Text

Proposed,Deleted TS Tables 3.6.4-1 Re Containment & Drywell Isolation valves,3.6.6.2-1 Re Secondary Containment Ventilation Sys Automatic Isolation Dampers/Valves & 3.8.4.2-1 Re MOV Thermal Overload Protection
	ML20118A570
Person / Time
Site:	Grand Gulf
Issue date:	09/14/1992
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20118A569	List: ML20118A568; ML20118A570;
References
	NUDOCS 9209220069
	Download: ML20118A570 (123)
	v • d • e

. _ _

m

' Attachment 3 to GNRO 92/00117 Page 1 of 94-i Mark up of Affected Technical Specification Pages PCOL-91/17 s

v l

9209220069'920914 PDR ADOCK~05000416 P

PDR

DEFINITIONS to GNRC 92/00117 Pace 2 of 94 CORE ALTERATION fuel, sources, incore instruments or reactivity controls

1. 7 pressure vessel with the vessel head removed and fuel in the vessel.

movement of the SRMt.

Normal considered to be CORE ALTERATION.IRMs, LPRMs, TIPS, or special movable de Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe conservative position.

CRITICAL POWER RATIO

1. 8 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly w~hich is calculated by application of the ANFB correlation to cause some point in the assembly to ex actual assembly operating power.perience boiling transition, divided by the DOSE EQUIVALENT I-131

1. 9 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TIO-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

DRWELL INTEGRITY 1.10 ORWELL INTEGRITY shall exist when:

All drywell penetrations required to be closed during accident a.

conditions are either:

1.

Capable of being closed by an 00ERABLE drywell automatic isolation system, or 2.

Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, T m pi exceotj; r;.;ded ir. T;Me 3.0.01 ;f Specification 3.6.4.

I b.

The dr>vell equipment hatch is clesed and sealed, The drywell airlock is in compliance with the requirements of c.

l Specification 3.6.2.3.

d.

The drywell leakage rates are within the limits of Specification 3.6.2.2.

The suppression pool is in compliance with the requirements of e.

Specification 3.6.3.1.

f.

The sealing mechanism associated with each drywell penetration; e.g., welds, bellows or 0-rings, is OPERABLE.

GRAND GULF-UNIT 1 1-2 Amendment No. 7 3, __.

{

l l

AG#hmerit 3 to GNRO 92/00117 l

' P;.gs 3 'of 94-INSERT-t

for valves;.that are:' opened under administrative control'as-permitted by-A t

4 f

[

Temp. - High 3

'1/roce 1, 2, 3 28-is j

'85'

=
c..
Reacter Vessel Water trac 1 -' Low, Level 3***
3-2M (f-)
4. 5 31
Y o
2
.1, 2, 3
~ 28 7.
g 3( )=
f-d.
Reactor Vessel-(NIR Cut-in
. OL.
Permissive) Pressure'-
d..
gy) y
.High***
2
" 1, 2, 3 28 j
-=
III 8
e.
Drywell Pressure - High***-
3
'2 1, 2, 3 28
.f.
Manual Initiation.
3 2
1, 2. 3:
L26l to GleRO 92/00117 Page 11 of 94 TA8LE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .Be in at least HOT SH ACTION 21 Close the affected system isolation valve (s) within one hour o In OPERATIONAL CONDITION 1, 2, or 3 a.
be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months an,d in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.
In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS handling of irradiated fuel in the primary containmen,t and Restore the manual initiation function to OPERA ACTION 22 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 23 Be in at least STARTUP with the associated isolation within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 24 Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
ACTION 25 Establish SECONDARY CONTAINHENT INTEGRITY with the s treatment system operating within one hour.
ACTION 26 Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affected system inoperable.
i ACTION 27 Cicse the affected system isolation valves within one hour and declare the affected system 'noperable.
ACTION 28 Withir one hour lock the affected system isolation valves closed or verify, by remote indication, that the valve is closed and electrically disarmed, or isolate the penetration (s) and declare the affected system inoperable.
ACTION 29 Close the affected system isoittion valves within one hour and declare the atfected system or component inoperable or:
In OPERATIONAL CONDITION 1, 2 or 3 be in at least HOT SHUTD a.
within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN withi following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.
tions with a potential for draining the reactor ve ACTION 30 Declare the affected SLCS pump inoperable.
ACTION 31 Isolate the shutdown cooling common suction line within one hour if it is not needed for shutdown enoling or initiate action within one hour to establish SECONDARY CONTAINMENT INTEGRITY NOTES When handling irradiated fuel in the^ primary or secondary containment an during CORE ALTERATIONS and operations with a potential for draining reactor vessel.
SNUTDOWN or for reactor STARTUP when cond point to allow opening of the MCIVs.
condenser vacuum exceeds the trip setpoint.The manual bypass shall be remove
" Trip function commom to RPS Instrumentation.
During CORE ALTERATIONS and operations with a potential for draining reactor vessel.
With any control rod withdrawn.
per Specification 3.9.10.1 or 3.9.10.2.Not applicable to control rods removed (C
R: 0;,;;if btM
.0 ;, Tch 3.C.M fer sehe; b esch-vaM srew. A I
GRAND GULF-UNIT 1 3/4 3-14 Amendment No. 70, 97 I
7
Attachm:nt 3 to GNRO 92/00117 J
Pag) 12 af 94 TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION NOTES (Continued)
A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for l
required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter, ic) Al;; ::tuat : th: :t:r.dty ;;; tr::5:,t :y:t :
id) Also e: vete; the c ntr;l rc : :
rger.cv filt+ tien ;yet:: in th: i;;10ti:-
--d-
-1
.r

t tn.
) h o us:&ie ni Hi, one upsc6'e-h1 Hi and one ooW. scale, or two c:
.1 scale signals from the same trip system actuate the trip system and initiate isolation of the associaud containment and drvwell isolation valves.
%(g)Also trips and isolates the mechanical vacuum pumps.
Al(soad ge ted.
(h) ates secondary containment ventilation isolation d&P and valves per le 3.6.6.2-1.
(i) Closes only R stem isolation valves G33-F001, G 04, and G33-F251.
(j) Actuates the Standby s Treatment System and i es Auxiliary Building penetration of the vent ion systems wit he Auxiliary Building.
(k) Closes only RCIC outboard va A
urrent RCIC initiation signal is required for isolation to occur.
(1) Valves E12-F037A and E12-F0 re clo high drywell pressure.
All other Group 3 valves aM osed by high rea pressure.
(m) Valve Group 9 req concurrent dryvell high p ure and RCIC Steam Supply Pressu ow signals to isolate.
(n) Valves E 42A and E12-F042B are closed by Containment
. System ini ion signals.
(c) so isolates valves E61-F009, E61-F010, E61-F056, and E61-F057 fro lve nenun 7 (t) Only required to isolate RHR system isolation valves E12-F008 and E12-F009.
One trip system and/or isolation valve may be inoperable for up to 14 days without placing the trip system in the tripped condition provided the diesel generator associated with the OPERABLE isolation valve is OPERABLE.
j GRAND GULF-UNIT 1 3/4 3-15 Amendment ha. 70, 97, _ l
" Att:chment 3 to GNRO-92/00117 E p
Pags 13 c' 94' INS'TRUMENT ATION1 TABLE 3.3.2-3 (Cont nued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME:
. TRIP FUNCTION RESPONSE TIME-(Seconds)#:
S.-
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High
< 10(*) #
b.
RCIC Steam Supply Pressure - Low I 10(a) c.
RCIC Turbine Exhaust Diaphragm Pressure - High RA d.
RCIC Equipment Room Ambient Temperature - High NA e.
RCIC Equipment Room a Temp. - High NA f,
Main Steam Line Tunnel Ambient Temp. - High NA g.
Main Steam Line Tunnel a Temp. - High NA h.
Main Steam Line Tunnel Temperature Timer-NA i.
RHR Equipment Room Ambient Temperature - High NA j.
RHR Equipment Room a Temp. - High NA k.
RHR/RCIC Steam Line Flow - High NA 1.
Manual Initiation NA m.
Drywell Pressure - Hf
.ECCS Division 1 i
and Division 2)
< 10(a) 6.
RHR SYSTEM ISOLATION a.
RHR Equipment Room Ambient Temperature - High NA b.
RHR Equipment Room a Temp. - High NA c.
Reactor Vessel Water Level - Low, level-3
< 10(,)
~
d.
Reactor Vessel (RHR Cut-in Permissive)
Pressure - High NA e.
Drywell Pressure - High NA f.
Manu.-l Initiation NA (a) The. isolation system instrumentation response time shall be measured.and.
recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system-instrumentation response time-specified includes the delay for diesel generator starting assumed in the accident analysis.
(b) Radiation detectors are exempt from response time testing.
Response time shall be measured from detector output or the input of the first electronic-component in the channel.
" Isolation system instrumentation response time for MSIVs only.
No diesel generator delays assumed.
2
- ** Isolation system instrumentation response time for associated valves
except MSIVs.
Isolation system instrumentation response time for air operated dampers.
No diesel generator delays assumed.
(jk v. Ave.'s %A Al
Isolation system instrumentation response time specif ed for the Trip Function actuating each valve ; = ; shall be added to9 isolation time t r ir Table; 0.C.0 1 er.d 2.0.0.2-1 Mr ;;'.n b u d.,el,e grew, to obtain ISOLATION SYSTEM RESPONSE TIME............i.
g,
Includes time delay of 3 to 7 seconds, s
GRAND GULF-UNIT 1 3/4 3-21 krne n d m e_M No. -
l
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~
~
Attachmtnt 3 to' GNRO 92/0C,/ j i
~ Paga.'14 of 94 -
3/4.6 CONTAINMENT' SYSTEMS:
3/4.6.1 PRI E RY CONTA! WENT-
~-
PRIMARY: CONTA!WENT INTEGRITY-LIMITING CON 0! TION FOR OPERATION 3.6,1,1' PRIMARY CONTAINMENT INTEGRITY shall_ be maintained..--
- APPLICA8!LITY:
OPERATIONAL CONDITIONS 1, 2* and 3.
ACTION:
l Without PRIMARY CONTAINHENT INTEGRITY, restore PRIMARY CONTAI MENT INTEGRITY.
withir 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months _and in
- COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS t
4
4. 6.1.1 PRIMARY CONTAI MENT. INTEGRITY shall be. demonstrated:
After each closing of each penetration-subject to. Type 8 testing, a.
except the containment air locks, if, opened following Type A 'or B test, by-leak rate testing-the seals with gas at P,,711.5 psig. and vertfying that wnen the measured leakage rete for these seals 'is:
added to the-. leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type 8 and C penetrations, the combined leakage rate is -less than or equal to 0.60 La.
b.
At least once per 31 days by. verifying that all containment penetrations **;not capable of bek p c'osed by OPERABLE containment automatic isolation valves and required to be closed durin4 accident' conditions are closed by valves,' blindtflanges, or deactivated -
i automatic valves secured in' position, except = ; r N P ns c4 T;;'; 2.C.0 1 # 5pecification 3.6.4-
- c.
Sy verifying _sech containment air lock is in coepliance with the requirements of Specification 3.4.143.
d.
- Sy verifying the suppression pool is in compliance.with.the:
requirements of Specification 3.6.3.1.
"See special. Test Sceptios 3.10.1
Except: valves,- blind flanges, and deactivated automatic valves which 'are.
p located.inside theLeontainment,- steam tunnel or drywell:and are locked, sealed.
L
/or.otherwise secured in.the closed position.s These penetrations shall be=
verified closed:during each COLD.. SHUTDOWN except such verification need not be performed more often than once per 92 days.
L
- GRAND GULF-UNIT 1
- 3/4 6-1 pnenandme.M b-y 4-y
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Attahhment' 3"t3 GNRO 92/0011 P69015 of 94-1
.NSERI
-for. valves-thatfare opened under administrative control'as:-
permitted:by-d 1
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e
(
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Insert for TS-page:3/4 6-1 v':
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to GNRO.92/00117 CONTAINMENT $_YSTEMS Pcge 16 of 94 CONTAINMENT LEkKAGE
_LINITING CON 0! TION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to L a.
0.437 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P 11.5 psig.
b.
A combined leakage rate of less than or equal to 0 60 L for all pressurized to P,,
11.5 psig. penetrations and all valves # subject to Type B and C a
through the isolation valves when tested at P, 11 c.
d.
A combined leakage rate of less than or equal to 1 gpm times the number of containment isolation valves in hydrostatically tested lines oa which penetrate the primary containment, when tested at 110 P 12.65 psig.
APPt.ICABILITY:
Specification 3.6.1.1.When PRIMARY CONTAINMENT INTEGRITY is required per ACTION:
With:
0.75 L,, orThe measured overall integrated containment leakage a.
b.
The measured combined leakage rate for all penetrations and all valves #
subject to Type B and C tests exceeding 0.60 L,, or main stone lines through the isolation <a)ves, orThe me L
c.
d.
The measured combined leakage rate for all containment isolation containment exceeding 1 gpa times the total num restore:
0.75 L,, andThe overall integreted leakage rate (s) to less than or e a.
-b:ht; :11 ;;h:; iht:::
hydrostatically leak tested.'. T:.th
.C. Ply"except for those that are GREO GULF-UNIT 1 3/4 6-2 Arnendmerd No.
w
~ ~., ~
Attachmsnt 3 to GNRO-92/00117 Page.17 of 94.
CONTA!NMENT-SYSTEMS:
LIMITING-CON 0! TION FOR OPERATION (ContinuedF
' ACTION (Continued)_
'b.
The comhined leakage rate for all-penetrations ~and all valvesI
~
subject to Type 8 and C tests to less than or equal to 0.60 L; and c.
The leakage rate to less t%n 100 scf per hour for-all four main steam lines through the ',olation valves, and d.
The coabined leakage rate for all containment isolation valves ini hydrostatically tested lines which penetrate-the pristry containment-to less than or_ equal to 1 gpe times the. total number of such valves,.
prior to. increasing reactor coolant system temperature above-200*F.
SURVEILLANCE REQUIREMENT $
i 4.6.1.2-The containment leakage rates shall be demonstrated at the followitg test schedule and shall be determined in conformance with the criteria speci- -.
fied in Appendix-J of.10 CFR 50 using the methods and provisions of ANSI N45.4 -
1972:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall he conducted at 40 + 10 month intervals
during shutdown at P,,11.5 psig, during each 15 year service period.
b.
If any periedic Type A test fails to meet 0.75-L the-test schedule
-forsubsequentTypeAtestsshallbereviewedanl,approvedbythe-Commission.
If two consecutive Type A tests fail to meet 0.75 L TypeAtestshallbeperformedatleastevery18monthsuntiltw0,a:
consecutive Type A tests meet 0.75 L,, at which time the above test schedule may.be resumed.-
i c.
The accuracy of each Type A.est shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the e3ntainment leakage rate.-L',, calculated in accordance with AN51 N-45.4-1972, Appendix C, is within 25 percent of _the containment leakage rate, L,, measured prior to the introduc.
tion of the superimposed leak.-
'2.
-Has dur,ation sufficient _te establish accurately the channe in leakage rate between-the Type A test and-the-supplementa' test.
3.
Requires thematity of gas injected.into the containment or bled free d containment during the supplemental test to be between 0.M cad 1.25 L,.
g P.:hd; :11 " h:: 1htM S Tek 3.5.'% "except for those that are #
I hydrostatically leak tested.
"The third Type A. test within the first 10-year. service period shall be con-
-ducted prior to startup following the sixth refueling outage.
This is an exemption from 10 CFR Part 50,' Appendix J Requirements.
// 4 1
GRANO GULF-UNIT _1 3/4 6-3 Amendment No. 89
_ l o
.-..a..
~.
_.m o 13 GNMO 92/00117 Page 18 cf 94 CONTAINMENTSYME3 SURVf!Lt.ANCE REQUIR NENTS (Continued) d.
Type 8~end C tests shall be conducted with gas at P, 11.5 i
intervals no greater than 24 months except for testl involvin 1.
Air locks,-
2.
Main steam line isolation valves, 1
3.
Penetrations using continuous leakage monitoring systems, 4.-
Valves pressurized with fluid from a seal system, 5.
i Containment isolation valves in hydrostatically tested lines which penetrate the primary containnsnt, and 6.
Purge supply and exhaust isolation valves with resilient material seals.
Air locks shall be tested and demonstrated OPERABLE per Surv e.
Requirement 4.6.1.-3.
f.
Main steam line isolation valves shall be leak tested per 18 months.
Type I tests for penetrations employing a continuous leaka g.
system shall be conducted at P,, 11.5 psig, at intervals no greater i
than once per 3 years.
h.
Leakage from isolation valves that are sealed with fluid from a sea system may be excluded, subject to the provisions of Appendix J,
~
Section !!!.C.3, when determining the combined leakage rate provi the seal system and valves are pressurized to at least'1.10 P..
12.65psig,andthesealsystemcapacity.itadequatetomaintlin system pressure for at least 30 days, i.
Containment isolation valv.s in hydrostatically tested lines which penetrate _ the primary containment.shall be leak tested at l
least once per 18 solt's, j.
Purge supp0 and' exhaust isoletion valves with resilient material sea's. shall' be tested and demonstratad OPERABLE per,: Surveillance Requirement 4.6.1.9.2.
k.
The provisions oc Specification 4.0.2 are not applicable to 4.6.1.2.e, and 4.L 1.2,g. Specifications'4.6.t.2.s. 4.6.1.2.b 4.6.1.2.c. 4.6.1.2.d, E lE a hydrostatic test is require b " '......,*..-
1 1
GRAND CULF-UNIT 1 3/4 6-4 kmeridmerdNo.
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- _ _ - _ - _ _ _ _ _ _ _. _ _ _ - - to GNHO.93/00117 Page 19 of 94 CONTAINMENT SYSTEMS 3/4.6.2 _DR M LL OR M LL INTEGR!TY LIMITING CONDITION FOR OPERATION 3.6.2.1 DR M LL INTEGRITY shall be maintained.
APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 28 and 3.
ACTION:
Without ORMLL INTEGRITY, restore DRMLL INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SNUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE RE0VIREMENTS 4.6.2.1 DRYWELL INTEGRITY shall be demonstrated; a.
At least once per 31 days by verifyinn that all drywell penstrations**
not capable of being closed by 0PERA8[I drywell autosetic isolation valves and required to be closed during accident conditions are closed by valves bl secured in position,ind flanges, or deactivated automatic valves except *Fi;.=id:d P it.th.". P1 ;'
l Specification 3.6.4.
b.
By verifying the drywell air lock is in compliance witti the requirements of $pecification 3.6.2.3.
c.
By verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.
, see special Test Exception 3.10.1.
Except valves, blind flanges, and deactivated autoestic valves wni;h are located inside the drywell or containment and are locked sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SWTDOWN except such verification need not be performed more often than once per $2 days.
GRAND GULF-UNIT 1 3/4 6-13 Amendment No. 31 l
j I
l
.. _ =.. _ _ _ _ _. _ _,
_ to GNRO 92/00117 ' :
Pcoo 20 cf 94 i
I INSEltT for valves that are opened under administrative control ~as permitted by-
~
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k i
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.i I
l Insert for.TS:page 3/4 6-13 P
AttachmCnt 3 te GNRO.92/00117 Pogo 21 of 94 CONTAINMENT $YSTEMS 3/4.6.4 CONTAINMENT AN0 ORWELL ISOLATION VALVE $
LIMITING CONDITION FOR OPERATION 9_^M 3.6.4 conta am shall be,0PERA8L @ ant and drywell isolation valve
5 -
4-Tm-s W
,th f: letter, ti :: 1::: th:,, 27 :g:1-:: ; F,i ; E ;
g APPLICABILITY:
OPERATIONAL CON 0!TIONS 1, 2, 3, and f.
ACTION:
With one or more of the containment or drywell isolation valves thr:- '-
T:tt: 3.'.1-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months eithert Restore the inoperable valve (s) to OPERA 8LE status, or a.
b.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position," or Isolate each affected penetration by use of at least one closed c.
manual valve or blind flange *.
Otherwise, be in at least Hof SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .""
" Isolation valves, except M$1Vs, closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls.
OPERATIONAL COMITION changes, as provided by $pecification 3.0.4, are not allowed while isolation valves are apen under these administrative controls.
f!solattoe valvee 5. 5 T C ; 3.0.t-1 are aise required to be OPERABLE when I
their associated actuation instrumentation is required to be OPERABLE per e
Table 3.3.2-1.
Except for E12-F000 and E12-F009 in OPERATIONAL CON 0! TION $ 4 and 5 take action per Specification 3.3.2, Table 3.3.2-1 Trip Function 6.c.
~
hyhd l
__.._m_
- _ - - _ - _ - _, t) GNRO 92/00117 l
P:ge 22 cf 94
)
J INSERT
Normally closed or locked closed manual valves may be opened A an intermittent basis under administrative control.
' -1 s
l E
?
I Insert for TS page 3/4 6-28 j.-
~ -.,..____..- -_- _. -.
.... _.. to GNRO 92/00117 Pa0s 23 of 94 (p'llWIN1SY51[M5 l
F i
$URvillLANCE #f00!*fMENT$
Jcq mID g 33
@n%.'n mm4
.c 4.6.4.1 fachhnolationvalvr:h:_
S hti; 3.?.0 shall be demonstrated l
~
OPERA 8LE prior to returning the valve to service after maintenance, repair er replacement work is performed on the valve er its associated actuator, control or power circuit by cyc1fng the valve threunh at least one complete cycle of full travel and verifvine t % -
1so's I n time, a ppg. g Gods'.nuw& or 7cque6D 4.6.4.2 Each automatic +1solatten valve. =.:.c '; 3.0.0-1 shall be I
demonstrated OPERA 8LE during COLD SHUIDOWN or REFUELING at least once per 18 months by verifying that on an isolation test signal each automatic isolation valve actuates to its isolation position.
The isolation time of each power operated er automatic'MQ:.7, G e+.nm.4 ocd wIi 's=1 +
4.6.4.3 valve.
h l
htt; 3.5,0 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.4.4
[ DELETED) a I
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GRAND GulbuMIT 1 3/4 6-29 A mn b e.n4 rJo.
L i
Attachi-v'.2 3 t) GNRO 92/00117 Page 24 cf 94 INSERT The provisions of specification 4.0.4 are not applicable to automatic Dain steam line valves for entry into OPERATIONAL CONDITIONS 2 or 3, provided the surveillance is performed within 12-hours after reaching a reactor steam pressure of 600 psig and prior to entry into OPERATIONAL CONDITION 1.
i t
+
4 7
4 Insert for TS page 3/4 6-29
' Att:chment 313 GNMO 92/00117 ' l Page 25 of 94
[
~
l t
t L
4 4
?
i
' 't Pages 3/4 6-30 through 3/4 6-45 have been Intentionally Deleted.
' t e
GRAND GULF-UNIT 1 3/4-6-30 Amendment No'. 15, (Next page is 3/4 6-46)_
r
p 4
k r
v
,,,.r.,-e
-Emu-h--~y,-v..-+,,
w -s w -e v-
.-,,,,e-,3
--+v%y-vy w-.*-
' ww -
.,--y.

*---*-w-w

--r
_ to GNRO 92/00117 Pags 20 of 94 TABLE 3,5.4-1
.CONTAl *EWT AND prywL L ISOLATION VALVE 3 AIEl PENETRATION MAXIMUM VAL lESSIS~
NUPGER VALVEGROUP'}
LATION TIME I
1.
.AvtoehteIsolationValves#
(Seconds)
Cohainment e.
Main Ste Lines
$21-F028A 5
1 5
Main Steam ines 821-F022A 5
1 5
Main Steam L s
B21-F067A-A 5(0)*
1 9
Main Steam Li B21-F0288 6(0
Main Steam Lines 821-F0228 6(I
1 5
5 Main Steam Lines 821 F0678-A 6(0
1 9
Main Steam Lines 521-F028C 7(0)*
1 5
Main Staan Lines 821-F022C 7(1)"
1 5
Main 5 team Lines 1-F067C-A 7(0)*
1 9
Main-Steam Lines B L-F0280 8(0)*
1 5
Main steam Lines 82:. F0220.
8(I)*
1 5
Main Steam Lines 821-70-A 8(0 1
9 RHR Reactor E12-F A
1 0) 3 40 Shutdown Coeling Suction AHR Reactor E12-F009-8 14(1) 3 40 Shutdown Cooling Suction i
i Steam supply to E51-F 8
17
)
4 RHR and ACIC Turbine 20 Steam Seply to E51 064-A 17(0) 4 20 RHR and RCIC Turbine 1
Steam Supply to 1-F076-3 17(I) 4 20 RNA and RCIC Turbine i
RHR to Need Spray E12-F023-A 18(0) 3 94 RNA to Head Spray E12-F3M-8 18(!)
3 43 (a) See specificatt 3.3.2 Ivo greg. Table 3.3.2-1. for isolati signal (s)that operates sech b) Deleted c) %drostett y tested with water to 1.10 P 12.65 psig.
(d
%drostati 11ytestedbypressurizinesyst$m,to1.10P
.65 psig, e
%dres 11y tested during system functional tests,,,
f Deleted sg Mortal eleoed or locked closed manual valves ma stent-basis under eministrative centreT. y be opened en inte
'The p isions of specification 4.0.4 are not applicable for entry i OPERA ONAL COISITIONS 2 er 3 provided the surveillance is perfereed thin
- 12 after reaching a reacter steam pressure of 600 pois and prior ints OPERATIONAL CONDITION 1.
en WT
-A -B
-C, -(A). -(B) -(C ssociated electrical divis ons.)" designators en the valve numbers indica r
GRAle GULF-UNIT 1 3/4 6-30 Asentent No.15)
..- _. - ~,., -. - -.., -,. -. -.. - - - - - -,,., _.., -.. _,.
....w.--.,,....m.,-,.,-.,_,,..,,,.,,.,---v-,.,ry-w,
.,,-w.
-- -. ~..-
Attachm:nt 3 to GNRO 92/00117 g
TABLE 3.6.t'*1 (Continued)
CONTADeeri Ape ORVWELL !$0'JTIM VRVs f
II" Vf N
VALVE GROU,(a)
Sec Containaset (Continued) f.
Main Steam ine 821-F019-A 13(o )
1 Drains
'O Hain Steam Lin 821-F016-8 13(!)
Drains 20 RHR Heat Exchange E12-F028A-A 20(!)
5 90 "A" to CTNT SPR Sparger INL RHR Heat Exchanger
-F037A-A 20(!)
"A" to CTMT Pool 74 RHR Heat Exchanger E
F0288-8 21(!)
5 90 "8" to CTNT SPR Sparger INL
?HR Heat Exchanger E12-F0 B-8 21(I) 3 74 "B" to CTMT Pool RHR "A" Test Line E12-F024A-23(0)I 5
90 to Supp. Pool RHR "A" Test Line E12-F012A-A 23
)(d) 5 36 to Supp. Pool RHR "C" Test Line E12-F021-8 (0)(d) 5 144 to Supp. Pool HPCS Test Line E22-F023-C 27(
(d) 68 75 ACIC Pump Suction E51-F031-28(0) d) 4 56 RCIC Turbine E51-F0.
A 29(0)(*
Exhaust 9
25 LPCS Test Line E21-12-A 32(0)(d) 3 144 Cont. Purge and M -F011-(A) 34(0) 7 4
Vent Afr Supply Cont. Purge and 1-F012-(8) 34(I)
Vent Air Supply 4
Cont. Purge and M1-F034-(B) 35(!)
7 4
Vent Air Exh.
Cont. Pwys M1-F035-(A) 35(0) 7 4
Vent Air l
Drywell Ch led P72-F123 B 36(I)
GA 33 i
water a Drywell iflied P72-F122-A 36(0)
GA_
33 Wate Return l
Orywe Chilled P72-F121-A 37(0) 6A 33 i
e Supply C 11ed Water P71-F150-(A) 38(0) 6A Swly t
GRAN0 GULF-UNIT 1 3/4 6-31 Amendeont No. 21) l
- Attachm:nt 3 to GNRO 92/00117 -
Pag: 28 of 94 TABLI 3.6.4*1 (Centinued) _
CONTAllpENT AND DRYWLL !*8LATION VALVis IV W
VALyt it -
h TION itAX t
NLseta VAtyt smay(a) 130LA TIME Containnskt'(Continued) g
,)
Chilled Wat e Return P71 F146-(A)'
39(0) 6A Chilled Water 12 4
Return P71 F141-(B) 39(!)
6A 12 5ervice Air Supply PS2-F105-(A) 41(0)
GA 6
Inst. Air supply ll-F41-(A) 42(0) 4A RWCU to Main 4034-A 43(0) 6 Condenser RWCU to Main 35 G33- 028 8 43(!)
8 Condenser 35 NWCU lackwash to G36-F10 -(t) 49(!)
6A C/U Phase sep. Tank n
RWCW Sackwash to G36 F101-(
49(0) 4A C/U Phase Sep. Tank 11 -
Drywell & Cont.
P45-F047-(B) 10 )
GA Equip. Orain 7
Sump Olsch.
Dryeell & Cont.
P4FF066-(A) 50 Equip. Drafn 6A 7
Sump Disch.
Drywell & Cont.
P4FF061- )
$1(!)
4A 7
Fleer Orain Sump C' isch..
Drywell & Cont.
P4F 2-(A) 51(0)
GA Floor Orain 7
Sump Ofsch.
Condensate Supply 11-F075-(A) 56(0)
FPC & CU to Upper 841 F02F A 57(0)
EA 51 10 cent. Peel j
Upper Cont.
I 441-702FA
$8(0)*
GA 51 u Fw1 Drain T upper Peel 441-F044-6 56(1)
GA 40 to Fue' 9ee)
Drain
'ank-
~
Aux.
dg. F1r.
P45-F273-A 60(0) 4A 32 4
Equip. Orn.
. to S g. Peel
. Bldg. F1r.
P45-F274-6
- 60(0)
GA 32 and E Tks. quia. Orn.
to supp. Pool GRAND Gut,F-UNIT 1 3/4 6-32 hed gt $o.
..__c,,-
w..
2 m
,,,,_._,,.,_m.
c._.__,
...,,rm.
,,,,,_,,,.-m,,
_me.,-,,_
.,,-,.,,_,,,.,,,m_,..,.,
,,.m,_._
Attachm:nt 3 to GNRO 92/00117 i
Pags 29 of 94 TABLE 3.8.4 1 (Continued)
CONTA!NMfWT AND DMEL;. !$0LAT!0N VALVE 5 SY AM' VALVE ER -
PENETRATION IMUM 150 10N TIME NL8SE!t VALVE GROUP (a) t Centai d t (Continued)
Seconds)
Camb. Gas ntrol E61 F009-(A) 65(0) 7 f.ont. Pu 4
(Outside 1
Sup Come. ply)
Gas contro E41 F010-(t) il(!)
7 4
~
Cont. Purge (Outside Air supply) i Purge Filter Train E -F056-(8) 66(!)
! solation 4
Purge Filter Train -E61-57-(A) 66(0) 7 Isolation 4-RHR "B" Test Line E12-F024 8 67(0)(d)
To Suppr. Pool 5
'90 RHR "B" Test Line E12-F0118-67(0)(
To Suppr. Pool 5
36 Refueling Water P11 F130-(A) 69 )I')
Transf. Pump 6A 8
.5uction i
Retualing Water P11-F131-(B) 6
)(C)
Transf, Pump 6A 8
Suction Instr. Air to ADS P53-F003-70(0) 6A 4-RCIC Turnine Exh.
E51-F07 -8
-75(0) 9
' 10 Vacuus treaker-RWCU to Feedwater
$33 040-4 43(1) 3' 35 RWCU to Feedwater F039-A 43(0)
'S 35 chemical Wasta 5-F098-(t)
M(l')
. Sump Discharge-8 Chemical Weste P45-F099-(A) 84(0)
Sump Dische 8
Supp. Poe) C1 P60-F009-A 45(0) 6A 4
up Return Supp. Peel een-P60-F010-8 46(0).
6A 8_-
up Retu 4
Osmin. -
ter P21-F017-A 86(0) 6A 19 Supp to Cont.
Demi Water-P21-F018-B 86(I) 6A 1F
-5 ply to Cont.
U Pump Suction G33-F001-8 47(I) s 5
}
SRAW GULF-UNIT 1
-3/4 6-13 M mendment Mo.
l
. ~.
-.... - ~..
______._.-.w,..
.(
Att: chm:nt 3 to GNRO-92/00117 TABLE 3.6.4-1 (C:ntinued) Paos 30 of 94
-l CONTAI W WT A 4 DRYWELL !$0LATION VALVE 5 SYS AND VAL NUSER PENETRATION MAXIMUM
_ NUMBER VALVE GROUP (a)
SOLATION TIME Contalhn't(Continued)
JSeconds)
RWCU P Suction G33-F252-8 87(I) 8 RWCU Pump uction G33-F004-A 87(0) 8 35 RWCU Pump 0 ch.
G33-F053-8 88(I) 8 35 RWCU Pump 01 h.
G33-F054-A 88(0) 8 35 b,
Drywell
~
35 Instrument Air P53-F007-8 335(0)
A Drywell Chilled P72-F125-A 331(I) 6A 7
Water Return 32 Drywell Chilled 72-F126-8 331(0) 6A Water Return 32 Drywell Chilled P -F124-8 332(0) 6A Water Return 32 RWCU Pump Suction G33-50-A 337(I) 8 RWCU Puep Suction G33-F 11-8 337(
8 35 Combustible Gas E61-FOC
-8 338 )
5 35 Con.
84 Combustible Gas E61-F003A 9(0) 5 Con.
84 Combustible Gas E61-F005A-A-340(0) 5 l
Con.
84 Combustible Gas E61-F0058-8 340(0) 5 Con.
84 Cosbustible Gas E61-F007-A)
(0) 5 Con.
9
' Combustible Gas E61-F0 -(B) 341(
5 Con.
18 Drywell Air Purge M41 0'!-(A) 345(I) 7 Supply 4
Drywell Air Purge 1-F013-(8) 345(0) 7 Supply 4
Drywell Air Purge M4PF016-(A) 347(I) 7 Exhaust 4
Drywell Air Pu M41-F017-(B) 347(0) 7 Exhaust 4
Equipment Or ns P45-F009-(A) 344(I)
Equipment D sins P45-F010-(8) 348(0) 6A 6
6 Floor Drs<
P45-F003-(A) 349(1) 6A 6
Floor as P45-F004-(8) 349(0) 6A 6-Servict te PS2-F195-8 363(0) 6A 16 Chemi 1 Sump P45-F096-A 364(I) 6A-9 01 h.
C ical Sump P45-F097-8 364(0)
.6A
'9 isch.
U to Heat G33-F253-A 366(0) 8 35 Exch.
Reactor Water 833-F019-8 465(1) 10 36 Sample Line Reactor Water 833 F020-A 465(0) 10 3k Sample Line GRAND GULF-UNIT 1
\\
3/4 5-34 Amendment No. 43)
~
Attachm:nt 3 to GNRO 92/00117.
Page 31 of 9 TABLE 3.4.4-1 (Continued)
CONTAlleENT AIS DRWELL is0LATION VALVES SY EM AfS _
PENETRATION VAL ORSSER NUMER___
2.
ManuahIsolationValvesION Con \\ainment a.
Main Ste Lines E32-F001A-A 5(0)
Main Ste Lir.os E32-F001E-A 6(0)
Main Steam ines E32-F001J-A 7(0)
Main Steam L nos E32-F001N-A 8(0)
Feedwater In' t
821-F065A-A 9(0)
Feedwater Inl 821-F0658-A RHR Pump "A" E12-F004A-A 10(0)I Suction 11(0)
RHR Pump "B" E12-F0048-5 12(
(d)
Suction RHR Pump "C" E12-F004C-8 (0)(d)
G Suction AHR Heat Exchanger
-F042A-A 20(!)
"A" to LPCI
RHR Heat Ex. "A" E12 027A-A 20(0) to LPCI RNR Heat Exchanger E12-F 28-21(I)
"B" to LPCI RHR Heat Ex. "B" E12-F02
-8 21(0) to LPCI IIHR Pump "C" to E12-F 2C 22(0)
LPCI
' RHR "A" Test Line E12 064A-A 23(0)(d)
To suppr. Pool RHR "C" Test Line
-F064C-8 24(0)(d)
To suppr. Fool HPC5 Suction 122-F015-C (0)Id)
HPCS Dischargq
_E22-F004-C (0)(d)
HPCS Test Line,
-E22-F012-C 2
0)I")
RCIC Turbine E51-F068-A 29 )(d)
LPCS Pump Sect on E21-F001-A 30(
LPC5 Pump E21-F005-A 31(0 01schst LPCs Mio.ge sw E21-F011-A 32(0)(
CM Pump C11-F083aA 34(0) 01 CCW y
P42-F064-A 44(0)
CCW P42-F067-A 45(0)
CCW turn P42-F068-8 RCI Pump-E51-F019-A 45(1)(d$
44(0)
,p scharge in. Flow actor Recire.
833-F128-8 47(!)
Post Accident Sampling GRAND GULF-t#IIT 1 3/4 6-35
Attachm:nt 3 to GNRO 92/00117 TA8LE 3.6.4-1 (continued)
CONTAINMENT AND ORWELL !$0LAT!0N VALVES 5 TEM AM
]
PENETRATION VAL NLSSER
_ Nug[R Cont \\ansent(Continued)
Reacto Recirt.
833 F127-A 47(0)
Post cident Sampli Vent Hoa to E12-F0738 8 48(0)(d)
Supp. P RNR Pump "O E12-F0648-8 67(0)Id)
Test Line RHR "C" Re1ie E12-F346-B 718(0)(C)
Viv. Vent Ndr to Suppr._ Pool
& Post-Acc.
Sample Ret.
RHP. Heat Ex. "A" E12-F073A-A 77(
(d)
Relief 3eector Recire.
B -F126-8 8 (I)
ReAccident $s,apling acter Recire.
B33 125-A 81(0)
Accident Sampling SW Supply "A" P41-F SA-A 89(0)
SW Return "A" P41-F1 M(I)
SW Return "A" P41-F1 M(0) *)
SW Return "B" P41-F S.
91(0)h 91(I)
SW Return "B" P41-F1 SW Supply. "t" P41-F 92(0) g)
Drywell Press.
M71-F 93-A 101C(0)
Inst.
Drywell Press.
N7 F591A-A 101F(0)
Inst.
Drywell Press.
1-F5915-8 020(0)
Inst.
Ctat. Press. Inst - N71-F592A-A (0)
Ctat. Press. Ins.
N71-F5920-3 (0)
Orywell H E61-F595C-(A) 106A )
Analyzer le Drywell Na E61-F5950-(B) 106A(I Analyser le s
Drywell
. E61-F597C-(A) 1064(0) lyser le Aet, trywell Ane-E41-F5970-(8) 1068(I) t syze Sample Ret.
Ctat.
E61-F596C-(A) 165A(0) yzer Sample C
. No E61-F5960-(B) 105A(I) lyser Sample H Analyzer E41-F590C-(A) 106E(0)
$asple Ret.
Ctat. He Analyzer E61-F5900-(8) 106E(I)
Semple Ret.
GRAND GULF-UNIT 1 3/4 6-36 be,hdme.rd No.
TABLE 3.6.41 (Continued)
Page 33 of 94 j
CONTAINMENT AND D#VW LL ISOLATION VALVE 5 SYSTEM AM PENETRATION l
VALVE NWSER Nungge
~
ntainment(Continued) l Cth Me Analyzer E61-F596A-(A) 108A(0) 5 le Ctat.
Analyzer E61F5968-(t) 108A(1)
Saap :
Ctat. H Analyzer E61F5984-(A) 1078(0)
Sample e t.
Ctat. H A lyzer E61F5988-(t) 1078(!)
Sample Re Drywell H (61F595A-(A)-
107D(0)
Ana1yzer 5 e
Drywell N E61F5958-(8) 1070(!)
Analyzer Sample Drywell H Ana-E61 F597A-(A) 107E )
lyzer Sample Ret.
Drywell H Ana-1-F5978-(t) 1 (1) lyzer Sample Ret.
Drywell Fiss.
D23 592-A 09A(0)
Prod. Monitor Sample Drywell Fiss.
023 F59 8 109A(!)
Prod. Monitor Sample Drywell Fiss.
023 F5
-A 1098(0) v Prod. Mon.
Sep1. Ret.
Drywell Fiss.
02 F593-8 09t(!)
Prod. Mon.
Seol. Ret.
Ctat.-Press. Inst.
M71-F5M-B 1
0)
(Post Acc. Sep1 Ctat. Press. In M71-F595-A 1090(!
(Post Acc.
1. )
Suppr. Pool el
- E30-F593A-A 113(0)(*
l Inst.
Suppr. Poe Level E30 F592A-A 114(0)
Inst.
Suppr.
1 Level-E30-F594A-A 115(0)(*)
Ins Supp Peel Level E30 F591A-A 116(0)
I t
5 r." Pool Level E30 F5938-8 117(0)(*)
L
Inst, uppr. Pool Level
- E30-F5928-8 118(0)
Inst.
Suppr.' Pool tevel E30-FSMS-8 119(0)(*)
-Inst.
Suppr. Pool Level-E30-F5918-8 120(0)
Inst.
GRAND GULF-UNIT 1 3/4 6-37 AmendM80'~ No.
,9r w
a.---.gs.*,
...w
--y,,,.,y.g-p.,w,
,,,,.,,,,,..4#c
.,w-,-y-w,,
,.e_,...,2,-.-ww,...-%-w-,,..-
.,.-_,,,.--.._.-.y,,e.,_-,,.._.
.,,,+,,-m
.us,
TABLE 3.8,4-1 (Continued)
Attachni nt 3 to GNRO 92/00117 p,g3 34 of 94 CONTA!MNT A88 DRYWELL !$0LAT10N VALVE 5 SYSTEM AIS VALVE inseER PENETRATION 3R b.
Drywell ont. Cooling P42-F114 8 329(0)
Water Inlet to t. Cooling P42-F116 A 330(!)
ter Outlet Cont. Cooling P42 F117 8 330(0)
Wate Outlet 3.
Other is ation Valves 8)#
I a.
Contai nt Fuel Transfer F11-E015 4(1)
Tube Feedwater Inlet 821-F010A 9(1 Feedwater Inlet 821-F032A 9(0)
)
Feedwater Inlet 821-F0108 10(!
Feedwater Inlet 21-F0528-10 RHR "A" Suction
-F017A 1 0)(d)
RHR "B" Suction E
F0173 (0)(d)
RHR "C" Suction Eu 017C 13(0)(d)
RHR Shutdown EU-14(1)
Cooling suction RNA Heat Ex. "A" E12-F 20(1) to LPCI RNR Heat 2x. "A" E12-F0 20(1) to LPCI RHR Heat Ex. "A" E12- 07A 20(I) to LPCI RHR Heat Ex. "S" E -F0258 1(1) to LPCI RHR Heat Ex. "B" EM-F0448 21 )
to LPCI RNR Heat Ex. "3 E12-F1078 21(I to LPCI RNR Heat Ex.
C" EU-F234 22(0) to LPCI v
RHR Pump
to EU-F041C-8 22(I)
LPCI
~
NIR "A" Test EU-F259 23(0)I')
Li to suppr.
P "A" Test EU-F261 23(0)I')
Line to suppr.
Pool
\\
GRAND GULF-UNIT 1-i 3/4 6-30 Amen & ant No. 7, l
Att: chm:nt 3 to GNRO 92/00117 Page 36 ot 9d.
TABLE 3.8.4-1 (Continged)
CONTA!WENT AND ORWELL ISOLATION VALVES -
TYSTEN A E i
VALyt NupetR --
PENETRATION NigegR Chtainment(Continued) i I
RHR unin'"A" Test E12-F227 23(0)(')
Li to Suppr.
i PooT RHR P "A" Test E12-F262 23(0)(')
Line t suppr.
1 Pool
-i RHR Pump "A Test E12 F228 23(0)I')
Line to Su r.
Pool RHR "A" Test Li E12-F290A-A 23(0)(d) to Supp. Pool RHR Pump "A" Test E12-F338 23(0)(*)
Line to suppr.
Pool RHR Pump "A" Test E
F339 23(0)(C) i Line to Suppr.
Pool RHR Pump "A" Test E12-F2 23(
')
Line to Suppr.
Pool i
RHR Pump "C" Test E12-f280 4(0)(#'
Line to Suppr.
Pool
,RHR Pump "C" Yest E12-F281 4(0)(d)
Line to suppr.
Pool HPCS Suction E22-F0 25(
Id)
HPC5 Discharge E22-P 5-(C) 26(I)
HPC5 01scharge 218 25(!)_
HPCS Discharge F201 26(!)
HPCS Test Line F035 27(0)(d)
HPCS Test Line E22-F302 27(0)(,)
HPCS Test Line F.22-F301 27(0)g,)
~,
LPCS Pump Secti E21-F031.
30(0)(d)
LPC5 01 sche E21-F006-(A) 31(!)
LPC5 Of E21-F200 31(1)-
LPC5 Of E21-F207 31(!)(d)
LPCS Test ine-821-F217 32(0)
LPCS Tes Line E21-F21s 32(0){d}
CR0 C11-F122 3'!(I)
Ofs rge OCW ly P72-F18" 37(I)
P1 t-Chilled-P71-F151 38(I) tar Supply vice Air PS2-F122 41(I)
Supply GRAND GULF-UNIT 1 3/4 6-39 Amenement No. 21
.a...
M I 3.4.4 _1 (Continued)
Att: chm:nt *) 13 GNRO 92/00117 p.g3 30 of 94 CONTA!WENT ANO 0,RYWELL -ISCLATION VALVES SYSTEM ANO ALVE NUMBER
'PetETRATION WUPSER Ch tal g (Continued)
Ins
. Air Supply P53-F002 CLv ply P42-F035
2(!)
RCIC D ch.
E51-F251 46(0)IC) 44(1)
Min, ow RCIC Dis Hin. F10 E51-F252 45(0)(C)
RNR Heat Ex.
"B" E12-F0558 48(0)(d)
Relief von Heaver RHR Heat Ex. "8 E12-F1038 48(0)(d)
Re11tf Vent Header RHR Heat Ex.
"B" 12-F1048 48'3)(d)
Relief Vent Header' Refueling Wtr.
G41 053 54(0)
Stg. Tk to Upper Ctat. P001 Refueling Wtr.
G41-F20 54(!)
Stg. Tk. to Upese Ctat. Pool Cond9nsate supply P11-F004 FPC & CU to Uppe-G41-F040 (1) 5 I)
Cent. Pool
$ by. Liquid C41-F151 1(l';
Control S Mix. Tk. ys.
(future use)
Stoy. Liquid C41-F1 Control Sys.
61(0)
Mix. Tk.
(futurs,use)
RHR Pump "R" Test Line
-F275 67(0)(,)
RHR Pump "8" Test E12-F277 67(0)(')
LI"'
RHR Pump "S" T t E12-F212 87(G)(e)
Line RHR Pump "$"
est '"E12-F213 67(0)(*)
LI"'
RHR Pump 9" Test E12-F249 67(0)(e)
II"'
RHR P "S" Test E12-F250 67(0)(e)
Pump "8" Test E12-F334 67(0$"I ine
/
GRAND GULF-UNIT 1 3/4 6-40 kmandmCnk b.
Att:chment 3 to GNRO 92/00117
\\
,Ty g 3;6,4 1 (Continued)
IdLMA!WW AND Dawrtt ISOLATIow Vatus 4
$[MIR AS t
PENE7 RATION 4
.3lg[R_
Cohainment(Continued)
'4" Test E12*F335 67(0)(')
RNA *t"\\ Test Line E12 F2908 5 87(0)(8)
To is. Foo1 intt. Air ADS-Pl3 F006 70(!)
LPC5 Retie t'alve E21 F018 72A(0)(d)
. Vent Heade, RHR Puse CC" E12 F025C 718(0)Id)
Relief Yals Vent Header NR "C" Ac11ef E12.F404 713(1)(C)
YatvG V2n$ R$r.
/
to suppr.' Pool
& Post Acc.
\\
Sample Return MNR Shutdown E12-34 73(09 Vent Header RNR Shutdown E12-F0 765(0)
Suction Reliet Valve Disch.
atHR Neat Ex. "A" E12 F055A 77(0
)
Relief Vent Header RHR Heat Ex. "A" D2 F103A (0)(d)
Relief Vent
. Needer RNR Heat Ex.."A" n2-F104A 77 )(d)
Relief Vcn?
Needer SSW "A" i;pply P41 F16 55W "F/ soply P41-09(1 (C st(!
Ctat. Laak kata Mll-F ueA(J)
Test Inst.
Ctat. Laak Rata F014 110A(0)
Test Inst.
Ctat. Laak Esta 1-F017 n0C(!)
Test Inst.
Ctat. Lank tota M1-7018 n0C(0)
Tsat Inst.
Ctat. Lect M1-F017 110F(!)
. Test Inst Ctat. Laak
'a M1-F016 ueF(0)
. Tes*, I b.
D 11 LPCI A"
E12-F041A 313(!)
LPC
't" EM-F0418 314(1)
LP I '3" E12-F2M 314(0) to Rectre.
B33 F013A 326(!)
Pump A heals grape GULF-UNIT 1 3/4 6-41 Amendment No. 24;-
r rew.---
emw,-.
- + -. - -., -
,y,,,-,e-r,a----
an,-
, a w
, v
.n
--n-..,,-.m.,
Att:chment 3 to GNRO 92/00117 Page 3B of 94 T4LE 3.6.41 (Continued)
CONTA!NNENT AND ORWEtt. ISOLATION VALV SYSTEM AND yALVE NUM8fR PENETRATION NUMS[R Orywell (Continued) 4 RD to Rectre.
833 F017A 326(0) ump A Seals In rument Air P53 F008 335(I)
Stan y Liquid C41-F007 328(1)
Con el Standb Liquio C41-F006 328(0)
Contro Standby L uid C41 F218 328(1)
Control-0 in Cont. Coolin P42 F115 Water Supply 329(1)
Devwell Chilled P72-F147 332(1) kater h9 ply Condensate 71u h 833 F204
'333(I)
Conn.
Condensate Flush 8 -F205 333 )
Conn.
Combustible Gas E61- 02A 9(0)
Control Combustible Gas E61-F00 338(0)
Control Combustible Gas E61-F004A 340(0)
Control Combustible Gas E61-F0 340(0)
Control Upper Containment G41 F 65
?,(0)
Pool Drain CRD to Rectrc.
8 F0138 346 )
Pump F Seals CR0 to Rectrc.
33-F0178 344(D)
Pump 8 Seals Service Air P52-F196 363(1)
Cont. Leak Rat M1-F021 438A(I)
Test Inst.
Cont. Leak ta M61-F020 438A(0)
Sys.
BLIND F ES Co t ask Rate NA 40(I)(0)
Co
. Leak Rate NA Sys.
82(I)(0) ontainment NA Leak Rate System 343(!)(0)
GRAND GULF-UNIT 1 3/4 6-42 Amendment No. 41)-
._..___.. ~
Attachm'et 3 4 GNRO 92/00117 Page 29 of 94
~
i TABLE 3.8.4*1(Continued)
)
CONTA!apeff M DtWELL IgeLATION VALVtl 5YSTEM AND VALYE Nupeit PEMTRATION lesstR I
4.
est Connections I)
- +
a, Centsfnannt Main taas T/C 821 F025A S(0 Main as T/C En-F02H 4
Main 5 T/C tn m2SC 7
Main Ste 7/C 421-F0250 8
Feeswater C
321 F030A 9(0 Feeswater T 421 F063A 9(0)
Feeswater T/
421 F0638 10(0)
Feedwatsr T/C Su-FOM8 10(0)
RNR Shwtdown Coo D2 F002 14(0)
Section T/C RCIC Steas Line 1 F072 17(0)
T/C 1HR to Head
-FM2 18(0) spray T/C RNR to Need E12-18 )
sera LPCI *y T/C C' T/C tit-F (0)
RMR 'A' Pump E12-7322 23(0)(8)
Test Line T RNR *A* Pump /C E12-F134 23(0)(c)
Test Line 7/C RMR "A" Pump (12-FM9 (D)I')
Test Line T/C RMR *Aa pump
- R2-F 23)M -I I
Test Line T/C RMR "A" Pune
Test Line T/C 23(0) 83 RMR *A* Pump FMS D(0)(*
Test Line T/C RHR*C" Puse E12-F311 24(0)(8)
Test Line 7/
i ht"C" Pump E12 F304 2$(0)(8)
Test Line /C NPCS M T N E g etti 25(0 WC3 7 Lias T/C E324383 27(0 8)
NPCs T Llan T/t 832-F304 27(0 y ACIC as IB1-F284 29(0 M T/C RC Turtpine EB14257 29(0)(gg t T/C T/C En-Fel3 IMS Test Line E21 F2*t-
.-31(0)g,)
T/C 32(0)
WC5 Test Line E21-F221 32(0)gg)
T/C GRAND OULF-UNIT 1 3/4 6 43 Amenement No. 4 7
.,-,,%,-,--r--
,--.~e-tiv-
--+-w o-s v - -. -
w A
-P
e Attachm:nt 3 to GNRO 92/00117 Page 40 of 94 MM 3.6,41 (Centimund)
OWLL !$0LAMON VALyrs IYSTEM Alt stuuma reemnon
_ NL8sta n*s(neemt (Contingeg) 5 C
Cant, p Exhaustf/C
"'1*IO81 35(0)
OCW Suppi
/'a
UII Plant Chi le 37(0)
,YEEE Water T/C 38(0)
F1cnt Chf11ed py1,F244 Water T/C 3g(g)
Leak Rate M61 F009 j
40(I)
I*rvice Afr T/C p.III8 Inst. Air T/C 41(0)
M T/C
[p 7036 42(0)
CCW Supply T/C P42 F 4 (0)
_CCW Return 7/C
F42, 44(0[)
C8ysatesupply pig.F095 7
FPC A CU To
~
U#er Cent. Fool (I)
T/C Aua. 814,. M r.
p4g,F273
- A Equip. Orafn 0)
Tk. to suopp, feel T/C Aus. 31gg, n7, pg
& IWip. Orsin 84(0)
Tk. to suppe.
F681 T/C Stby. Lfg gg
,F152 Control sys.
81(0)
Min. Yk. T/C (future use)
Cassustible Gas ggi'I'lI 8S(0)
Centrol 7
% w a/C s
net. fos 4 notester 84(0)
UN21 87(0)CC)
/C 7,; " - = u -
m nu
,,(0)(.)
5 rot u.
m.nu
,,(,,(,)
G8AND CULF-UNIT 1 3/4 s.44 Assamment No.21)
Attachm:nt 3 to GNRO 92/00117 Pag 3 41 of 94 TABLE 3.6.4-1 (Continued) i CONTA! M NT AND ORYWELL ISOLATION VALVES VALVE m_M *4 PENETRATION
[
5YSTEM AND Num[R Contalment (Continued)
RHR "B" Test Line E12-F350-67(0)(C)
.T/C RHR "B" Test Line E12-F312 67(0)(C)
T/C R "8" Test Line E12 F305 67(0)(c)
C Ref ling Water P11 F425 69(0)(C)
Tra if. Pump suct' n T/C Refuelf Water P11-F132 69(0)I")
Transf.
ump Suction Inst. Air to 5
P53 F043 70(0)
T/C Post Acc. Sampf E12 F409 718(1 C)
Return and RHR "C" Relief Valve Vent Ndr. to Suppr.
Peel T/C Post Acc. Sample E12- 08 TIB(0)(,)
Return and t
RNR "C" Relief Yalve Vent Her. to Suppr.
Peel T/C Cent. Leak Rata M61- 010 82(i)
T/C RWCU To Feedveter
-F055 (0) 7 iC Suppr.. Peel P60-F011 45(
Cleanup T/C suppr. Peel P69-F034 45(0)
Cleang T/C RWCU Pump 5 fon G33 F002 87(0)
T/C RWCU S$3 F061 88(0)
Di T/C 55W 7 P41-F163A 39(0)(,)
53W P41-F1838 92(0)g,)
6. m I "A".T/C E12-FOMA 313(0)
LPCI "B" T/C E12-F0558 314(0)
Instrument Air T/C P55-F493 335(0)
SLCS T/C C41-F026 328(0) service Air T/C PS2-F476 363(0)
RWCU T/C G33 F120 366(I)
Reacter Sample 833-F021 445(0)
T/C GRAND GULF-UNIT 1 3/4 6-45 AmendmentNo,2g
CONTATNMENT Sv57 EMS Attachm:nt 3 to GNRO.92/00117 Page 42 of M j
SECONDARY CONTAINMENT AUTOMATIC 150LATIOW i
LIMITING C0 f !ON FOR OPERATION U"j 3.6M*Me s~econdary containment ventilation system automati damper \\/valveh ehewn-4*-Tele 3.5.5.21 shall be OPERA
\\
c isolation
--t i::: tes: th er :pe! te the times-ehra, fr. Tett:
eekt4n
2. 0,,, - 13 APPLICABILITY:
OPERATIONAL CON 0!TIONS 1, 2, 3 and *.
ACTION:
With one or more of the secondary containment ventilation system isolation dampers / valves ehrr. fr. T31e 3.0.0.01-inoperable automatic least one isolation damper / valve OPERA 8LE in each affected pene
, maintain at I
open, and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:
ration that is Restore the inoperable damper / valve (s) to OPERA 8LE status a.
b.
automatic damper / valve secured in the iso
, or manual valve or blind flange. Isolate each affected penet c.
within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT Otherwise, in Operational Ccndition ours.
tions with a potential for draining the reactor vesse opera-of Specification 3.0.3 are not applicable.
The provisions SURVEILLANCE REQUIREMENTS 4.6.6.2 damper / valve -:hrr !- Tdle 3.5,5.2 shall be demo Prior to returning the damper / valve to service after maintenance I
a.
control or power circuit by cycling the damper
, repair or complete cycle of full travel and verifying the-gnif' g at gt b.
During COLD SHUTDOW or REFUELING at least once per 1 time.
that on a containment isolation test signal each isolation damper / val actuates to its feelation position.
By verifying the isolation time to be within its 11eit when tested c.
pursuant to Specification 4.0.5.
"When irradiated fuel is being handled in the primary or secondary conta and during CORE ALTERAT!DNS and operations with a potential for reactor vessel.
GRAND GULF-UNIT 1 3/4 6-49 Amendment No. 69, _
{
1 Attachm:nt 313 GNRO 92/00117 i
Pag 3 43 of 94 l
C l
u q
i i
l Pages 3/4-6-50 through 3/4 6-54 have been Intentionally Deleted.
V
.{,
t GRAND GULF-UNIT 1 3/4 6-50 Amendment-No. _
(Next page is 3/4 6-55)
{
r
Attachm:nt 313 GNRO 92/00117 Peos 44 of 94 Ig g 3.s.s.2-1 SECDMARY CONTA!8ptWY VtWTILATION $viism Alff0MY!C !$0LATION V[$
- lNICSM DAfPER/ VALVE PUNCT!0M ISOLATION TI flecends) a.
Despers 111ery tuilding ventilation Supply Damper IT41F006)-(t) 4 Am inry Building Ve til tia on Supply Damper n
(Q17. F007)-(A) 4 Fuel Ha ling Area Vent 11stien tahoust Desper (01742F0(
-(8) 4 Fuel Handit Area Ventilation Exhaust Dame (Q1T42F004)-
4 Fuel Handling A (Q1T42F011)-(A)
Ventilatten supply r
4 Fuel Handling Area V tilation 5 y Damper (Q1T42F012)-(t) 4 Fuel Peel $ weep Ventil;t 5
ly Damper (Q174tF019)-(A) 4 Fuel Peel $ weep Ventilati 5
Iy Damper (Q1T4tF0f0)-(t) 4 Containment & Drywell rea Ventti ion Supply pager 4
(Q1M1F007)-(t)
Containment & 0 11 Area ventilati Seely Damper 4
(Q1M11004)*(A)
Centaineent Dr (Q1M1703s (A) ywell Ares Ventilation t Damper 4
Castai
& Dr (tlM
)-(8) ywell Area Ventilation Enhanet r
4 8
A) sas -(t)* eastonators en the valve /esaper neuters indicate associated i get sem.
e P. RAND GIHF-UNIT 1 3/4 6-50 AMendmed No.
i w
v.
--n-rn.e
-m,-
e
,,,n.,n..v m
n-
.m-
--n,a
.-,.-s
Attachm:nt 3 to GNRO 92/00117 TA8LE 3.C 6.2-1 (ccntinued)
SECONDARY CONTA!WNT VENTILATION SYSTEN AUT ES MAXIMJM V VE FUNCTION ISOLATION TIME (Seconds) b.
alves P1 t Chilled Water System Aux. Bldg. Isol. Valve (P7 F306)-(A) 0 Plant filed Water System Aux. R Mg. Isol. Valve (P71-F3
-(A) 30 Plant Chil d Water System Aux. Bldg.'Isol. Valve (P71-F302)-
4 Plant Chilled (P71-F300)-(A) ter System A.u. Bldg. Isol. Va e
4 Plant Chilled Water (P71-F307)-(8) ystem Aux Bldg. Isol Valve 30 Plant Chilled Water Sys Aux. Bldg.
sol. Valve (P71-F305)-(8) 30 Plant Chilled Water System.
. 81
. Isol. Valve (P71-F303)-(8) 4 Plant Chilled Water System A Idg. Isol. Valve (P71-F301)-(8) 4 Service Air System Aux. 8
. Isol.
Ive (PS2-F221A)-(A) 4 Service Air Systes
. 81dg. Isol. Valv (PS2-F160A)-(A) 4 Service Air S (PS2-F2218)-(ys Aux. 81dg. Isol. Valve 8) 4 Service Air 5 ten Aux. 81dg. Isol. Valve (P52-F1888)- )
4 Inst Air S (P53-F0
)-(A) ystes Aux. Bldg. Isol. Valve 4
Instr nt Air S (P5 F0268)-(8) ystem Aux. Bldg. Isol. Valve F
C Filt-Desin Systes Backwash Aux Blog. 1501.
alve (G46-F253)-(A44) 30 GRAND GULF-UNIT 1 3/4 6-51 hmendmeM No.
~ Att:chment 3 tdGNRO 92/00117 :
Page 46 of 94 TABLE 3.6.6.2-1 (Continued)
- SECONDAltY'CONTAIMENT VENTILATION SYSTEM LVES MAXIltM VLVE FUNCTION.
I5OLATION TI (Seconds)
Valves (Continued)
{
U Backwnh RCVG Tk. Aux. Bldg. Isol Valve i
(G
-F108)-(A) 30-RWCU ckwash RCVG Tk.- Aux. Bldg. Isol. Valve (G36-F 9)-(B) 30 ler System Aux. Bldg. Isol. Valve j
Nuclear B (821-F113) l A) 30 Nuclear Boile System Aux. Bldg. Isol. Valv (821-F114)-(B) 30 RWCU Aux. Bldg. Is 1. Valve (G33-F235)-
)
30 RWCU Aux. Bldg. Isol. Valve (G33-F2
-(B) 30 SPCU Aux. Bldg. Isol. V ve (P60-F 3)-(A) 30 SPCU Aux. Bldg. Isol. Valv (P aF004)-(B) 30 SPCU Aux Bldg. Isol. '!alve F007)-(B) 30 j
SPCU Aux. Bldg. Isol Val (P60 008)-(A) 30 Fire Protection System ux Bldg. I
1. Valve (P64-F282A)-(A) 4 Fire Protection Sy (P64-F283A)-(A)
Aux. Bldg. Isol, alve 4
Fire Protectio System Aux. Bldg. Isol. Val (P64-F332A)-
)
4 Fire Pro ion System Aux. Bleg. Isol. Valve (P64-F
)-(B) 4 Fire taction System Aux. Bldg. Isol. Valve (P64 2638)-(8) 4 F
e Protection System Aux. Bldg. Isol. Valve P64-F3328)-(B)
Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F062)-(A) 9-GRAND GULF-UNIT 1 3/4 6-52 kmendme,d No..
tr
~
.a. to GNRO.92/00117 paga 47 of 94 -
. TABLE 3.6.6.2-1 (Continued)
SEC0 4 ARY CONTA! *ENT VENT!t.ATION $YS SOLATION DAMPE/ VALVES VALV FUNCTION-MAXIMUM ISOLATION T E Va es (Continued)
(secon44 Cond.
Refuel Water Transfer Aux. Bldg. Isol. Valve (Pil-F
)-(A)
Cond. & Re 4
1 Water Transfer Aux. 81dg. Isol. Val (P11-F066,-
)
Cond. & Refuel 4-(P11-F047)-(A) ater Transfer Aux. 81dg. Isol.
alve Cond. & Refuel Wata 4
(P11-F063)-(8)
Transfer Aux. Bldg. I
1. Yalve Cond. & Refuel Water Tra 4
for Aux. 81
. Isol. Valve (P11-F065)-(8)
Cond, & Refuel Water Transfe 4
(P11-F067)-(8)
Aux.
Idg. Isol. Valve cond. & Refuel Water Transfer 4
(P11-F061)-(8) 81dg. Isol. Yalve Floor and E 4
(P45-F158)-(quipment Drains ystem Aux.Idg. Isol. Valve A)
Floor and E 9
(?4S-F160)-(quipment Dr ns Systas Aux. 81 Isol. Valve A)
Floor and E 9
(P45-F163)-(quipmen Drains System Aux. 81dg. In 1. Valve A44)
Floor and E 9
(P45-F159)-(qui Dreins System Aux. 81dg. Isol.
lve Floor and i
9 (P45-F16 -(t)pment Drains System Aux 81dg. Isc.1. Valve s
Makeup (P21- 024)-(A&B)ater Treatment Sys. Aux. 81dg. Isol. Valve 0
30 66-F029A)-(A&R)stic Water System Aux. 81dg. Isol. Valve PSW Aux. 81dg. Isol. Valve 4~
(P44-F121)-(A)
GRAND GULF-UNIT 1 100 3/4 6-53 Amendment No. 42 3
- v-t3 GNRO.92/00117 Pags 48 of 94 TA8tf 3.6.6.2-1 (Continued)
HICONDARYCOETA1WENTVENTILATION$YSTEMAUTOMA gg min
/
VAL FUNCTION ISOLATION TIME /
Va es (Continued)
__ (Seconds)- /
P8W A
. 81dg). Isol. Yalve (P4 Fi J-(A 00 PSV Aux. 8 (P44 F117). 9). Isol. V61ve PSV Aux. B1dg.
sol, yelve 4
(PG'F118)-( A)
M0 PSW Aux. 81dg. Isol. Yalva (P44-F120)-(s)
PSW Aux. 81dg. Isol. Val (P44-F123)-(5) g P5W Aux. 81dg. Isol. Valve (P44-F116)-(t).
PSW Aux. 81dg. Isol. Yalve (P44-F119)-(8) 100 RHR Dischar (E12-F203)-(ge To Liquid Radwte Valve A&8) 33 GRAND GULF-UNIT 1 3/4 6-54 Amendment go, ;c)
I
- - - ~ - ^ ' ~ ~
~ ' ~
Attachmont 3 to GNRO-92/00117 Page 49 of 94 ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL EQUIPNENT PROTECTIVE DEVICES PRIMARY CONTAINPENT PENETRATION CONDUCTOR OVERCURRENT LIMITING CON 0! TION FOR OPERATION 3.8.4.1 -kM grimary*fand bc.k JA) devices err '- hbh 3.0. t.1-1 shall be OPERA 8LE. containment p'enetration conductor Dnsch D 9
5*U b APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With one or more of the primary containment penetration conductor over-a.
current protective devices 2rr '1 hth 3.0.0.1-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the a'fected syst*m, and:
1.
For 6.9 kV circuit breakers, de energize the 6.9 kV circuit (s) by tripping the associated redundant circuit breaker (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the redundant circuit breaker to be tripped at least once per 7 days thereafter.
2.
For 440 volt circM t breakers, remove the inoperable circuit breaker (s) from service by racking out the breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the inoperable breaker (s) to be racked out at least once per 7 days thereafter.
'Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREN NTS
~
ganA t:n=c.W 0 1
4.8.4.1 Each of the primary containment penetration conductor overcurrent protective devices 2 r h Tdh 2.0.i.1-t shall be demonstrated OPERA 8LE:
a.
At least once per 18 months:
1.
By verifying that the medium voltage 6.9 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:
a)
A CHAl#IEL CALIBRATION of the associated protective relays, and b)
An integrated systes functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuitsfunctionasdesigneg:-d:: :;--ifhd h hth GRANO GULF-UNIT 1 3/4 8-19 Amendment No. 69)
(l
. +.
' Attachm:nt 3 to GNRO-92/00117
Page 50 of 94
! INSERT 1-(i;e., circuit breakers)1 associated with each primaryJ containment 1 electrical pene'tration circuit
-INSERT 2 The scope of these protective circuit breakers excludes those circuits for which credibleffault currents:would not exceedithe:
electrical penetration design rating.
4 Insert for TS page 3/4_8-19
_..~.
m.-
1 Attachm:nt 3 to GNRO-92/001M
' Page 51 of 94 ;
i
. ELECTRICAL POWER SYSTEMS-3 SURVEILLANCE REQUIREMENTS (Continued 1 l
i c)
For each circutt. breaker found-inoperable durin
-functional-tests,;an: additional representative g these-sample of;
~
'at least 10% of all the circuit breakers ofrthe inoperable.-
type shall 'also:be functionally tested untillno:more failures.
l are found.or all circuit breakers 1of.;that type have been; functionally tested.
2.
By-selecting and functionally: testing a representative = sample of at least.10% of each type of.;1ower voltage circuit breakers.
Circuit breakers selected for, functional l testing..shall be selected on a rotating basis.
T:7 th: ?:n r ;;!!: :':fr::it Srnt;r; i
th: nzfr:! tri; ::t; t rd 05:71'ci n d t = :;: n d'ti n ;;;.
'!:t:d '- T:tt; 3.".' 1-L Testing of these circuit breakers shall; consist of injecting a current in excess:of.120% of_- the breakers' nominal setpoint-and measuring the response time; s _The measured response; time will=be compared.to the_ manufacturer'si data to: insure 1that it isLiess than or_ equal to;a value spectfled by_the manufacturer._=Circult'breakersifound inoperable.during.
' functional testing-shall be = restored-to OPERABLE'statusLprior
- to resuming operation of theiffacted equipment.- For_each circuit-breaker found inoperable during these functional-tests, an additiona1Lrepresentative: sample of-at least 105 of-all'the circuit breakers of the inoperable type shall also be functionally.
tested untti:no more failures;are found orta11 circuit breakers of that typeLhave:been functionally tested.
b,.
-Atlleast once-per 60 months by subjecting each circuit breaker!to'an inspection and. preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
4 -
s
GRAND GULF-UNIT 1 3/4 8-20_ A m m b a.e8 ' b
. =...
a
> : Attabhm:nt 3 t3 GNRO 92/0011.T
Page 52.of 94 <
l-)a 7
-t
-1
-i i
j Pages 3/4'8-21 through-3/4 8-45 have been-Intentionally' Deleted.
d 9
GRAND GULF-UNIT 1
-3/4 8-21 Amendment No.
-(Next page is 3/4 8-46) r
-- to GNRO 92/00117-Pago 53 of 94~
TA8LE 3.8.4.1-1 i
PRIMARY CONTAINMENT PENETRATION CON 00CTOR
-~~
OVERCURRENT PROTECTIVE UliVICE5 TRIP
RESPONSE
SYSTEM /
DEVIC NUMBER SETPo!NT AND LO TION TIME COMPONENT (Amperes)
(Cycles)
AFFECTED 4.
6. 9 Circuit Breakers 252 1103-8 7200/45/*10d 60 Reactor Recir. Pue:
252-1103-C 7200/45/* 1 60 833C001A 252 1205 8 7200/45/2 1 6
252-1205-C 7200/45/2 1 Reactor-Recir. Pump 0
833C0018 b.
480 VAC Circuit reakers Stored Energy Type 005 with S$3G3 Trip ing Device TRIP RES E
BREAKER SETPOINT T
SYSTEM / COMPONENT-NUMBER (Asperes)
(5 onds)
AFFECTED 52-12202 1200
- 0, 7 CONTAlleqENT COOLING 0
FILTER TRAIN NEATERS (NIM 4100028-M) 52-12209 2000 0.
CNTNT POLAR CRANE (Q1F13E001-N) 52-11502 1200 0.07 CNTMT CLG. FILTER TRAIN HEATER (N1M410002A-N) 52-15105 0.07 04 LL PURGE COMPRESS.
(Q1E C001A-A) 52-16204 2000 0.07 DRYWELL RGE COMPRESS.
(Q1E61C001 -8)52-164 1200 0.07 HYOt0 GEN REC NER (Q1E61C0038-8) 5 5205 1200 0.07 HYOR0 GEN RECOMBINE i
(Q1E6IC003A-A)
Primary current /setpoint.
GRAND GULF-UNIT 1 3/4 8-21 An pry ND
_ _. to GNRO.92/001.17 i
Pags 54 of 94 TA8LE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVEncvRRENT PROTEGTIVE DEVICE 5 460 VAC Circuit Oreakers.
c.
Ided Case Type M2M TRIP SREAKE SETPOINT RESPON5E TIME SYSTEM /
PONENT NUMBER (Amperes)
(Seconds)
AF CTED 52-1112 01 500 0.100 4 TRON MN SYS IVE MECHANISM (IC51-J001A) 52-1112-02 500 0.100 NEUTRON MON SYS DRIVE MECHANISM (1C51-J0018) 52-1112-03 500 0.
NEUTRON MON SYS ORIVE M CHANISM-
,(iC51-J001C) 52-1112-04 500 0.100 NEUTit3H NON SYS DRIVE M CHANISM (1C51 J0010) 52-1112-05 175 0.100 STEAM TUNNEL CLR INSIDE CTNT FAN (NIM 41C004A-N) 52-1112-06 500 0.100 NEUTRON NON SYS ORIVE M CHANISM (1C51-J001E) 52-1112-07 0.1 LIGHTING XFMR 1X105
-(N12145105-0).
52-1112-10 1200 0.100 LIGHTING XFMR 1X109 (MIR185109-0) 52-1112-14 500 0.100 WATER SAMPLE STA ILTER TRAIN HEAT (N1M41-0006-N) 52-11 15 320 0.100
.NWCU BAC TRANSFER P
(N1G36C004->
-1112-18 24 0.100 PREC0AT TANK A0 TOR (NIG360019-N)
GRAND GULF-UNIT 1 3/4 6-22 Amendment No.
66, I
Effective Date: # x t e 4 I
Attachmsnt 3 to GNRO 92/00117 Page 55 of 94 TABLE 3.6.4.1-1 kCentinued) pt! MARY CONTAllgetf,SgNETRAT"'ON E-Cigt
~
CVERCURRamT Pgurz6rlyg LgVIcn
~
440 VAC Ctecuit greakers (Continued) c.
ded Case,. Type NZN 4
TRIP RESPON$(
IREAKER SETPOINT TIM
$Y COMPONENT NUNGER (Asperes)
(seconds)
FECTED-52-1112-20
-M 0.100 AWCU FII. TEA DEMIN HOLDING PUMP-(M1434C001A-N) 52-1112-21 0.100 440 V RECEPTACLE 52-1112-22 5
0.
NOV-$7N TUMMEL COOLIR INLIT (N1772F1804 M) 52-1112-24 32 0.100 NOV CLEANMP LINE RECIE LOOP A (Q1433n00-W) 52-1112-27 24 0.100 RES!N TANK AGITATOR (N18380020-#)
52-1112-28 34 0.100 m ACU WAT EENANGER BYPA$s (M1833F104-W) 52-1112-31 34 0.
m ACU WAT IE NANIER SYPA&$
(N1833PO44-W) 52-1112-34 0.100 KAC. RECIE. Map SPACE MATER (TR1833C061A) 52-lu2-37 aos 0.100 v RtctPTACLE.
52-1112-44.
0.100 1e4TER SN9tf STA LTER T M N FAN
-9006 #)
52-41 6
0.100 RfAC SMFtf PAML M
(
52-1113-07 125 0.100 CImtf Fla0R DAAIN 3489 (N174SC019-N)
GAAND GULF-UNIT 1 3/4 8-23 Amenennt No. 21, f
Effective r, ate: OCT 2 0 !!I6
Attachnitg @ to,GNRO 92/00117.
Page 56 of 94 TABLE 3.8.4.1*1 (Cantinued)
MIDMY CONTAlleeff_parftATION fp0gCTee ev===~. ara Peauivt ouvigi J.thVAbAfetuittreaknes(Cantinued) i.Q... Tm Nm
/
\\.MTPOINT TRIP 2E370N$t
~
\\
BARAKER TM MUMBER KAspeces)
(Sessnes) l' ECftB 52 n'121 0.101 LL EUIP.
AAIN Sise MJMP (N1P43C005-M) 52-1113-30 28 0.100 NOV AldCU MR OUTL TM Vt.V (M1813F2St4N) 1 GAAND RAJ-UNIT 1, 3/4 6 23a h t 88- *e-i Effective Gam: OCT i 5 till S
... ~-
. to GNRO-92/00117 Pago 57 of 94 TABLt 3 3.4 1 1 (Continued)
PN! MARY CONTAlletWT EniruATION M y
unsaansi rwiec Ivy pavict}
c.
VAC Circuit Seeakers (Continued) sitAttR TR!P NLMit stTro!wf usP0Ns(
(Asperes)
TIM SY$T COMPONENT (seconds) 5: M 11 44 FECTE0 5I-1113 4!
0.100 5
V RECEPTACLE 0.100 52-1151 06 SPAAt 240 0.100 CNTNT COOLING FILTit TRAIN FAA 52 1151-07 (N1M 10002A N) 17.5 0.
REAC. RECIRC. nPU GIL PWP FAN 52-n51 10 (IG0330003A3-N) 600 0.1M REAC. IRCIRC. NPU 0!L M89 52-1151 12 (IC3330003Al N) t 75 100 IOV - AtCIAC PUMP SUCTION 52-n53-19 (01833F023A N) 75 0.100 lov atClac PUMP 015CNetSt 52-n5120 (41033F087A N) 600 0.100 atAC. REC!tC. MPU L FWD 52-1151-21
(
.5 N) 0.100 MCitC. MPu SIL FAA 52 1151-22
(
40 M) 0.100 SRWELL CAL tensTI 52-ust-(
se 0.100 gewtLLEqPT.
mesp Msp 52-1 1-24 125
-(SP4840084-N) 0.100 Omit FL300 St.
See PUNP 4 GULF-UNIT 1 (IE1740C010A M) 1 3/4 0 24 A "'M + +8
~
~ ~ ~
. to GNRO-92/00117
' Page 58 of 94 TABLt 3.8.4.1 1 (Continued)
PRDWrY CONTAffeeff PENETRATION ** _iut ev
---T -o u u n san m bv4Ccfmvitareakan(CantinE) c.
yC....T,,..
TRIP Rispenst BREAKit StTPOINT TDE SY NUMBEA (Aa,erts)
(Sesomes) iin 52-u22-04 800 0.100 CLa FAs
!L WIT FAN
( M 180014-N) 52-1222 05 240 0.100 C G T C00U NG SYS CHAR TRAIN FAN (M1M4100028 M) 52-u22-Os uoo 0.
u 0nfins xpna IX104 (Nutiss206-t) 52-E22-11 400 0.100 400 V MCIPTACLES 52-1222 3 500 0.100 REAC. MCIRC. MSF
~
SPACEISATER (151833C383)
S2-u22 u 75 0,
pov - meu affunn
-TO REACTOR (R1833PO42-N)
$2-1222-20 M
0.100-IEk - VERSEL OAh!N LDE WIEC.
(43833PMk#)
52-1222-E 75
-4.100
- CLEAIEF LDE
.- N WHELL
(
N) 52-us2-u a
0.10e lov -
Janur unt-
. MClat t
(
)
52-1251 175 4.100 STEAM Cut.
DEME GlBit OGM41CIOG 8).
-sa-
-07 30 0.100-o mir c et u sTI 289 Mgr (N1MsCar74 a)
GRAf8 GULF-Wi!T 1 3/4 4-25 ggg e
~
w
Attachm:nt 3 to GNRO 92/00117 Page 59 of 94 TA8tf 3.8.4.1-1 (Continued)
^
_ ~ P#DWrY COWAlmtWT =' TAT"0N E7f etoa QVIOnniKT PggTEGT;;YI ON CII VAC Chit treaken (Cantinued) c.
Me a case, Type mzM TRIP 8REAKIA SETPOINT agsponsg TIM SYSTEM /
NUM6(R (Asperes)
(5eConds)
AF CTED 52-1251-13 000 0.100 cLA FAm IL UNIT FAN N1M414001C-N) 52-1251-15 3
0.100 MOV - RWC3 MX INL 150L VLV (NIG33F254-M) 52 u51-la 34 0.100 MOV - RESEN NEAT DCHAnSER SYPASS (41433F107-M) 52 US1-19 34
.100 Nov - SCU ORAIN FLOW ORIFICE SYP (M1830P831-#)
52-uSI 20 320 0.100 CNTNT soutp ceAIN punP (N1745C0044-R) 52-u51-22 32 0.
MOV - SCU 70 FLT "5" ISOL VLV j
(N1833F296-M) 52-1251-28 1200 0.100 LISITDIS XFMt 1Xu2
~(ptstatiis-g) 52-usi-2s 5
0.100
- sm TunntL INLIT
(
N) 52-1252-23 80 0.100 FLOOR ORAIN Pup
(
N) 52-1252 500 0.100 PUEL SYS m (M1F11ER15-MC 14 u-01 34 0.100 Mov - vt15tL V9ff!LAT10n
/
(Q18217002-M)
GRAND GutF-UNTT 1 3/4 6-28 Amendment Ms.21,. -
Effsettve cata:
90 t o LE.
.. to GNRO.92/00117 Page 60 of 94 TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTA"lMENT PENETRATION CMXTOR UYgNCURRUMT PuurtcTIVE DEVICE 5 VAC Circuit Breakers (Continued) c.
Mold se, Type N2M TRIP
RESPONSE
BREAKER ETP0!NT TIME
$75T COMPCNENT NUPSER
(
res)
(Seconds)
FFECTE0 52-1412-01 17-0.100 REAC RECIRC HPU OIL P H FAN (N1833000383-N) 52-1412-02 60 0.100 CNTNT CNEM WASTE StMP PM (N1P45C0278-k) 52-1412-03 60
0. 00 DRWELL FLD04 DRAIN S W P M (N1P45C001A-N) t 52-1412-05 12.5
.100 M V C 2 C00LWTR PRESS CONTROL (NIC11F003-N) 52-1412-08 105 0.1 MDV REAC RECIRC
W 8 SUCTION (Q1833F0234-M) 52-1412 09 175 0.100 RWCU DEMIN PREC0AT PUMP f
(NIG36C002-N) 52-1412-12 0.100
(* MIN ING P M (N
IS-N) 52-1412-15 800 0.100 REAC CIRC HPU 0!L (N183 381-N) 52-1412-320 0.100 CNTNT EQU ORAIN Simp (N1P45C004A )
52-12-20 800
0. 100 440 V RECEPT E
4-1412-23 600 0.100 REAC RECIRC HPU OIL PUNP (M1833000342-N)
GRAND GULF-UNIT 1 3/4 8-27 A w d m e A h)o.
I
Attachmsnt 3 to GNRO.92/00117 Page 61 of 94 TABLE 3.8.4.1-1(Continued)
PRIMARY CONTAIMWIT PENETRATMON CC9XTOR switGTIVE UEVIGt5
~
/
t UVE8Ch uMI 480 VAC Circutt Breakers (Continued) c.
ed' Case. Type NZM
\\
TRIP BREAKER SETPOINT
RESPONSE
TIME NUMER (Amperes)
(Seconds)
STEM / COMPONENT AFFECTED 52-1412-25 17.5 0.100 REAC RECIRC HPU 0!L Ptw FAN (M1833000384-M) 52-1412-26 38 0.
MOV REACTOR VESSEL HEAD YOtr (Q1821F001 N) 52-1412-28 34 0.100 MV REACTOR VESSEL HEAD YENT (Q1821F005-M) 52-1412-32 800 0.100 CNTNT CLR FAN COIL UNIT FAN (NIM 418001A-N) f 52-1412-33 105
.100 MDV - REAC RECIRC PLN A GiSCHARGE (Q18'3F0678-M) 52-1412-35 500 0.1 CR0 RE M VAL HOIST L
(M1M31E003-N)-
52-1412-39 0.100 DRWELL VALVE H0IST -
(Q1M31E002-M) 52-1412-41 32 0.100 AIRLOCK A
SHOWER FAN (N
1C005-M) 52-1511-0 50 0.100 MOV -
INL IM I VLV (Q1G33F PA) 52-1-24 50 0.100 NOV RWCU NL QUT 150L VL (Q1G33F253-A) 52-1511-44 12.5 b.100 MOV - DRWELL CLG WATER ISOL (Q1P42F116-A)
GRAND GULF-UNIT 1 3/4 6-28 Amendment No. 43._
l j
~~
~~
~
Attachm:nt 3 to GNRO 92/00117 N
TA8LE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 480 VAC Clacuit Breakers (Continued) c.
M ded Case, Type NZM i
TRIP
RESPONSE
BREAKER SETPOINT TIME SYSTEM /C.PONENT NUMBER (Amperes)
(Seconds)
AFF CTED 52-1511-54 24 0.100 Sp e 52-1521-02 0.100 V COMBUSTIPLE GAS CONTROL SYS o
(Q1E61F003A-A) i, 52-1521-03 6
0.100 HOV COMUSTIBLE GAS CONTROL SYS (Q1E61F005A-A) 52-1521-07 32 0.
O MOV SUPPR. POOL MAKE-l!P VALVE (Q1E30F002A-A) 52-1521-14 600 0.10-0 SCL SYSTEM PUMP (Q1C41C001A-A) 52-1521-15 5
.100 STORAGE TANK OUTLET VALVE (Q1C41F001A-A) 52-1521-28 12.5 0.100 MOV IN3T LINE ISOL VALVE (Q1M71F595-A) 52-1521-44 32 0.100 MOV - SUPPR POOL KE-UP VALVE 1E3CF001A-A) 52-1531-24 12.5 0.100 MOV DRWELL COOL ISOLATION (Q1P72 5-A) 52-1531-25 8
0.100 MOV - R OR WATER SAMP (Q1833F020-A GRANO GULF-UNIT 1 3/4 8-29 Amendment No. 21, 100 _
f 1
Attachm:nt 3 to GNRO 92/00117 Page 63 of 94 1
\\
{A8LE 3.8.4d-1 (Continued) i Pa! MARY CONTAWDif PfiETRAT'ON CONDUCTOR gytscuni,nT rwrec 'Ivt v ertcts c.
VAC Cincuit treakers (Continued)
~ N Mule Ca.se, Type NZM sk y
RESPON$E BREAKER
.",yER (Asceres)
SYS CONPONEM (5
es)
FECTED 52-1531-36 20 0.100 V - LPCI A INJECTION ISOL 52-1531-44
)
125 0.100 Nov - w a U9PER cm pngg $pg,,
~^)
52-1531-49 32 0 00 Mov-Dawgu C m W371 Is0L 52 1531-50 105 O.100 m.g, CONTAIm eff SPRAY
$2-1541-32 32 0.100 noy.Cas W CONT C3 y A ggy
'}
52-1542-05 320 0, m DR M LL Cootta FAN COIL UNITW
$2-1542-06 3
02 Dewett Coo (a FAN C0!L WIT
(
}
l 52-1542-07 320 0.100
% ggg g AN CDIL tal!T 180034-A)-
52-1542-g l
01#
a C00La FAN IL181IT l
52-2-Og 320 02 GaWER a
FAN COIL IT (NIMS
-A)
""II I 3/4 6-31 (3% nag eb.
A 1
l..
Attach'mGnt 3 to GNRO 93/00117 Page 64 of 94 i
TABLE 3.8.4.1 1 (Cont h )
>Rl'AARY CZJChlIGGli WW%T'QN M.M
~
QVERCh=-=T PuWTE TEVE OEVIGII
~
c.
440 AC Circuit treekers (Continued)
Mold ese. Type NZM TR19 alsponst
~
8REAXER SETPCINT TIMg
$YST.
{#7 NUMSER (Aspen.5)
(Seconds)
FECitr, '
52-1542-10 20 0.100 RYWELL C00LER FAN COIL UNIT (NIMS 180044 A) 52-1542-14 5
0.100 NOV - ORYWE R COOLER INLIT (N1772F145-A) 52-1542-15 5
0 00 MOV - ORYWER COOLEA INLE7 (N1P727114-A) 52-1542-16 5
0.100 MOV - OtvWER COOLIR INLEY (N1772F139 A) 52-1542 17 5
0.100 NOV - ORTWER C00LtR INLET (N1772F111-A) 52-1542-18 5
0.
nov - OrvWtu COOLIR INLIT (N1772F101-A) 52-1542-19 5
0.100 MV - ORTWLL t
6 ! ALIT (N1772FU4-A)
$2-1542-21 000 0.100 stC1 OPRATIM L
MATD 10002) 12-1542-22 34 0.100 PUME CSIP AMI L PWW
(
A)
L 52-
-23 500 0.100 asPut PLATP0aN Assy i
(
)
1542-24 175 0,100 atVWELL MCI FAN (MUSIC 001-A)
GRAND OULF-UNIT 1 3/4 4-31 Aaeneent M. 21, -
Effective date:0Cf 2 0 '!!i
Attachmsnt 3 to GNRO 92/00117 Page 65 of 34 i
TAalf 3.0.4.1-1 (Continued)
PttMARY CONTA W ;
iwAff0N M?tet ovuncunnuir rnorucTrvtytvIcts f
c.
440 AC Cfrestt Inst rj (continued) ttsided sa. Type N2M TRIP 5AEAKEA A!!PON5l INT TIME SY mtR
( % ms)
(seconds)
COMP 0NEW Arrtcito
$2-1542-29 1200 0.100 STtY uQ CONTACT.
SYS MIXIM HEATIA (Q1C410003) 52-1611-10 12.5 0.100 W - ORWELL COLT. TX 0'IT117 1501.AT10N (Q1G41704441 52-1En 13 12.5 100 MOV - OCW CTNT STM TNL CLR I5QL (Q1772F113-8) 52 14n-18 50 100 MOV-M RI NO 5M IMO ! SOL (Q1E12F3944) 52-16n-25 12.5 0.100 Mov - DEWELL CLA WTR ISOL (41742F117-8) 52-16n-31 12,5 0.100 W - ORWELL
L8 Wft INL ISOL L
4-8)
'52-15n-;*
0.100
- CfW CLA
!a0LATION
(
)
52-18u-42 12.5 0.100 m
TimutL ISOL
(
)
52-1811 IL5 0.100 M OCW 113eWL CL4
-(Q1772F129-8) 52-14 -44 34 0.100 W - SERVICE A DawtLL !sRATI
/
(Q1PS2F199-8)
/
GAAsc GULF-UNIT 1 3/4 #*12 Amenement me. 21, T 2 011..
(ffective Date: vC 8
t
Attachm:nt 3 to GNRO.92/00117 Pago 66 of 94 TASLE-3.8.4.1-1 (Continued) 7 9ERCutRENT PRorucTIVE DEVICE
~
~
c.
440 V Circuit Breakers (Continued)
Moldeo C
, Type NZM TRIP
RESPONSE
BREAKER TPOINT TIME NUMBER
(
,eres)
(seconds)
SYSTEM / COMPONENT AFFECTED 52-1621-03 7
0.1 MOV - DRWL NYDR INST LINE 150 (Q1E61F5958-B) 52-1621-04 7
.100 MOV - DNWL NYDR INST LINE 150 (Q1E6175974-B) t GAMG GULF-UNIT l' 3/4 6-32a Amendment No. 7 --. !
j
.. to GNRO 92/00117 Page 67 of 94 TA8LE 3.8.4.1-1 (Continued)
PRIMARY CONTAIMNT PENiTRATION CONOUCTOR OVERCUnngNT PRUTEC'IVE DEVICE 5 80 VAC Circuit Breakers (Continued) cc Mo d Casa, Type NZM TRIP
RESPONSE
/
BREAKER.
SETPOINT TIME SYSTp/ COMPONENT NUMBER (Asperes)
(Seconds)
/AFFECTED 52-1621-05 7
0.100 MOV - ORWL HYOR INST LINE 150 (Q1E61F5950-8) 52-1621-06 7
0.100 MOV - DRWL HYDR INST LINE ISO (Q1E61F5970-8) 52-1621-07 7
.100 MOV CTNT HYOR INST LINE ISOL-(Q1E61F5968-8) 52-1621-08 7
0.100 MOV CTNT HYOR INST LINE ISOL (Q1E61F5900-8) 52-1621-09 7
100 MOV CTNT NYOR INST LINE ISO (Q1E61F5960-8) 52-1621-10 7
0.100 MOV CTNT HYOR INST LINE 150 (Q1E61F5900-8) 52-1621-16 10 0.100 CONTAI N NT ISOL' LVE
(
33F128-8) 52-1621-17 6
0.100 MOV DRWL PUAGE IN (Q1E61 38-8) 52-1621-18 6
0.100 MOV - 0 PURGE-VACULM REL EF (Q1E41F00 B) 52-1 1-19 24 0.100 SPARE GRANO GULF-UNIT 1 3/4 8-33 b"I"*
to GNRO 92/00117 -
Page 68 of 94 TA8LE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CON 00CT
_~~
OVERCURRENT PROTECTIVE DEVICE 5 480 VAC Circuit 8reakers (Continued) c.
ed Case, Type NZM BREAKER SE NT NUMBER (Asperes)
(S nds).
A C
52-1621-40 32 0.100 MOV - COM8 GAS CONT COMP 8 OUT (Q1P41F1688 3) 52-1631-06 1
0.100 MOV - RNR 8 UPPER CTMT POOL SPRAY (Q1E12F0378-8) 52-1631-13 320
.100 MOV - RNR 8 LPCI (Q1E12F0428-8) 52-1631-15 105 0.100 MOV-SSW TO RNA SYSTEM (Q1E12F0968) 52-1631-20 12.5 0.100 MOV - MIN STEAM LINE DRAIN IN80 (Q1821F016-8) 52-1631-29 600
.100 STAN08Y LIQUID CONTROL PUMP (Q1C41C0018-8) 52-1631-33 105 0.1 goy. RNR 8 TO CONTAIMENT SPRAY (Q1E12F0288-8) 52-1631-34 05 0.100 MOV - RCIC STEAM SUPPLY LINE ISOL Q1E51F063-8) 52-1631-35 5
0.100
$ RAGE TANr.
OU VALVE (Q1C F0018-8) 52-1631 7 240 0.100 May.
A SHT DN CLG I ISO (Q1E12F009 )
5 1631-38 32 0.100 MOV - RCIC ST WARMUP LINE I (Q1E51F076-8)
GRAND GULF-UNIT 1 3/4 8-34
/b,m Am=.o+ d - J
. = _
Anachment' 3 to GNRO 92/00117 Pago 69 of 94 t
TA8LE'3.8.4.1-1 (Contineed)
PRINARY CONTA!W DfT PENE7 RAT;'0N N igg-PL""=rt"I rmn tGT VE LEVI 6as
c. _480 VAC Circuit Breakers (Continued)'
ided Case, Type NZN TRIP R
SET M NT
RESPONSE
TINE SYST COMPONENT (Asperes)
(Seconds)
FFECTED 52-1631-41 3
0.100
- REACTOR WATER SAMPLE-
-(Q1833F019-8) 4 52-1631-47 0.100
-NOV - INST-AIR ORWL OUTBD ISOL (Q'#53F007-8):
)
52-1631-50 32 0.
m y. RWCU OUTLET TO MAIN CO M ENSER (Q1833F028-B) 52-1631-51 32.
0.100 MV NWCU SYS ISOLATIN VALVE (Q1833F053-B) 52-1631-52 50 0.100 my - RWCU SYS ISOLATION L
(Q1433F040-B) 52-1631-53 50 100-
- m y. RWCU 5YS IS0tATION (Q1833F001-8).
52-1641-06 32 0.100-My - Mutt up WRTH CNTM ISOL (Q1P21F018-4) 52-1641-07 50 0.100 my. nNeu int l
150L VLV
(
251-8)
L 52-1641-08 50 0.100-my aNcy Our Im I
-VLV
(
8) 52-1
-16 7
0.100
-MVI LIM'I
. ISO (Q1823F591-8 GRAND GULF-UNIT 1 3/4 3-35 Amendment No. 43 I
l.
~ ~., _,
.. to GNRO 92/00117 4
Pegs 70 of 94
- TABLE 3.8 4.1-1 (Continued)-
_ PRIMARY CONTAIMENT PENETRATION CMXTOR OVERCUnn6NT PRUTECTIVE DEVICE 5.
480 VAC Circult-Breakers (Continued) c.
ed Case, Type NZM TRIP
RESPONSE
BREAKER
-SETPOINT TIME SYST COMPONENT NUMBER (Amperes)
(Seconds)
FECTED 52-1641-18 7
0.100 V --INSTRUMENT LINE IN80ARD ISO (Q1023F593-8) 52-1641-24 0.100 CONTAIMENT ISOL VALVE-(Q1833F126-8)..
52-1641-26 32 0.
NOV - ORWELL'
CHEM WASTE ISOL (Q1P45F097-8)_
52-1641-35 32 0.100 MDV - SUPPR POOL l
MAKE UP VALVE-(Q1E30F0018-8) 52-1641-36 32' O.100 MOV~- SUPPR POOL' MAKE UP VALVE (Q1E30F0028-8)-
52-1642-05 320
.100 DRWELL COOLER -
FAN COIL UNIT-(N1M5180018-8)'
52-1642-06 3
1 0.1 DRWELL COOLER ' ' '
FAM C0IL UNIT (NIM 5180028-8) 52-1642-07 328*M*,.*
0.100 DRML C00 LEU Y. c -
FAN CGIL-UNIT f
NIM 5180038-8)
% 'e. I 52-1642-0.100 0
L C00LER
F C0IL-UNIT (N
-8)-
52-42-09 320 0.100-ORWELL C0OLER
-FAN C0IL UNIT
-(N1M51800 -8)
. GRAND GULF-UNIT 1 3/4 8-36 Amendment N 100, -
Attachmont 3 to GNRO.93/00117 Page 71 of 94 4
1 TA8LI 3.3.4.1-1 (Continue 4)
PRIMARY CONTAIMENT PENETRATION CEr_--;igt UVERCUnnaNT ruuTECTIVE DEVICE 5
~
VAC C1PCutt treakers (Centinued)
C.
Mold aee Type NZN TRIP RESPON5E 8REAKER SETPo!NT TIME SY COMPONENT MUM 8ER Amperes)
(Seconds)
AFFECTED 52-1642-10 3
0.100 Ot M LL C00Lgn FAN COIL UNIT (NIM 180044 8) 52-1642 14 12.5 0.10 M O V - O R W E Lt.
C00LfR INLET (N1772F144 8) 52-1642-15 12.5
.100 NOV - OtWELL COOLIR INLIT (N1772Fu7-8) 52-1642-14 12.5 0.100 NOV - ORWELL C00LIA INLIT (M1772F140 8) 52-1642-17 12.5 O.
NOV - OR M LL C00 Lit INLIT (NIF72F112-4) 52-1642-18 12.5 0.100 NOV - OR M LL COOLER INLf7 (N1F72 Flat-9) 52-1842-19
.5 0.100
- ORWELL INLIT
( P72F136-8) 52-1642-21 24 0.100 PUISE COMP AUK L^ Ptw
-(Q154 14-8) 52-1542-175 0.100-OWL SC FAN (N1M
)
/
GAAND GULF-UNIT 1 3/4 8-37 w t No. 21c Effective Date:g., O E -
l Attachm:nt 3 to GNRO 92/00117 Page 72 of 94
{
1 t
TA8LI 3,3,4,1 1 (Catfw)
- Pt!MARYCONTAlmeri-M UD m QVENCURRINT W i,E rtyr psyIcis- "m e (d) 125 C Cfrevit Seeakeg GL T to SsE4ER gj -
At3POMsg
~~
NV"SIA
( Aseeres) m,)
(NT 72-11A-23 30 5.0 AUTOMAT!C OtPRt354atIAftes72-11A 25 SYSTEM vatygs 15
$.0 agyg7g gygygg, PANEL /AU70M47!C DEPRES5UA!ZAft0N 72 11A 30 SYSTEM VALyt3 gg 5.0 REAC704 Pa0ftCit0m SYSTEM /SAcap
11A-33 5CAAM VAtyt 15 CONTA!m ert &
O m stLt 130Larg e 72-11A-33 SYSTEM AssamCIAfice 15 5.0
85!OUAL NEAT AEMOVAL SYSTEN 72-115 14 VALyts 50 5.0 285!OuAL~ NEAT 72-112-28 R8MIVAL SYSTR 15 5.0 gm 72-112 JD ANEL/At$ VA:,vts 5.0
% ~iION sm 72-113-34 Scam VAtyt 30 IO AUTons 1 DEPetsaut T!ON 72-113 37 sYst a vat 15 5.0 CONTAllsert &
ONitLL
!$0LATION,
/
/
4AANO GULF-ungt 1 3j4,,3g
' Mmenkmtnk M.~ -
to GNRO.92/00117 Page'73 of 94
- 1 TA8LE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CON 00
_ ~ ~
OVERCURRENT PROTECTIVE DEVICES (d) 1 VOC Circuit Breckers (Continued)
GE THED BREAKER TIME 0.C.
PICKUP
RESPONSE
NUMBER TIME (Asperes)
(Seconds)
SYSTEN/ COMPONENT 72-110-39 AFFECTED 15 S.O FEEDWATER CONTROL 72-110-71 SYSTEM 5
5.0 CHARCOAL FILTER TRAIN N1M410002A-N 72-110-72 ALARMS 15
5. 0 FLOOR &
EQUIPMENT 72-110-73 ORAIN SYSTEM-15 5.0 CONDENSATE AND REFUELING WATER STORAGE AND 72-110-79 TRANSFER SYSTEM 15 5.0 FILTER DEMIN.
CONT. V8 72-11E-36 G36-P002 15 5.0 FIRE PROTECTIr; PANEL 72-11E-69 15 5.C FLOOR & EQUIPMENT 72-11E-73 ORAIN SYSTEM 15 5.0 CHARC0AL FILTER RAIN MIM41D0028-N A RM I
GRAND GULF-UNIT 1 3/4 6-39
~4-
. to GNRO.92/00117 Page 74 of 94 M E 3.4 4.1-1 (Continued)
/
_PRIMMY CONTA!WNT PEmiTRATLON CL*NXTOR DVERCURr[NT PgTgC"IVE UEVICE5 (e)
/120 VAC Cfecuit treakers GE THg5 s
TIME 0.C.
RESPONSE
BREAKER PICKUP TIME NUPGER (Aaperes)
(Seconds)
SYSTEN/ COMPONENT AFFECTED 52-1P112-12 40 4.0 RWCU REACTOR SAMPLE STATION (CONSTANT TEMP.
8ATN) 52-1P112-13 35
4. 0 RWCU SYSTEM FILTER DEMIN. CONT.
52-1P112-14 15
.0 CONT. POWER SUPPLY NS$$5 (1G33T5N000) 52-1P112-17 20 0
RWCU REACTOR SANPLE STATION (INST. POWER) 52-1P112-20 15 4.0 RWCU SYS. OUSTER COLLECTOR TANK (N1G360016) 52-1P112-22 15
4. 0 RWCU SYS. RES!N PUW
\\
(M14.
13-N) 52-17112-23 15 4.0 AREA M. MONIT.
YSTEM CTMT.
. ALAltt5 52-17151-20 15
4. 0 M0 R SPACE NEATER FOR EACTOR RECIRC.
SYST (N183 3Al-N) 52-1P151-2 15 4.0 MOTOR 5 E
HEATER F REC TOR R IRC.
SYSTUt (N1833000 N) f GRAND GULF-b.
1 3/4 8*40 Amudmt'b O' ~
Attachm:nt 3 to GNRO.92/00117 Pags 75 of 94 TAALI 3.8,4,1*1 (Continued)
T PernAav confArmert PenrTnAften raamoa UVEe? STENT resisETIVE pKVICE5
~
(e) 2
/120 VAC ctenit fesakers (Continued) i 8AEAKt4 TIME 0. C.
P!CKUP st$Pon$t
/
NUM4(4 (Asseres)
TIME (suones)
STIM /CompowINT
$2 17151 23 MFECTto 15 4.0 CTWT. CLA. $YsttM~
CMARCoAL Flit.
TRAIN MEAftA
$2 1P151 24 (M3M410002A N) 4.0 HOTOR SPAct NEAftR POR REACT 04 RECIRC.
$Yl.
$2 17131 25 (N12330003A3 N) in
.0 mirn sTtAM P!PINC ARIA BAM. C00L82 StWICE Witt CONT.
TRANIMITTtt 52 17151-25 (TT Neel) 15 4.0 MOTOR $ Pact HEAftR POR REACTOR EECIAC.
SYSTEM 12 17151 37 (N1833000344 M) 4.0 054. PER$ONNE.
LOCK 52 17151 3s (120'*18" ELIV)
IP 4.0 C1NT, Ptas0 Natl 12 17122-17 LOCR (LOWtt) 18
4. 0 C1NT. CLA. SYSTEM CN64CSAL FLTR.
TRAIN WTE.
52-190639-N)-
18 4.0
. 4 tedt.
L'A3R LaCR ING SYST38 CONT.
Regn
/
GRAND OULP-UNIT 1 3/4 #*41 bM"
'~
Attachmsnt 3 to GNRO.92/00117 Page 70 of 94 TAaLE 3.4.4,1-1 (continung) i parery ConfA :mest winAT"0N ra -
~ -
UVtKhasi NT verRLi1VE L
.ive (e) 204/120 EVIERI
~
VAC Cfeevit DeakeM (Continued)
Ty9# THQS BREAKEA T1f*t 0. C.
PICKUP ht290Ntt
^
NtMER (Ameeres)
TIMg
^
(Seconds)
TtWCOMP NENT 52 17222 27 AFFICTit 11
4. 0 ORWL. COOLERS SERVICI WAftt CONT.
TRANsNITTgt
,52 17151-13 (TT
NOA4) 15 4
PUNp VALyg 50LEN010 CONT CET. &
TEMP (AATutt FOR REACTOS ETER CLEAN 52-17252 37 U9 STS.
15"
4. 0 CoerfAINeriEQu!P.
MTCH 52 17252 34 (Q1MB3Y0071) 15"
4. 0 CorrAtleert equ!P.
MT06 52 1P411-19 (01Mt3Y0072) 15 0
ORWELL CHILLE W TH SYS. CONTROL VALVI IMICAT10lt 52-174 u 22 (1775L2034)
4. 0 MTOR $PACI NEAftR Pet AEACTOR AECIAC.
SYSTS 52 174 u 23 (It1833008381-M) 39
4. 0 LITY POWER FOR 510mL 5.t-174u-17101:188 PANEL 18 4.0 M70R Act NEAftt k
een ascrac.
SYSTS (mannan s-n) 52-4u-25 20
4. 0 UTTLITY Pot leeft'5!WAL CONDIT! git!NE L
GAAN0 GULF-UNIT 1 3/4 $*43 Asenennt No. Ils -
gffecttre Date: m 7 t
L
stachment 3 to GNRO 93/00117 TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTAI N NT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE 5 (e) 08/120 VAC Ctecuit Breakers (Continued)
G pe THQ5 BREAKER TIME 0.C.
PICKUP
RESPONSE
NUMER TIME (Amperes)
(Seconds)
SYSTEM / COMPONENT 52-1P412-26 AFFECTED 15 4.0 HOTOR SPACE HEATER FOR REACTOR RECIRC.
SYSTEM 52-1P412-28 (N1833000383 N) 15 4.0 MOTOR SPACE HEATER FOR REACTOR RECIRC.
SYSTEM 52-IP511-10 (M1833000384-M) 15 4.0 MOTOR SPACE HEATER FOR ORYWL. PURGE COMPRESSOR 52-1P521-21 (Q1E61C001A-A) 15 4.0 MOTOR SPACE NEATER FOR SLCS 52-19531-19 (Q1C41C001A A) 40 4.0 HYDROGEN IGNITOR CONTROL 52-1P531-21 4.0 HYDROGEN IGNITOR CONTROL 52-1P621-25 15 4.0 MOTOR SPACE HEATER OR DRWL. PURGE RE550R
(
E61C0018-8) 52-1P631-15 40
4. 0 HYO EN IGNITOR CONT 52-1P63 17 40 4.0 HYOR0GE IGNITOR CONTROL 52-631-21 15 4.0 MOTOR SPAC HEATER FOR CS (Q1C41C0018-GRAND GULF-UNIT 1 3/4 6 43 b e t'
Attachmont 3 to GNRO 92/00117 Page 78 of 94 TA8tf 3.8.4.1 1 (Continued)
PRIMAY CONTA!WNT PENdTRAT. ON CON 00CTOR OVERCURRENT PROTEC"IVE UEVICE5 (e) 2 120 VAC Cfecuit Breakers (Continued)
GE THQL TIME 0.C.
RESPONSE
R P!CKUP TIME STEN / COMPONENT (Aaperes)
(Seconds)
AFFECTED
$2-10P641-07
\\
15 40
\\.
CTMT. CLG. SM0KE DETECTOR POWER SUPPLY 1H22 P391A-2 2
4.0 POST ACCIDENT SAMPLE LINES HEAT TRACE N1R637944A 1H22-P3918-2 20 4.0 CTNT & DRYWELL MONITOR HEAT TRACE N1R63T98At f
GRAND GULF-UN!T 1 3/4 3.44 A c,2 nc9 m e M M o, -
Att;; chm:nt 3 to GNRO.92/00117 Pagi 79 of 94
_ TABLE 3 8.4.1 1 (Continued)
PRIMARY CONTA!WENT PENTRAT ON CC&a cTOR DVERCURRINT PwgTECTIVE OEVICE5 i
(e)
/",20 VAf Ctreuit treekers (Continued) 3-se M T!HE 0.C.
BREAKER P!CKUP
RESPONSE
NUMBER TINE (Amperes)
(Seconds)
STEM / COMPONENT AFFECTED 1H22 P110A 1 15
4. 0 HEAT TRACC FOR SLC$
N1R63T321A 1H22 F110A 4 5
4. 0 HEAT TRACE FOR SLCS N1R63T322A 1H22 P110A-5 15 4.0 NEAT TRACE FOR SLCS N1M3T323A 1H22-P110A 4 15 4.0 NEAT TRACE FOR $LCS N1M3T324A 1H22-P1100-1 15
.0 NEAT TRACE FOR $LCS M1M3T3215 1H22-P1108 4 15
.0 NEAT TRACE FOR SLCS N1M373228 1H22-P1100 5 15 4.0 NEAT TRACE FOR SLCS NIM 3T3238 1H22-P1100 8 15
/
4.0 NEAT TRACE FOR SLCS N1M3T3248 Pole treaker GRAND GULF-UNIT 1 3/4 8 45 Nma n AA
~~l
_ _ - - - -. _ _ _ to GNRO 93/00117 Pace 80 of 94 ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION when mdre c>pech.c LIMITING CONDITIO#I-FOR OPERATION D" * *'5 'SE b [9[
3.8.4.2 The thermal overload protection of each valvebr ' Teh 3.e.'.M l
shall be OPERA 8LE or shall be bypassed either continuously or only under accident conditions, as Ed k:t:1 _by an OPERABLE bypass device.
l Q ppl'e.a u )
APP L ICAB I L 1,,T,,Y:
Whenev~er the motor operated valve is required to be OPERABLE.
ACTION:
hl.'mh With the thermal overload protection for one or more of the above requited valves not OPERABLE or not bypassed either continuously or only under accident conditions, as
' ' 1, bypass the thermal overload within l
8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).
SURVEILLANCE REQUIAEMENTS 4.8.4.2.1 The thermal overload protection which is bypassed either continuously or only under accident conditions for the above required valves shall be veri-fled to be bypassed continuously or only under accident conditions, as applicable, by an OPERA 9LE bypass device (1) by the performance of a CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are normally in force during plant operation and bypassed under accident conditions and (2) by verifying that the thermal overload protection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing:
For those thermal overloads which are normally in force during plant a.
operation and bypassed under accident conditions:
1.
At least once per 92 days for the individual valve bypass circuitry.
2.
At least ciace per 18 months for the ECCS portion of the channel, b.
At least once per 18 months for those themal overloads which are con-tinucusly bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing.
c.
Following maintenance on the motor starter.
4.8.4.2.2 The thermal overload protection which is not bypassed for the above required valves shall be demonstrated OPERA 8LE at least once per 18 months by the performance of a CIWelEL CALIBRATION of a representative sample of at least 25% of all thermal overloads for the above required valves.
4.8.4.2.3 The thermal overload protection for the above required valves-which is continuously bypassed and temporarily placed in force only when the valve motor is undergoing periodic or maintenance testing shall be verified to be bypassed following periodic or maintenance testing during which the thermal overload protection was temporarily placed in force.
GRAND GULF-UNIT 1 3/4 8-46 A m c.r d m a. d h/o.
l
Attachm:nt 3 t) GNRO 92/00117 Page 81 of 94 i
Pages 3/4 8-47 through 3/4 8-53 have been Intentionally Deleted.
+
GRAND GULF-UNIT 1 3/4 8-47 Amendment No. 29, (Next page is 3/4 8-54)
-. -.-- --- - - - - - - - ~ ~ ~ ~
~
~ ^ ~ ' ' ~ ~
^~
A Attachm:nt 3 to GNRO 92/00117 Page 82 of 94 V G- / C &
TAalt 3.3.4.2 1
~
MOTOR OPERATt0 VALYts THEWL OVERLOAD PROTICT j
4 BYPA55 DEY!CE (CON-
{
TINUDUS)(ACC10 TNT Sy (5)
_ALVE NUMER COMITIONS) (NO)
At#tCTED i
Q 51F010 Continuous CIC Systes Q1 IF013 Continuous RCIC Systes Q1t F019 Continuous RCIC Systes Q1tl1 22 Continuous RCIC Systen Q1tl1F 1 Continuous RCIC Systes 4
01t51F Continuous RCIC Systee Q1tl1FM6 Centinuous RCIC Syatoo i
Q1tl1Folt Continuous RCIC Systes Q1t$1F064 Continuou RCIC systee RCIC Trip an Throttle Contin s
Valve on Turbt Q1tSIC002 RCIC systes-Q1851F095 Conti s
RCIC System- -
Q1821F065A e
teacter Caelant systes Q1821F06C3 No Reacter Caelant Systes Q1821F0MA No Reacter Coelant Systes Q321F0900 Ne teacter Coelant stes Q321F090C No Reacter Caelant stas Q1821F0000 Ne teatter Caelant Systen Q321F019 Continuous
'toester Coolant System-Q321F067A Continuous teacter Coolant Systes Q1821F0678 Continuous teacter Caelant Systes Q1821F067C Continuous Reacter Coelant Systes l
-Q1821F0670 ontinuous.
Reacter Coelant Systes Q1821FC16 tinuous teacter Caelant Systes Q1821F147A inuous M5L Drain Post LOCA Leak-l aps Centrol Q1821F1475 Cent NSL Drdin Post LOCA Leak-age Centrol-Q1833F019 Conti Recirculation Systen Q1833F020 Continuous Recirculatten Systen 1833Ful Continuous
' Recirculation Systes 183NUS Continuses Reciroslation System-Continuous Recirculation Systes Continuous
-Recirculation System-a 11 Manitori ysten-a 11 Manitori ystem a
11 Manitori ystes-3 34 a
11 Manitori stes t
Q:
12F040 Continuous M
tem J127023 Continuous,
M Sys LE12F0064 Continuous M Sys Q1112F052A Continuous M
W Q1812F006 Continuous M
tes Q1512F394 Continuous RHR Systen GRAN0' GULF-UNIT 1 3/4 3 47 Amendsen No.
2b
.,,,,-..,,..m,avrw'+
'wa+"""'
' ' ' " " * ' - ' " - ' " ~ ~ ~ '
te nt 3 to GNRO 93/00117 TABLE 3.8.4.2-l'(Continued)
HOT 0A OPERATED VALVES THERMAL OVERLOAD PRO BYPASS DEVICE (Coli-VAL Nt96ER TIHUOUS) (ACCIDENT SYSTE 5 CONDITION 5) (NO)
EO)
Q1E12 74A AFFE Q1E12F 6A Continuous RH Systes 01E12F0 A Continuous R
Systes Q1E12F08 No R Systen Q1E12F290A Ho Q1E12F047A Continuous HR Systes Q1E12F027A Cantinuous RHR Systen Q1E12F073A Continuous RHR Systen Q1E12F348 Continuous RHR Systes Q1E12F024A Continuous RHR System Q1E12F087A Continuous RHR Systes
(
Q1E12F048A Continuous RHR Systes Q1E12F042A Continuous RHR Systes Q1E12F004A Contir.aou RHR System Q1E12F003A Continuo s RHR Systee RHR Systes 01E12F011A Contin us RHR Systes Q1F.12F051A Conti us RHR Systen Q1E12F037A Conti us RHR Systes Q1E12F028A Con nuous RHR Systes Co inuous Q1E12F064A RHR Systes C tinuous Q1E12F0HA RHR Systes Q1E12F2908
' ntinuous RHR Systen Q1E12F004C ntinuous RHR Systes C tinuous RHR Systes Q1E12F021 Co inuous RHR Systen Q1E12F064C Con nuous RHR Systaa Q1E12F042C Q1E12F0488 Cont s
RHR Systen Q1E12F049 Contin us ioW Mystee Q1E12F0378 Conti s
RHR system Q1E12F0:6 Continue RHR Systee Q1E12F0748 Continuou RHR Systen Q1E12F0428 Continuous RHR Systen Q1E12F0648 Continuous RHR Systae Q1E12F0M Continuous RHR Systae Q1E12F094 Continuous RHR Systen Q1E12F0W8 Continuous AHR Systes Q1E12FW118 Continuous RHR Systae Q1E12F0528 Continuous RHR Systen Q1E12FC473 Continuous RHR System Q1E12F0778 Continuous systes Q1E12F004 continuous-Systan i
Q1E12F0 Continuous R
System Continuous RHR ystes Q1E12F 38 Continuous RHR sten Q1E12 268 Q1El 0248 Continuous RHR S ten Q1E 2F0288 Continuous RHR Sy 0
12F009 Continuous RHR sys s
E12F0738 Continuous RHR Syst 1E12F0668 Continuous RHR Systen Continuous RHR System G
0 GULF-UNIT 1 3/4 8-48 Amendment No.59 c
^
_ _~
Attachmsnt 3 to GNRO.92/00117 Page 84 of 94 TA8LE 3.8.4.2 _1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD T
SYPASS DEVICE (CON-VAL E NUPSER TINUOUS) (ACCIDENT CON 0!TIONS) (NO)
SYSTEM (S)
AFFECTE0_
Q1C11 083 Q1C11 22 No CR0 Hydr lic Systes Q1C41F0 1A Continuous CR0 Hy aulic Systen-Q1C41F00 Continuous Stano Liquid Control Continuous Stan Q1E21F001 y Liquid Control Q1E21F011 Continuous LP System Q1E21F012 Continuous Q1E21F005 Continuous CS System Continuous PCS Systee LPCS Systes Q1E30F002A Q1E30F591A Continuous Suppression Pool Makeup System Q1E30F592A Suppression Pool Makeup System Q1E30F593A Suppression Pool Makeup System Q1E30F594A Suppressfon Pool-Makeup System-Q1E30F001A Q1E30F0018 Continuous Suppression Pool Makeup Systee Q1E30F0028 Continuou Suppression Pool Makeup Systen Q1E30F5915 Con!!nuo Suppression Pool Makeup System Suppression Pool Makeup Systes Q1E30F5928 Suppression Pool Makeup Systen Q1E30F5938 Suppression Pool Makeup System Q1E30F5944 Suppreseion Pool Maksup System Q1E31F100A Suppression Pool Makeup System n nuous Fuel Pool Cooling and Cleanup Q1E31F1000 System n inuous Fuel Pool Cooling and Cleanup System Q1E32F001A Q1E32F001E Conti MSIV - LCS Q1E32F003A Conti MSIV - LCS Q1E32F003E Continuous M51V - LCS Q1E32F003J Continuous M51V LCS Q1E32F003N Continuous MSIV - LCS Q1E32F001J Continuous M5IV - LCS Q1E32F003N Continuous MSIV - LCS Q1E32F002A Continuous M51V - LCS Q1E32F002E Continuous tS!V - LCS Q1E32F002J Continuous IV - LCS Q1E32F002N Continuous V - LCS Q1E32F006 Continuous M51 - LCS Q1E32F007 Continuous M51V LCS Q1E32F Continuous M51V - #5 Q1E32F Continuous MuV - L Continuous MSIV --LC Q1E 001A Q1 F0014 Continuous Feedwater LC Continuous Feedwater LCS GULF-UNIT 1 3/4 8-49 b
~
e-6 v'
T-L-evWyew
--+,e--
a w-+
v'i y
ww--wwrd 7,,
y,
-w g-,,e e
9
Attachm:nt 3 to GNRO 92/00117 j
Page 85 of 94
)
fASl,E 3.8.4.2-1-(Continued)
MOTOR OPERATED VALVES THE8 MAL OVERLOAD PROTECTION
~
8YPASS DEVICE (CON-T!NUOUS) (ACCIDENT SYSTEM (S)-
VA VE NUMER-CON 0!TIONS) (NO)
AFFECTED
-Q1E5 064 Continuous RCIC Sys a Q1E51 3
Continuous RCIC Sy em 4
Q1E51F0 Continuous RCIC stes Q1E51F07 Continuous RCIC ystee Q1E51F078 Continuous RC Systee Q1E22F001 Continuous H $ System Q1E22F004 Continuous CS System Q1E22F010 Continuous HPCs Systen Q1E22F011 Continuous HPCS Systen Q1E22F012 Continuous HPC5 Systes-Q1E22F015' Continuous HPCS Systen Q1E22F023 Continuous HPCS Systes Q1E61F595A Combustible Gas Control System Q1E61F596A Combustible Gas Control-System Q1E61F597A Combustible-Gu control Systee Q1E61F598A Combustible Gas Control Systen Q1E61F595C Combustible ?,as Control Systes Q1E61F596C Q1E61F597C Combustible Gas Control-Syates~
Combustible Gas Control System-Q1E61F590C Q1E61F5058 Combustible Gas Control System-Combustible Gas Control Syster Q1E61F5968 Combustible Gas Cer, trol System-Q1E61F5978 Combustible Gas Control System Q1E61F5988 Combustible Gas Control System Q1E61F5950 Q1E61F5960 Combustible Gas-Control System Q1E61F5970 Combustible Gas Contro1LSystem Q1E61F5980-Combustible-Gas control System a
Combustible Gas Control System-Q1E61F003A Continuous Combustible Gas Control' System-Q1E61F005A Continuous Combustible Gas Control System l
Q1E61F0038 Continuous Combustible Gas Control System Q1E61F0058 Continuous stible Gas Control System Q1G33F251 Continuous Systes QIG33F253 Continuous.
RWCU stes Q1G33F004 -
Continuous RWCU S tes l
Q1G33F039 Continuous RWCW Sy se-Q1G33F034 Continuous RWCU Syst
^
Q1G33F054 Continuous RWCU Sys Q1G33F0 Continuous NWCU Systen Q1G33FC 3
. Continuous RWCU Systes e
Q1G33 40 Continuous RWCU Systes Q1G3 001 Continuous NWCU Systes Q1 3F250-Continuous RWCU System Q 33F252 Continuous RWCU Systes GRAND GULF-UNIT 1 3/4 8-50 bMet A3o. --.-.
L
_ _. ~.. -,
Att: chm:nt 313 qRO 92/00117 Page 86 of 94 TA8LE 3.8.4.2 1 (Continued)
_ MOTOR OPERATED VALVES THERMAL OVERL0A0 PROTE
{
~
BYPASS DEVICE (CON-TIN 0005) (ACCIDENT SYST (S)
E NtMER CON 0!TIONS) (NO)
AFF TE0_
Q1G41 28 Continuous
\\
ont Fuel Pool Cooling and Q1G41F02 Continuous Cleanup System Spent Fuel Pool cooling and Q1G41F044 Cleanup System Continuous Spent Fuel Pool Cooling and Q1G41F021 Cleanup System No Spent Fuel Pool Cooling and Q1041F043 Cleanup System No Spent Fuel Pool Cooling and Cleanup Systee Q1M71F591A Q1M71F593 Containment /0rywell IE Q1M71F5928 Containment /Drywell IE Q1M71F595 Containment /Drywell IE Q1M71F5918 Containment /Orywell IK Q1M71F592A Containment /Orywell IK Q1M71F594 Containment /0rywell IK Containment /Orywell I K Q1P21F017 C tinuous Co inuous Makeup Water Treatment-System Q1P21F018 Makeup Water Treatment System
.Q1P41F237 Conti us SSW Systes Q1P41F018A Conti s
SSW Systen Q1P41F241 Continuo iSW Systes Q1P41F238 Continuous SSW Systes QSP41F041A QSP41F064A Continuous SSW System Q1P41F064A Continuous SSW System Q1P41F014A Continuous SSW Systen Q1P41F159A Continuous SSW Systen Q1P41F160A Continuous SSW Systes-Q1P41F113 Continuous SSW Systen Q1P41F148A Continuous SSW Systes Q1PA1F001A Continuous Systes Q1P41F018A Continuous-5 Systes
}
Q1P41F015A Continuous SS System I
Q1P41F Continuous SSW stem.
f Q1P41F Continuous SSW $ tee Continuous SSW Sy se
_i Q1P41F A
l Continuous SSW Sys QSP41F 4A Continuous SSW Syst QSP4 066A Continuous SSW Syst QSP4 F125 Continuous SSW Systen Q1P 1F0188-Continuous SSW System
- Q:
41F1608 Continuous SSW Systes
.,P41F1598 Continuour SSW System IP41F1688 QSP41F154 Continuous SSW Systen Accident Conditions SSW System GRAND GULF-UNIT 1 3/4 8-51 A ena.n A m
Attachmsnt 3 to GNRO.92/00117 Page 87 of 94 TA8LE 3.8.4.2-1 (Continued) t MOTOR OPERATED VALVES THERMAL OVERLOAD PROT!
BYPASS DEVICE (CON-TINDOUS) (ACCIDENT VALVE N ER SYSTEN(5)
CON 0!TIONS) (NO)
AFFECTED QSP41F155 Q1P41F0688 Accident Conditions SSW Syst e QSP41F1558 Continuous SSW Sy em Q1P41F0148 Accident Conditions SSW S tee QSP41F0648 Continuous SSW ystee QSP41F0818 Continuous SS System Q1P41F0068 Continuous S
Systee Q1P41F0078 Continuous SW Systen Q1P41F0018 Continuous Q1P41F0168 Continuous SSW System SSW Systes Q1P41F0058 Continuous SSW Systen Q1P41F0158 Continuous S$W Systes QSP41F0668 Continuous QSP41F0748 Continuous SSW Systes-SSW Systes QSP41F189 Continuous SSW Systes Q1P41F011 Continuou SSW Systes Q1P41F119A Continuo s SSW Systes No Q1P41F1198 SSW Systes Q1P41F121A SSW Systes Q1941F1213 SSW Systes Q1P41F122A SSW Systes Q1P41F1228 SSW Systes SSW System QSZ51F001 Conti s
Control Roon HVAC QSZ51F008 QSZ51F014 Continuo Control Room HVAC QSZ51F016 Continuou Control Room HVAC Continuous Control Room HVAC Q1P42F067 Q1P42F116 Continuous CCW Systen Q1P42F028A Continuous CCW Systes Q1P42F032A Continuous CCW System Q1P42F201A Continuous CCW System Q1P42F204 Continuous CCW Systen Q1742F205 Continuous CCW System Q1742F106 Continuous CW System j
Q1P42F2004 Continuous Systee Q1P42F203 Contirdenas C
Systia Q1P42F117 Continuous C
Systes Q1P42F11 Continuous CCW stes Q1P42F0 Continuous CCW 5 stes Q1P42F 008 continuous CCW Sy tes Continuous CCW Sys Q1P4 0288 Q1P 2F2018 Continuous CCW Sys Q 42F0328 Continuous CCW Syst P42F066 Continuous CCW System Co3tinuous CCW System nual bypass of thermal overload protection of manually contro11ed v Ivs.
GRAND GULF-UNIT 1 3/4 8-52 Ame.MmsnhMo.\\
~
l to GNRO 92/00117 Pege 88 of 94 TASLI 3.8.4.2=1 (Centinued)
?
NDTOR OPERATED V4LVts THEMAL OVtRLe** PiciiCTION OYPA$$ OfV!CE (CON-VALVE tR TINUOus) (ACCIDENT SYSTEM (5)
CON 01T10h5) (NO) -
AFFtCTED Q1P F121 Centinuous Orne11 Systen Q1P727 2 Continuous Q1772F 5 Q1P72F Continuous Drywel" CV Systes Drywer CW systes Q1P72F124 Continuous 0
11 CW systee Q1P72F126 Continuous 0
Q1P44F042 Continuous 11 CW Systea Q1P447054 Continuous 11 CV systee i
Q1P44F047 Continuous lent SW systen Plant W Systes Continuous Plant W systes Q1P45F096 l
Q1P45F097 Continuous Continuous Fleer & Eget. Orain systu Ploer & Igst. Orain systes Q1PS2F195 Conti Service Air Systen Q1PS37003 Conti s
Instrument Air systes Q1753F007 Conti s
Instrument Air Systes Q1T4aF00s Q17447006 inuous
$s73 Q1744F024 inuous
$875 Q1744F026 tinuous SETS Q1T44F023 inuous dETS Q1T44F025 nuous
$471 Canti stil 01P45F271 Canti Q1P4SF274 Fleer & Egst. Orsin Systes Conti Fleer & Igst. Drain systes i
s J
GRAND GULF UNIT 1 3/4 g.g3 Aseneent No. 21,,
Effective Oste: OCT 2 0 :n:
CONTApostWT $YSTEMs to GNRO 92/00117 1
BAlf5 3/4.8.4 GmiAlleeft Ald) ORWELL ISOLATION VALVts i
tainment eteesphere will be toelated from the ou of a release of radioactive esterial to the containment eteno e
at the con-1 v ronment in the event action of the containment and is cancistant with the req throuilh 57 of Appendia A to le CFR Part 90.
er pressuri-time tetts specified for these isoletten valves desigmod to closCe s
ensures that the release of radiesetive asterial to consistent with the assumptions used in the analyses for a LOC e autenatically will be The operabliity of the drywell fastation valves ensures tha atmosphere will be direct)d to the sgpression peel for tan fu pipe breaks inside the drywe)1.
e drywell is se large, individual drywell penetration leakage is not asas c rum of valve operability en any penetratten which could contribute ef the design leaktge, the total leakage is maintained at lesa re. By checking value.
raction-e sesign N
Table 3.6.4-1 lists the Containment and k; sectie valves that ves in four an avtamatic isolation si tation and are loca included in section 3 are the Containment er1 fm d Table 3.
11 pene notrumen-fInQ_.
signal free a handswitch and are Isolation Valves ns. The valves en ive a remote manuel isolatten signals from inst 5eme of the valves in section 2 any inment er Drywell Penetrations.
tic si receive isoletten s<
1.gnals, but not automatic Section 3 are these which in Tab' The valves included in listed in Table 3.
i and de not ut111 res instrumentation inc19ees che utilise a,handswitch. local annual operae a remote manual ves tch.
Sectie9 3 that ted valves and power opera
_ Section 4 of Table 3.6.4 1 contains tes Ives (tion valves.
ical closing times. valves are the times used in th c isolation For autanetic isoletten valves not having analyticals with a closing times, closteg times are derived by applying margins closing test data ehtained by uging ASIE Section XI criteria times for these valves was determined ty using a facte a ve Maximum closing able (free previous test closure to next test closure)r of two times the all and adding this to the previous test closure time. ASME 5ection XI estgin 3/4.5.5 DRWELL VWE RftftF are drywell toelatten proper operation of the dry OPERABILITY in-a large,-break LOCA to centrol weir well ove ms leads.
, and The drywell 'seistion and drywell purge 0PERA4ILITY function and impact cussed in Bases 3/4.6.4 and 3/4.6.7 not required for hydrogen dilution e,r te protect drywell structura respectively.
Drywell vacuun relief is in a design-basis accident.
GRAND GULF-UNIT 1 8 3/4 6-7 Amenoment No. 21 l
l
AttachmOnt 3 to GNRO 92/00117 Pege 90 cf 94 l
INSERT All requirad Containment and Drywell Isolation Valves and their maximum isolation times are listed in the applicable plant procedures.
The opening of locked or scaled closed (2.e.,
manual) containment isolation valves that results in an open penetration under administrative control includes the following considerationus (1) stationing an individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
Insert for TS page B 3/4 6-7
-.. -. ~.. - _ _ - _
- _. to GNRO 93/00117 Page 91 of 94 M NTAINMEkT SYSTEMS SA5E5
~
$ECONDARY C0iiTATNMEWT (Continued) t previous valve closing test data obtained by usir.g Maximum closing times for these valves was determined by using a f eria.
times the allowsble (free previous test closure te next test closure er of two Section XI margin and adding this to the previous test closure time Estabitshing and esintaining a vacuum in the Auxiliary tut 1 ding g
'l, Enclosure Buf1 ding with the staney pas treatment systes once pe along with the surveillance of the doors, latches, dampers, valves flanges, and rupture discs is adequata % ensure Sat there are no, v blind of the integrity of the secondary containment.
a ons todine removal capability will be availahte in the event in containment iocine inventory reduces the resulting site boundary r The riduction doses associated with containment lealtage.
a on The operation of this system and resultant iodine removal capacity are consistent with %e assumptions u the LOCA analyses, for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce th on the adsorters and HEPA filters.
moisture l
J GRAND GULF UNIT 1 l 3/4 6-84 Asenement No. 21s - l Effective Date:
. 13 GNRO 92/00117.
Pago 92 of 94 INSERT
]
-All required secondary containment Isolation valves / Dampers and il their maximum i~ solation. times are listed in applicable plant procedures.
i i
i F
F 1
l I ';
1 l:
Insert for TS page B 3/4 6-Sa i-P j-
Attachmsnt 3 to GNRO 92/00117 Page 93 of 94 ELECTRICAL-POWER, SYSTEMS 8ASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary containment electrical penetrations and penetration conductors are protected by either de energizing circuits not required during reactor operation or demonstrating the OPERA 8!LITY or primary and backup overcurrent protection circuit breakers by periodic surveillance. YI i
n sdt C
-l The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker feliability by testing at least one representative l
sample of each manufacturer's brand of circuit breaker.
Each manufacturer's molded case and metal case circuit breakers are grouped into eepresentative samples which are then tested on a rotating basis to ensure that all breakers are tested.
If a wide variety exists within any manufacturer's brand of circuit breakers, it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.
The OPERA 811.ITY or bypassing of the motor operated valve themal overload-protection centinuously or under accident conditions by integral bypass devices ensures that the thermal overload protection during accident conditions will not prevent safety related valves from performing their functicn.
l lance requirements for demonstrating the OPERA 81LITY or bypassing of the ther The surveil-overload protection continuously and or during accident conditions are in Motors on Motor Operated Valves," Revision nse t f)
The reactor protection system (RPS) electric power monitoring assemblies provide redundant protection to the RPS and other systems which receive power from the RPS buses by acting to disconnect the RPS from the power source-circuits in the presence of an electrical fault in the power supply.
BASES for the functional requirements of the RPS are discussed in the BASES The for Specification 3/4.3.1.
E GRAND GULF-UNIT 1 B 3/4 8-3 ben nd emnt Mo. -
)
-y,-
w,,
4+-+.-,
wye.~%ww-v
-g---
.,,.%+-
-,ms,c m - - n n w.m y-w
,y y.ei--w.m
...-,-c,-
w-,wy,-,..wyc~r.-w,.w-w.--av
.-.#w.
vr
--,www..,-
v iw.--
wrwew..r.--em-.rw.---n.
w
. ta GNRO 92/00117 Peg) 94 of 94
_JNSERT 1 A list of required circuit breakers and'their required response times and trip setpoints is contained in the applicable plant procedures.
INSERT 2 A list of required thermal overloads is contained in the applicable plant procedures.
a
E Insert _ror TS page B 3/4 8-3
I Attachm:nt 4 to GNRO 92/00117 -
P:031 of 29
'l i
1 Samplo Proposed Technical Specification Pages PCOL 91/17 l
t
[
i 9
)
b
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ 13 GNRO 92/00117 Paoe 2 cf 29 DEFINITIONS (ORE ALTERATIM 1.7 CORE ALTERATION shall be the addition, removal, relocation or movement of fiel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Normal movemen' f the SRMs, IRMs, LPRMs, TIPS, or special movable detectors is not considered to be CORE ALTERATION.
Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe conservative position.
CRITICAL POWER RATIO 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the ANFB correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE E0VIVALENT l-131 1.9 DOSE EQUIVALENT l-131 shall be that concentration of 1-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The thyrt 'd dose conversion factors used for this calculation shall be those listed in Table 111 of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
MYWELL INTEGR11Y 1.10 DRYWELL INTEGRITY shall exist when:
a.
All drywell penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERABLE drywell automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except for valves that are opened under administrative l
control as permitted by Specification 3.6.4.
b.
The drywell equipment hatch is closed and sealed, c.
The drywell airlock is in compliance with the requirements of Specification 3.6.2.3.
d.
The drywell leakage rates are withir. the limits of Specification 3.6.2.2.
e.
The suppression pool is in compliance with the requirements of Specification 3.6.3.1.
f.
The sealing mechanism associated with each drywell penetration; e.g., welds, ballows cr 0-rings, is OPERABLE.
GRAND GULF-UNIT 1 1-2 Amendment Ns. M,
._______ ____--_- -______ ____ __ _ _______ _ __-_ -_. 13 GNRO 92/00117 Page 3 of 29 DEFINITIONS ERIMARY CONTAINMENT INTEGRITY 1.;! PRIMARY CONTAINMENT INTEGRITY shall exist when:
a.
All containment penetrations required to be closed during accident conditions are either:
F 1.
Capable of being closed by an OPERABLE containment automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except for valves that are opened under administrative control as permitted by Specification 3.6.4.
b.
The containment equipment hatch is closed and sealed.
c.
Each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
The containment leakage rates are within the limits of Specification 3.6.1.2.
e.
The suppression pool is in compliance with the requirements of Specification 3.6.3.1.
f.
The sealing mechanism associated with each primary containment penetration; e.g., welds, bellows or 0 rings, is OPERABLE.
PROCESS CONTROL PROGRAM (PCP) 1.32 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,.
sampling, analyses, test, and determinations to be made to ensure that proces-sing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
PURGE - PURGIEG 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, 3ressure, humidity, concentration or other-operating condition, in such a manner t1at replacement air or gas is required to purify the confinement.
RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3833 MWT.
GRAND GULF-UNIT 1 1-6 Amendment No. 87, ___
n, s
Attachm nt 4 to GNRO 02/00117 Paos 4 of 29
{
DEFINITIONS r
REACTOR PROTECTION SYSTEM RESPONSE TIME 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire resporse time is measured.
REPORTABLE EVENT 1.36 A REPORTABLE EVENT shall be any of those conditions specified in 3
Section 50.73 to 10 CFR Part 50.
ROD DENSITY 1.37 ROD DENSITY shall be the number of t.ontrol rod notches insarted as a-fraction of the total number of control rod notches.
All rods fully inserted is equivalent to 100% R0D DENSITY.
SECONDARY CONTAINMENT INTEGRITY 1.38 "0NDARY CONTAINMENT INTEGRITY shall exist when:
a.
All Auxiliary Building and Enclosure Building penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERABLE secondary containment automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, rupture disc or deactivated automatic valve or damper, as applicable, secured in its closed position.
I b.
All Auxiliary Building and Enclosure Building equipment hatches and blowout panels are closed and sealed.
c.
The standby gas treatment system is in compliance with the requirements of Specification 3.6.6.3.
d.
The door in each access to the Auxiliary Building and Enclosure Butiding is closed, except for normal entry and exit.
e.
The sealing mechanism associated with each Auxiliary Building and Enclosure Building penetration, e.g., welds, bellows or 0-rings, is OPERABLE.
GRAND GULF-UNIT 1 1-7 Amendment No. 42,
~. -
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP JNCTION PER TRIP SYSTEM (a)
CONDITION ACTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-Low Low, Level 2 2
1, 2, 3 and #
20 b.
Reactor Versel Water Level-Low Low Level 2 (ECCS -
Division 3) 4 1, Z, 4ad #
29 c.
Reactor Vessel Water Level-Low Low Low, Level 1 (ECCS -
Division I and Division 2) 2 1, 2, 3 and #
29 d.
Drywell Pressure - High***
2 1, 2, 3 20 e.
Drywell Pressure-High (ECCS - Division I and Division 2) 2 1, 2, 3 29 f.
Drywell Pressure-High (ECCS - Division 3) 4 1, 2, 3 29 g.
Containment and Drywell Ventilation Exhaust Radiation.- High High 2(b)
I, 2, 3 and
21 h.
Manual Initiation 2
1, 2, 3 and *#
22 2.
MAIN STEAM LINE ISOLATION 3g' a.
Reactor Vessel Water Level-
a Low Low Low, level 1 2
1, 2, 3 20 o5 b.
Main Steam Line Ci Radiation - H!gh,,,
2 1, 2, 3 23 c.
Main Steam Line 5l Pressure - Low 2
1 24 e
'd.
Main Steam Line 3i Flow - High 8
1, 2, 3 23 9
e.
Condenser Vacuum - Low 2
1, 2,** 3**
23 yoS GRAND GULF-UNIT 1 3/4 3-10 Amendment 97, G-
_.m D
TABLE 3.3.2-1
}
ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP SYSTEM (a)
CONDITION ACTION
'~
2.
MAIN-STEAM LINE ISOLATION no.-.
i f.. Main Steam Line Tuanel
' Temperature - High 2
1,.2, 3 23 1
g.: Main Steam Line Tunnel Temp.- High 2
1, 2, 3 23
.. h. Manual Initiation' 2
1, 2, 3 22.
3.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vessel Water
' Level-Low Low, level 2 2
1, 2, 3,...d #
25 4
.b.
Drywell Pressure - High***
2 1, 2, 3 25
}.
c.
Fuel Handling Area 2
1, 2, 3, and
25 Ventilation Exhaust l
Radiation.- High High d.
Fuel Handling Area
. Pool Sweep Exhaust Radiation - High High.
2 1, 2, 3 and
25 4
e. ' Manual" Initiation 2-1, 2,-3 26 25 2
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION
a. - AFlow - High 1, 2, 3 27 b.
AFlow Timer 1
1,-'2, 3
27 y3 c.:-Equipment Area Temperature 1/ room 1,~2, 3 27 a Er i High
E!- !
ua i d.-
Equipment Area ATemp. --
3:
High_
1/ room-1, O.
3 27 o
i o.
z -
e.
Reactor Venel Water 2~t
. Level:- Low Low, tevel 2.
2.
1, 2, 3 27 u,
~ GRAND GULF-UNIT 11 3/4'3. Amendment 97,
}
~...
TABLE 3.3.2-1
.c ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP SYSTEM fa)
CONDITION ACTION 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION.<
f.
Main Steam Line Tunnel 1
1,2,3 27 Ambient Temperature - High g.
Main Steam Line Tunnel A Temp. - High 1
1, 2, 3 27 h.
SLCS Initiation 1
1, 2, 58#
30
i. Mar.ua' Init;ation 2
I. 2, 3 26 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High 1.
Pressure 1
1, 2, 3 27 2.
Time Delay 1
1, 2, 3 27 b.
RCIC Steam Supply Pressure.- Low 1
1, 2, 3 27 c.
RCIC Turbine Exhaust Diaphragm Pressure - High 2
1, 2, 3 27 d.
RCIC Equipment Room Ambient Temperature - High 1
1, 2, 3 27 e.
RCIC Equipment Room A Temp.
- High 1
1, 2, 3 27 jfE
a f.
Main Steam Line Tunnel
-4 r
Ambient Temperature - High 1
1, 2, 3 27 E!'
u2 g.
Main Steam Line Tunnel A Temp. - High 1
1, 2, 3 27 6
Oz h.
Main Steam Line Tunnel g
Temperature Timer 1
1, 2, 3 27 g, -
5 o
GRAND GULF-UNIT 1 3/4 3-12 Amendment
}
TABLE 3.3.2-1.co. o ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLTCADLE OPERABLE CHANNELS OPERiJIONAL TRIP FUNC.10N PER TRIP SYSTEM ia)
CONDITION ETION 5.
REAC10R CORE ISOLATION COOLING SYZTEM ISOLATION
- 1.. RhR Equipn;ent Room Ambi-t Temperatura - High I/ room 1, 2, 3 27 j.
RHR Equipment Room a mv. - High 1/ room 1, 2, 3 27 k.
RHR/RCIC Steam Lip.e Flow - High 1
1, 2, 3 '
27 1.
Manual Initiation 1
1,2,3 26 m.
Drywell Pressure-High 1
1, 2, 3 27 (ECCS-Division 1 and Di ' tion 2) 6.
RHR SYSTEM ISOLATION a.
RHR Equipment Room Ambient Temperature - High 1/ room 1, 2, 3 28 b.
RPR Equipment Room A Temp. - High I/ room 1, 2, 3 28 c.
Reactor Vessel Water Level - Low, Level 3***
2 3
28 2(c) 31 d.
Reactor Yessel (RHR Cut-in
-- 3 Permjggive) Pressure-8[:-
High 2
1, 2, 3 28 o}3 Drywell Pressure - High***
2 1, 2, 3 29 e.
o u f.
Manual Initiation 2
1, 2, 3 26 g
o g --.
9' E-B9 GRAND GULF-UNIT.1 3/4 3-13 Amendment 70, 97, G.
[
412 GNRO 92/00117__
h"29 H
Pa 4
ISOLATIONACTUIT[0N [s % g g AEllM ACTION 20 - Be Lin at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 21
- Close the affected~ system isolation valve (s) within one hour or:
c.-
-In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN-within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN-within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.
In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and operations with a potential' for draining the reactor vessel.
Restore the manual initiation function to OPERABLE status within-ACTION 22 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Be in at least STARTUP with the associated isolatiot valves ACTION 23 closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN-within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
ACTION 2s Ea ablish SECONDARY CONTAINMENT INTEGRITY with the standby gas ACTION 25 treatment system operating within one hour.
Restore the manual initiation function to OPERABLE status within ACTION 26 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves with_in.the next hour and-declare the affected system in operable.
Close the affected system isolation valves within.one hour ACTION 27 and declare the affected system. inoperable.
Within one hour lock the affected system isolation valves ACTION 28 closed, or verify, by remote indication, that the valve _ is closed and electrically disarmed, or isolate the penetration (s)-
and declare the affected system inoperable.
Close the affected system isolation valves within one hour and ACTIr" 29 declare the affected system or component inoperable, a.
In OPERATIONAL CONDITION 1, 2 or 3 be in at least HOT SHUTDOWN within the next 12. hours and in COLD SHUTDOWN within the following 24-hours.
b.
In OPERATIONAL CONDITION # suspend CORE. ALTERATIONS.and operations with a potential for draining the reactor vessel.
Declare the affected SLCS pump inoperable.
ACTION 30 Isolate the shutdown cooling common suction line within one hour ACTION 31 if it is not needed for shutdown cooling or initiate action within ore hour to establish-SECONDARY CONTAINMENT INTEGRITY.
NOTES When handling irradiated fuel in the primary or secondary containment and during CORE ALURATIONS and operations with a potential for draining the~
reactor vessel..
-The low condcnser vacuum MSIV closure may be manually bypassed during _ _
reactor SHUTDOWN or for reactor STARTUP when condenserevacuum is below the trip setpoint to allow opening of the MSIVs. The manual bypass shall be-removed when condenser vacuum exceeds the trip setpoint.
Trip function common to RPS Instrumentation.
During CORE ALTERATIONS and operations with a potential far draining the reactor vessel'.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
GRAND-GULF-UNIT 1-3/4 3-14 Amendment No. M,
Attachm:nt 4 to GNRO-92/00117
- P BLE 3.3.2-1 u o.-
ISOLATION ACTUATION INSTRUMENTATION NOTES u-o-,
-(a) A channel may be placed in.an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for-required surveillance without placing the trip system in the tripped con-i dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b) Two upscale-Hi Hi, one upscale-H1 Hi and one downscale, or two downscale:
l-signals from the same trip system actuate the trip system and initiate isolation of the associated containment and drywell isolation valves.
(c) Only required to isolate RHR system isolation valves E12-F008 and E12-F009.
l One trip system and/or isolation valve may be inoperable-for up to 14 days -
without placing the trip system in-the tripped condition provided the diesel-generator associated with the OPERABLE isolation valve is 0PERABLE.
GRAND GULF-UNIT ~1 3/4 3-15 Amendment No. M,
Attachm:nt 4 to CNRO-92/00117 Pega 11 of 29 INSTRUMENTATION _
T ABL E 3. 3. 2-3 ico....e ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTI0B RESPONSE TIME (Seconds)#
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High
$10(a)###
b.
-RCIC Steam Supply Pressure - Low
$10(a) c.
RCIC Turbine Exhaust Diaphragm Pressure - High NA d.
RCIC Equipment Room Ambient Temperature - High NA e.
RCIC Equipment Room a Temp. - High NA f.
Main Steam Line Tunnel Ambient Temp. - High.
NA g.
Main Steam Line Tunnel A Temp. - High NA h.
Main Steam Line Tunnel Temperature Timer NA i.
RHR Equipment Room Ambient Temperature - High NA j.
RHR Equipment Room a Temp. - High NA k.
RHR/RCIC Steam Line Flow - High NA g
1.
Manual Initiation NA m.
Drywell Pressure - High (ECCS Division 1 and Division 2) 510(a) 6.
RHR SYSTEM ISOLATION a.
RHR Equipment Room Ambient Temperature - High NA b.
RHR Equipment Room a Temp. - High NA c.
Reactor Vessel Water Level - Low, level 3 s10(a) d.
Reactor Vessel (RHR Cut-in Permissive)
Pressure - High NA e.
Drywell Pressure - High NA f.
Manual I.itiation NA c
(a) The isolation system instrumentation response time shall be measured' and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.
(b) Radiation detectors are exempt from response time testing.
Response time shall be measured from detector output or the input of the first electronic component in the channel.
Isolation system instrumentation response time for MSIVs only. No diesel d
generator delays assumed.
Isolation system instrumentation response time for associated valves except MSIVs.
Isolation system instritmentation response time for air operated damaers.
No diesel ger rator delays assumed.
Isolation,ystem instrumentation response time specified for the_Tn ;
Mction actuating each valve shall be added to the valve's requi er isolation time to obtain the valve's ISOLATION SYSTE~ti RESPONSE T %
Includes time delay of 3 to 7 seconds.
GRAND GULF-UNIT 1 3/4 3-21 Amendment So. M,.
]
j 13 GNRO 92/00117 Paoe 12 of 29 3/4.6 CONTAINMENT SYSTEMS
- )f_4. 6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
i APPLICABLLIJJ: OPERATIONAL CONDITIONS 1, 2* and 3.-
1 ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT CHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
a.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following Type A or B test, by leak rate testing the seals with gas at P,11.5 psig, and verifying that when the measured leakage rate for these seals is added -
to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
b.
At least once per 31 days by verifying that all-containment-penetrations ** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except for valves that are opened under administrative control as permitted-by Specification 3.6.4.
. By verifying each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
By verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.
See Special Test Exception 3.10.1 Except valves, blind flanges, and deactivated-automatic valves which are-located inside the containment, neam tunnel or drywell and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.
GRAND GULF-UNIT 1 3/4 6-1 Amendmeni. No.
i to GNRO 92/00117 Pag) 13 of 29 CONTAINMENT SYSTEMS CONTAINMENT LEAKAG(
LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to L, 0.437 percent by weight _of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,,
11.5 psig.
b.
A combined leakage rate of less than or equal to 0.60 La for all penetrations and all valves # subject to Type B and C tests when pressurized to P,11.5 psig.
c.
Less than or equal to 100 scf per hour for all four main steam lines through the isolation valves when tested at P,,11.5 psig, d.
A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10-P,,
12.65 psig.
APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
ACTION:
With:
a.
The measured overall integrated containment leakage rate exceeding 0.75 L, or b.
The measured combined leakage rate for all penetrations-and all valves # subject to Type B and C tests exceeding 0.60 L,, or c.
The measured leakage rate exceeding 100 scf per hour for all four main steam lines through the isolation valves, or d.
The measured ccubined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 1 gpm times the ' total number of such valves, restore:
a.
The overall integrated leakage rate (s) to less than or-equal to 0.75 L, and
Except for those that are hydrostatically leak tested.
l GRAND GULF-UNIT 1 3/4 6-2 Amendment No. _ l
Attechment 4 to GNRO 92/00117 Page 14 of 39 CONTAINMENT SYSTEMS
-LlHITING CONDITION FOR OPERATION (Continued)
ACl10_N (Continued) b.
The combined leakage rate for all penetrations and all' valves # subject to Type B and C-tests to less than or equal to 0.60 L,,
and c.
The leakage rate to less than 100 scf per hour for all four main steam lines through the isolation valves, and d.
The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200 F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at _the following test schedule and shall be determined in conformance with the criteria speci-fled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 -1972:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 + 10 month intervals
during shutdown at P,11.5 psig, during each 10-year service period, b.
If any periodic Type A test fails to meet 0.75 L the test schedule forsubsequentTypeAtestsshallbere'!iewedand,approvedbythe Commission.
If two consecutive Type A tests fail to meet 0.75 L,,
a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L,,-at which time the-above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplementa' test.which:
1.
Confirms the accuracy of the test by verifying that the containment leakage rate, L'y, calculated in accordance with ANSI N-45.4-1972, Appendix C, is within 25 percent of the containment leakage rate, L,, measured prior to the introduc tion of the superimposed leak.
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.-
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 L, and 1.25_ L,.
Except for those that are hydrostatically leak tested.
l
The third Type A test within the first 10-year service period shall be con-ducted prior to startup following the sixth refueling outage.
This is an exemption from 10 CFR Part 50,-Appendix J Requirements.
GRAND GULF-UNIT 1 3/4 6-3 Amendment No. 89, l
.c to GNRO f ~ y 1 -
Pro 215 of 29 CONTAINMENT SYSTEMS l
SURVEILLANCE REQUIREMENTS (Continued) d.
Type B and C tests shall be conducted with gas at P,11.5 psig,* at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Main steam line isolation valves, 3.
Penetrations using continuous leakage monitoring systems, 4.
Valves pressurized with fluid from a seal system, 5.
Containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 6.
Purge supply and exhaust isolation valves with resilient material seal s.
e.
Air locks shall be tested and deWM;trated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at P,,11.5 psig, at intervals no greater than once per 3 years, h.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J, i
Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P,
l 12.65 paig, and the seal system capacity-is adequate to maintain system pressure for at least 30 days,
i. Containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at least once per.18 months.
1 j.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.9.2.
k.
The prov'isions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a. 4.6.1.2.b, 4.6 1.2.c, 4.6.1.2.d, 4.6.1.2.0, and 4.6.1.2.g.
Unless a hydrostatic test is required.
l GRAND GULF-UNIT 1 3/4 6-4 Amendment No.
l
Attachmint 4'tiGNRO 92/00117
Page 16 of 29
r LCONTAINMENT SYSTEMS 3/4.6.2 DRYWELL
- DRYWELL INTEGRill LIMITING CONDITION FOR OPERATION _
3.6.2.1-DRYWELL INTEGRITY snall be maintained.
APPLICABl(III: OPERATIONAL CONDITIONS 1, 2* and 3.
ACTION:
.Without DRYWELL INTEGRITY, restore DRYWELL INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within.the following 24-hours.
L SURVEILLANCE REQUIREMENTS 4.6.2.1 DRYWELL INTEGRITY shall be demonstrated:-
a.
At least once per 31 days by verifying that all-drywell penetrations **'
~
not capable of being closed by OPERABLE drywell automatic isolation-valves -and required to be closed.during accident conditions are closed by valves, blind flanges, or deactivated automatic' valves secured in-
~
position, except for valves that are opened under administrative-control-as permitted by Specification 3.6.4.
b.
By verifying the-drywell air: lock is in-compliance with_the requirements if_ Specification 3.6.2.3.
J-c.
By verifying the-suppression pool is in: compliance with the-requirements of Specification 3.6.3.1.
o i
-See Special Test-Exception 3.10.1.
Except valves, blind flanges, and deactivated 1 automatic 1 valves which areL located inside the drywell or containment and are. locked,- sealed or' s
otherwise secured in the closed position. These penetrations shall be-verified closed during each' COLD SHUTDOWN except such verification needt not be performed more often than once per 92 days.
. GRAND GULF-UNIT 1 3/4 6-13 Amendment No. 31,
Att:chment 4 to GNRO 92/00117 Pcg 17 of 29 CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT AND DRYWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4 Each containment and drywell isolation valve shall be OPERABLE ***.
l APPLICABILITV: OPERATIONAL CONDITIONS 1, 2, 3, and #.
ACTION:
s With one or more of the containment or drywell isolation valves inoperable, l
maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:
a.
Restore the inoperable valve (s) to OPERABLE status, or b.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,* or c.
Isolate each affected penetration by use of at least one closed manual valve or blind flange *,
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**
Isolation valves, except MSIVs, closed to satisfy these requirements may be reopened on an interoittent basis under administrative controls. OPERATIONAL CONDITION changes, as provided by Specification 3.0.4, are not allowed while isolation valves are open under these administrative controls.
Isolation valves are also required to be OPERABLE when their associated l
actuation instrumentation is required to be OPERABLE per Table 3.3.2-1.
Except for E12-F008 and E12-F009 in OPERATIONAL CONDITIONS 4 and 5 take action per Specification 3.3.2, Table 3.3.2-1, Trip Function 6.c.
Normally closed or locked closed manual valves may be opened on an intermittent basis under administrative control.
GRAND GULF-UNIT 1 3/4 6-28 Amendment No. 40, l
ta GNRO-92/00117 Page 18 of 29 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each containment or drywell isolation valve ## shall be demonstrated l
OPERABLE prior to returning the valve to service after maintenance, repair or replacement work _is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the applicable isolation time.
l 4.6.4.2 Each automatic containment or drywell isolation valve ## shall be l
demonstrated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on an isolation test signal each automatic isolation valve actuates to its isolation position.
4.6.4.3 The isolation time of each power operated or automatic containment or drywell isolation valve ## shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.4.4
[ DELETED]
The provisions of Specification 4.0.4 are not applicable to automatic main steam line valves for entry into OPERATIONAL CONDITIONS 2 or 3 provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching a reactor staam pressure of 600 psig and prior to entry into OPERATIONAL CONDITION 1.
GRAND GULF-UNIT 1 3/4 6-29 Amendment No.
. ~.
' to GNRO 92/00117 '
P ge 19 of 29 Pages 3/4 6-30 through 3/4 6-45 have been Intentionally Deleted.
GRAND GULF-UNIT 1-3/4 6-30 Amendment No. 44, (Next page is 3/4 6-46)
Att:chment 4 t2 GNRO.92/00117 P o] 20 of 29 CONTAINMENT SYSTEM SECONDARY CONTAINMENT If0LATION DAMPER / VALVES' LIMITING CONDITION FOR OPERATION 3.6.6.2 Each secondary containment ventilation system automatic isolation damper / valve shall be OPERABLE.
-APPLICABILITY: CPERATIONAL CONDITIONS 1, 2, 3 and *.
ACTION:
With one or more of the ';econdary containment ventilation system automatic isolation dampers / valves inoperable, maintain at least one isolation l
damper / valve OPERACLE in each affected penetration that is open, and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:
a.
Restore the inoperable damper / valve (s) to'0PERABLE status, or b.-
Isolate each affected penetration by use of at least one deactivated automatic damper / valve secured in the isolation position, or c.
Isolate each affected penetration by use of at least one closed manual valve or blind flange.
Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Otherwise, in Operational Condition
, suspend handling of irradiated fuel in the primary or secondary containment, CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVElLLANCE REQUIREMENTS 4.6.6.2 Each secondary containment ventilation system automatic isolation damper / valve shall be demonstrated OPERABLE:
I a.
Prior to returning the damper / valve to service aftt:r maintenance, repair or replacement work is performed on the damper / valve or its associated actuator, control or power circuit by cycling the damper / valve through at least one complete cycle of full travel-and verifying the applicable l
isclation time, b.
During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation damper / valve actuates to its isolation position, c.
By verifying the isolation time to be within its limit when tested pursuant to Specification 4.0.5.
When irradiated fuel is being handled in the primary or secondary containment-and-during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
This exception is applicable until startup from the third refueling outage.
GRAND GULF-UNIT 1 3/4 6-49 Amendment No. 69, l
Attachment t t) GNRO 92/00117-r; Page 21 of 29 L
Pages 3/4 6-50 through 3/4 6-54 have been Intentionally Deleted.
s GRAND GULF-UNIT 1 3/4 6-50 Amendment No.
(Next page is 3/4 6-55)
Attachmint 4 to GNRO-92/00117 Paos 22 of 29 ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL E0VIPRENT PROTECTIVE DEVICES PRIMARY CONTAINMENT DENETRATION CONDUCTOR OVERCURRFNT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.1 Primary and backup containment penetration conductor overcurrent protective devices (i.e., circuit breakers) associated with each primary containment electrical penetration circuit shall be OPERABLE.
The scope of these protective circuit breakers excludes those circuits for which credible fault currents would not ext.eed the electrical penetration design rating.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With one or more of the primary or backup containment penetration conductor overcurrent protective devices inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system, and:
1.
For 6.9 kV circuit breakers, de-energize the 6.9 kV circuit (s)'by tripping the associated redundant circuit breaker (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the redundant circuit breaker to be tripped at least once per 7 days thereafter.
2.
For 480 volt circuit breakers, remove the inoperable circuit breaker (s) from service by racking out the breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the inoperable breaker (s) to be racked out at least once per 7 days thereafter.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.8.4.1 Each of the primary or_ backup containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
a.
At least once per 18 months:
1.
By verifying that the medium voltage 6.9 kV circuit breakers are OPER/BLE by selecting, on a rotating basis, at least 10% of the circu't breakers and performing:
a) I CHANNEL CAllBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuits function as designed.
l GRAND GULF-UNIT 1 3/4 8-19 Amendment No. 69, l
. - ~.. -
Attachment 4 to GNRO 92/00117 Pco) 23 of 29 ELECTRICAL POWER SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued):
c) For_ each circuit breaker found inoperable during _.these
functional tests, an additional _ representative : sample of at-least.10% of all the circuit breakers of-the inoperable: type shall also be functionally tested until:no more; failures;are found or all circuit breakers of that type have been functionally tested.
2.
By selecting and functionally testing a representative sample:of, at-least:10% of each type of lower voltage _ circuit-breakers.
Circuit breakers selected for functional: testing shall:te selected _
on a rotating basis.- Testing of.these circuit: breakers shall consist of injecting a current in excess of 120% of-the breakers. 'l--
nominal-setpoint and measuring the response time.t-The-measured.
s response time will be compared to the manufacturer's data to-insure that it is less than or: equal to a value specified by thei y
manufacturer.
Circuit breakers'found inoperable during functional testing shall_be restored to OPERABLE-status-prior >to resuming operation:of the affected equipment.
For_-each circuit breaker found_ inoperable _ dur_ing these.. functional tests,. an-additional-representative. sample of at. least 10% of. all the-circuit breakers'-
of: the-inoperable-type shall also be functionally ^ tested until no more failures are found or all circuit-breakers of that type nave -
been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an' inspection and preventive maintenance in accordance with procedures-prepared in conjunction with its manufacturer's recommendations.-
m r
GRAND GULF-UNIT 1 3/4 8-20 Amendment No.
L
. - + -,
4
.~- ta GNRO 92/00917 Page 24 ef 29 ~
Pages 3/4 8-21 through 3/4 8-45 have been Intentionally Deleted.
GRAND GutF-UNIT 1
-3/4 8-21 Amendment No.
(Next page fr. 3/4 8-46)
Attachm:nt 4 to GNRO 92/00117 ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PP0TECTION LIMITING CON 9ITION FOR OPERATION 3.8.4.2 The thermal overload protection of each valve whose moter operator performs a safety function shall be OPERABLE or shall be bypassed either contir.uously or only under accident conditions, as applicable, by an OPERABLE bypass device.
APPLICABillTY: Whenever the motor operated valve is required to be OPERABLE.
ACTION:
With the thermal overload protection for one or more of the above required valves not OPERABLE or not bypassed either continuously or only uncer accide conditions, as applicable, bypass the thermal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).
SURVEILLANCE RE0VIREMENTS 4.8.4.2.1 The thermal overload protection which is bypassed either continuously or only under accident conditions for the above required valves shall be verified to be bypassed continuously or only under accident conditions, as applicable, by an OPERABLE bypass device (1) by the performance of a CHAhNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are nor.nally in force during plant operation and bypassed under accident conditions and (2) by verifying that the thermal cverload protection i:, bypassed for those thermal overloads which are continuously bypassed and temporarily plated-in force only when the valve motors are undergoing periodic or maintenance testing:
a.
For those thermal overloads which are normally in force during plant operation and bypassed under accident conditions:
1.
At least once per 92 days for the individual valve bypass circuitry.
2.
At least once per 18 raonths for the ECCS portion of the channel, b.
At least once per 18 months for those thermal overloads which are con-tinuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing.
c.
Following maintenance on the motor starter.
4.8.4.2.2. The thermal overload protection which is not bypassed for the above required valves shall be demonstrated OPERABLE at least once per 18 months by the performance of a CHANNEL CALIBRATION of a representative sample of at least 25% of all thermal overloads for the above required valves.
4.8.4.2.3 The thermal overload protection for the above requireo valves which is continuously bypassed and temporarily placed in force only when the valve motor is undergoing periodic or maintenance testing shall be verified to be bypassed following periodic or maintenance testing during which the thermal overload prctection was temporarily placed in force.
1 GRAND GULF-UNIT 1 3/4 8-46 Amendment l
t3 GNRO 92/00117 P:03 26 cf 29 Pages 3/4 8 47 through 3/4 8 53 have been Intentionally Deleted -
GRAND-GULF-UNIT 1 3/4 8-47 Amendment No. 29, (Next page is 3/4 8-M;
4 t GNRO 92/00117
, N'"*2 9 p
GNTAINMENT SYSTEMS BASES 3/4.6.4 CONTAINMENT AND DRYWELL ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the con-tainment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The operability of the drywell isolation valves ensures that the drywell atmosphere will be directed to the suppression pool for the full spectrum of pipe breaks inside the drywell.
Since the allowable value of drywell leakage is so large, individual drywell penetration leakage is not measured.
By checking valve operability on any penetration which could contribute a large fraction of the design leakage, the total leakage is maintained at less than the design value.
All required Containment and Drywell Isolation Valves and their maximum isolation times are listed in the applicable plant procedures.
The opening of locked or sealed closed (i.e., manual) containment isolation valves that results in an open penetration under administrative control includes the following considerations:
(1) stationing an individual, who is in constant communication with the control room, at'the valve controls, (2) instructing-this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
The maximum isolation times for containment and drywell automatic isolation valves are the times used in the FSAR accident analysis for valves with analytical closing times.
For automatic isolation valves not having analytical closing times, closing times are derived by applying margins to previous valve-closing test data obtained by using ASME-Section X1 criteria.
Maximum closing times.for these valves was determined by using a factor of two timestheallowable(fromprevioustestclosuretonexttestclosure)ASME Section XI margin and adding this to the previous test closure time.
3/4.6.5 DRYWELL VACUUM RELIEF The safety-related functions of the four drywell vacuum relief subsystems are drywell isolation, proper operation of the drywell purge compressors, and OPERABILITY in a large-break LOCA to control weir wall overflow drag and impact loads.
The drywell isolation and drywell purge OPERABILITY functions are discussed in Bases 3/4.6.4 and 3/4.6.7, respectively. Drywell vacuum relief is not required for hydrogen dilution or to protect drywell structural integrity in a design-basis accident.
GRAND GULF-UNIT 1 B 3/4 6-7 Amendment No. M,
Attachm:nt 4 to GNRO 92/00117 Pcge 28 of 29.
CONTAINMENT SYSTEMS BASES
.-_ - a SECONDARY CONTAINMENT (Continued) analytical closing times, closing times are derived by applying margins to previous valve closing test data obtained by using ASME Section XI criteria.
Maximum closing times for these valves was determined by using a factor of two times the allowable (from previous test closure to next test closure) ASME Section XI margin and adding this to the previous tr.st closure time. All required Secondary Containment Isolation Valves / Dampers and their maximum isolation times ard listed in the applicable plant procedures.
l Establishing and maintaining a vacuum in the Auxiliary Building and Enclosure Building with the standby gas treatment system once pe.' 18 months, along with the surveillance of the doors, latches, dampers, valves, blind flanges, and rupture discs is adequate to ensure that there are no violations of the integrity of the secondary containment.
The OPERABILITY of the standby gas treatment systems ensures that sufficient iodine removal capability will be available in the event of a LOCA.
The reduction in containment iodine inventory reduces the resulting site boundary radiation doses associated with containment lea'Kage.
The operation of this system and resultant iodine removal capacity are consis;ent with the assumptions used in the LOCA analyses.
Continuous operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
3AND GULF-UNIT 1 B 3/4 6-8a Amendment No. M, l
- Attachm:nt 4 to GNRO 92/00117-,
' ELECTRICAL-POWER SYSTEMS-1
-BASES.
3/4.8.41 ELECTRICAL E0VIPMENT PROTECTIVE DEVICES
-a Primary conthinment electrical penetrations and penetration conductors.are:
-F
_ protected by either de energizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent -
protection circuit breakers by periodic surveillance.
A list of required circuit breakers-and their required response times and trip'setpoints-is contained in the applicable plant procedures.
The surveillance requirements applicable to lower voltage circuit breakers-provide assurance of breaker reliability by testing at least one- -
representative sample of each manufacturer's brand of circuit breaker.
Each manufacturer's molded case and metal case circuit' breakers are grouped into representative samples which are then tested'on a rotating basis =to ensure:
that all: breakers are tested.
If a wide variety exists within:any manufacturer's brand of circuit breakers, it is necessary. to divide that.
manufacturer *s-breakers into groups and treat each group as a separate type of.
breaker.for surveillance purposes.
The OPERABILITY or bypassing of the motor operated valve thermal overload '
protection continuously or under accident conditions by integral _ bypass devices ensures that the thermal overload protection during accident conditions will not prevent safety-related valves from performing their.
e function. Thn surveillance requirements for demonstrating the OPERABILIT_Y-or
- bypassing of the thermal overload protection continuously and or during accident conditions are in accordance with Regulatory Guide 1.106, " Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.
A list of required thermal overloads _is contained in the applicable plant procedures.
The reactor protection system (RPS) electric power monitoring _ assemblies provide redundant protection to the RPS.and other systems which receive power from-the.RPS buses by acting to disconnect the RPS'from the power source-circuits in the presence of an electrical fault in _the power supply. The BASES for the functional requirements of the RPS are discussed in the BASES 4
for Specification 3/4.3.1.
P GRAND' GULF-UNIT I B 3/4 8-3 Amendment No. m _

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