ML20235S282
| ML20235S282 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/16/1988 |
| From: | Calone L LONG ISLAND LIGHTING CO. |
| To: | Lange D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20235S275 | List: |
| References | |
| NUDOCS 8903070056 | |
| Download: ML20235S282 (10) | |
Text
_.
N T7~/tc HM 64 7.3 I
Eg LONG ISLAND LIGHTING COMPANY J W. DYE, JR. TRAINING CENTER 131 HOFTMAN LANE CENTRAL ISUP, NY11722 (516)436-4000 December 16, 1988 Dave Lange Chief, BWR Section U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Post NRC Written Examination Review Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 Exam Report 88-12
Dear Dave:
i.
LILCO's Operator Training Division, utilizbig the expertise of several Shoreham senior reactor operators (SROs),. had' performed a review of the NRC
).
written examinations and answer,. keys.
, This.. review.. centered upon the SRO examination and answer key.
The attached comments, along with supporting documentation, are provided to assist you and your staff in evaluating the responses to exam questions provided by our license candidates.
If clarification is needed on any of this material, please do not hesitate to contact me at (516) 436-4046.
Very truly yours, l
Leonard J. Cal.one Hanager f Operator training Division LJC:j1 attachment y
I cc: SR2 l
8903070056 890217 CDR ADOCK 05000322{
PNU.
n
, FC-9671.1
fy 5.
Theory cf Nuc10*r Power Pimt Operation, Fluids, rnd Thermodynamics PJg3 2 QUESTION 5.01
-(3.00)
At SNPS the typical operating. parameters for a reactor feedwater (3.0) pump are: suction pressure 650 psig, discharge pressure 1050 psig, and feedwater flowrate of 5.8x10E6 1bm/hr. Since the pump has an efficiency of 80%, heat is added to the feedwater by the pump.
DETERMINE the TEMPERATURE RISE of the water passing through the feedwater pump due to the pump's inefficiency.
(show all work and state all assumptions)
CONSTANTS: density of fluid = 62.4 lbm/ft3 1 BTU = 778 ft-lbf Cp = 1 BTU /lbm-degF Pump head = delta pressure ANSWER 5.01 (3.00)
CONSTANTS: density of fluid = 62.4 lbn/ft3 1 BTU = 778 2t-lbf Cp = 1 BTU /lbm-degF Hp = Pout-Pin a.-
Pump Head-Hp = (Pout-Pin)/62.4 (0.5)
= (1050-650)x144/62.4 = 923 ft (0.1) b.
Ideal Work-Wp, ideal = Hp x flowrate (0.5) 9
= 923 x (5.8 x 10E6) = 5.4 x 10E9 ft-lb/hr (0.1) c.
Input Power-Wp, actual = Wp, ideal / efficiency (0.5)
= (5.4 x 10E9)/0.80 = 6.8 x 10E9 ft-lb/hr (0.1) d.
Power converted to heat-Q = Wp, actual - Wp, ideal (0.5)
= (6.B-5.4) x 10E9 = 1.4 x 10E9 ft-lb/hr (0.1)
Convert to BTU:
= (1.4 x 10E9)/778 = 1.8 x 10E6 BTU /hr e.
Delta T across pump-delat T = Q/(flowrate x Cp)
(0.5)
= (1.8 x 10E6)/(5.8 x 10E6) x 1.0) = 0.31 degF (0.1)
.A REFERENCE I
LP: HL-901-SH1 Lesson 3 pages 4-58 to 4-61 OBJ: HL-901-SH1 Lesson 3, CB-5 KA: 293003 K1.23 (2.8/3.1) 291004 K1.05 (2.8/2.9) 3
'~~
291004 K1.13 (2.6/2.7) 291004K113
.291004K105 293003K123
..(KA's)
COMMENT: This question appears to be beyond the scope of the K&A catalog objectives
'and LILCO Lesson Plan objectives referenced.
3-l L-.
.1 4
~
QUESTION-5.05
- (3.00)
Thei.following information was obtained from the'lastest P-1 EDIT:
6.7 APRM GAP 0.99 CNMT 1169 A.
DETERMINE..the required gain adjustment factor (RGAF).
(2.0)
(Suow ALL wokK)
B..
Based on the information above, is the reactor operating (1.0) on a limiting control rod pattern? EXPLAIN kyour answer.
ANSWER 5.05 (3.00)
A.
RGAF = FRTP/MFLPD (1.0)
MFLPD = 6.7/13/4 = 0.05 (0.5)
RGAP = (48.0/100)/0.50 = 0.96 (0.5)'
B.-
NO
- (0.5)-
The reactor is not at'a thermal limit value of LHGR (0.5)
(13.4 kw/ft is thermal limit for LEGR) 9 P
REFERENCE y
LP:' HL-904-SH1 Lesson.1 pages 10-9 I
HL-904-SH1 Lesson 3, pages 10- 28 to 10-32 OBJ:-HL-904-SH1 Lesson 1', CA-3
~HL-904-SH1 Lesson 3, CD KA: 293009 K1.09 (3.1/3.7) 294001 A1.15 (3.2/3.4) h 294001K115 293009K109
..(KA8s)
'. Answer for Part
'B' act.nal VALUE of LHGR limit -(13.4 kw/ft) should not COMMENT:
bi 'itt answer - it wasn't ASKED FOR.
+
b en, *.
y
.M k.'
_-t l+
lJ k-,
w-_--_.
I'
. DEFINITIONS FRACTION OF LIMITING POWER DENSITY.
V 1.13 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location divided by 13.4 kW/f t.
FRACTION OF RATED THERMAL POWER 1.14 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
FRE00ENCY NOTATION' 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requiree.ents shall correspond to the intervals defined in Table 1.1.
, GASEOUS RADWASTE TREATMENT SYSTEM 1.16 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup' for the purpose of reducing!the total radioactivity prior to release to the environment.
-IDENTIFIED LEAKAGE 1.17 IDENTIFIED LEAKAGE shall be:
Leakage into collection systems, such as pump. seal or valve packing a.
leaks,' that isicapt'ured and conducted to a sump or collecting tank, or y,
b.'
Leakage into the containment atmosphere, from. sources' that are both specifically located and known either not to interfere with the opera-c tion of the leakage detection systems or not to be PRESSURE E03NDAhY
(:
LEAKAGE.
ISOLATION SYSTEM RESPONSE TIME 1.18TheISOLATIbNSYSTEMRESPONSETIMEshallbethattimeintervalfro'mwh the monitored parameter exceeds its isolation actuation setpoint at, the channel sensor until the isolation valves t' ravel to their required' positions.
Times shall. include' diesel generator' starting and sequence' loading delays
- where appMcable.. The response time may be.ceasured.by any series of sequential, overlapping or total steps such that the entire response time
.is measured.
J
.13MITING' CONT'OLROD'PATTERA R
.~
1.19 A' LIMITING CONTROL-ROD PATTERN shall be a pattern which"results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value f,or APLHGR, LHGR, or MCPR.
i LINEAR HEAT GENERATION RATE 1.20 LINEAR HEAT GENERATION RATE (LHGR) sha'1 be the heat generation per unit 1
length of fuel rod. It is the integral of the heat flux over the heat transfer area ass.ociated with the unf t length.
-J v
SHOREHAM - UNIT 1 1-3 i
...._......a
QUESTION 5.07 (1.00)
Answer the following TRUE OR FALSE. Concerning the Fuel Zone (1.0) level instruments:
A.
LOCA occurs from 100% reactor power.when the reactor is at 150 psig, the indicated level will he HIGHER than actual icvel.
B.
If LPCI was injecting, the indicated level would be HIGHER than actual level.
5.
Theory of Nuclear Power Plant Operation, Fluids, and Thermodyna=ics Page 49 ANSWER 5.07 (1.00)
A.
TALSE (0.5)
(Since the instrument is calibrated at 0 psig, higher pressure would give indication of a level that was lower than actual.)
D.
TRUE (0.5)
(Since the instirument is calibrated with no je't pump flow, with LPCI injecting the indicated level would be pegged
,high.)
REFERENCE LP: HL-980-SH1 Lesson 7, page 7-16 OBJ:.HL-980-SH1 Lesson 7, CF KA: 291002 K1.09 (3.3/3.3) 295031 A2,01 (4.6/4.6) 293001 K1.03 (2.5/2.7) 293001K103 29503tA201 291002K109
..(KA's)
COMMENT:
'A' can either be True or' False since a LPCI signal exists and LPCI would be injecting at 1508 Rx Pressur%
REFERENCE:
SFF 23.201.01 ADS (LPCI shut-off HEAD 238 psig)
.Oq
\\
wS l
,YQMN L <..lWfd $5N 8%i%...nd.giWSd (iGtQ[d,@M@kCUkSIO
- t. 3 % M jEN
,[. pf Shk EdN,dN((h((O((';hh,{... 44dU% ' "f
, 4 hh 3bhidI hE ki/H,1[g({(5j,k'shC[ pressurization S M
E S g M ' W. M,, [ ~.
Mdd$)fMg
! j9 kv.NMd@n'5 g H.f$
5 T DThe1Automati'c3De
?90lFA3.51
^
o;12nftl.jnj ectioS p(HPCI)F f
T i
ikdCP.f*8'8SfIMJ.I "k f0E.1,te geagtor.'veyseh4gc f j:a, small? pip.e e-h;~b.wJ:7 primary.isystem#pThis will allow operation".ysepoofthe:LowPressu f(/;
d j;Y 41
'9/g
^
o[pkp}ayj(CS)} system.. [:3@f G%g.
'.}& k[(g[b', I9h[',InjEctili{(N h[)iisypl tem,.and/or,the:.
.A 6..
$k L '.00$
!k
? h! N kkN?k$:
&i'
' ' ~
?
f k/.rei i
h the HPCI systemiis[gyg].y,es',B21P(*RV-092 A',TBn CJ3dfhThe.fADfrvf.
agf
'ggp'd[pseven,saet h 25h[MN$[K, L)(ikt h.
$ ' $h 3
e'ven a g leyelF h h &." ] $ $
g dondlit'id$fi h'$
f'iiliM/In V
e4to'r;vaterdeVeUEn k 0: f D}851ntaidinN f'(hhhl. T
- NY ih 5"
tW h Oti1IM g$k? k
^
132;5?owith t c 3]
yessel,fRgy)
Reapctqi prespurey'yisignaIg re Intr." Mff$$f.3ff.I j
. g) iiE dlb h,dh[irmatprY ?$h$.
f%f?&h&....
Lt'.}
p $ tbh [i h
'h l
j@Wypjd2;ioy '
y.A imef$or/HPCIf t'o? start {f, an refloo r
eksjh,gaditimerexpiredf(All'ovsfgfThis timer,can(b'e[r k t,f' S[
105 ec p h T h E h,,de ay eN" s h.
b fo.hi prevention
. 3.pgp regpa.g p 4 y;,g gh$[i.'N';(5N:isicallebhhg
. jfkl1EN M hN h
h, 5Y.'M
/* lip h
m
,ge, Sp[,974pumo jrunni,ng (ong J,Dpymp,lopithf.,aidi;s.char mgmjf 3'
4
- A.
ijj gly.u33Lpsig4 ggj,ggjKHR aofPPg
(,$digg pgejhe'ad so f! app roximqQJy.E238 Kp's fgl(ppmiqs,{1
~ ~
y
~
d125 gspectivel
~C a
$hkk,g?Yh g
A b
Q n
'J !
ithSQtclUn!$$
p k y' ' 3 l
otfEh m
}
A tj" i [OWNWNTd 63
._ p
'o g g All Qqu,ipaen,t com pyn,t 1,d,gt,if cat,1oguy rs',,r,e f4 g BRI ni e
~ ~. f falPrgccedeph 91nu%gg"fl,.ygk t
(g J
$1 ptherifiseEN
. gm4 y wan g
?
yAll1 cont,ro g n4
' f 3t,ign'ep,umb,, egg cc, 3-u H1'1 nlessyspecifie ervi
(
ylthegsystem
.outrop{$khhhh?
k.. Wl f h $hN
- swi,tchesA_for. [pe,m e
- MgA11.4 581D E M M k
7
?
/
l,ocatedgtbej.;mai,n2., con oom Perated!y,alye
.a g
W@A$4h'k hM%.
Sihbk K
b M1G 3' 4 5
c res,areiprovi'd eration f; t e..
.m..
m m
YYhY ff 5
m{sormaerformance+k.z.$any; yk
~n
- a Pac u
4'
..n g
enka
. ;f 4.
gm
[Q 4
Pigngge[Sge,.
a en f
ca uggW r 4 bl,g it n -
y J:
o e
h.g,'Depres u g.
v losing the zat onxV ves..
Q n, #
... E ! M i n Sh W-aF. f%, ".e 3 3.jgy['h*C%v%>
aw u
, 4, J. (8, normaltPerformance g ~
w ggvm yg 1
1
,J h
mwunwngomae-ist h4 hu $) h 10syg gaayry gj
. g. ae op g
2' e
4 w
y w!!
s h
lf g
2Q1.0Li Re i fp. q..,,,.-!!,s. p: ? $ M(MOWWragi'2 pn g
Q:
t 2#g %q..g ; ?5;/%g5 G %,
. ~..
g
$Nbdi$p$hk$h{MINE MNb.dMNEddhN$3Mg ah@gg{jh F
3
- 1 M
S m
r~;:
' y. e a:-
" Jd f'
!p,f.:5hh; j
3IIIh$$10fh
.jip.y!,{i s
sNmh'iiS)ffis';ItNbaIb
,'s$bsif b,
tomatiy resad za te
- Tt2dMnd{hillj prkvid'ET/di!Idoma ge
'WM.H'ig I!P?E7s$re TEnElnjec (H5CI o
/
y.ePry k hj $ n{$f[tj[jrcaety f,p Q{
% % fpa$ mall ji[ %
4r 2.lprigar.yfyystem,_ gis wil allovi..op,eray,oggf/chekt.owA ressur,e. ooiant l
P h,4,Y$$gggd%6:.o jW '" h_
- &gy0 97:'mM[r(gy,,D*? k??4? kV h*
T,3N4 n;(,
egtythe'HPCI' system,
g ges.4B219 *Rg092(yA,,;or l
,9gf y
fh,d 4,
t n
e.> App ggaggsennrsafetpfe f
bleYo'f increasingp 's' o
1 ca ATY$U skotifiAibn maintaini ~
or water; ^ 'y '
!.d d ) N h.
%%4I j
I
..e M 835)iyM58,e1'(
132:5 owt,,
e irmatory4si.gna
- 1 f,
bIIdfh4d.hiby l
o CI,Jo star lo j
n
'imer.: expired (Al im E $"$6n;tro {Eo'oln
{
is timer ;,can b 're feve[ntion{$W{'E i
essel i
1s call
$ Pd ~
de' l9h mujs flop $$ N
?$?O.2 s?
' pump;}runni g fl] j [
wit se t 1
ore
$3)dP [ Sky "gRPHNN)4miMrun$i edn5'di3' ow v' j '(f n
S
,)
]
gg he'adsofiapprox
' 'eV,E21f} Mist
~ gg'a
~
jg
(
=
sQp y,
.gg;j 1
k l
Idsb
.i numbe
(
i l ltl
@E
{.
proceede'pmen
- hgM
,l en fi.c g
A11Rqui 1
l.1 1
dl 9
g u
l 3
- g..((%kI N
a n1
~. mm h
I Il
]g ri h@h
.1 SJ SP%
^[
o, cate Et$
..mai
-2.. _ _;
operate
,alyes e
p.;h jf 11 NIgg2 Jt um b
r$are2pa peration u
o-o - nce i
ml ag
-n ? & q*
Q QQ
- f}
~
li a
4 a'
-a e
ni i l
l j
w ospa g. e
- upR
- a hi
~
s e
c a
aregg y,
[kdo, noma Performance!.,
- C -
l w.
l e
- r 4
ggmine e(Wif%'M&L; - weggr1...._
t l
4 9
QUESTION 8.08 (2.00)
Concerning SP 12.035.01, CONTROL OF LIFTED LEADS AND JUMPERS:
A.
STATE WHEN a lifted Icad must have a station equipmcat
'(0.5) clearance permit (SECP) affixed.
B.
STATE WHICH on-duty personnel can grant permission for (0.5) approval or lifting of an LLGJ.
C.
A permit is not required if a jumper is installed or a lead (0.5) is lifted momentarily. DEFINE " momentarily" as used in reference to an LLGJ.
D.
STATE HOW IONG a lead can remain lifted before a permit must (0.5) be issued if the lead was lifted as a sign-off step in an approved station procedure.
ANSWER 8.08 (2.00)
A.
A lead that is normally exposed to voltages above 130 V.
(0.5)
B.
Watch Engineer or Watch Supervisor (provided the Wacch Engineer (0.5) is' kept fully informed)
C.
As long as the wire in question is intended to remain in the (0.5) worker's hand.
D.
One (1) working shift e
REFERENCE LP:. SP 12.035.01 CONTROL OF LIFTED LEADS AND JUMPERS OBJ: NONE FROM TRAINING MATERIAL KA: 294001 K1.02 (3.9/4.5) 294001 A1.02 (4.2/4.2) 294001 K1.07 (3.3/3/6) 294001 A1.03 (2.7/3.7) 294001K102 294001A103 294001A102 294001K107 (KA's)
COMMENTS:
Part C: There is no basis for this answer in the Lifted Lead and Jumper Permit procedure, SP 12.035.01.
Momentarily is not defined.
REFERENCEis SP 12.035.01 ATTACHED
.*3
LIMITATIONS (ND ACTIONS The on-duty Watch Engineer should normally grant permission for 6.1 appro' val or lifting of a LL&J. This authority may be delegated to the on-duty Watch Supervisor provided the Watch Engineer is kept fully informed of the system status. The on-duty NSO shall be kept inforced d
of LLLJ changes.
6.2 The " qualified" person who performs the verification of the correct implementation of a LL&J or proper alignment of a system prior to returning equipment to service shall possess knowledge of the particu3ar system and its relationship to plant safety.
6.3 LL&J Tag should'be placed by the workman requesting the tags.
7.0 TEST EOUIPMENT N/A 8.0 PROCEDURE 8.1 Conditions R'equiring Docum,entation
~
s A permit shali be issued prior to the placement of a' jumper or the lifting of a lead except in the. situations described in 8.1.1, 8.1.2,
'8.1.3, 8.1.41 "'
~
8.1.1 A permit.need not be issued where a jumper is installed momentarily _ to initiate a desired action and then removed, or yhgp' when a lead is momentarily lifted to initiate a desired hetion and then replaced.
a.
8.1.2
. A permit need not be ' issued where the placing of a jumper /the lifting of 's lead'and 'the subsequent. jumper removal / lead replacement are sign off steps in an approved station procedure...If the temporary condition may remain in effect for a greater period of time than one working shift a permit shall be' issued.
8.1.'3
- A permi.nced not be issued when removal of certain equipment has been authorired~hy.a HWR or, SAWS. The equipment not requiring a permit is limited to' circuit boards, recorders, controllers, or other " modular devices" which do not require alteration of permanent wiring.to remove (Removal of a
'onnector-or' disconnecting.a power cord is.not considered an c
alteration of permanent wiring)..However,if the temporary
'ondition remains in effect for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an c
information tag or HWR deficiency tag shall be hung to denote g
the temporary condition.
- ._.]
SP 12.035.01 Rev. 12 Page 3
l.
\\ 1
' ATTACHMENT 4
- NRC' RESPONSE TO FACILITY FORMAL COMMENTS-The following representszthe.NRC resolution to the-facility comments (listed in Attachment 3) made as a result of the written examination. review policy.
Comments that'were.made during the pre-examination review were. resolved prior to administering the written examination and are not. listed below.
Question 5.01: Comment NOTED. Objective CB-5 of lesson plan HL-901-SH1'(Heat Transfer and Thermodynamics) requires students to calculate feed pump work given the appropriate data and equations.
l.
Objective CB-6 of-the same lesson' plan requires the. student to calculate cycle efficiency given the appropriate data.
No change required.
- Question 5.05: Comment NOTED. All information in brackets.in the answer key is not required for full credit. Rather, it is clarifying information for the grader. No change required.
Question 5.07: Comment ACCEPTED. Question'5.07.a. was deleted from the-examination and the examination point value was' adjusted accordingly.
Question 8.08: Comment NOT ACCEPTED. The training material sent to the NRC.
for preparation of the. examination was Rev. 13 of SP 12.035.01' which specifically-defines " momentarily" in paragraph 8.1.1; The reference used for the facility comment was.Rev. 12 of.-
SP 12.035.01. No change required.
t i
s:
[~
y ATTACHMENT 5 i.
SIMULATION FACILITY FIDELITY REPORT-Facility Licensee:
Long Island Lighting Company P.O. Box 618 Wading River,.NY 11792 Facility Licensee Docket No.:
50-322 Facility Licensee No. :
NPF Operating Tests Administered at:
Shoreham Simulator Operating Tests Given'On:
' December 14, 1988 Simulator Familiarization Given On:
November 21, 1988 r
During the conduct of the simulator portion of the operating tests and/or simulator familiarization identified above, the following apparent performance t
discrepancies were observed:
Malfunction ED-27A (de-energizing 120VAC panel IC91-PNL-N1) should have.
caused a loss of the rod position indication system, RPIS (according to.
.the simulator cause and effect manual) and it did not.
Malfunction RM-03 (main steam line radiation monitor inop) should have caused the' associated overhead annunciator and the associated RPS channel to trip and it did not.
y' Malfunction FW-11B (condensate pump 'B' trip) should have caused condensate booster pump 'A' and reactor feedwater pump 'A' to trip due to low suction pressure if the malfunction occurred from 100% power.
j (according to system lesson plan HL-103-SH1) and it did not.
Overall, the simulator fidelity was acceptable.
_ _. _. _. _ _ _ _ _ _ _ =. _ _ _ _ _ _ _ _ _ _ _ _.. _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
__.__.________._____._.J
_