ML20214U422
| ML20214U422 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/25/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20214U425 | List: |
| References | |
| DPR-57-A-129, TAC 61054, TAC 61280, TAC 61281, TAC 61504 NUDOCS 8610010003 | |
| Download: ML20214U422 (19) | |
Text
f UNITED ST*.TES y
,g NUCLEAR REGULATi.Y COMMISSION 5
ij WASHINGTON, D. C. 20555
\\...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA i
D_0CKET N0. 50-321 0
EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated April 15, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
~
C.
There -is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted l
in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicablo requirements have i
been satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby I
amended to read as follows:
Ooj00
@CK05000321 o3 86072s P
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/
M Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications 4
Date of Issuance:
September 25, 1986
e ATTACHMENT TO LICENSE AMENDMENT NO.129 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET N0. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages~are' identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert ix ix 3.7-16 3.7-16
.3.7-16a 3.7-17 3.7-17 3.7-18 3.7-18 3.7-18a 3.7-18b 3.7-19 3.7-19 3.7-19a 3.7-23 3.7-23 3.7-24 3.7-24 3.7-25 3.7-25 3.7-26 3.7-26 3.7-26a 3.7-26b 3.7-27 3.7-27
LIST OF TABLES (Concluded)
Table Title Pace 3.7-1 Primary Containment Isolatica Values Which Receive a Primary (bntainment Isolation Signal 3.7-16 3.7-2 Testable Penetrations with Double O-Ring Seals 3.7-21 3.7-3 Testable 1%netrations with Testable Bellows -
3.7-22 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 3.13-1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 3.14.1-1 Radioactive Licuid Effluent Monitoring Instrumentation 3.14-2 3.14.2-1
. Radioactive Gaseous Effluent Monitoring Instrumentation 3.14-7 4.14.1-1 Radioactive Licuid Effluent Monitoring
~
Instrumentation Surveillance Recuirements 3.14-4 4.14.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Recuirements 3.14-11 4.15.1-1 Radioactive Licuid Effluent Sampling and Analysis Program 3.15-2 4.15.2-1 Radioactive Gasecas Waste Sampling and Analysis Program 3.15-10 3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Reporting Ievels for Radicactivity Cbncen-trations in Environmental Samples 3.16-7 4.16.1-1 Iower Limit of Detection 3.16-8 6.2.2-1 Minimam Shift Crew Composition 6-4 6.9.1.7-1 Environmental Radiological 2nitoring Program
. Sunr.ary 6-18 6.9.2-1 Special Reporting Recuirements 6-19 HA101 - UNIT 1 ix Amendment No. 65, 69, 110, 112, 119, 129 9
~
l
\\
TABLE 3.7-1 if g
PRIMARY CINTAIhMENT ISOLATION VALVES WlIO1 g
RECEIVE A PRIMARY ONTAIM4ENT ISOLATION SIGNAL g
g
- 1 z m
'?
8 Isolation Mimber of Power Maximsm Normal Action on g@
Grcup Operated Valtms Operating Ibsition Initiating (b)
Valve Identification (d)
Inside Qitside Time (sec)
(a)
Signal (a)
~
1 Main steam line 4
4 3(T(5 0
GC (B21-F022 A,B,C,D; B21-F028 A,B,C,D) 1 Main steam line drain 1
1 15 C
SC (B21-F016, B21-F019) 1 Reactor water sanple line 1
1 5
O OC l
(B31-F019, B31-F020)
I 2
Drywell pirge inlet 2
5 C
SC w
g (T48-F307, T48-F308) -
5 l
2 Drywell main exhasst 2
5 C
SC (T48-F319, T48-F320) 2 Drywell exhasst tralve bypass to 2
5 C
SC standby gas treatment (T48-F341, T48-F340) l 2
Drywell nitrogen make-up line 1
5 Q
SC (normal operation)
(T48-Fil8A) 2 Stippression chamber parge inlet 2
5 C
SC (T48-F309, T48-F324) l 2
Suppression chamber main exhaist 2
5 C
SC (T48-F318, T48-F326) k q
l 1
i TABLE 3.7-1 (Oont'd)
E PRIIRRY CDNTAI!NENP ISOLATION VALVES NIIO{
2-RECEIVE A PRIMARY CDNTAIPNENP ISOLATION SICNAL SM
" 9
!?,
l Isolation ntnber of Power Maxinum tbrmal Action on e
C5 Grmp Operated Valves Operating Position Initiating
- -i (b)
Valve Identification (d)
Inside Otttside Time (sec)
(a)
Signal (a) 2 H -02 Analyzer A 'Ibms Sample 0
2 5
l Line C
SC l
2
)
(P33-F006, P33-F014) 2 H -02 Analyzer A Drywell Sanple Line 0
2 5
O GC 2
(P33-F002, P33-F010) 2 H2-02 Analyzer A Return Line 0
2 5
0 GC (P33-F004, P33-F012)
Py 2
H -02 Analyzer B 'Ibms Sanple 0
2 5
0 GC 2
g Line (P33-F007, P33-F015)
H -02 Analyzer B Drywell Sample 0
2 5
C SC 2
2 Line (P33-F003, P33-F0ll) 2 H -02 Analyzer B Return Line 0
2 5
O GC 2
(P33-F005, P33-F013) 2 Fission Prod 3 Cts Mo'nitor Sample Line 0
2 5
O GC j
(Dll-F051, Dll-F053) 2 Fission Prodticts Monitor Sturn Line 0
2 5
O GC (Dil-F050, Dll-F052) o i
1
l I
i TABLE 3.7-1 (Cont'd) i g
PRIMNE CINTAItNENT ISOIATION VALVES WIIO{
RECEIVE A IRIMARY CDtifAllNDTP ISOTATION SIGNAL "g
r
!? a=
E' Isolation NJnber of Ibwer Maxinum Normal Action on Group Operated Valves Operating Ibsition Initiating
~q (b)
Valve Identificstion (d)
Inside Q2tside Time (sec)
(a)
Signal (a)
U 2
Suppression chamber exhalst valve 2
5 C
SC bypass to standby gas treatment l
1 (T48-F339, T48-F338)
J l
2 Suppression chamber nitrogen 1
5 C
SC l
j make-up line (normal operation)
(T48-F1188) 2 Drywell and mppression chamber 1
5 C
SC nitrogen mpply line (inerting) wy (T48-F103)
N 2
Drywell and mppression chamber nitrogen 1
5 C
SC make-up line (normal operation)
(T48-F104) l I
2 Drywell eculpment drain alup discharge 2
15 0
GC (Gil-F019, Gil-F020) i i
2 Drywell floor drain siimp discharge 2
15 O
GC l
(Gll-F003, Gil-F004) il 2
TIP Glide ' lube 1 each NA C
SC
}
(C51-J004) line (c)
Drywell pneudatic system 2
5,,'
O GC (P70-F002, P70-F003) e
-s..
1 e.,
l
'mBLE 3.7-1 (Cont'd)
N g
PRDRRY CDNPADNENT ISOIATION VALVES WIIO{
g-RECEIVE A PRDERY CDNTAIINENP ISOIATION SIGNAL c.
$z4 y9 i
Isolation Mimber of Ibwer Maxinum Normal Action on gc Group
' Operated Valves Operating Position. Initiating
- 5 (b)
Valve Identification (d)
Inside Q1tside Time (sec)
(a)
Signal (a)'
-4 C-s e
6 RIR reactor shitdown cooling 1
1 24 C
SC alction (alpply)
(Ell-F008, Ell-F009) s 6
RIR reactor head spray 1
1 20/12 C
SC l
(Ell-F022, Ell-F023) 3 HPCI - tilrbine steam 1
1 50 0
GC (E41-F002, E41-F003)
Y 4
RCIC - turbine steam 1
1 20 O
GC i
T (E51-F007, E51-F008) is 5
Reactor water clearup from.
1 1
30 0
GC l.
recirat11ation loop l
(G31-F001, G31-F004)
)
j 2
Ibst-accident sanpling system alpply 2
5 C
SC (B21-Flll, B21-Fil2) 2 Post-accident sanpling system retilrn 2
5 C
SC (E41-F122, E41-F121)
- e
- i.
2 Core spray test line to alppression 1 each 50 C
SC pool 1ine (E21-F015A,B)
I i
3 i '-
i g
BBLE 3.7-1 (Cont'd) 1 to E.
e PRIMARY CINFAINMENT ISOIATION VALVES W1I01 g
RECEIVE A MtIMARY CDNTAIPNLNr ISOIATION SIGNAL e
n c
if 2 8
Isolation NJmber of Power Maxinum Normal Action on
@g Grcep Operated Values Operating Ibsition Initiating (b)
Valve Identification (d)
Inside Outside Time (sec)
(a)
Signal (a) 2 HPCI turbine exhaust vacuum breaker 2
16 O
GC (E41-Flll, E41-F104) 2 RCIC turbine exhaust vacuum breaker 2
16 0
GC (E51-F105, E51-F104) 2
'Ibrus drainage and parification 2
12 C
SC suction (G51-F0ll, G51-F012) 5-2 RIR drywell spray 1 each 11 C
SC go (Ell-F016A,B) line 2
HIR test line to the alppression 2 each 110/26 C
SC pool line (Ell-F024A,B; Ell-F028A,B) t 2
HIR to torus spray header 2 each 10/26 C
SC (Ell-F027A,B; Ell-F028A,B) line 2
MIR heat exchanger to the alppression 2 each 22 C
SC j,'
pool line (Ell-F0llA,B; Ell-F026A,B) 4 W
es.
I
'e e
l BBLE 3.7-1 '(Cont'd) if PRIMARY CDNTADNENT ISOLATION VALVES WIIGI RECEIVE A PRIMARY CDNTAINiENT ISOLATION SIGNAL e
$g if 9 Isolation M2mber of Power Maxinum Normal Action on Ce Group Operated Valves Operating Position Initiating
'i (b)
Valve Identification (d)
Inside Outside Time (sec)
(a)
Signal (a)
-A 2
RIR discharge to radwaste 2
20/32 C
SC (Ell-F049, Ell-F040) 2 JIbrus ventilation exhasst 2
2 5
C SC (T48-F332A,B; T48-F333A,B) 2 Drywell ventilation exhasst 2
2 5
C SC (T48-F334A,B; T48-F335A,B) 3 HPCI pump mininum flow 1
11 C
SC i
F (E41-F012) 7a 3
HPCI ping alction 1
84 C
SC (E41-F042) 4 RCIC p1mp minin1m flow 1
11 C
SC (E51-F019) i l
4 RCIC p1mp alction 1
33 C
SC (E51-F031)
O N-i t
9 LV
i Table 3.7-1 Primary Containment Isolation Valves Which Receive a' Primary Containment Isolation Valve Signal These notes-refer to the lower case letters in parentheses on the previous page.
NOTES:
a.
Key:
0 = Open SC = Stays closed
~ ~C = Closed GC = Goes closed b.
Isolation Groupings are as follows:
GROUP 1: The valves in Group 1 are actuated by any one of the following conditions:
1 Reactor vessel water level Low Low Low (Level 1) 2.
Main steam line radiation high 3.
Main steam line flow high 4.
Main steam line tunnel temperature high 5.
Main steam line pressure low
~6.
Condenser vacuum low 7.
Turbine building temperature at the steam lines high l
GROUP 2: The valves in group 2 are actuated by any one of the following conditions:
1.
Reactor vessel water level low (Level 3) 2.
Drywell pressure high GROUP 3:
Isolation valves in the high pressure coolant injection (HPCI)
'~~ ~
system are actuated by any one of the following conditions:
l 1.
HPCI steam lin'e flow high
~
2.
High temperature in the vicinity of the HPCI steam line 3
3.
HPCI steam sup' ply pressure low 4.
HPCI turbine exhaust diaphragm pressure 5.
Torus room differential temperature high l
GROUP 4:
Primary Containment Isolation valves in the reactor core isolation cooling (RCIC) ~ system are actuated by any one of the following conditions:
1.
RCIC steam line flow high 2.
High temperature in the vicinity of the RCIC steam line 3.
RCIC steam line pressure low 4.
RCIC turbine exhaust diaphragm pressure high 5.
Torus room differential temperature high i
HATCH - UNIT 1 3.7-19 Amendment No. 103, 121, 129
=--u-- 2 A =, d: -
=..-.
l Table 3.7-1 (Concluded)
Primary Containment Isolation Valves Which Receive a Primary Containment Isolation Valve Signal GROUP 5: The valves in Group 5 are actuated by any one.of the following conditions:
l.
Reactor vessel water level Low Low (Level 2) 2.
Reactor water cleanup equipment room temperature high 3.
Reactor water cleanup equipment room ventilation differential temperature high
~
~
4.
Reactor water cleanup system differential flow high
~
5.
Actuation of Standby Liquid Control System - closes outside valve only 6.
High temperature following non-regenerative heat exchanger -
closes outside valve only GROUP 6: The valve's in Group 6 are actuated by any one of the following l
conditions:
1.
Reactor vessel water level low (Level 3) 2.
Reactor vessel steam' dome pressure low permissive c.
Requires a Group 2 signal or a Reactor Building ventilation high radiation isolation signal.
d.
For redundant lines, only one set of valves is listed.
Other sets are identical except for valve numbers, which are included.
Valve numbers are listed in order from within primary containment outward for each li"
l l
l l
l l
HATCH - UNIT 1
- 3. 7-19a Amendment No. 129
. -. - l
.,..,-w w.
~
Table 3.7-4 Primary Containment Testable Isolation Values Penetration NJmber Valve Desianation Notes X-7A B21-F022A & F028A Main Steam Isolation Valves (1) (2) (3) (5) (9).-
X-7B B21-F022B & F02BB Main Steam Isolation Valdes (1) (2) (3) (5) (9) 4 X-7C B21-F022C & F028C Main Steam Isolation Values
- (l) (2) (3) (5) (9)
X-7D B21-F022D & F028D Main Steam Isolation Valves (1) (2) (3) (5) (9)
X-8 B21-F016 & F019 (1) (2) (4) (5) (9)
X-9A B21-F010B (1) (2) (3) (5) (10)
X-9A B21-F032B (1) (2) (3) (5) (10)
X-9A E41-F006 (1) (2) (4) (5) (9)
X-9A G31-F203 (1) (2) (4) (5) (10)
^"
X-9B B21-F010A (1) - (2) (3) (5) (10)
X-98 B21-F032A
.(1) (2) (3) (5) (10)
X-9B E51-F013 (1) (2) (4) (5) (9)
X-9B G31-F039 (1) (2) (4) (5) (10) i X-10 E51-F007, E008 (1) (2) (4) (5) (9)
X-ll E41-F002 & F003 (1) (2) (4) (5) (9)
X-12 Ell-F008 & EV09 (1) (2) (4) (5) (9)
X-13A Ell-F015A (1) (2) (4) (5) (9)
X-13B Ell-F015B (1) (2) (4) (5) (9)
X-14 G31-F001 & F004 (1) (2) (4) (5) (9)
X-16A E21-F005A (1) (2) (4) (5) (9)
X-16B E21-F005B (1) (2) (4) (5) (3)
X-17 Ell-F022 & F023 (1) (2) (4) (5) (9)
HATOI - UNIT 1 347-23 Amendment No. 51, 129
'b
- e'*n' e
Table 3.7-4 (Continled)
Primary Containment Testable Isolation Valves Penetration Nanber Valve Designation Notes X-18 Gil-F019 & F020 (1) (2) (4) (5) (9)
X-19 Gil-F003 & E004 (1) (2) (4) (5) (9)
X-20 P41-F049 & F050 (1) (2) (4) (5) (9)
{
6 i
X-21 P51-F513 & F514 (1) (2) (4) (5) (9)
X-22 P70-F004, F005 (1) (2) (4) (5) (10)
X-23 P42-F051 (1) (2) (4) (5) (10)
X-24 P42-F052 (1) (2) (4) (5) -(10)
X-25 T48-F307, F308, F309, F103 & F324 (1) (1) (4) (5) (9)
X-25 T48-Fil3 (1)- (2) (4) (5) (14)
X-25 T48-F321 (1) (2) (4) (5) (14)
X-25 T48-F104 (1) (2) (4) (5) (14)
X-25 T48-Fil4, Fil8A, Ell 8B & F322 (1) (2) (4) (5) (10)
X-26 T48-F319 & F320 (1) (2) (4) (5) (9)
X-26 T48-F334A (1) (2) (4) (5) (14)
X-26 T48-F334B (1) (2) (4) (5) (14)
X-26 T48-F335A & F335B (1) (2) (4) (5) (10)
X-26 T48-F340 & F341 (1) (2) (4) (5) (9)
~
X-26 P33-F002 (1) (2) (4) (5) (10)
X-26 P33-F010 (1) (2) (4) (5) (14)
X-27A Dll-F051 & F053 (1) (2) (4) (5) (10)
X-27F P70-F066 & F067 (1) (2) (4) (5) (10)
HAICH - UNIT 1 3.7-24 Amendment No. 53, 120, 129
~-
=
Table 3.7-4 (Contirued)
Primary Contain:r.ent Testable Isolation Valves Penetration M1mber Valve Designation Notes X-28F P33-F003 & F011 (1) (2) (4) (5) (9)
X-28A B31-F019 & F020 (1) (2) (4) (5) (9)
X-31D P33-F004 & F012 (1) (2)..(4) (5)_ (9)
X-31F B31-F013A & F017A (1) (2) '(4) (5) (10)
X-33C Dll-F050 & F052 (1) (2) (4) (5) (10)
X-34E P33-F005 & F013 (1) (2) (4) (5) (9)
X-35A C51-Ball Valve (1) (2) (4) (5) (10)
X-35B C51-Ball Valve (1) (2)_(4) (5) (10)
X-35C C51-Ball Valve (1) (2) (4) (5) (10)
X-35D C51-Ball Valve (1) (2) (4) (5) (10)
X-35E C51-Nitrogen Inerting (1) (2) (4) ' (5) (10) g X-39A Ell-F016A (1) (2) (4) (5) (9)
X-39B Ell-F016B (1) (2) (4) (5) (9)
X-40C P70-F002 & F003 (1) (2) (4) (5) (9)
I X-42 C41-F006
,,(1) (2) (4) (5) (10)
X-42 C41-F]07 (1) (2) (4) (5) (10)
X-45F T23-T004 & F005 (1) (2) (4) (5) (9)
X-46 P21-F353 & F420 (1) (2) (4) (5) (9)
X-52B B21-Fill & Fil2 (1) (2) (4) (5) (10) (11)
X-59A B31-F013B & F0178 (1) (2) (4) (5)
(.' 0)
X-203 E51-F003 & F031 (1) (2) (4) (5) />)
HA'KH - 1. NIT 1 3.7-25 Amendment No. 53, 129
- 1: m. - -
=
Table 3.7-4 (Continaed)
Primary Containment Testable Iscistion Valves Penetration hunber Valve Designation Notes X-204A Ell-F004A (1) (2) (5) (9) (12)
X-204A Ell-F030A (1) (2) (4) (5) (11)
X-20@B Ell-F004B (1) (2) (5) (9) (12) -
X-204B
. Ell-F030B (1) (2) (4) (5) (11)
X-204C Ell-F004C (1) (2) (5) (9) (12)
X-204C Ell-F030C (1) (2) (4) (5) (11)
X-204D Ell-F004D (1) (2) -(5) (9) (12)
X-204D Ell-F030D (1) (2)' (4) (5) (11)
~'
X-205 T48-F310 & F328A (1) (2) (4) (5) (9)
X-205 T48-F115 & Fil6 (1) (2) (4) (5) (9)
X-205 T48-F311 & F32BB (1) (2) (4) (5) (9)
X-205 T48-F325 & F327 (1) (2) (4) (5) -(9)
X-206A E41-F121 & F122 (1) (2) (4) (5) (9)
X-207 E41-F042 & F051 (1) (2) (4) (5) (9)
X-208A E21-F001A (1) (2) (4) (5) (9)
X-208B E21-F001B (1) (2) (4) (5) (9)
X-210A Ell-F007A (1) (2) (4) (5) (11)
X-210A E21-F044A (1) (2) (4) (5) ill)
X-210A E51-F019 & F021 (1) (2) (4) (5) (9)
X-210A E21-F031A (1) (2)' (4) (5) (11)
X-210A Ell-F024A, F027A & F028A (1) (2) (4) (5) (9)
HATOI - UNIT 1 3.7-26 Amendment No. $$, $$, 89, 129
. T " ~~
a.
=
Table 3.7-4 (Contirued)
Primary Containment Testable Isolation Valves Penetration M2mber Valve Designation Notes X-210A Ell-F011A & F026A
~
(1) (2) (4) (5) (9)
X-210A Ell-F025A, F029, F055A, F103A (1) (2) (4) (5) (11)
X-210A E21-F015A (1) (2) (4) (5) (11)
X-210A Ell-%ermal Relief Valve (1) (2) (4) (5) (11).
X-210B Ell-F007B (1) (2) (4) (5) (11)
X-210B E21-F044B (1) (2) (4) (5) (11)
X-210B Ell-F097 (1) (2) (4) (5) (11) l X-210B E41-F012 & F046' (1) (2)
- 4) (5) (9)
X-210B E21-F031B (1) (2) (4) (5) (11)
X-210B Ell-F024B, F027B & F028B (1) (2) (4) (5) (9)
X-210B Ell-F011B & F026B (1) (2) (4) (5) (9)
X-210B Ell-F025B, F055B, F103B (1) (2) (4) (5)- (ll)
X-210B E21-F015B (1) (2) (4) (5) (11)
~
X-210B Ell-%ermal Relief Valve (1) (2) (4) (5) (11)
X-212' E51-F001&F040 (1) (2) (4) (5) (9)
X-213 E51-F002 & F028 (1) (2) (4) (5) (9)
X-214 E41-F021 & F049 (1) (2) (4) (5) (9)
X-215 E41-F022 & F040 (1) (2) (4) (5) (9)
X-217 P33-F007 & F015 (1) (2) (4) (5) (9)
X-218A G51-F002 (1) (2) (4) (5) (10)
X-218A G51-D001 (1) (2) (4) (5) (13)
HA'IG - LNIT 1 3.7-26a Amendment No. 129 s
0 Table 3.7-4 (Centirued)
Primary Containment Testable Isolation Valtes Penetration M1mber Valtre Desionation Notes X-218A G51-F0ll (1) (2) (4) (5) (10)
X-218A G51-F012 (1) (2) (4) (5) (10)
X-220 P33-F006 (1) (2),4) (5) (14)
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X-220 P33-F014 (1) (2) (4) (5) (10)
X-220 T48-F318 & F326 (1) (2) (4) (5) (9)
X-220 T48-F332A (1) (2) (4) (5) (14)
X-220 T48-F332B (1) (2) (4) (5) (14)
X-220 T48-F333A & F333B (1) (2) (4) (5) (10)
X-220 T48-F338 & F339 (1) (2) (4) (5) (9)
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X-221C E51-F104 & F105 (1) (2) (4) (5) (9)
X-222A E41-Flll & F104 (1) (2) (4) (5) (9)
X-223A T48-Air Cylinder (1) (2) (4) (5) (11)
X-223A T48-F342G-L (1) (2) (4) (5) (11)
X-223B T48-Air Cylinder (1) (2) (4) (5) (11)
X-223B
'I'48-F342A-F (1) (2) (4) (5) (11)
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HATO{ - LNIT 1 3.7-26b Amendment No. 129
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Notes for Tables 3.7-2 thrauch 3.7-4 (1) Test c12 ration for all valves and penetrations listed will generally exceed one hour.
(2) Test presmres are at least 59 psig for all valves and penetrations except MSIV's which are tested at 28 psig.
(3)
MS.T" acceptable leakage limit is 11.5 scfh/ valve of air.
(4) The total acceptable leakage for all valves and penetrations other than the MSIV's is 0.6 La-(5) Local leak tests on all testable isolation valves shall be performed each major refueling stutdown tut in no case at intervals greater than 2-years.
(6) Incal leak tests on all testable penetrations shall be performed each major refueling stutdown tut in no case at intervals greater than 2 years.
(7) 'Ihe personnel air lock shall be tested at intervals not to exceed 6 months.
(8) The personnel air lock door scals are tested at 10 psig after each opening.
(9)
Identifies isolation valves that are testal by applying presmre between the inboard and outboard isolation valves.
Inboard valve is not tested in the direction recnited for isolation tut will have ecuivalent or more conservative leakage remits.
(10)
Identifies isolation valves that are tested by applying presmre between the isolation valve and a marually operated valve mch that the isolation valve is tested in the direction recuired for isolation.
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(11)
Identifies isolation valves that are tested by applying presaire between the isolation valves and other system valves.
Isolation valves not tested in the direction recuired for isolation will have ecuivalent or nore conservative reallts.
(12) 'Ihe MIR system remains water filled post-IDCA.
Isolation values are tested with water.
(13) Identified blind flange that is tested by applying presaire between the flange and a marually operated valve asch that the flange is tested in i
the direction recuired for isolation.
(14) Identifies isolation valves that are tested by applying presaire betwen the inboard and cutboard isolation valves.
'11RIGI - UNIT 1 3.7-27
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Amendment No. 53, $5, 89, 129 n-ge,?$h"cs%..
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