ML20081B501
| ML20081B501 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/06/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20081B491 | List: |
| References | |
| TASK-2.F.1, TASK-2.F.2, TASK-2.F.3, TASK-TM TAC-54461, TAC-54462, NUDOCS 8403090196 | |
| Download: ML20081B501 (18) | |
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%.fg s HINS1RIMINTATION ~ WHIGI PROVIDE 5 'SURVEILIANCE INRRETION "
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'. 4 No.1 sInstrument1 , Type and Range ' Action: Remarks ]
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. h? - (a) - Channels- ;
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1 Reactor, Water' Level (GE/mC) 1 -Recorder -
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Indicator 0 to 60" .(c)' '7(d):
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- 2' Shroud Water. Level- ' '
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. Recorder . '(c) -(d)
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. .1' . Indicator -317" to -17"f =(c) '(d);
3 ' Reactor Pressure: 1 Recorder ~ (c) ~-(d) -
Indicator O'to 1200 psig (c) -(d) 2
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L 4 ~. Drywell . Pressure :2 Recorder,-10 t'o + 90 psig Ic) ,%(d) .
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l5' 'Drywell Temperature 2- - Recorder 0 to 5000F (c) T (d)-
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_y - '6'. _ Suppression Chamber Air. Temperature 2 ' Recorder 0 to 5000F (c) (d)- -
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'7 -Suppression' Chamber Water Temperature l J2 Recorder 0 to 2500F (c) *
'(d) 8 Suppression Chamber Water Level. 2 Indicator 0 to 300" (c) :(d) J.,
2 : Recorder O to 30" '(c)i(e)
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-9 Suppression Chamber Pressure 2 Recorder:-10 to +90 psig , 4 (c) ;f;jd) g 10' Rod Pbsition~Information. System (RPIS)? I '28 Volt Indicating Lights (c) < f(d) f'
- 11 Hydrogen and Oxygen Analyzer . 1 .- Recorder ,0 to 52 (c) _ _(d). (~~' 4 12 Post IDCA Radiation Monitoring. System . I Recorder (d) - (d)
Indicator 1 to 106 R/hr (c) (d) 13 Drywell/ Suppression Chamber. 2 Recorder -0.5 to + 2.5 psid. (c) (e) .(d)
Differential Pressure 14 a) Safety / Relief Valve Position Primary 1 Pressure Switch 4-100 'psig (1)
Indicator b) Safety / Relief Valve Position Secondary 1 Temperature element 0-6000F (f)
Indicator 8403090196 840206 PDR ADOCK 05000321 P PDR
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TABLE 3.2-11;1(Continued).
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- *INSTRtMNTATION WHIOi PROVIDES SURVEILLANCE INFGtMATION.
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.-Required - '
.-1' : Ref. -
'No..
' Instrument'
. Operable Instnament Type and Range'
' Action
. Remarks
. (b) -
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(a) Channels
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v :15 Drywe1UHigh Rarge Pressure 2 - Recorder 0 to 250 psig - (c)'.
-(d) 16 ' Drywell Hi h1 Range Ra'disttion t
- 2. Indicator 1 to 107 R/Hr ' (g) '.
'2 Recorder 1 to.107 R/Hr (g) 17 Main Stack:' Post-Accident Effluent Monitor, 1 Recorder 5x10-3 to' -(g) -
(h) i; , Ix105 pCi/cc
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18 R5aistorBuildingVenkPlenum 1 Recorder 5x10-3 to -(g) -(h)
Post-Accident Effluent Monitor 1x105 pCi/cc -
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NUfES FOR TABLE 3.2-11 m
. a. 'Ihe column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-11 and items in Table 4.2-11
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- b. Limiting Conditions for Operation for the Neutron Monitoring System are listed in Table 3.2-7.
E y c. From and af ter the date that one of these parameters is reduced to one indication, continued operation is e pemissible during the succeeding thirty days unless such instrumentation is sooner made operable.
Continued operation is pemissible for seven days from and after the date that one of these parameters is not indicated in the control room. Surveillance of local panels will be substituted for indication in the control room during the seven days.
- d. Dryuell and Suppression Chamber Pressure are each recorded on the same recorders. Each output channel has its own reconfer.
Drywell and Suppression Chamber. air temperature and suppression chamber water temperature are all recorded w on the same recorders. Each output channel has its can recorder. Each recorder takes input from several y temperature elements.
w
" Hydrogen and Oxygen are indicated en one recorder. The recorder has two pens, one pen for each parameter.
Each channel of the post LOCA radiation monitoring system includes two detectors; one located in the drywell and the other in the suppression chamber. Each detector feeds a signal to a separate log count rate meter. The meter output goes to a two pen reconter. One high radiation level alarm is provided per channel and annunciation of alarm is provided in the control room.
High Range Drywell Pressure and High Range Drywell Radiation are recorded on the same recorders. Each output channel has its own recorder.
- e. In the event that all indications of this parameter is disabled and such indication cannot be restored in six (6) hours, an onierly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.
- f. If either the primary or secondary indication is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which might be indicative of an open SRV. With both the primary and secondary monitoring channels of two or more SRVs inoperable either restore sufficient inoperable channels such that no more than one SRV has both primary and secondary channels inoperabic within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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m NOTES FOR TABLE 3.2-11 (Continued) -
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.5 g. - With the' plant in the power operation, startup, or hot shutdown conditilon and ~with the number of operable channels less than the .' reouired., operable ' channels, initiate the : preplanned ' alternate .
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method of monitoring the; appropriate parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and:
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@ 1. either restore the inoperable' channel (s) to operable status'within 7 days of~the event, or.
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- 2. prepare and submit a special; report to .the-NRC. pursuant . to Specification 6.9.2 within 14 days' v.
following - the event. outlining the' action taken, the cause of the -inoperability, and . the plans .
and schedule for restoring the system to operable' status. '
h.- L A channel 1 contains - two detectors: one for mid-range noble gas, and one for .high range noble gas. '; _
Both detectors must be operable to consider,the channel operable.. ,
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TABLE:4,2-11 (Continued) '
OiECK AND ~ CALIBRATION MINIlef FRBQUENCY FOR INSIRIMINTATION a:i l ,
WHICH PROVIDES SURVEILLANCE INFORMATION-Instrument w
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.' . , Instrument T: " RefJ - . ..
Instxtasent Check . Functional Test Calibration U L No. Instrument. Minimum Frequency ~ Minimum Frequency - Minimum Frequency'
- (b) (c)
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.15 Drywell High Range Pressure Each Shift N.A. Every 6 Months s_
16 Drywell.High Range Radiation Each Shift N.A. .Every.18 Months (e) J il7. Main Stack Post-Accident N.A.-.
Every 6 Months' Every 18 Months s
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Effluent Monitor i
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- .' 18 Reactor Bui1 ding' Vent Plenum' N.A. Every 6 Months Every 18 Months .
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' Post-Accident Effluent Monitor L y's . .
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Notes'for' Table 4.2 ,51 -
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- 1. ~ a.- ' The column entitled "Ref. No.'? isonly for'~ convenience so ' that a' one-to-one' relationship can i be - -
- l lh! . . established between items!in Table 4.2-11 and items in Table 3.2-11.
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g b. Instrument checks are not required Ewhen . the -instrtments are not _ required ~ to be operable or : are L ,
f tripped. However, -if instrument checks are missed, they shall .be performed prior to returning the J l y instrument to an operable status.'
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- c. Calibrations are not required when the instruments are not. required to be operable . or are . .
tripped. ' However, if .-calibiations are ' missed, 'they 'shall be performed prior to returning the instnment to an operable status.
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- d. Functional tests . are enot required when the instruments are. not required to be operable or . are tripped. However, if functiona.1 tests-are missed, they shall be performed prior to returning the ,
instrument to an operable status. .
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- e. Calibration of a drywell highf range ronitor shall consist of an electronic calibration of the '
channel, not including the -detector,2 for range decades above 10 R/hr and a one point calibration y check of the detector below 10 R/hr with an' inst.:11ed or portable gamma source.
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BASES F0h ' NITING CONDITIONS FOR OPERATION 3.2.Ji4.i Scintillation Detector For Monitoring Radioiodine (Continued) level reading is indicative of a leak in . the nuclear system process barrier in the primary containment. A sample that is continuously drawn from the primary containment is- collected on an iodine filter and monitored by a gamma sensitive scintillation detector. Radiation' levels
, are -read out by a log rate meter. and recorded on a strip chart located in the control room. A high radiation level alarm and a- failure alarm are aise provided and are, annunciated in the control room. Also, a high-low
- flow alam is annunciated in the control- room." ,
- 5. W Tubes for Monitoring Noble Gases A set' of W tubes ' contained in an 'in'strument rack are used tomonitdr the miease of ' noble. gases in the drywell and torus'. A high radiation level reading is indicative of a leak in the nuclear system process barrier in the primary containment. A sample that's_ contiruously , drawn from the 3
primary containment is i passed through a shielded sample chamber which contains the beta sensitive W tubes. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control mom.
~A .high radiation level alam and failure alarm are provided and are annunciated in the. control room. Also, a high-flow alam is annunciated in the control room.
K. Instmmentation Which Provides Surveillance Information (Table 3.2-11)
For each parameter monitored, _as listed in Table 3.2-11, there are two channels of -instrumentation except for the control rod positions indicating system and the Post-Accident- Effluent Monitors. By comparing readings between the two channels, a near continuous surveillance of instrument l
-performance is available. Any significant deviation in readings will initiate an early recalibration, . thereby maintaining - the: quality of the instrument readings.
The hydrogen and oxygen analyzing systems consist of two redundant, separate systems and are each capable of analyzing the hydrogen and oxygen content of L- the drywell-torus simultaneously. They are designed- to be completely testable at both the analyzer rack and in the control room. With an-oxygen concentration of less than 4% by volume, a flammable mixture with hydrogen
-is not possible.
L. Instrumentation which Initiates Disconnection of Offsite Power Sources (Table 3.2-12) y The J undervoltage relays shall automatically initiate the disconnection of' offsite' power sources whenever the voltage setpoint and time delay limits have been exceeded. This action shall provide voltage protection for the emergency power systems _by preventing sustained degraded voltage conditions due to the offsite power source and interaction between the offsite and onsite emergency power systems. The undervoltage relays have a time delay i characteristic that provides protection against both a loss of voltage and
' degraded voltage condition and thus minimizes the effect. of short duration disturbances without exceeding the maximta time delay, including margin, that is assumed in the FSAR accident analyses.
, PUWF HATCH UNIT 1 3.2-68
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,AININISTRATIVE CONTROL- -
- t, 6.15 POST-ACCIDEKr SAMPLING AND ANALYSIS -
A program 'shiak[' be esta51shed, implemented, and maintained to ensure the capability to obtain and analyze samples of radioactive iodines and particulates in plant gaseous effluents under accident conditions.
The program shall include the following:
a) . Training of personnel, ,
b) Procedures for sampling and analysis, c) Provisions for maintenance of sampling and analysis equipment.
N 4
e HATO{ - UNIT 1 6-?2
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.- , i-ENCIDSURE' 2 (CONTINUED)
NRC DOCKETS 50-321, 50-366 -
OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO AMEND TEONICAL SPECIFICATIONS-1MI ACTION PLAN ITEMS m
The proposed' charges- to Unit 2: Technical Specifications (Appendix A to (Operatirs License'NPF-5) would be incorporated as follows:
Remove Page Insert Page 13/4 3-53 3/4 3-53 3/4 3-54 3/4 3-54 3/4 3-54a 3/4.3 3/4 3-55
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INSTRIMENTATION '
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POST-ACCIDENT MONITORI'NG7INSTRlNENTATION LIMITINGICONDITION FOR OPERATION
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3.3.'6.4b Thd:' post-accident monitoring fins't'rumentation channels' shown in Table 3.3.6.4-1 shall be OPERABLE.
APPLICABILITY: CONDITIONS 1 :2; and 3 *; .
ACTION:
b a. 'With one' or more of the above required post-accident'-monitoring channels
= inoperable, either restore the inoperable channel (s) to OPERABLE status within.30. days or be'in at least~H0r.SHirrDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- b. The provisions of Specification.3.0.4 are not applicable.
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SURVEILIANCE REQUIREMENT 3 -
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4.3.6.4.: Each of the above required post-accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and GANNEL CALIBRATION operations at the frequencies l shown'in Table 4.3.6.4-1 Y
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. *~ . Condition 3 is applicable only to Items 12,13, and 14 of Table 3.3.6.4-1.
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POST-ACCIDENT I siiDRING INS 1RtMENTATION. '
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MINIMM -.. ,
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CHAMELSe .
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> OPERABLE -
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w 1. Reactor Vessel Pressure .(2C32-R605 A,;B, C) . 1" 2:
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I' 12.-:ReactorVesselWaterLevel(2B21-R610,[2B21-R615)I..? 2
- 3. Suppression Chamber Water Level:(2T48-R622.A, B) C 2 .
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2 l 4. Suppression Chamber Water Temperature;(2{47-R626,)2T47-R627) ,
-2
- 5. Suppression Chamber Pressure -(2T48-R608Cl2i48-R609)... a .~,- - :
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M : 6. Drywell Pressure (2T48-R608, 2T48-R609) = I"' 't -
2
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Y ' 7. Drywell Temperature . (2T47-R626, 2T47-R6'27)' . .. [ 2 ,
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' 8. Post-IDCA Gamma Radiation (2D11-K622. A,' B;; C, D)~/"] ,
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- 9. Drywell H 2-02 Analyzer (2P33-R601 A, B) ; l - ~
1, 2 _ ,
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- 10. a) Safety / Relief Valve Pbsition Primary.Indicato'r';(2B21-N301 A-H and K-M). (a)
~
' b) Safety / Relief Valve Position Secondary IIndicator-(2B21-N'04 0 A-H and K-M) (a)
- 11. Drywell High Range Pressure'(2T48-R601 d,;B) -
'~ ( ', 2
.12. Drywell High Range Radiation (2D11-K621'A' B, 2T48-R601A;2B ) , 2 (b)
,13. Main Stack Post-Accident Effluent Monitor (D11-R631) 1 (b)(c)
- 14. Reactor Building Vent Plenum Post-Accident Eff1hnt. Monitor (2D11-R631) 1 (b)(c) !
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NOTES FOR TABLE 3.3.6.4-1 , , ,
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- i(a)' If
- either' the primary 'or secondary indication is inoperable, the torus temperature will be ; monitored ' at -
,least;once.' per shift to observe any unexplained ^ temperature increases which might be indicative of an open '
l :SRV. . With.both the ; primary.and secondary monitoring channels of an SRV inoperable, either -verify that 'the - .
g S/RV is closed through monitoring the backup low low set logic . position indicators (2B21-N302. A-H and K-M)
.g J at least; once per shift or restore sufficient ' inoperable . channels such that' no more than one SRV' has both
~ ?rimary and secondary. channels inoperable'.within' 7'. days or be in~ at least hot shutdown within the next 121
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i (b) With the number- of . ope'rable channels. less than~ required by the miniatui channels operable : requirements,
. initiate the preplarmed alternate nethod of' monitoring the appropriate parameters within 72= hours and:
- - . . - .H l (1) either restore the Tno,perableichannel(s). to operable status within 7 days. of the event, or.
! .(2) prepare and submit Ja Specital Repo'rt to the NRC pursuant- to - Specification 6.9.2 within .14 days T
followirs the eventi outlining the action taken, the course of the inoperability, and the plans and schedule.for restoring thel system to' operable status.
^
( o one ;for mid-range noble gas and one for high range noble gas. Both .R
{ . c) detectors A ' channel must be ;contains operable;totwoidetectoirs:
consider the channel operable. - - -
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iTABLE-4.3.6.4-1
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4 POST-ACCIDENT MONITORING. INSTRUMENTATION SURVEILLANCE RBQUIRIMENTS .= y y 4b; ,
OIANNELt; , , '~. .
CHA!WEL FUNCTIONAL - . CHANNEL . f g,INSTRIMENT CALIERATION:'
- y.
- CHECK TEST -
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I 1. Reactor Vessel Pressure M .N.A. -
- 2. Reac' tor Vessel Water level, ~
.M. N.A. ,
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N.A.
- 3. Stppmssion. Chamber. Water Level: , M >-
- 4. Suppression Chamber Water: Temperature M' N.A.- 1 _; R
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-5. Suppression Chamber Pressure ~M N.A. *a ' R ..
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D 6. Drywell' Pmssure M N.A. , ..Q w '
- 7. Drywell Temperature M N.A. 'R
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- 8. Post-IDCA Gamma Radiation .M N.A. 'R
- 9. Drywell H2 -02 Analyzei* M N.A. -
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- 10. a) Safety / Relief Valve Position Primary Indication ' M* .N.A. ..R !
b) Safety / Relief Valve Position Seconday Indication M* N.A. 'R P
- 11. Drywell High Range Pressure M N. A.' 'Q
- 12. Drywell High Range Radiation M .. N. A. (. R
- 13. Main Stack Pos't-Accident Effluent' Monitor N.A. SA R
- 14. Reactor Building Vent Plenum Post-Accident- Effluent N.A. SA R Monitor
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AININISIRATIVE CONTROL 6.14 10 DINE MONI'IORING r The licensee '.'shall implement' .a' program' which will ensure the capability to accurately determine- the. airborne iodine ' concentration in vital areas
- under
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E accident conditions., This program shall include the following:
- 1) Trainirig of personnel;
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-> 2) , Proceduresiforimoriitoring,) af , . } ,
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[ 3) Provisions for maintenance of sampling and analysis equipment.
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6.15 POIST- CCIDENT SAMPLING AND ANALYSIS ! U 1 A program .shall -be established, implemented and - maintained to ensure the capability - to robtairr 'and; analyze samples . of radioactive iodines and particulates .in plant gaseous' ' effluents 'under accident. conditions. The i
pjogram shall include the following:
- 1) J Training of personnel, '
- 2) Procedures for sampling' and analysis, and 1-
- 3) - Provisions- for maintenance of sampling.and analysis equipment.
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- Areas requiring personnel access' for' establishing . hot shutdown corwiition.
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' HATCH-UNIT '2 6-20 A
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__ _ _ 1
ENCLOSURE 3 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANf UNITS 1, 2 REQUEST TO AMEND TECHNICAL SPECIFICATIONS-TMI ACTION PLAN ITEMS Pursuant to 10 CFR 50.92, Georgia Power Compcny has evaluated the attached proposed amendments and has determined that their adoption would not involve a significant hazard. The basis f 3r this detemination is as follows:
(a) PROPOSED CHANGE Add to Units 1 and 2 Technical Specifications limiting conditions for operation and surveillance requirements for the following accident monitoring instruments: (1) drywell high range pressure monitors, (2) drywell high range radiation monitors, (3) Main Stack post-accident effluent monitor, and (4) Reactor Building Vent Plenum post-accident effluent monitors.
BASIS This change constitutes an additional restriction not presently included in the Technical Specifications. This change does not af4ct tb -
probability or consequences of an accident or malfunction analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this change is consistent with Item (ii) of the " Examples of Amendments 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. .
-f A (b) PROPOSED CHANGE Addito the Units 1 and 2, Technical Specifications requirements for an administrative ' program- to ensure the capability to sample and analyze plant gaseaus effluent for radioactive iodine and particulate under accident conditions.
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BASIS 3
This change constitutes an additional restriction not presently included in the . Technical Specifications. This, change does not affect the f y
probability or consequences of .an accident or malfunction analyzed in -
]
the FSAR. 'Ihe margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this change is ]
, therefore within the acceptance criteria and the change is consistent ;
with Item (ii) of the " Examples of Amendments that are Considered Not i Likely to Involve Significant Hazards Considerations" listed on page 1 14,870 of the April 6,1983, issue of the Federal Register. g 5
e (c) PROPOSED CHANGE _
R Change bases to reflect the above changes. 3 m
5 BASIS 3 i
This is ' a purely administrative change to the Technical Specifications. i
- n. . This change does not affect the probability or consequences of an 3z
- 7.~ . , accident or malfunction analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected.
/f.jd The effect of this cange is therefore within the acceptance criteria and j
9
.M
},/ S the change is consistent with Item (i) of the " Examples cf Amendments ?
O~'- that are Considered Not Likely to Involve Significant Hazards i
- '. Considerations" listed on page 14,870 of the April 6,1983, issue of the 3 Qp Federal Register. j W a. ^l_
- g. (d) PROPOSED CHANGE g
. c . .n
- jl3 01ange the range of the drywell and suppression chamber pressure 1
,; 7 7 recorders from "-5 to +80 psig" to "-10 to +90 psig" in the Unit 1 j Technical Specifications (Items 4 and 9 of Table 3.2-11).
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if. h. ' EMIS_ !
I; This change updates the Technical Specifications to reflect modifications to the plant. This is a purely administrative change. -
This change does not affect the probability or consequences of an a accident or malfunction analyzed in the FSAR. The margin of safety as J defined in the basis for any Technical Specification is not affected. i The effect of this cange is therefore within the acceptance criteria and ;
the change 'is consistent with Item (i) of the " Examples of Amendments ;
that are Considered Not Likely to Involve Significant Hazards :
Considerations" listed on page 14,870 of the April 6,1983, issue of the 3
Federal Register. 7 2
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i- (e) PROPOSED O MNGE Qiange the reference to Section 4.4.2 a in Table 4.3.6.4-1 of the Unit 2 Technical Specifications'to Section 4.4.2.1 a.
BASIS This ' change achieves consistency in the Technical Specifications. A
- past' revision to Section 4.4.2 was inadvertantly not reflected in the above : reference. - This is a purely administrative change. This . change does not affect the probability or consequences of an accident or-malfunction analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this cange is therefore within the acceptance criteria and the change is. consistent with Item (i) of .the " Examples of . Amendments 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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ENCIDSURE 4 NRC DOCKETS 50-321, 50-366 h . OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2
[ f REQUEST 'IO AMEND TECIMICAL SPECIFICATIONS 'IMI ACTION PLAN ITINS e
l' Pursuant : to '10, CFR l170.22,- Georgia Power Company has evaluat'ed the b attached proposed amendments _.and has determined that they are a Class III
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' amendment for one , unit and a Class - I amendment for the other unit. The I ' basis'for this determination'is as follows:
-(n) 'the ' proposed amendments 'donnot required the evaluation of a new safety analysis report or a rewrite of the facility license; (b) h proposed amendments do not require the evaluation of several complex
-issues,- involve .ACRS review, or require an environmental ' impact statement; .
(c) The -proposed ' amendments involve 'a single.' safety issue, namely the
- Technical Specification charges necessary to. reflect the installation of .
additional accident monitoring' instrumentation.
. (d) h ' proposed amendments are therefore 'a Class III . amendment for one unit" and a Class I amendment for.the other unit.
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