ML17221A509
| ML17221A509 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 11/16/1987 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17221A508 | List: |
| References | |
| NUDOCS 8711200348 | |
| Download: ML17221A509 (62) | |
Text
APPLICABILITY SURVEILLANCE RE UIREHENTS 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25li of the test interval, and b.
A total, maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
a
(
boo QLuD
~i'.0.3 Performance of a Surveillance Requirement'within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
4.0.4 Entry into an OPERATIONAL MODE.or other specified applicability condi-tion shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
The provisions of Specification 4.0.4 are not applicable to the performance of surveillance activities associated with fire protection technical specifica-tions 4.3.3.7.1, 4.3.3.7.2, 4.7.11.1, 4.7.11.2 and 4.7.12 until the completion of the initial surveillance interva. associated with each specification.
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~ 0 ~ Surveillance Requirements forQinservice inspection and testing of ASME Code Class 1,
2 and 3 components shall be applicable as ollows:
a.
[Inservice inspection of ASNE Code Class 1,
2 and 3 componentsQand inservice testing ASME Code Class 1,
2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50,'ection 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection Pand testing/activities required by the ASME Boiler and Pressure Vessel Code ind applicable Addenda shall be applicable as follows in these Technical Specifications:
ST.
LUCIE - UNIT 1
~ 3/4 0-2 Amendment No. g$. 40 87 ii200348 87iii6 s
PDR ADOCK, 05000335
,PDR
4.0e5 (Continued)
ASME Boiler and Pressure Vessel'Code and applicable Addenda terminology for inservice PsnspectioQn and testin activities Required frequencies for performing inservice Lrnspectiongand testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days C.
d.
The provisions of Specification 4.0.2 are applicable to the above required frequencies f'r performing inservice inspection and testing activities.
Performance of the above inser viceDnspection)and testing activities shall be in addition to other specified Surveillance Requirements.
e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
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of ~e i~"hr a ([acr(iectnons, A<<c 4ieins ro'i% Isrcorne. dporr) op g~bh g~~fOVO'i O~ )pl ge'bf rbC1 g-g-al,
REACTIVITY CONTROL SYSTEMS 3 4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN-LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron fnjectfon flow'paths and one assocfated heat tracing circuit shall be OPERABLE:
a 0
A flow path from the boric acid makeup tank via either a
boric acid pump or a gravity feed connectfon and charging pump to the Reactor Coolant System ff only the boric acid makeup tank fn Specification 3.1.2.7a fs OPERABLE, or b.,The flow path from the refueling water tank vfa either a
charging 'pump or a high pressure safety injection pump*
to the Reactor Coolant System if only the refueling water tank fn.Specification 3.1.2.7b fs OPERABLE.
APPLICABILITY:
NODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
At least once per 7 days by 5&I R.~h~w-pa &-requfred-for-bor on-4njection-through'oast-one-complete-eycl~
fful-1-travel,and Aerffyfng that the temperature of the heat traced portion of the flow path fs above the temperature limit line shown on Figure 3.1-1 when a flow path from the boric acid make-up tanks is used.
Amendment No. p g, 8i 3/4 1-8
(a) the RCS pressure boundary does not exist, or (b) no charging pumps are operable.
In this case.all charging pumps shall be disabled, and heatup and cooldown rates shall be limited in accordance with Fig. 3.l-lh.
ST.
LUCIE >> UNIT 1
REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:
a
~
b.
Two flow paths from the boric acid makeup tanks via either a
boric acid pump or a gravity feed connection, and a charging pump to the Reactor Coolant System, and The flow path from the refueling water tank via a 'charging pump to the Reactor Coolant System.
APPLICABILITY:
MODES.1, 2, 3 and 4.
ACTION:
With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths'o the Reactor Coolant System to OPERABLE status within 72
'ours or make the reactor subcritical within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and borate to a
SHUTDOWN MARGIN eouivalent to at least 2X b,k/k at 200'F; restore at least two flow paths to OPERABLE status within the next 7
days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required Flow paths shall be demonstrated OPERABLE:
a.
At least once per 7 days 'by) Bee <.Oonlnaee)on pea(Tsaqei ewer-ep h~
. N-Ih ST.
LUCIE - UNIT 1
3/4 1-10 e'mendment No. g g
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS Continued)
(a..eanhw~a6')
~
vpurifying that the temperature ot the heat traced portion of the flow path from the boric acid makeup tanks is above the temperature limit line shown on Figure 3.1-1.
b.
c At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, At 1east once per 18 months during shutdown by(
M Cyc14ng-each-'pew'-epe~e~x&~~g-a~4em 4h~ ~&4-Ct 4
'-pW
-throu nee-eomr&ete-eyrie-oi-$ u%trav~
verifying.that each automatic 'vaIve,in the flow path actuates to its correct position on a Sa,ety Injection Actuation signal.
yv ST.
LUCIE - UNIT 1 3/4 l-ll
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP -
SHUTDOWN LIMITING CONDITION FOR OPERATION
.3.1.2.3 At least one charging pump or one hfgh pressure safety infection pump* fn the boron infection flow path required OPERABLE pursuant to Specifi-cation 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no char ging pump or high pressure safety infection pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one of the required punps fs restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.3 At 1 east the above required War~ng PumpSorh4gh-pressure-s+fe4y-ene+
WecQon-pump. shal 1 be demonstrated OPERABLEq~as4-onae-p QMcnfquqBee~ig f>>>P Boys a.)40
-Sta~n~&ess-already-opem44n~he-pump-from-the-contr ol- <<~< 9)<~~"
~QG~
@en cr pe) ko 9b )pm or Yr e.hen
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Vev+$y%ig-pump-operation-f'o r-at~~l~a4n&~~nd pr~<ota sq 4<
iA ego, pm h88Gp
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Ver+Cy4ng-tka4-4h wer-
-$rom-an-OPERAS'-em~enay-bus a Eo4ihead of (gag(~ Vhhn aC gll0.
p~ zgfl pt, mhaa
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(a) the RCS pressure boundary does not exfst, or (b) no charging pumps are operable.
In this case, all charging pumps shall be disabled and heatup and cooldown rates shall be lfmfted fn accordance with Ffg. 3.1-lb.
ST.
LUCIE - UNIT 1 3/4 1-12 Amendment No. 5 0.81
4
REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
~
0 r
r With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least, two charging pumps to.OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
~
SURVEILLANCE REQUIREMENTS g >0'>Pglng 4.1.2.4, At least two. charging pumps shall be demonstrated OPERABLE<~
Zeal-once-per-%-days-on-a SNGGERED-TEST-BASIS-by:- %e~q+ t um p IIedqs, a:
phd roV< op gKa4c %door Qub+o tloqpm <4w4esY+ putsuoo) HsiINx'L(tNEm90+,
a Starting-(unIess-already-operaC4ng)-each-pump-from-the-control.
room
, and-Verifyi.ng-that-each-pum~per atesMor-at-1-east H-minutes..
ST.
LUCIE - UNIT 1 3/4 1-13
REACTIVITY CONTROL 'SYSTEMS BORIC ACID PUMPS - SHVTDOMN "LIMITING CONDITION FOR OPERATION 3.1.2.5 At. least one boric acid pump shall be OPERABLE if only the flow path through the bor ic acid pump in Specification 3.l.2.la above, is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no boric acid pump OPERABLE as required to complete the flow path of Specification 3.1.2.1a, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until at least one boric acid pump is restored to OPERABLE status.
SURVEILLANCE REgUIREMENTS T
4.1.2.5 AtMe~:the above required boric acid pump shall be demonstrated OPERABLE~ ~
Cd~ by(
~Starting (unIe-ssa1rea-dyopera-tkng) the p ump -trom--th'econtrw-'1 r-ooQy-I gerifying, that on recirculation flow, the pump develops a
discharge pressure of ~ 75 psigi, ance-Les>~h qorsoonk 4 5@,~~),~qog VeH+jing-pump-oper ation-forat 1 east-lh-minutes-..
ST. LUCIE - UNIT 1 3/4 1-14
REACTIVITY'ONTROL SYSTEMS BORIC ACID PUMPS OPEPATING LIMITING CONDITION FOR OPEPATION 3.1.2.6 At least the boric acid pump(s) in the boron injection flow path(s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE if the flow path through the boric. acid pump in Specification 3.1.2.2a is OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
o r
P With one boric acid pump required for the boron injection flow path(s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIRE'lENTS
-T 4.1.2.6 Act1+as4'the above required boric acid pump(s) shall be demonstrated IIPEINBIE~
Md~hyf tertin~eleee-eh eedy-ope
'-peep-prem-@he-'eeeteel
'roe~
Werifying, that on recirculation~fgow, the pump develops a
discharge pressure'f' 75 psig< end.Mih pursuank)op~,~~qg)~<~
Q.Q,5.
Vev<yi.ng-pump-operandi-on-far a4Waa-s4-W5-mmo4es ST.
LUCIE - UNIT 1 3/4 1-15
REACTOR COOLANT SYSTEM SAFETY VALVES -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 PSIA + ll.
APPLICABILITY:
MODES 4 and 5.
ACTION:
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and'lace an OPERABLE shutdown cooling loop into operation.
SURVEILLANCE REOOIREMENTS No addhiooal Surveh)ance Wget<eeo4 Ae~ Rose. r eyed b sqeilpieakioq9.0.5.
4.4:2 Tt '~~
P8%3t'E uimnerH~)~
ST.
LUCIE - UNIT 1 3/4 4-2
REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 PSIA + 1'A.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With one pressurizer code safety valve inoperaole, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE UIREMENTS Ho addheah Sirveihl(el.e 9e uirei~e4 g 4.4.3 A g-efR66 ASH r5a c r uiredbq {'
icahw> 9.0 ~
P9tABLE-
-Ã4-H'-41 ST.
LUCIE - UNIT 1
3/4 4-3
IrI
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
~
0 Valve Number 1.
V-3659 Valve Function 1.
Mini-flow isolation Valve Position l.
Open b.
2.
Open 2.
V-3660
~2.
Mini-flow isolation g-,"(.Sap ne.~t pan,<Q At least once per 31 days 4 a-S:PAGGEZC4-7E~ASZS-4y-'
Ver&'y-i~
M Pi
+Mtartc~rRm-&rcad@-operaWg-) from-~he-control-room.
~~ev&ops-a-d-i~ha ge-pvemur-e-A~1 %8-ps-iq-on
.pBC~&~4on-f-~ov4 g
Operates-ae
'tes p'f~pp'aj~tert~n9essm9ready-operat+ng+fr om-the-oontrol r oom-.
g Oev~+)ps-a-~-sc harge-pr95sup~ f~~s-i~n c+
Oper-ates for-a4-'4a-s4-1Wm~ute-s r
M t
' ~
l p
~~yc+fng-each-test~~power-operated-val-ve-in-the
~w~~thr ough-atleastone-compute-cycle-of the-fvLl trav~
ST.
LUCIE - UNIT 1 3/4 5-4
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued Verifying that each valve (manual, power operated or automa-I tic) in the flow path that is not locked, sealed, or other-wise secured in position, is in its correct position.
A KGB-~ ll d't-C ~
QielABIk 8
w-b c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
2.
Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System pressure is above 300 psig.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components '(trash racks, screens, etc.)
show no evidence of structural distress or corrosion.
ST; LUCIE - UNIT 1
3/4 5-5 Amendment No.
26
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) e.
At least once per 18 months, during shutdown, by;
- -yc~g-each-pew~
p de g-a~
11~~he.-'
~h hh eh h-l ~
~hhN
~ %
Verifying that each automatic valve in the flow path actu-ates to its correct position on a Safety Injection Actuation Signal.
2$.
Verifying that each of the following pumps start automatical-i ly upon receipt of a Safety Injection Actuation Signal; a.
High-Pressure Safety Injection pump.
~b.
Low-Pressure Safety Injection pump.
Wan(yhnq oa e hump Sech(eu?enon Ahuekor les'V Signed, (Vhe eo4ainmmt seep lsoio)i~p wahses open end 5e, re6ct.u'io4on ~ai<e.ko ~
r~$<<ii~q voo.'tt.< 4'osch, 5qsevt(qinq [+at a~Q O~kg (ohiaoho
@~ps &<hop4, sp<<alfie~
Wan?ah hhu?lop?0'heo6 on tee??euioeon foul huhen 4skh fu<<4Qn( ko Qmhf?ennui g.o,s:
- i. Hhuh-Press<<e
(???? e4> 'znlee4un pm?ss'.
q(e??ee? ~?h m e~<<)g esqi p P.
lou -~<<ssure.
?aqe4 Qp enguhhpmths
. awk4Aof8(a?
f?o>sop".
1h ST.
LUCIE - UNIT 1 3/4 5-6
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CONTAIHNEHT SYSTEMS 3/4.6.2 DEPRESSURIZATIOH Ai'lD COOLING SYSTEMS COHTAINNEHT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two indeoendent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RMT on a
Containment Spray Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.
APPLICABILITY:
NODES 1, 2 and 3*.
ACTION:
Mith one containment, spray system inoperable and all our containment fan coolers OPERABLE, restore the inoperable spray sysi m to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Mith one containment spray system inoperable and one containment fan cooler inoperable, restore either the inoperable spray system or the inoperable fan cooler to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDGMH within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIRENEiHTS 4.6.2.1 a 0 Each containment.
spray system shall be demonstrated OPERABLE:
~
~
At least once per 31 days 0
- by)yentuIA~+~
each'>vC Lwawah,pv ~opeeyed,or&kea ro >wm~qa% 44, i<A>ec.Red, gh)gl,or 0 be~
ecoreD in poshion>>~ Wi'jianH4~44~1't fN~sw<8~<oo a Cshtc iflwoiippn~gg--
g-each-spr ump-t-rom the-contro I-room; u,~y.'~l<g 2.B~ gerifying, that on recirculation flow, each spray pump develops a.discharge pressure of > 200 psig,Ui'ties'tes'i'd po(swan~
tn S~iPe 4ioq N.aB.
a
'urnpere-~e~t-+eaM-
+5-m-iaWes-,
- Applicable when pressurizer pressure is > 1750 psia.
ST.
LUCIE - UNIT 1
3/4 6-15
COHTAIfNENT S YSTEi fS SURYEELLANCE REQUIREMENTS (Continued)
M Gyc+in Yerifying that upon a recircul"tion actuation signal-,
the containment, sump isolation, valves oaken and that a.
recirculation mode flow pa6h via an OPERABLE shutdown cooling heat exchanger is establish g
aa4-cN40m suede
~~a@
I
~ 4I R-a-Ge~
og.
At least once per 18 months, during shutdown, by:
gm~m~+'~
+PctvW.
Yerifying that each automatic, valve in+
>1ou path actuates tg<its correct position on a<
faugh-Ngh&h 1 gna 1.
Yerifyi g that each spray pumo starts automatically on a
signal.
P e d.g.
At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle.
is unobstructed.
ST.
LUCIE -" UNIT 1
3/4 6-16
a W~
I d
I'J N
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION YALVES LIMITING COilDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE.
'APPLIC"BILITY:
MODES 1, 2, 3 and 4.
ACTION:
Hith one or more of the isolation valve(s) specified in Table 3.6-2 inoperable, either:
a.
Restore the inoperable valve(s) to OPEPABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected pen tration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURYEILLANCE R QUIREM NTS 4.6.3.1.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE). (c ngwvg ohnewkm aQ'T.
LUCIE - UNIT 1
3/4 6-18
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CONTAINMENT SYSTEMS 3/4.6.5 VACUUM RELIEF VALYES LIMITING CONDITION FOR OPERATION 3.6.5.1 The containment vessel to annulus vacuum relief valves shall be OPERABLE with an actuation setpoint ofv2.25 + 0.25 inches Water Gauge differential.
lm>leg ercep~$ o APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one containment vessel to annulus vacuum relief valve inoperable, restore the valve to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURYEILLANCE RE UIREMENTS Na@dhiaioh fwveh4nse 8e etetwi4o4~~
re egg b (
icon h.oJ aq]
4.6.5.1~
t nu4us-vacua
~PERABIR-
'1 p
6- ~~ ~
W p
I
(&Qercen&M&ve+uHtravel+and-that va=-ve-operation-4 notr estrmted-by-eorr os%on,&rt
,wear-or-debrm.
0.
~gucgl T4Ilcf
%t least once per 3 years 4y verify~ that thevalves open fully within 8 seconds at 2.25 + 0.25 inches Water Gauge differential.
ST.
LUCIE - UNIT 1 3/4 6-26 P
3/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLEyuihhlig se%lMp o,s, s~ifled ih a+le. 9. l-l.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
Mith both reactor coolant, loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4, 1ll,P vlsQ~ OP~iflGK4p $.Q,Q o,t'p fM)gpgI~Q SURVEILLANCE RE UIREMENTS no cukhiaM) ~o<vmoone'immcnts 04 ash v
all b pl na'iO o 4.7.1.1 p,
emo
-ed
'~4-the-ASME-BAMraa Z&~9a4-ENC
'T.
LUCIE - UNIT 1 3/4 7-1
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PLANT SYSTEMS AUXILIARYFEEDWATER'SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two motor driven feedwater
- pumps, and b.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven pumps and one capable of being powered by an OPERABLE steam supply system) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILL'ANCE RE UIREMENTS 4.7. 1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once er 31 days by:
Venf
)e ~)
1.
9-eaN~um~~b~
2.
erifying that] ~
'Each motor driven pump develops a discharge pressure of > 1342 psig on recirculation flow~ ca@
-t+
'Qe steam turbine driven pump develops a discharge pressure of > 1342 psig on. recirculation flow.*
- When not in MODES 1, 2 or 3, this surveillance shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering MODE 3 and prior to entering MODE 2.
ST.
LUCIE UNIT 1 3/4 7-4 n~0nt Ho ~. 35
PLANT SYSTEMS SURVEILLANCE RE UIREHENTS (Continued g
IH h~
p>>p I'a+Qg-each-t~;-ab:Fe-power-open%ed-e~Ce 4h~~
I -4h lt~
-AA-'lMmveL uses I'$
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct posi tion.
b.
At least once per 18 months during shutdown by,'eying-eaeh-
-powar-operated-valve-i+-@he-Mow-path-tha4-is-not-testabl.e deAg-pRnt-8 pe*a8e~treugh-at hast-pne-comp).etc-'eyQe-af 4uAMmvaL,hand.
2.
Verifying that each automatic valve in the flowpath actuates to its correct position upon receipt of.the Auto Start actuation s)gnal.
A Verifying that each auxiliary feedwater pump starts automatically as designed upon receipt of the Auto Start actuation%i gnal.
ST.
LUCIE - UNIT 1
Amendment No. 37
lt tt
PLANT SYSTEMS MAIN STEAN LINE ISOLATION VAI VES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
MODE 1
MODES 2 and 3
With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in HOT SHUTDOWN within.he next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With one main steam line isolation valve inoperable, sub-sequent operation in MODES 1, 2 or 3 may proceed after the inoperable valve is restored to OPERABLE status or the isolation valve is maintained closed; otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURYEILLANCE RE UIREMENTS 4.7.1.5 Each main steam line isolation valve that is open shall be demonstrated OPERABLE byI Venqqiq pe bceuf w~%4 4.0 seQenm~
~'hest'tes4 pursue.nt ko S,peefiehioh q g,g, I
d.
/
eV-SWNB each-lactea-sh~own-except th
~er~~ays..
ST.
LUCIE - UNIT 1
3/4 7-9
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING tlATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by)
- }~S4ar~g-(e~s-s-a-lady-ope~g-each-pump~~e
-coatroom.
I
-Ph
'Pp' I-h I
8 h
h IIp~ p~
-abided f'-ro~hemanufzcturer~Pump-Per4onaanc~uce
'ph hp I
p H
P PP'Pp'phh~p'~hhh-\\'ower-from-sep~e-QPGQBLE-emergency-busses P'g ~~II p
p I
Php -~.P Ih P.
Verifying that each valve (manual, power operated or automatic) servic'ing safety related equipment that is not
- locked, sealed or otherwise secured in position, is in its correct position.
ST.
LUCIE - UNIT 1
3/4 7-14
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.
At least once per 18 months during shutdown, by~(
h-p P
d4 l<<D<<
':'~d qA N i d
<<%F Verifying that each automatic valve servicing safety related equipment actuates to its 'correct position on a
Safety Injection Actuation Signal.
ST.
LUCIE - UNIT 1
3/4 7-15
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~ t PLANT SYSTEMS 3/4.7.4 INTAKE COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent intake cooling water loops, shall be OPERABLE..
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one intake cooling water loop OPERABLE, restore at leas. two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I I
~ ~ )'1 SURYEILLANCE RE UIREMENTS 4.7.4.1.
At least two intake cooling water loops shall be demonstrated OPERABLE:
3 1:
p 31 3 y 33333~3 byi 3 A'~3~'
J-3 H conCW~oom
'-APN P-p p-d ~
3 9~~"3 333 '3~3 meed-f rom-@he-man&ac4urer
's-P-ump-$ '-er4omance C~e.
'A~
3-p ~ d~
'pp~~
power-%rom-separa4e-QRKRABhE-emergency-busses p~
S&PV+6+A
~d corn/eke-c V'erifying that each va1ve (manudal, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
ST.
LUCIE - UNIT 1
3/4 7-16
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.
At least once per 18 months during shutdown, by)h
~g gH p
d-f ~d'
'd q~ t-tl>>l bl dur4n~at-opem4Ao~hrough-a4W+as4-one-com~e
~
~
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Xerifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection Actuation Signal.
ST.
LUCIE - UNIT 1
3/4 7-17
~
~ -
p
e REACTOR COOLANT SYSTEM BASES 3/4.4.2 and'3/4.4.3 SAFETY VALVES (Continued)
During operation, all pr essurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.
The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERE'LL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no c'redit is taken for a direct reactor trip on the, loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.
Demonstration of the safety valves'ift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code~ 1-g74-EcV~en 3/4 4 4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydrauli-cally solid system and is capable of accommodating pressure surges during opera-tion.
The steam. bubble a'iso protects the pressurizer code safety valves and power operated relief valve against water relief.
The power operated relief valve and steam bubble function to relieve RCS pressure during all design transients.
Oporation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer-Pressure-High signal miniaizes the undesirable opening of the spring-loaded pressurizer code safety valves.
The required pressurizer heater capacity. is capable of maintaining natural circu1ation sub-cooling.
Operability of the heaters, which are powered by a diesel generator
- bus, ensures ability to maintain pressure control even with loss of offsite power.,
3 4.4.5 STEAM GENERATORS One OPERABLE steam generator provides sufficient heat removal capability to remove decay'heat after a reactor shutdown.
The requirement for two steam generators capable of removing decay heat, combined with the requirements of Specifications 3.7.1.1, 3;7.1.2 and 3.7.1.3 ensures dequate decay heat removal capabilities for RCS temperatures greater than 325 F if one steam generator becomes inoperable due to single failure considerations.
Below 325'F, decay heat is removed by the shutdown cooling system.
l The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspec-tion of steam generator tubing is essential in order o maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical demage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
ST.
LUCIE - UNIT 1 8-3/4 4-2 Anent-.,ent No. gg, g7, 5 6
ATTACHMENT2 EVALUATION As required by IO CFR 50.55a(g), FPL updated the Inservice Inspection (ISI) and Inservice Testing (IST) programs, together with proposed Technical Specification amendments for St. Lucie Unit I, to the requirements of the l974 Edition through Summer l975 Addenda of the ASME Boiler and Pressure Vessel Code.
The ISI and IST programs were submitted to the NRC in July and September of l977.
On December 20,
- l977, the NRC granted
- relief, on an interim basis,'ending completion of a detailed review of the programs.
On April 2, l985, the NRC issued a safety evaluation on the St. Lucie Unit I IST Program, and, in particular, the requests for relief from regulatory requirements applicable to the program.
The proposed amendments which were submitted in l 977, removed reference to a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code for inservice testing and, instead, proposed a new Specification 4.0.5 addressing Surveillance Requirements for inservice inspection and testing.
The subject revised amendment maintains a similar format as was originally submitted.
Differences which exist between the original l977 submittals and the revised submittals are a result of using a more recent revision of the Combustion Engineering - Standard Technical Specifications (CE-STS).
The following Specifications are either added, revised, or deleted with respect to the St. Lucie Unit 2 Pump and Valve Testing Program:
S ification Revison 4.0.5 New Specification 4.0.5 is added to specify the pump and valve test requirements.
This addition reflects wording in the CE-STS.
4.I.2.l.a.l 4.I.2.2.a.l 4.I.2.2.c.l Boration Systems - Shutdown Flow Paths:
The surveillance activity for testing each power operated or automatic valve in the flow path required for boron injection has been removed from the technical specifications.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
Boration Systems'-
Operation Flow Paths:
The surveillance activity for testing each power operated or automatic valve in the flow path required for boron injection has been removed from the technical, specifications.
This activity is included in the St.Lucie Unit 'I Pump and Valve Program.
Boration Systems Operating Flow Paths:
The IS month surveillance activity for cycling each power operated valve in the flow path that is not testable during plant operation has been removed from the technical specifications.
This activity is included in St. Lucie Unit I Pump and Valve Program.
MSD I /036/4
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S ification Revison (con't) 4.1.2.3 4.1.2.4 4.1.2.5 4.1.2.6 Boration Systems Charging Pumps (shutdown):
The surveillance activities of starting the pump and verifying pump operation for at least 15 minutes have been removed from the technical specifications.
This activity is included in St. Lucie Unit I Pump and Valve Program.
Also, the surveillance activity of verifying electrical power form an OPERABLE emergency bus has been removed.
The operability requirement in Modes 5 and 6 for electrical power, sources are maintained as required in the Electrical Power System portion of the St. Lucie Unit 2 Technical Specifications.
The new Surveillance Requirements refer to testing pursuant to Specification 4.0.5 (ASME Pump and Valve test requirements).
Boration Systems Charging Pumps (operating):
The surveillance activities of starting the pump and verifying pump operation for at least 15 minutes have been removed from the technical specifications.
These activities are included in the St.
Lucie Unit I Pump and Valve Program.
The new Surveillance Requirements refer to testing pursuant to Specification 4.0.5 (ASME Pump and Valve test requirements).
Boration Systems
- Boric Acid Pumps (shutdown):
The surveillance activities of starting the pump and verifying pump operation for at least 15 minutes have been removed from the Technical Specifications.
These activities are included in the St.
Lucie Unit I
Pump and Valve Program.
The new Surveillance Requirement refers to testing pursuant to Specification 4.0.5 (ASME Pump and Valve test requirements).
Boration Systems
- Boric Acid Pumps (operating):
The surveillance activities of starting the pump and verifying pump operation for at least 15 minutes have been removed from the Technical Specifications.
These activities are included in the St.
Lucie Unit I
Pump and Valve Program.
The new Surveillance Requirement refers to testing pursuant to Specification 4.0.5 (ASME Pump and Valve test requirements).
4.4.2 Reactor Coolant System
- Safety Valves (shutdown):
The reference to Surveillance Requirement 4.4.3 (Surveillance Requirement for Safety Valves-Operating) has been removed.
The safety valves will be demonstrated OPERABLE in accordance with Section XI of the ASME Boiler and Pressure Vessel Code as referenced in new Specification 4.0.5.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
MSD I /036/5
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S cification Revison (con't) 4.4.3 Reactor Coolant System - Safety Valves (operating):
Reference to a specific Edition and Addenda of the ASME Code has been removed.
The safety valves will be demonstrated OPERABLE in accordance with Section XI of the ASME Boiler and Pressure Vessel Code as referenced in new Specification 4.0.5.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
4.5.2 Emergency Core Cooling Systems ECCS Subsystems Tavg 325 F: The surveillance activities of starting both the HPSI and LPSI pumps and verifying pum'p operation for at least l5 minutes have been removed.
These activities are included in the St. Lucie Unit I Pump and Valve Program.
The surveillance activities of verifying the HPSI and LPSI pump discharge pressures; surveil lance items 4.5.2.b.l.b and 4.5.2.b.2.b have been moved to surveillance items f.l and f.2, respectively.
The new surveillance items require verification of the total developed head on recirculation flow for both the HPSI and LPSI pumps.
The original discharge pressures were used to calculate the total developed head for the pumps.
The surveillance activities of cycling each
- testable, power operated valve in the flow path and cycling each valve in the flow path that is not testable during plant operation have been removed.
These activities are included in the St. Lucie Unit I
Pump arid Valve Program.
The surveillance activity of verifying electrical power from an OPERABLE emergency bus has been removed.
The operability requirements for electrical power sources are maintained as required in the Electrical Power System portion of the St. Lucie Unit 2 Technical Specifications.
The surveillance activity of verifying that the containment sump isolation valves open upon a recirculation actuation signal has been changed from a 3 I day surveillance (4.5.2.b.3) to a new 18 month surveillance (4.5.2.e.3).
The containment sump isolation valves are tested in'accordance with the St. Lucie Unit I Valve Program and will continue to be tested on a frequency consistent with the approved Edition and Addenda of the ASME Code.
The basis for verifying these valves open on a
recirculation isolation signal every 3 I days has not been determined.
Therefore, it is proposed to perform this surveillance activity on an I8-month interval, consistent with the CE-STS, St. Lucie Unit 2 Technical Specifications and the periodic integrated test of the Engineered Safety Features.
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S ification 4.6.2.I Revison (con't)
Containment Systems Containment Spray System:
Surveillance activity 4.6.2. I.a.6 has been moved to item 4.6.2.l.a. and worded to be consistent with the St. Lucie Unit 2 Technical Specifications.
Surveillance activity 4.6.2.I.a.2 has been changed to item 4.6.2.l.b, describing testing pursuant to Specification 4.0.5.
The surveillance activities of verifying each spray pump operates for at least l5 minutes, cycling each
- testable, power operated or automatic valve in the flow path, and cycling each power operated valve in the flow path that is not testable during plant operation have been removed.
These activities are included in the St. Lucie Unit I Pump and Valve Program.
The surveillance activity of verifying that upon a recirculation actuation
- signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is estab lished has been removed from a 3I day surveillance (4.6.2.l.a.5) to a new I8-month surveillance (4.6.2.l.c.3).
The basis for the frequency of verifying that these valves open on a recirculation actuation signal and that the recirculation flow path is established every 3 I days has not been determined.
Therefore, it is proposed to perform this surveillance activity on an I8-month interval consistent with the CE-STS, the St. Lucie Unit 2 Technical Specifications and the periodic integrated test of the Engineered Safety Features.
4.6.3.I.I Containment Systems
Containment Isolation Valves:
Surveillance activity 4.6.3.l.l.a has been removed.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
4.6.3.I.2 Containment Systems
- Containment Isolation Valves:
The surveillance activities of cycling each power operated or automatic valve and cycling each manual valve has been removed.
These activities are included in the St. Lucie Unit I
Pump and Valve program.
Also, a surveillance activity has been added (4.6.3.I.3) which refers to isolation time testing of power operated or automatic valves pursuant to Specification 4.0.5.
4.6.5.I Containment Systems - Vacuum Relief Valves: The surveillance activity of verifying valve partial opening has been removed.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
Reference to Surveillance Requirements required by Specification 4.0.5 has been added.
All other changes are editorial.
MSD I /036/7
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S cification Revison (con't) 3.7.l.l Plant Systems - Turbine Cycle - Safety Valves:
Words have been added to the Turbine Cycle - Safety Valve LCO providing reference to the main steam line code safety valve liftsettings as s'pecified in Table 4.7-I. An addition to the action statement has been made to show that the provisions of Specification 3.0.4 are not applicable for entry into an OPERATIONAL MODE.
This is consistent with Table 3.7-I, Maximum Allowable Power Level - High Trip Setpoint with Inoperable Steam Line Safety Valves During Operation with Both Steam Generators, in that Startup and/or Power Operation is allowable with safety valves inoperable within the limitations of the Action requirements.
This addition is consistent with the St. Lucie Unit 2 Technical Specifications.
4.7.l.l Plant Systems - Turbine Cycle - Safety Valves:
Reference to a specific Edition and Addenda of the ASME Code has been removed.
The safety valves will be demonstrated OPERABLE in accordance with Section XI of the ASME Boiler and Pressure Vessel Code as referenced in new Specification 4.0.5.
This activity is included in the St. Lucie Unit I Pump and Valve Program.
4.7.1.2 4.7.I.5 Plant systems - Auxiliary Feedwater System:
The surveillance activities of starting each pump and verifying each pump operates for at least l5 minutes have been removed.
Also, the surveillance activities for cycling each testable power operated or automatic valve and cycling each power operated valve that is not testable during plant operation have been removed.
These activities are included in the St. Lucie Unit I Pump and Valve Program.
Plant Systems Main Steam Line Isolation Valves:
The surveillance activities of part-stroke exercising the valve has been removed.
The surveillance activity for verification of valve full closure has been reworded to show testing pursuant to Specification 4.0.5.
In both cases, these surveillance activities are part of Section XI of the ASME Boiler and Pressure Vessel Code and, therefore, are part of the St. Lucie Unit I Pump and Valve Program.
4.7.3.l Plant Systems Component Cooling Water System:
The surveillance activities of starting the pump, verifying pump discharge
- pressure, and verifying that each pump operates for at least l5 minutes have been removed.
The surveillance activities of cycling each power operated or automatic valve" and cycling each power operated valve that is not testable during plant operation have also been removed.
These surveillance activities are included in the St. Lucie Unit I Pump MSD I /036/8
~ ~
and Valve Program.
Also, the surveillance activity of verifying electrical power from separate OPERABLE emergency busses has been removed.
The operability requirements for electrical power sources are maintained as required in the Electrical Power System portion of the St.
Lucie Unit I
Technical Specifications.
4.7.4.I B 3/4.4.2 and 3/4.4.3 Plant Systems - Intake Cooling Water System:
The surveillance activities of starting the
- pump, verifying pump discharge
- pressure, and verifying that each pump operates for at least I5 minutes have been removed.
The surveillance activities of cycling each power operated or automatic valve and cycling each power operated valve that is not testable during plant operation have also been removed.
These surveillance activities are included in the St. Lucie Unit I Pump and Valve Program.
Also, the surveillance activity of verifying electrical power from separate OPERABLE emergency busses has been removed.
The operability requirements for electrical power sources are maintained as required in the Electrical Power System portion of the St. Lucie Unit I Technical Specifications.
Reactor Coolant System - Bases:
Removed reference to a specific Edition of Section XI of the ASME Boiler and Pressure Code.
MSD I /036/9
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ATTACHMENT3 NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission's regulations, IO CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (I) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated or (3) involve a significant reduction in a margin of safety.
Each standard is discussed as follows:
(I)
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The addition to Technical Specification Section 4.0, Surveillance "Requirements, is a change to achieve consistency between the St. Lucie Unit I
Technical Specifications and the St.
Lucie Unit 2 Technical Specifications.
The intent of the Specifications has not been changed.
The change incorporates the format/wording of the Combustion Engineering - Standard Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
Reference to Surveillance Requirements of a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code have been removed.
A new Specification 4.0.5 has been added to provide Surveillance Requirements for Inseryice Testing of ASME Code Class I, 2 and 3
Components in accordance with Section XI of the Code and applicable addenda as required by IO CFR 50.55a(g).
The pump and valve surveillance activities which have been removed from the Technical Specifications are contained in Section XI of the ASME Code
- and, therefore, are included in the St. Lucie Unit I Pump and Valve Program.
Requirements of the ASME Section XI Inservice Testing Program
- and, therefore, the St. Lucie Unit I Inservice Testing Program, provide for measurement and evaluation of pump mechanical characteristics as well as additional measurement and evaluation of pump hydraulic characteristics.
These activities are performed to determine pump operational readiness.
Also, requirements of the ASME Section XI Testing Program provide for additional measurement and evaluation for determining valve operational readiness.
The St. Lucie Unit I Inservice Testing Program provides a level of quality in testing of pumps and valves consistent with recent versions of the ASME Section XI Code
- and, therefore, the removal of certain pump and valve surveillance activities from the Technical Specifications does not involve a reduction in the level of quality in testing of pumps and valves at St. Lucie Unit I.
The surveillance activity of verifying electrical power from an operable emergency bus has been removed from individual specifications in that the operability, requirements for electrical power sources are maintained as required for the Electrical Power System portion of the St. Lucie Unit I
Technical Specif ications.
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The surveillance activity of verifying that the containment sump isolation valves open upon a Recirculation Actuation Signal has been changed from a 3 I-day surveillance activity to an I8-month surveillance activity. This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
As required by the St. Lucie Unit I Technical Specifications, the manual recirculation actuation signal feature is tested on an l8 month frequency as are the other manual engineered safety features.
Also, as required by the ASME Valve Program the containment sump isolation valves are tested on a quarterly basis.
A review of the surveillance activity sheets for verifying that the containment sump isolation valves open upon a recirculation actuation signal has been completed for an l8 month period from May l986 to October, l987 and no failures were observed.
The containment sump isolations valves on St. Lucie Unit I are similar to the valves on St. Lucie Unit 2 in that they are 24 inch valves manufactured by Henry Pratt.
An addition to the Turbine Cycle-Safety Valves action statement has been made to show that the provisions of Specification 3.0.4 are not applicable for entry into an OPERATIONAL MODE.
This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications.
This is consistent with the Technical Specifications, in
,that Startup and/or Power Operation is allowable with safety valves inoperable within the limitations of the ACTION requirements.
Therefore, based on the above, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2)
Use of the modified specification would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The addition to Technical Specification Section 4.0, Surveillance Requirements, is a change to achieve consistency between the St. Lucie Unit I
Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
The intent of the Specifications has not been changed.
The change incorporates the format/wording of the Combustion Engineering - Standard Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
Reference to Surveillance Requirements of a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code have been removed.
A new Specification 4.0.5 has been added to provide Surveillance Requirements for Inservice Testing of ASME Code Class I, 2 and 3
Components in accordance with Section XI of the Code and applicable addenda as required by IO CFR 50.55a(g).
The pump and valve surveillance activities which have been removed from the Technical Specifications are contained in Section XI of the ASME Code
- and, therefore, are included in the St. Lucie Unit I Pump and Valve Program.
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Requirements of the ASME Section XI lnservice Testing Program
- and, therefore, the St. Lucie Unit I Inservice Testing Program, provide for measurement and evaluation of pump mechanical characteristics as well as additional measurement and evaluation of pump hydraulic characteristics.
These activities are performed to determine pump operational readiness.
Also, requirements of the ASME Section XI Testing Program provide for additional measurement and evaluation for determining valve operational readiness.
The St. Lucie Unit I Inservice Testing Program provides a level of quality in testing of pumps and valves consistent with recent versions of the ASME Section XI Code
- and, therefore, the removal of certain pump and valve surveillance activities from the Technical Specifications does not involve a reduction in the level of quality in testing of pumps and valves at St. Lucie Unit I.
The surveillance activity of verifying electrical power from an operable emergency bus has been removed from individual specifications in that the operability requirements for electrical power sources are maintained as required for the Electrical Power System portion of the St. Lucie Unit I
Technical Specifications.
The surveillance activity of verifying that the containment sump isolation valves open upon a Recirculation Actuation Signal has been changed from a 31-day surveillance activity to an I8-month surveillance activity. This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
As required by the St. Lucie Unit I Technical Specifications, the manual recirculation actuation signal feature is tested on an I8 month frequency as are the other manual engineered safety features.
Also, as required by the ASME Valve Program the containment sump isolation valves are tested on a quarterly basis.
A review of the surveillance activity sheets for verifying that the containment sump isolation valves open.upon a recirculation actuation signal has been completed for an I8 month period from May l986 to October, l987 and no failures were observed.
The containment sump isolations valves on St. Lucie Unit I are similar to the valves on St. Lucie Unit 2 in that they are 24 inch valves manufactured by Henry Pratt.
An addition to the Turbine Cycle-Safety Valves action statement has been made to show that the provisions of Specification 3.0.4 are not applicable for entry into an OPERATIONAL MODE.
This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications.
This is consistent with the Technical Specifications, in that Startup and/or Power Operation is allowable with safety valves inoperable within the limitations of the ACTION requirements.
Therefore, based on the above, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
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Use of the modified specification would not involve a significant reduction in a margin of safety.
The addition to 'echnical Specification Section 4.0, Surveillance Requirements, is a change to achieve consistency between the St. Lucie
'Unit I
Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
The intent of the Specifications has not been changed.
The change incorporates the format/wording of the Combustion Engineering - Standard Technical Specifications and the St. Lucie Unit 2
" Technical Specifications.
Reference to Surveillance Requirements of a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code have been removed.
A new Specification 4.0.5 has been added to provide Surveillance Requirements for lnservice Testing of ASME Code Class I, 2 and 3
Components in accordance with Section XI of the Code and applicable addenda as required by 10 CFR 50.55a(g).
The pump and valve surveillance activities which have been removed from the Technical Specifications are contained in Section XI of the ASME Code
- and, therefore, are included in the St. Lucie Unit I Pump and Valve Program.
Requirements of the ASME Section XI Inservice Testing Program
- and, therefore, the St. Lucie Unit I Inservice Testing Program, provide for measurement and evaluation of pump mechanical characteristics as well as additional measurement and evaluation of pump hydraulic characteristics.
These activities are performed to determine pump operational readiness.
Also, requirements of the ASME Section XI Testing Program provide for additional measurement and evaluation for determining valve operational readiness.
The St. Lucie Unit I Inservice Testing Program provides a level of quality in testing of pumps and valves consistent with recent versions of the ASME Section XI Code
- and, therefore, the removal of certain pump and valve surveillance activities from the Technical Specifications does not involve a reduction in the level of quality in testing of pumps and valves at St. Lucie Unit I.
The surveillance activity of verifying electrical power from an operable emergency bus has been removed from individual specifications in that the operability requirements for electrical power sources are maintained as required for the Electrical Power System portion of the St. Lucie Unit I
Technical Specifications.
MSD I /036/ I 3 The surveillance activity of verifying that the containment sump isolation valves open upon a Recirculation Actuation Signal has been changed from a 3I-day surveillance activity to an IS-month surveillance activity. This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications and the St. Lucie Unit 2 Technical Specifications.
As required by the St. Lucie Unit I Technical Specifications, the manual recirculation actuation signal feature is tested on an l8 month frequency as are the other manual engineered safety features.
Also, as required by the ASME Valve Program the containment sump isolation valves are tested on a quarterly basis.
A review of the surveillance activity sheets for verifying that the containment sump isolation valves open upon a recirculation actuation signal has been
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completed for an I8 month period from May l986 to October, l987 and no failures were observed.
The containment sump isolations valves on St. Lucie Unit I are similar to the valves on St. Lucie Unit 2 in that they are 24 inch valves manufactured by Henry Pratt.
An addition to the Turbine Cycle-Safety Valves action statement has been made to show that the provisions of Specification 3.0.4 are not applicable for entry into an OPERATIONAL MODE.
This change is being made to achieve consistency with the Combustion Engineering-Standard Technical Specifications.
This is consistent with the Technical Specifications, in that Startup and/or Power Operation is allowable with safety valves inoperabl e within the limitations of the ACTION requirements.
Therefore, based on the above, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
In conclusion, we have determined that the amendment request does not (I) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.
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