ML20097A721
| ML20097A721 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/05/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20097A714 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM TAC-56049, TAC-59542, NUDOCS 8409130358 | |
| Download: ML20097A721 (6) | |
Text
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ENCIOSURE 1 NRC DOC 1TP 50-366 OPEPATING LIGNSE NPF-5
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EDWIN I. HA'IGI NUCLEAR PIANI UNIT 2 F4LtBr 'IO MEND TEUINICAL SPECIFICATIONS The' proposed change to the. Unit 2 Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:
Renove Page Insert Page 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16
.3/4 3-21 3/4 3-21 3
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S4 9130358 840905 p
p ADOCK 050003sg PDR
. TABLE'3'3'2 '
9 ISOLATION ACIUATION INS'IRIDENTATION gI VALVE GROUPS MINIMUM NINBER APPLICABLE
.-a OPERA'IED BY OPERA 3LE CHANNEIS
' OPERATIONAL
'IRIP FUNCTION SIGNAL (a)
PER 'IRI? SYSTDi(b) (c)
ODNDITION ACTION l.
PRIMARY QJNTAIINEN"I' ISOLATION a.
Reactor Vessel Water Invel' y
1.
Iow (Invel 3) 2, 6, 10, 2
1,2,3 20 (2B21-N680 A,B,C,D) 11, 12, 2.
Low-Iow (Level 2) 5, 2
1,2,3 20 (2B21-N682 A,B,C,D) 3.
Iow-Iow-Iow (Level 1) 1 2
1,2,3 20 (2B21-N681 A,B,C,D) b.
Drywell Presm re - High 2, 6, 7, 10 2
1,2,3 20 (2C71-N650 A, B, C, D) 12, c.
Radiation ~- High 1, 12, #, (d) 2 1,2,3 21 (2Dll-K603 A,B,C,D) 2.
Pressre - Iow 1
2 1
22 (2B21-N015 A,B,C,D) 3.
Flow - High 1, #
2/line 1,2,3 21 (2B21-N686 A,B,C,D)
(
(2B21-N687 A,B,C,D)
(2B21-N688 A,B,C,D)
^
(2B21-N689 A,B,C,D) w 1.
H H
d.
Main Steam Line 'Itinnel High Tenperature - High 1
2/line(e) 1, 2, 3 21 (2B21-N623 A,B,C,D)
(2B21-N624 A,B,C,D)
(2B21-N625 A,B,C,D)
(2B21-N626 A,B,C,D) e.
Condenser Vacuum - Iow 1
2 1,2 (f),3 (f) 23 (2B21-N056 A, B, C, D) f.
'Ilirbine Baildirg Area Temperature - High 1
2(e) 1, 2, 3 21 (2U61-R001, 2061-R002, 2U61-R003, 2U61-R004) g.
Drywell Radiation-High (j) 1 1,2,3 29 (2Dll-K621 A,B)
TABLE 3.H-l? (Contin 1ed)-
4 m
ISOIATION - ACIUATION : INS'IRUMENTATION
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ACTION O
ACTION 20 - Be in at' l' east'EDP SIUIDOW within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in (DLD SIUIDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
~ -ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be'in at least IDF SIUID3WN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COID SIUIDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 22 --Be in at least STARTUP within 2 hairs.
ACTION 23 - Be'. in ~at least STARTUP with the Group 1 isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or in at 'least IDF SIUIDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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ACTION 24 - Establich SECONDARY CONTAIINENT INTEGRITY with the standby gas treatment system operating within one hour.
ACTION 25 - Isolate the reactor water clean 1p system.
ACTION 26 - Close the affected system isolation valves and declare the affected system inoperable.
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^ ACTION 27 - Verify power availability to the tus at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or close the affected system isolation valves and declare the affected system inoperable.
ACTION 28 - Close:the shatdown coolirg supply ~and reactor vessel head spray isolation valves unless reactor steam deme presaire 6145 psig..
ACTION Eitherbclose the affected isolation valves within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in hot shitdown within the next'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold sh2tdown within the next 30 Fours..
IUTES f
Actaates operation of the main control room envircmental control system in the
- presairization mode. of operation.
- - Actuates the standby gas treatment system. -
- When handlirg irradiated fuel in the secondary containment.
c.
See Specification 3.6.3, Table 3.6.3-1 for values in each valve group.
- b. ; A channel may be placed in an inoperable _ status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for reg 2 ired alrveillance without placing the trip system in the tripped condition provided at least
-one other OPERABLE channel in the same trip system is monitoring that parameter.
c.
With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would casse the Trip Rinction to occar. In these cases, the inoperable channel shall be restored to OPERABLE status within.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION reglired by Table 3.3.2-1 for that Trip RInction shall be taken.
. d. -- Trips the mechanical vaalum pamps.
'O. ' A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
- f. ' May be bypassed with all turbine stop valves closed.
g.
Closes only RWCU outlet isolation valve 2G31-F004, h.
Alarm only.
i.~ Adjustable up to 60 minster.
j.- Isolates containment purge and vent Valves.
l HA'IQI - UNIT 2 3/4 3-15 I
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TABLE 313i2 2: ~
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ISO [ATION ACI1.% TION 'INSIRUM!NTATION SE"ITOINIS e
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ALIONABLE
. TRIP FU}CPION TRIP SETPOINT VALUE 1.
PRIMARY (DtfrAI!41ENT ISOLATION
-i g
e-a.
Reactor Vessel Water Invel-
~ 2, 8. 5 inches *-
- 2 8.5Jinches*
- 1. Low (Level 3)
- 2. Iow Iow:(Letel 2)
- 2 -55.. inches *
. R.-55 inches *
- 3. Iow Inw low (Levels.:1)- 121.5 inches
- E -121.5 inches
- b; : Drywell Presaire - High nE.55psig
.'$ l.85 psig-c.
. Main Steam Line 1.-Radiation - High 63.x full power background 1-3 x full power background
- 2. Pre'saire Iow 2825 psig 2>825 psig'
- 3. Flow - High.
- 613pofratedflow'
$,138% of. rated flow d.
Main Steam Line Tunnel Temperature - High 5 1940F
- $ 1940F.
g e.
-(bndenser Vaalum - Iow 27" Hg vacuum
. _ 7" Hg vacuum w
b f.
Turbine aillding Area Tenp. - High I2000F 6 2000F S
g..
Drywell Radiation-High N138R/hr i 138 R/hr.
2.
SECONDARY (DNEAIf41ENP ISOLATION
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Reactor alilding Exhalst
(,7
' Radiation High 160 mr/hr[
$ 60 mr/hr
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b.
Drywell Presaire - High i 1.85 psig f 1.85 psig c.
Reactor vessel Water 2-55 inches
- t -55 inches
- Level - Iow Iow (Level 2) d.
Refueling Floor Exhalst Radiation - High.
$20 mr/hr
$ 20 mr/hr-
- See Bases Ficf2re B 3/4 3-1.'
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gysLE 4413i:2-1,
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' ~ ISOIATION AC'IUATION INS'IMNERPATION SURVEILIANCE REQUIRDENIS
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'CHAMEL OPERATIONAL.
- ],,
O -
CHANNEL.
FUNCTIONAL
- CHANNEL, CONDITIONS - IN MIICH '
'IRIP FINCTION CHBCK TEST CALIBRATION' SURVEILLANCE REQUIRED'
.I Ci 1.
PRIMARY CON'IAIMENT ISOIATION-Z H-8 a.-
Reactor. Vessel Water Ietel' N
.1.. Iow (Ievel. 3)..
S
'M R.
' 1, 2, 3.'
. 2. Iow Iow (Ievel 2)
S M
R:
1,2,3-
- 3. Iow Iow Iow (Ievel-1)
S
'M
'R~-
'1,T2, 3
'b.
Drywell' Presaire - High S
M R-
' 1, ~ 2, 3 c.
~';,
- 1. Radiation - High D
W(a).
R-
'1, 2, 3
. 2. Presaire - Iow NA-M' Q
l
- 3. Flow - High S
M R.
1,. 2, 3
-+
d.
Main Steam Line 'ninnel'-
Terperature -' High-S.
M R.
1, 2, 3 -
e.
Condenser Vacium - Iow NA M-Q 1,2,3#
w a
f.
'nirbine asilding Area Tenp. --
,'M R
1, 2, 3 High NA' g.
Drywell Radiation-High D^
M R
1,2,3 2.
SECOMARY 00NTAIN4ENT ISOIATION Reactor Bidding Exhalst' M(a)
R 1, 2, 3, 5 and
- a.
Radiation - High D
b.'
Drywell Presaire -~High S
M R.
1,'2, 3' c.
Reactor Vessel Water Ietel -
Iow Iow (Ietel 2)
.Ss M
R 1,2,3 d.
Refueling Floor Exhalst Radiation - High D
M(a)
'O 1, 2, 3, 5 and *
. When handlirg -irradiated fuel in the secondary containment.
- May be bypassed with all turbine stop traltes closed.
(a) Instrument alignment using a standard carrent source.,
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f-ENCILSURE 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HA701 NUCLEAR PIAhT UNIT 2 RELUEST 70 AMEND TE01NICAL SPECIFICATIONS
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Pursuant to 10 CER 50.92, Georgia Power Cmpany has. evaluated the attached proposed merdnent and has determined that its adoption would not involve a significant hazard.. abe basis for this determination is as follows:
PRO ESED CHANGE Add ' limiting conditions for operation, trip setpoints, and surveillance requirments for the monitors which provide the
. high. radiation isolation signals to the contairnent purge and vent valves.
BASIS
@is change constitutes an additional restriction not presently included in the Technical Specifications.
This change does not affect.the probability or consequences of an accident or malfunction analyzed in the FSAR.
This change does not create the possibility of an acx:ident or malfunction of a different type than any. analyzed in the FSAR. % e margin of safety as defined in the basis for any technical specification is not affecteu.
%e effect of this change is therefore within the. acceptance criteria and the change is consistent with Iten (ii). of the "Exanples of Pnendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,
- 1983, issue of the Federal Register..
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