ML20213D563
| ML20213D563 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/05/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NLR-N86160, NUDOCS 8611120143 | |
| Download: ML20213D563 (10) | |
Text
'
' p. _
4 Public Service Electric and Gas Cornpany Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 Vics President -
Nuclear November 5, 1986 NLR-N86160 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of PrusFia, PA 19406 Attention:
Dr. Thomas E.
- Murley, Regional Administrator Ge ntlemen:
INITI AL START UP TEST PROGRAM CH ANGES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with license condition 2.c.10 of Operating License NPF-57 and the provisions of 10 CFR 50.59, Public Service Electric and Gas Company (PSE&G) is submitting 39 copies of the changes made to the Hope Creek Initial Start-up Test Program.
This program is described in Chapter 14 of the Final Safety Analysis Report (FSAR). contains a description, justification, and summary of the 10 CPR 50.59 safety evaluation for each change. contains associated marked up FSAR pages incorporating these changes.
Per the requirements of 10 CFR 50.59, paragraph (a)(2), none of these' changes involve an unreviewed safety question.
The 10 CFR 50.59 safety evaluations on file provide the basis for this conclusion.
If you have any questions in regard to this matter, please do not hesitate to contact us.
Sincerely, Attachment
!I 8611120143 86ADOCK 05000 54 PDR pg P
.?
- +:
.:.~
Dr. Thomas-E. Murley 2
11-5-86 C.
Mr.
D.
H. Wagner USNRC Licensing Project Manager Mr. R. -W. Borchard t USNRC Senior Resident Inspector Mr. J.
M. Taylor Director - Inspection and Enforcement
A 7
4 6
' ATTACHMENT l'
- Description'of Change
-FSAR-Sections 14.2.12.3.12 (Reactor Core Isolatibn Cooling
- (RCIC) System), l'4.2.12.3.13 (High
- Pressure Coolant Injection
- (HPCI). System),'and'FSAR Figure 14.2-5.(Test. Schedule and Conditions).have been revised.with the following changes:-
i): 1FS AR Sections ~14. 2.12. 3.12 and 14. 2.12. 3.13 were. revised tof clarify and distinguish between HPCI/RCIC tuneup and demonstration tests..These. changes-are.in addition to previous changes made to' these sections which weref sent to the NRC in a submittal dated July-21, 1986.
The
.. changes corresponding to this submittal are encircled and highlighted on the. attached-marked up ESAR-pages 14.2-165 and-14.2-167.
These changes to-both pages are summarized below.
The word " verification" was added to the last sentence of the first paragraph.
The phrase "and verify" was inserted into the first sentence of the second paragraph.
The word " hot"-replaced " cold standby" in'the first sentence of the second paragraph.
The second and third sentences of the second paragraph _ were Jmoved.to the end of the third
~
paragraph.
The first sentence of the fourth paragraph was modified to read as follows:. "After'the auto start portion of certain of the-above tests is completed, and while the= system is still; operating, small-step disturbances in flow demand are' input (in manual and L
automatic mode) in order to demonstrate -satisf actory response with the final control system -settings."
i
- 11) FSAR' Sections ' 14.2.12.3.12 and 14.2.12.3.13 were modified to show an approximate pump discharge pressure range above the reactor pressure vessel (RPV) pressure L
during Condensate Storage Tank (CST) to CST (HPCI and
[
RCIC) injection testing.
The changes corresponding to this revision are encircled and highlighted on the
'L
-marked - up. FSAR pages 14.2-164 and 14.2-167.
These changes to both pages are summarized below:
In-the last paragraph of page 14.2-164 and the first paragraph of 14.2-167, the pump discharge pressure during HPCI/RCIC CST injection tests is throttled to be "approximately 100 psi to 250 psi above reactor pressure," not "100 psi above reactor pressure."
e iii) FSAR ~ Figure 1' 4.2-5, entitled " Test Schedule and
^
4 Conditions,". was. revised to document-the performance of
.HPCIitests during. Test 1 Condition 1-(TC-1) and TC-2.
-This revision consisted of adding "x"'s to the test condition columns TC and TC-2 for Test #13 (HPCI Testing).
-iv)lFSAR Figure-14.2-5 was~ revised to show the possible performance of;HPCI. testing during TC-5'and TC-6.
This
-revision consisted of adding."x"'s-to test condition columns-TC-5 and TC-6 for Test #13 (HPCI. Testing) and also adding Note #28, which states "HPCI. testing, if.not previously perf ormed."
Reason for Changes i) 'This change distinguishes between HPCI/RCIC controller tune up and demonstration. tests.
Station tune up procedures provide for HPCI/RCIC controller adjus tments.
These are followed by Power Ascension Tests which demonstrate acceptable system response.
- 11) This change specifies a pressure range for CST to CST testing used to simulate HPCI/RCIC injection into the reactor pressure vessel.
Testing experience has shown that a range of pump discharge pressures is more appropriate for the present system capability.
iii) This: change to FSAR Figure 14.2-5 indicates that HPCI tests were run in TC-1 and'TC-2.
These tests are in addition to the planned testing'and were performed to demonstrate satisfactory system response following tune up' adjustments, which.were.made after the completion of TC-Heat Up testing.
The additional tune up adjustments were made in preparation for HPCI tuning at TC-3 and affected turbine ramp rate and hydraulic control.
iv) This change revised FSAR Figure 14.2-5 to show the possible performance of HPCI testing during TC-5 and TC-6.
With the deletion of the turbine trip test at TC-3 (part of'the NRC approved Test Reduction Program) there are no planned scrams until TC-6.
Consequently, the demonstration test at 200 psig which was planned for performance at TC-3 during the startup following the turbine trip test will now be performed during a startup later in the program.
The next planned startup (after TC-3) is during a scram recovery in TC-6.
Figure 14.2-5 was marked in both TC-5 and TC-6 for HPCI Testing in order to perform the HPCI demonstration during any startup.
Note #28 was also added for clarity.
10 CFR 50.59 Safety Evaluation Summary The following is a summary of the safety evaluation conducted pursuant to 10 CFR 50.59 for these changes.
Paragraph (a)(2) of 10 CFR 50.59 requires that the following 3 questions be responded to in order to determine if an unreviewed safety question is involved.
m sl.
Does the proposed change _inc~rease the probability of'
. occurrence or the consequences of an. accident or malfunction
- of equipment related to safety, as previously evaluated in
'the FSAR?
, i) ~ _ No. _ The _ proposed changes are ? for clarification only and do_ not impact system-design or operation. = :Therefore, they.have no impact on plant safety.-
11)_No.
.The addition of the throttling-pressure range (approximately 100 to 250 psi above~RPV pressures) will not impose any consequences or malfunction to.other~
safety equipment.
The upper limit (1250 psig) of the pressure. is less than the design pressure of HPCI/RCIC systems;(1375 and 1350 psig respectively).
iii). No.-
On the contrary, demonstration tests during TC-1 and TC-2 provide added assurance regarding the proper performance of the HPCI system.
iv) No.-
The design or' operability of the HPCI system is not modified.. Tuning this controller in TC-3 (the least stable test condition for HPCI) willl assure stability of-the system during _ operation at 200 psig).
2.
Does the proposed ' change create a. possibility for an accident or malf unction of a. dif ferent type than any evaluated previously in the FSAR?
(1-iv)
No.
The proposed - FSAR changes do not alter test methodology-
~
nor the analysis already provided in the FSAR.-
3.
Does the proposed action reduce the margin of' safety as defined in the basis for any Technical Specifications?
- (1-iv)
No.
There is no reduction in margin of safety defined by the plant technical specification basis because there is no change in the HPCI/RCIC performance requirements 'or design assumed in the basis statement.
Since the responses to these three questions is no, these changes do not involve an unreviewed safety question.
- ' " ' * * " - -~~,4 m
a,sy,-g,_
g s
h 1
I t
t i
L ATTACHMENT 2
+
i l
t f
P l
4 t
6 L
6 b
k L-~-_..,..,._,
DMV.
W
~~
\\
I I
i 2.
The LPRM gain adjustment factors calculated by the independers method and the process computer shall not differ by more than the value specified in the GE startup test specification.
14.2.12.3.12 Reactor Core Isolation Cooling System a.
Objective The test objective is to verify the proper operation of the RCIC over its required operating pressure range.
b.
Prerequisite Fuel loeding has been completed and sufficient nuclear heat is available to operate the RCIC pump.
l Instrumentation has been installed and calibrated.
c.
Test Method
)
The RCIC system is to be tested in two ways:
l 1.
By flow injection into a test line leading to the condensate storage tank (CST), and 1
2.
By flow injection directly into the reactor vessel.
The set of CST injection tests consist o'f manual and automatic mode starts at 150 psig and near rated reactor pressure conditions.
The pump discharge pressure during these tests is throttled to be 100 psi Tprein&$l) f l
l l
14.2-164 Amendment 14 l
above the reactor pressure to simulate the largest espected pipeline pressure drop.
This CST testing is done to demonstrate general system operabil
-?ic; speed controller W fu m easte'ee4 pertam -
Reactor vessel injection tests follow to m:-J10t: t w
N
,, N T
controller N and to demonstrate automatic startina tram n' ;10 ;t: O. condition.1 cola'as-
- eerined as a minimum 72-hours without-any kind of RCIC ioperation.
Data will be taken to determine the RCIC
/
?high steam flow isolation trip setpoint while injecting iat rated flow to.the reactor vessel.
d j
e After all final controller and system adjustments have j
been determined, a defined set of demonstration tests 4
must be performed.
Two consecutive reactor vessel j
injections starting from cold conditions in the automatic mode must satisfactorily be performed to i
demonstrate system reliability / 7:11:uing th::: t :ts, and g
a set of CST injections are done to provide a benchmark forcomparisonwithfuturesurveillancetests..(_
After the auto start portion of certain of the above tests is completed, and while the system is still operating, small step disturbances in :;::f Idf flow bi
-esamond are input (in manual and automatic mode) in order to demonstrate satisfactory vnp4 M 2 It"ilit1 This is to be done at both low (above RAeceiniG minimum turbine speed) and near rated flow initial : ceded /3/sha conditions to span the RCIC operating range.
suin f.
~
e s kly ta k e
/
\\
A demonstration of extended operation of up to two
/**1 hours (or until t:rbin: Oil t :e:::ture 1:
t:biliz:d)
" An tiu s e,'c of continuous running at rated flow conditions is to be reuh e d o,,
scheduled at a convenient time during the startup test 46 6 /
/,b,'t 3 og i
p hat o I,,w 6,',,,
Depressing the manual initiation pushbutton is defined i as automatic starting or automatic initiation of the dee e.icu%hre/l. RCIC system.
d.
Acceptance Criteria Level 1:
i 1.
Following automatic initiation, the pump discharge flow must be equal to or greater than rated flow as specified in Section 5.4.6 within the time l
specified by the GE startup test specification.
l 14.2-165 Amendment 15 l'
u
=_.
By flow injection into a test line leading to the condensate storage tank (CST), and
^
2.
By flow injection directly into the reactor vessel.
The earlier set of CST injection tests consist of manual and automatic mode starts at 200 psig and near rated reactor pressure conditions.
The pump dincharae s pressureduringthesetestsisthrottledtobe400 psi"!f((g,~
I_
K 34W5 above the reactor pressure to simulate the largest expected pipeline pressure drop.
This CST testing is done to demonstrate general system operabili_t o
=ching speed controller dj;:t :nt:. fua A (ge** '85 7
% eid *
- g F
g er Reactor vessel injection tests follow to..-,1;t: t6e~/hE7 "b
controller ^ed4we4mente and to demonstrata automatic S
- g '
startir,a from a' q Id =' rfhr condition.
. Cold" is
!) defined. as a min:. mum-72 hours without 'any kind of HPCI l operation.
Data will be taken to. determine the HPCI
,high steam flow isolation trip setpoint while injecting.
lat rated flow to the emactar v====1J + Depressing tne i
manual initiation pushbutton is definsd as automatic starting or automatic initiation of the HPCI system.
After all final controller and system adjustments have
~;
been determined, a defined set of demonstration tests
~
must be performed.
Two consecutive reactor vessel injections starting from cold conditions in the
{
automatic mode must satisfactorily be performed to i
demonstrate system reliability 4 Tellering th::: t::t=, and ;
a set of CST injections are done to provide a benchmark I
for comparison with future surveillance tes,ts.
=
After the auto start portion of certain of the above tests is completed, and while the system is still 4emmene are input (in manual and automatic modes {Joperatin in order to demonstrate satisfactory 7,,p- + ~Ai '
ensem4
- ;::5:P;)
l
-etain Mey, This is to be done at both low (above wefsW minimumturbinespeed)andnearratedflowinitialb conhwbsfahm conditions to span the HPCI operating range.
I g,g;, g, A continuous running test is to be scheduled at a i
convenient time during the startup test program.
This demonstration of extended operation should be for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until steady turbine and pump conditions are reached or until limits on plant operation are i
[
encountered.
l 14.2-167 Amendment 15 i
7 y
I-
.O?
w 1
Q.'
TEST OPEN HEAT Test cond tes
- m sdant
' g21) Perfonned air.ing co.oldown g
Test =AMs i
a 3
4 5
.onet.on on F
,e i424 y,,,,,
. f-men e-Q) Perform Tea 5. tening of 4 (221 The esa nunter correteese no 1
Chenecal and Rasachemical X
X X
X
.X selected control root in FSAR Section142.12.3m 2
Ra aren Measurenarnt X
X X
coniunction enn mescoed m a is she M test 3
Fuel Loading x
4 Full Core Shutdown Margin M
X t
(3) oyne,nec System Tea Case to '
(233 May be personned any time test t,
s Contred Rod ori.e Y
x Xal Xm Xol be conoted buu.en met
- _ penn.t.
lt 8
SRM Personeance X
)(
conditons 1 and 3
(
3 1RM Performance X
.X
. !?4) RC8C teming if not previously g g,,,dhimion 9
LPRM Caltration X
X X
X Insta perfonned 10 APRM Casibration X
X X
-X X
X 11 Proces Conyuser X
X2 X
X W Between 80 and 90 pueont IAN Q
Th eeIJ s4.tdewe 12 RCIC \\
X X 88 g
M thennel power, and near 100 '
13 HPCI X
ggy ggy X
E g s*
gj f perant core flow gg,,, g g,,ggg gg 14 Teno X
XM X
,,, f
- 16) Men FW Runout Caesbility and erf'oew8j g"#**)
14 Water Lowet Ref Leg Temp X
X X
Reen Purno Runbeca neset 15 Syseem Empenson X
X X
X X
hame aiready been e compen.'ed 44g,,
17 Core Performonu X
X X
X X
X 13 Steam Production X
D) Reettor powerluemmen 80 and Oe= tes f ce=de'Me=
90 percent 20 Pressure Regulator X
X X
X X
X h
(8) Reactor p between 46 set 21 Feed Sys-Setpome Changes X
X X
X X
X X
86 percent and 75 and 90 percent 21 Feed Sys - Loss FW Heating 5
(M) M ermeJinM X3 21 Feedester Pump Tno X's!
(9) Deleted fren t' aid' f *(Eroeit'd Yo yP'E *T Turbine va Sunsei X 8BI Xt c,
. (10) At manimum power ther will not
/
23 MS3V Functanet Test X
X(lil 23 MStV Fadileciation offreIins6a(y Jg *!.
X (11) Perform between test conditions 24 Resef valves X, X DOI XM XM 1 and 3
(*cac40e p ede c.
I 25 Turb.no Tno and Load ReMion XN' XH73 M
26 Shutdown Outade CRC X
X M2) Mal d $p be fedee**d 27 Recyculation Flow Conts XH88 X(185 (13) Deleted
- 1*
- f '* * * [ ' * ' '
'8 28 Recre - One Pump Trip X
X 9ec.6er was oc pal te -
28 flPT Trip -Two Pumps Xt195 (14) Between nest conditions 2 and 3 28 Recrc 5ystem Performance X
X X
X 1
P
.gy g y, 23 Recire syg, c;;,m; (15) Turbine trip, withir, bypass valve capacity. leej eta.
g g
XUg 30 Los of 0%e Per sg y
X (16) Deleted I
M ppcy 4cif78 *p n i 31 Pipe vibration X
X X
X X
X 29 Racire Flow Cal.bration X
X (17) Load reiection fredewly perfo aed*
XQ13 (18) Between test conditens 5 and 6 r 34 Orywes and Steam Tunnel Cooling X
X X
X X
f191 >50% power and >95 core flow 35 Gaseous Radweste X
X X
38 SACS Performance
. X X,,j (20) Check SRV operability å gg y,9 gpy g
g 40 Conf.evnetary in-Pian Test X
y c,,s,oo,r,t,,C,RE,EK,o, y
x maror cam testa
,,7 Fusat sartTv Meatysts maronT r
TEST SCHEDULE AND COMOITIONS
- J FIGUnE 14 2 9 Asnene a g5 etT5 G
~-.-----i.
~~~"-
9
c m
REC 5tygg.ngg79,,,
1986 !;0y -7 M O 55 th
+
1 k
i
{
i s
t 3
8 h
l o...
., _ - -. - _