducted by qualified PSE&G and vendor. personnel. The training programs will be described in the Nuclear Department Training Manual.
.13.2.1.5 Replacement Trainino for NRC Licensed Plant Personnel i
Training for NRC licensed replacement personnel will, as a minimum, meet the existing NRC requirements as outlined in 10 CFR 55.21, .22, .23, appropriate NUREGs, and the H. Denton letter of March 28, 1980 and all applicable training requirements of ANS/ ANSI 3.1-1981. These programs are described in the Nuclear Department Training Manual and are revised as regulations and job requirements change. 13.2.2 FIRE BRIGADE TRAINING PROGRAM l Fire protection training will be conducted in accordance with the - guidelines of the.SRP (NUREG 0800) Section 13.2.2.II.6, 10CFR50 Appendix R and Branch Technical Position CMEB 9.5.1 Section C.3.d. This training will include classroom instruction, hands-on fire extinguishing and plant drills. 13.2-13 Amendment 7
HCGS FSAR 8/84 The classroom instruction will include the following course materials
- a. Firefighting Plan l
- 1. Response to alarms l
- 2. Responsibili'cy of members l
- 3. Reason for fire brigade l
- b. Identification of Fire Hazards l
- 1. Concept of fire ,
l
- 2. Properties of flammable and combustible liquids l
- 3. Hazardous chemical properties l
- 4. Boiling liquid, expanding vapor explosion l
- c. Products of Combustion l
- 1. Products of burning plastics l
- 2. Products of smoke l l
- 3. Properties of carbon monoxide l Properties of contaminated smoke
- 4. l
- 5. Effects of heat l
- 6. Ventilation l 13.2-14 Amendment 7
HCGS FSAR 8/84
- d. Firefighting Equipment l
- 1. Fire detection l
- 2. Fire suppression l
-e. Types of Fires l
- f. Auxiliary-Equipment l
- g. Plant Modifications l
. Actual hands-on fire extinguishing will be conducted to provide l brigade members with actual fire, extinguishing and the use of emergency breathing apparatus under strenuous conditions. These -
practice sessions will be held at least once per year for each fire brigade member. l Plant drills will be' held at specified intervals not to exceed 3 months for each shift to allow fire brigade members the opportunity to practice as a team and to ensure adequate procedures and readiness. Each drill will be preplanned to establish training objectives and will be critiqued to determine how well the training l objectives have been met. Performance deficiencies noted will be ! remedied by additional training. Fire drills as a minimum will assess the fire alarms effectiveness, time to assemble the fire brigade, use of the firefighting equipment, firefighting strategies and the effectiveness of the brigade leader. l The Fire Brigade Training program is designed to ensure that the - employees assigned to the fire brigade are capable of providing adequate manual firefighting strategies to control fires that might. occur at the Hope Creek Generating Station. The program j will cover, but is not limited to the following: f
- a. Indoctrination of the plant firefighting plan. l l 13.2-15 Amendment 7 l
HCGS FSAR 8/84
- b. Identificatior. of fire hazards. l
- c. The properties of the products of combustion. l l
l I
- d. Identification and use of all firefighting equipment. l i
- e. The proper use of communication, lighting, ventilation, and emergency breathing equipment.
- f. The proper method for fighting fires inside buildings and confined spaces.
- g. The direction and c'oordination of the firefighting activities. (Fire Brigade leaders only).
- h. Detailed review of firefighting strategies and procedures.
- i. Review of the latest plant modifications and corresponding changes in firefighting plans.
~
Procedures describing course content, grading criteria and recordkeeping are under development. These procedures are scheduled to be completed by January 1985. 1 13.2-16 Amendment 7
. ... . = _ -. .-- . - . - - . - . . . . . - . . . -
4 l s D E
/
4 T L O R U 5 O D
.O P E E N
S OR H T I S C A KASY I S - l l ] y ET G A 6J fS LA N 9 RG c89 N I 9J N 1 EI P T A I A M
, 0A TY R A 1 3
1 2 2 , 94R E F E T N A L 1 M E S L 2 C L A 3 F A R 1 N E E J I V A l l l g F O U
' I G
s j l g I p l l l D g 4 g N H u O S
$ $e e s
b s l f i d i
, 6 '_ I A i 5
J h } { H g I
\ i u
I l l g sJ 9 1M
] I 1
e ( s s g u 5 A j i y 1 l M { ) [ y 1, I F 3 g l J u 6 i l E D ; r , N a e a s . O , u o on .. , [ l S , 's . A s i g g 4J e 8 , 8 , y s 9J y u g J 1 N l g a s , A M l , g ; . F , 3 g o J g i l l l ] D s s y s y y l N l l 4 [ l l l , y , l O g J S p e 5 5 T A l a n N
, l a t s
t J i r 3 l l y , O 4 L 8J l 4 l l , E 9 g V 1M E 3 , D A , E R 3 M l U D 7 , g f F C l l ; I y O 2 2 R $ J l l t P. n G u to i D E D l l T S t C E n u TR SO N T O NP P E O 1 1 U T C EO 8e Rp m O S a A RUA$ P l l t Ts S O St 0 A fe dE s 2 A MTS et s 8J S e Sv E t l 9 t R8, A i R 1J LGe T US T l L E S DlC e, M Ese V Ee s G _ N N ADe Ns $, Co S Om f A6 2 3 A O Oas L Hi O S Sn L E H Ri A PC t P _ M E E T DE s e S _ P PsO N E hL 0 S T _ P T s AE. 80 E A ga eAtS sT A" M _ J L a A _ U ,heeO TE EN L RG . - e f s A Ge G t U Sn C "^ e Ome
.S F Yu R" R8e i %S N
s t R SmE S T' Pe _ r r e ss S aEGs LO S1 L$R C" A6 . R AseU A G L T o O EQS e E. o uEs%R L iN OAe psG L _ R T T _ L t t s l GT Csste aS s. C E,'AaTsI U a a n ) n n n c e =l hec E Ags tsLG L A mSN D E H C r e pt ol rR eW) pD r o es rw eD p o oec r rd oa t r e re od t a
)
r o t t n a t a t n i t o c i t c o o i t c i n a h r n n o s
- Sif LmO A6 TaVmTT eN sNGwR.OSdCEsAe s
Aeffe s AAIS0R AnMmpOuAsA mete EG4/nOhsEeA s A E 0sEGE f S N*nOE 7E C*MA 4M SC IA S o ag ar e e e
- T PAaIME4TSsCunA8s
=TDmOE ts VL t
a s c e r se MUR P MuLaTfGaseATe i t e I eC - rh oS rci onv ti rn oe t a r rp eu p rg ep r e s i s n a i s t o tt on t o e m e n e p
- ATAnA5CvNA OnC Y ERPsA RUOOFOGs OeaSm8 EtTPCuEA eae'IE 7. P R t
EE UI t )ter pu p i s r ra pr i =aaSISF TOC TsV OSslTN"CSE crr cie aoo arp eeu cr ae) e p o o. O.
- o. o s a i n
c n a pr e pt s na e n c g n y r 4 UTwMI es A R Ees ETIALT*sANvAAMTOAm maCTREEANet AO ESERLuEte$ PnEO f A LS E YesutTv$C g eis e pf t t)/ ya y nk ni n e o s iL f Y rni rps rxf nU tnO. nOh h ri r or os oi a s TTYCCCssMauatrMsCA N es e T ev x ca r e eC eE c c io is ic n tCTS OEeUiPEas uR r tAeFleLP8 TtTTTLes t c t N I rSr V o/e of ret r(t o s t o mm pe m pm mA e p T e T si s in i tw ta ti a a an t e o t i v r N s peuS S5At8 sU
- uENeOOEoOYsvEoo smSSCtGCEStS#CGSJ e e e
- a C
E Ee _ IiApini ir c il ie i w mh m ih ih $h n c e M . - T nTu noh nod a ua ul ue C C ec e dcdcdci a p **I. C eSS ENS etn e qS qa qn 6 6 he h ae ae ae a e u 91& R ES s 349ST 8 9e t33e 667 E334 n - AS( S( Saa E( E(1 1 CtC RtRtRT M R S 1 $ ti19l121
]/ i i
j ,*je iI
_., HCGS FSAR 8/84 APPENDIX 13B REACTOR STARTUP EXPERIENCE Se.\tcM btshC. c Presented by: tz#.i; Ot:te Univereity F::ili ty -- Obiective l To assign cold license applicants, with no previous nuclear experience, to & Resaarch Reactor Training Course.cendweted-by
;hir State U..i territy. This '
F actual hands-on experience with M.; g g nuclear .._. .. . e gives reactor the student and allows the cold license applicant to obtain at least the minimum of 10 reactor startups necessary to establish cold license eligibility requirements of ANS 3.1, 1981.
Reference:
. ANS/ ANSI 3.1-1981 Section 5.2.1.1 l 1
13B-1 Amendment 7 J e 1 m. e---r -, ,..e---n<,,m, . ,-,e--m-,. ,-----ee----wwnw-. ,-n-w,e--- mw..w,w,--,,,--wm,-ae---e-r--w, , _e-mw,,www., , mm ,w,,er
HCGS FSAR 8/84 APPENDIX 13C ADVANCED TECHNICAL TRAINING DE4 % or 54(eCkd. Ohhc_k e Presented by: "crphis Stete University
- Obiective To provide advanced technical training in Thermodynamics, Heat Transfer, Fluid Dynamics, Reactor Materials, Reactor Physics and Human Behavior to senior supervisors and STA candidates.
Course Description The Advanced Technical Training Program consists of nine (9) courses.which tet:1 2 cerester credit hours cf sc dc=ic ir.:tructice. A list of the courses and their content is outlined in the following pages.
References:
ANS/ ANSI 3.1-1981 Section 5.2.1.6, 5.3.3 l 10 CFR 55.22 NUREG 0737 Appendix C Section 6.1.2 l l W in%6.(Ambs progcam wcaA q u-bg mtm9% WR eGS .hht pp W M h b O.o A h.C.491 9T&4 0" 5Gle.CMLdt NW. l f 13C-1 Amendment 7
- HCGS FSAR 8/84 APPENDIX 13E COLD LICENSE CERTIFICATION TRAINING TM 8.6 o e- %e(Ecbe.A ^ - - -' "
Co o,hbc CL4 Cus 'cQpMued g' e"-~ hann *" Presented By-* --- ' nk"e4-- Ce ! ."... . ; H.._ : ". A.' .Z. . ' ,. 7 7. ., .' . .'".' 3m ' .r'1 =a.. __~_. a ..,,ing will be 25 ;ur fecil.Ly. Objective
- 1. To ensure that non-experienced (nuclear) personnel meet the cold license eligibility requirements of NUREG-0094 and
~
ANS 3.1 1981
References:
ANS/ ANSI 3.1-1981 Section 5.2.1.3.2 s NUREG 0737 enclosure 1 10 CFR 55.23 YW Ineb b uA fno m Locco do,-L y
.6 g GibeaQ N</h dcap a+ YJa sue g g
' m M A L. S s- p a wd 4 0'
& Am a - ss m. ,
l l 13E-1 Amendment 7 l
HCGS FSAR 8/83 i l
\' APPENDIX 13F SS-N TRAINING PROGRAM Presented By: I-a part Ly Cencr:1 Elcetri: 2". bin gerk hy -)!ompM s St:tc "..ivecsity
?k5 4 6 o r- die lec.NC[ 00nNkr Objective:
To provide advanced instruction to Senior Operators and - Supervisors on BWR Specific topics gnW
- gft GENER?.L ELECTRIC ,
-/
- 1. BWR Chemistry - I wk. J
- 2. Nuclear Engineering - 3 wks
'N
- 3. Corrosion - Materials - I wk.
- 4. Radiological Emergencies - I wk.
- 5. Abnormal Event Analysis - I wk.
- 6. . Degraded Core Damage - I wk.
*MSU l
[ 7F Materials Study - 2 wks. 'O crcdit3} 8 )T Human Behavior - 2 wks. '2 crcdit P l i l 13F-1 Amendment 1
HCGS FSAR 4/84 3 NOTES:
- a. College Credits for GE. Course - 8 (awarded through the
- M.Y.S,- Regents)
- b. . College Cre its for MSU Course - 6
- c. Total Course Length - 12 wks.
- d. Description of Modules 7 and 8 are provided in Appendix 13C. l.
*The STA's and SS-N's will be integrated for these .ourses. c
/ l
References:
s ANS/ ANSI 3.1-1981 10 CFR 55.21 and 55.22
.-h NUREG-0737
' o
* ' ' $20 &({cdes tvill ckliend dbe SS-'0 Wrainin] N fDfk kN Gy 0enktti UNEC ComM MW SW sku ct4*tqcm ,4u % m :Jv hed8 e cach .
Tu h pme% s galts b ekt z 63 Sg(ec.4Ed Ron Cder {WhCMod . 1 i 13F-2 Amendment 5
HCGS FSAR 8/84 APPENDIX 13I l COLD LICENSE OPERATOR INPLANT TRAINING ph l M Presentep'by!PSE&G [ selected contractor personnel jectives: To , provide cold license candidates with a structured and documented program of plant cbrervatien b reoperational testing and work assignment participation requirement sysh 6wAh,
Description:
The cold license in-plant training pragram is , designed to gic; th Op ::ter the minimus ::quirc;ent: n:::::: y t: 5: ;;.pl:t.d durin; p ::p;.;a;.ivii.i cas t i,iv a;.4 ensure that e.ch candidate receives sufficient practical work experience necessary to gain a thorough knowledge of the p10nt. In d addit on, this program provides for a structuraE :'rerustier. progran where each candidate receives an oral examination and system check out on plant systems emphasizing system operation, local control and interactions. This in-plant training is documented in the form of individual In-olant Trainino Guidelines fer the RO, SRO and STA candidates.Mhe completed in-plant M* b training guideline will be maintained in the individuals training record. N Sdhi -
References:
ANS/ ANSI 3.1-1981 Section 5.2.1.2.2, 5.2.1.3, 5.2.1.4. 13I-1 Amendment 7
ew-A**"" fA%p@(Amww W " W" > W widy -n p&
/way .
- 8" $
*P w O-* e w-m I
l l
m L y Leimsphva W c%ed .acBrW Qcard du
- - - . . . .$ 0. . . .
- . - . . . _ I. System Knowledge Guide Questions --
~ ~ - - -
~ ~ ~ ~ ~ '~
II. System Knowledge III. Performance Items IV. Technical Specifications V. Reactivity Manipulations SED I. Control Board Checkouts II. Technical Specifications III. Radiological Controls IV. Plant Safety V. Refueling VI. Procedures VII. Performance Requirements STh l I. Control Board Checkouts II. Plant Safety III. Procedures IV. Performance Requirements
HCGS FSAR 8/84 APPENDIX 13J PRE-LICENSE EXAMINATION TESTING AND TRAINING l Presented by: PSE&G or sdlected contractor personnel. l Objectives: To determine individual candidcte's ability to operate the plant in a safe and competent manner and to identify areas of weakness that may be corrected prior to administration of the NRC license examinations. ,
Description:
The pre-license examination testing and training period will consist of an intensive period of instruction and testing prior to the NRC license examinations. The instructional
-phase of this program will consist of the the following: ,
- a. Classroom presentations on: Wh l
- 1. Reactor. theory ves;es l
- 2. Heat transf erres;ed
- 3. Fluid mechanics res;e.J
- 4. Thermodynamics revies flea lW sics reVic.W
- 5. Preceder _ :nd Oper: ting phi 100 phic
~
Technical Specification add OdW"Shh d *'S Y8#2'" 6. {
- 7. Related industry events relevant to operation.
- b. Simulator Operation [c,lamoom Pvepera41ow [y 60/50) (~/tJ M S)
- 1. During normal, abnormal and emergency operations to e.nsare. under@adla) of procedural and opntbj ysopkieS 13J-1 Amendment 7
HCGS FSAR 8/84
- 2. To demonstrate the proper use of the emergency operating procedures.
- c. Ir ;1:nt femenctratirn er 27.ip=:nt enr=t! ~ % ~ -
1 ::1 :p:::ti.; p:nrir --l : i : cat 1.;; ti:nc. bec.ondint.4e2bf NF h"* The testing phase of this program willA:::.ci t f; (t Q cermally 45st3ne.d W:bbucMonal Sieff owd will cas.'s+ of ;
- a. A written examination to determine knowledge level of theory, operating procedures and philosophies, system
- constr'ction and design nnd technical specification requirements.
c b. An. oral examination to determine knowledge level of plant operation from both simulator demonstration and in-plant walk throu'gh.
References:
ANS/ ANSI 3.1-1981, Section 5.2.1.5. 1. r I i [ i l l l 13J-2 Amendment 7 l
\
i llI1\Il v,h
'ai Fj et 5+fg 9s C 8i s. .- f ti Y j g~ ~ 6Y 6 1 3 g. bT
~.
4 l. .. Ap)< $Dega a e p jgo4$J-
~
3 j e 1 k 3 s 4 5 s *aw } 'o
/ s 3 4 ; -
e 5cJ o8 ascd
)
~
suJ i # $ecA8~ 3 e c ?! > ,1 d g l b ( c 4' k 6 aJ ' e3
+a:)p f4e 5oyas -
a 4e1 } df23 4's o>g4' E-j< 'c 3 r. $a4 9 e/ ea i b. . U ~ eu 'e* 9n ]
~ ~
e- e5 W 8ef3 ralc st! ' 6 8'L2 3 2"3 ' a r. d9'r 5o3e, - anA34bo4?9t,ie2 ) j.sr h ha$o5 $3
~
s Y 2'c c ss if3voL21'
Gnc Se.&or Reac w opexebe, Spec 4c.
%etY5 & eQca seckiota ygay ae. ulaived r
(-ka senerd nowager % dreeK 6pernous Cor sete.ck lic Mouals &
. On pYeVIOu.5 7t1Rihlnd d.nc, e)q0e.de.Hde.
I ReacM dy T20) [
. A eomple e sivai4fator aedl fica 1/ou lvarat,,y
'pqram af e\SerNe Sr ue Aans siluulaf0f or N h5hYeeYshgluf$r as descriTdi 0}WoiK13E.
4TMspreyvomjives exd opralor haafot, expiente ehd % fatowaeg charachris+ics M a Sg (tloodit#) Evf2 uwsler,wormaly ahnorma cademepoy e_nudib'on.s, 3 dricipate m Sfl4 jr hao weeft af
& W c,euerdig swin(towwe Fue). .
- s. Tas erocram Jl tunhce.-Ide qexalor % Psct& aupale -
f0liciec yted hdl,ua reos arc int > ~
r O % oh M hr bh o d m's J A h p et b m ueueAng S A-ton 6 A 3 wC4.h bgng , e.mgeneg respome. ud wu,u%m, emame w wa a bsex Coe uc.ng oC hs,e. peeduns uW bt og rddde,r 4 4ew uud ce h M4% \b'ss, %t>tb poo's d.es, ecolg
%'tnig Qr h gembe om w . emnducA eC opab a e Wns,
- z. % p S cam a n sn b bee. % o p m b
% %. WAqtockch sqsh and hw E \( [. (<h doet v p ttme.n%s os.
% a a aaa m ap b
l a.We 9%gro.m teu 'tcAxduce, 9Aeb opercAer
%% sige. 6.nd. comp \eis%oCA
%mmesdA uxekte hA% JueLudeng %
= & g &a p eaun %s a<a bea m ess 9"ce6*tes-
c l 1 c.. Compe opra%e (n- pan + Mtncng ; gte.wmexA2 te.serLA sn appnh n z_..
'd. Go q \eka
- 9w-Ecens esa.mena4a ctsa 4est $ pogcam dedAd tw apptab ta r m e lt A q s m.t A c A c c S i t nta g o n % e.
Ae_ca 9 a.nA echanse_4 unu.AceLor
\ o r.
a smukcAce 0 0a sms(ca- hpt. pa.n4. a her heb opcAer tsao3 N\en- 9tto\otMg l.CtAn%9_d., . A. Comp %h bm.u.(cdoe MdbMon htn'tn} pa yam 24 h % sgur k onx M tncng smuko.h as, dercide& in godt ts e .
- 3. bktipcAs on.skA4 Cer AwoCA wek.s c6 ne_ h\,sm (he.norodang %bn (jooomue 9toQ w pa.A htatng e.. Comp \ek op92a6
__ _Y" _
~"?
C
- t. To.tkcdgo.h on sb4 (3 - a cdcd(nu.m d sk(Cs uatu a4. 1 \agt comme,6cd.
apxkng h 46V% 4 reed % eqwena w e p h e n t s. 4 Ans s.t- nel semon 4 S.\.2 { Q
- i. Yh, % d pc k 'ot\ adouS4 Or %t mucAumtn4- w %t %-b b opndon oc % M a g as a membe et %
opea4cng swk .%ts by . i ,:t paeWzhon inch 6es veuke e4 pc3ceduas ad. hWetc4 s.pdeka.Abas 3 c>bwvech a ck=5:7 acg susui.dhner ke:kag h6 Genbo\ ve capded<6ns .%s pcuAc cpcSon gtun % squukoe 4=4. %d egeEence inu opun%n a a \qe. commersed h& & sat %. l
- DA k N- \bkb% Ob M i nCA. 0A o.4 besmg peopca lestad 'tn oge.nL'tx tav incLudmg ucuAcAoe 4ecitecq on% 4tas 9 a.n4 L tekenced
J 7 hku.bler e c- a stmublor oC a s.h.'d w h pt p\ctn4.
. %usomq lscansed- NE.
A beteAt a h oL,h weA s 6 4c-Accancag pegeo.m as % hpt6m kalncag esabe o r- sAace gyt 9hnt % Co_adb'tge. % idiockud tuh% emabas ad wespona docabadas e4 a \qq. htc h . s, %%c9 4 en $44 Le 4wocobeeks ob %. bh bnamk.n3 hMon
- t. h ph. epm %. e 6-p % 4 h icag (n.
( de.gtActmuA desd>tbd 'sn opptnb. l
- b. %AkgcAt on &EL b w mintm.u.m d hx Uh us.sks oA a \.o#ge commento{
o p o 4. % we MA%%ma4% l a p te. nee ceptameas. oR Anss s.t-Ret
s e t % n. 4.%.i.aL%. i
- e. Comp \ tat %t p has emm:nah ui bbg pegram Asse#thd_ 'tn oge.ndu ts2 swe6&% umde,b bitnt$ on
%t uttw, pant ubnua ai4cAcc oc w s % W et a simike %pt 9%A .
- buteusag heans.d - 96mA A. b44@ en s%4 4 he Cah weeks c& W Lhm thquA.g %Atin 6, Com9\de. opewb sn-pb4 bitnt$
regulemob. dese.#t6ed <n apptnh ar. t. 0.om9% . h p -(ie.nss. exa.mIm b ui bg pp ent6a 'tn g ut h a 2 i ne.L u d a g u d ce b e
\M O h kE Stb 1 GnN M NCh a w b b oc a u<wu.W ct es s.tabe %t p%4.
h oc h Lco a % % b m t Mtgu1HLrweA.4 sbhd h a % eut, %v sao hee.nst. ecu&4. des
\ADho a.vt akasiuled % bt %Q.doo %%C4 wpwkon vsa p hipcAt in a % C.O cnon n Q g ML<n 06 Mt bsgu.qbnnot h cm che_ke h%a degned. %
meeA %bt expn'o.ner. gmAswuAs u* f.e A in C,e.ntek Lth. e 4 -1 (, dedad Tu.no. oh , Re4. %'ts 9qco en Jntespom4ed bcWs pea A M9 e k on exs cx twate 04
%.ba. sM. R4 e C o_n opo.xec% pouser receb cud 6 cq % \<dL6.d Cu.eA bc&nc t and go w e4 2, cutenom Newq 0C
% \% e_ b.o w .
l l
.-..--- . . __,__ .,._. ._,._ _ . _ ,._ _,-,,- _,,,. - ,-, - ,_,,,..,_,_.,,,,__,_ -. ,. ,,..__,,...y_, , , . _ _ _ _ ,
T Q.o\A. UtQ.nst hdthk wiu okhdn e h ekhndue., uooMtng \<now\tEgt 4 h tommerwa we n uck a r M&ku %(comunta wh peJoe
% W a g a.nst eg-~ qua%g equiu.eg
%ke wRe ctnd wk&Me opucAom.
Rebantes: A n u 3.1- R sh setMon 4.s.t. \ 4 3. \. a i 4 s . t. 2. so era ss.asGB
&nece Lehr e+-to acAd 4(al84 (bene >E Le h 84-tb b4ed 4(ade'l i
l l l 3 f
- . _ _ . . - . . ~ . _ _ - _ - . __. . . _ _ . _ _ - . . , _ _ , _ . , . _ _ .
8/B4 HCGS FSAR OUESTION 630.4 (SECTION 13.2) With regard to training in the use of plant systems to control or mitigate an accident in which the core is severely damaged, please provide the training programs and schedule for:
- a. Licensed operators ard senior operators
- b. Other plant personnel (Ref. H. R. Denton letter of March 28, 1980 and II.B.4 of NUREG-0737)
RESPONSE
I Licensed Operators and Operations Personnel l NUREG 0737, Section II.B.4 requires that training of plant 4 personnel be conducted to teach the use of installed equipment and systems to control or mitigate accidents in which the core is severely damaged. Enclosure 3 to the H. R. Denton letter dated 3/28/80 identifies the to ics that should be included in thp M Sdvess NC GS 5 sfeA i W W'ah'o training asWmiah:s he prodram.% GddiFtvtansk .Stai Mac hdngodynWes Ws Mn [ ecu fee The HCGS operator training for mitigating core damage is under development. It will incorporate all areas identified in jf enclosure 3 of the 3/28/80 letter as they are applicable to a BWR: Incore Instrumentation l A.
- 1. Use of fixed or movable incore detectors to determine the extent of core damage and geometry changes.
- 2. Methods of determining peak temperatures, extended range readings and direct readings at terminal p junction.
t
- 3. Methods of calling up incoro data from plant process computer.
[ L l B. Vital Instrumentation [t 1. Instrumentation response in an accident environment; ). , failure sequence & indication reliability. y ll 2. Alternate methods for measuring flows, pressures, levels and temperature. { i: i I, h 630.4-1 Amendment 7 i L . . . . , .__ _ _ . - - - _ _ _ _ _ _ . . . _ . - _ _ . _ _ , - - _-_____,..___,,_,,,.m- _ . _ _ . _ _ . . , _ , , _ - - _ . - . _ _ _ . , . - .
8/84 . HCGS FSAR fh OUESTION 630.7 (SECTION'13.2) Section 13.2 of the HCGS FSAR contains the training program The segments for licensed and non-licensed operations personnel. Please segment outlines-are contained in the Appendices of 13.2.
- provide the details or information for the following:
- a. Prerequisites for personnel assigned to each program.
- b. For licensed training, which course (s) will contain the use of HCGS specific procedures including; Individual Systems, Inte Administrative, Abnormal and Emergency, Radiological Emergency Response Plan, Technical specifications, Initial Fuel Loading, Low Power and. Periodic Surveillance Testing?
- c. Please provide the applicable references (Industry
-Standards, NUREGs, 10 CFR and Regulatory Guides for each of the segments outlined in the Appendices.
- d. Identify those training segments which include the subject areas contained ,in 10 CFR Part 55 Section 21, 22 and 23.
- e. The Appendices do not contain a course Please provide description the course of segments 1-k of 13.2.1.1.
description or a schedule for submittal of the course 3 description. The Appendices do not contain the details of the f. observation training referenced in 13.2.1.1. Please provide the course description or a schedule for submitting the observation program. for NRC
- g. Concerning replacement training (hot licenses) candidates in Section 13.2.1.5, the FSAR must contain, as a minimum, those courses or segments identified inor Section 13.2.1.1 Ref. (NUREG-0800, this program prior to fuel loading.
13.2.1.B)
- h. Please provide information on the details of SS-N why In addition, training contained in Appendix 13F.
are Senior Operators with previous experience excluded from this course as indicated in Figure 13.2-17,(sic) (Ref. NUREG-0800, 13.2.1B)
RESPONSE
- a. Personnel assigned to the licensed and non-licensed operator training programs come with diverse backgrounds; however,
,)
630.7-1 Amendment 7 l i 1
-- mv m...-,...,,--e,----...,--- ..,w-m,,_.-.--,.. ,,,w.,,,-- e--.-r.-,-..m.,
l HCGS FSAR .,' 8/84 'N
\ ;
requirements of ANS/ANSIecch individual will meet tha educetion c loading. 3.1 - 1981 prior to initiate fuel $;jJ y training come from one of the following areas:In gen
- 1. Degreed engineer 2.
- 3. Previously licensed (BWR/PWR)
Navy nuclear plant operator 4. 5. Fossil plant operator Salem EO upgrade In general, personnel assigned to the non-licensed trainin@ will come from one of the following areas: operator 1. Qualified utility Generating / equipment operator from Salem Station 2.
- 3. Navy nuclear plant operator Fossil plant operator satisfactory score on a screening examination a as aT At present, to assignment to the operator training program prerequisite Power Operator Service Selection (POSS) is used. .
previously held a NRC license and for degreed All prcspective empicyees must p . aq pe t 4 physiological screening process.articipate in a Personnality Inventory (MMPI) is presently The Minnesota in use.Multi-Phasie b. specifications will be conducted as the procedures available. a become available at various intervals throughout theThese training period. To ensure that all licensed operator candidates are thoroughly familiar with the procedures and technical specifications, training on plant specific procedures and technical specifications will be incorporated into the training programs outlined in Appendices 13 G , 13 H & training (3) program Appendix 13 J, will be implemente to six (6) months prior to the license examinations This training will cover all the HCGS specific operating,, abnormal and emergency procedures, administrative and emergency response procedures, technical specifications and low power and surveillance testing procedures. Training will be covered by classroom instruction, in plant oral on the Hope Creek specific simulator. examinations, written ex sl l 630.7-2 Amendment 7
HCGS FSAR
- 8/84 t
c. Applicable references for each of the segments outlined in the appendices are shown on the appropriate cover sheet of each appendix.
Training segments which include 10CFR Part 55 Section 21, 22 d. and 23 are identified in Appendix 13A, 13C, 13E, 13F and 13G.
- e. The following segments of the training program are still under development:
Appendix I - Cold license operator in-plant training Appendix J - Pre-license examination testing and training l
- f. A course description for segments i and j of the training program is contained respectively. Appendsy GinKAppendices 13 I andof13 prov; des a desevificu J,kiff ofeMfinj on-s
. etr**ie== 4wiwi43
- g. Hot license training for NRC candidates will be conducted to augment the shift staffing allotment, This allowtraining for promotion will or fill vacancies due to reassignment.
utilize & major portion of the existing cold license l training program; however, certain areas may be waived based i on an individual's prior experience and educational background. Procedures describing the content and j$ administrative requirements will be completed by June 1985.
- h. Appendix 13F has been revised to incorporate this response.
l l l l h 630.7-3 Amendment 7
l i HCGS FSAR 4/84 l 3 l OUESTION 630.10 (SECTION 13.2) Please provide the training programs for all-management personnel, technical support staff, and other personnel contained in Figure 13.1-9 thecugh 13.1-13. We believe that Figure 13.2-1 may be modified ta include the personnel and training programs. (Ref. NUREG-0800 Section 13.'2.I) RESPONSE . 1 Figures 13.1-9 through 13.1-13 outline the organization The training for structures of the HCGS operations department. each department varies as does the training Thisfor the different training is , leyels of perso nel within each department.
.onducted as the need arises and the procedures describing the
< content of t Y pecgrams EsYcontained in the Nuclear Department Training Procedure Manual. Figure 13.2-1 reflects the initial training of plant staff personnel; however, it is our policy to provide additional training whenever personnel performance idantifies as training need.,
16 addiklow h k Mw' cal +vainiM9 retedoed h6 E*8dprso4%Ij row (TssP) M fef4 ge.( f L ewisovy ;Sidlls,g[oye4
+ke Te.cknicd
%d. wna3ewear" s kth tra a.] +n; f 4o k ; dea 4;f L (M+ \iwe. sMiou s,u.fi20YS anol seu,'or supewitovs, ke ele.wea+s ole SW 7mram %\\ %. ampfehAh&2d+m +ke-l secOwd owniver a p$ lL_ ig'_ c,4 MC of an twdtutduel l wi4k 4ke nope _ CueR WW.
Sgor diveas covered are .' L EtJQ.Ter4woley
-, tegenW g a kW klaxo< rdem+,0,ca+ ion
- Lakt QNANohS' I- , Mawapemewt* DCe.soef i
- Tecku;tal Limskra4,'on I - QA
{
?rocedecs desenbiq k conh4 d Wese. propas are. cadWxd I
ik %e k ee % p h se m iu/y / headway,u ut.}}