ML20056D562

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Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control
ML20056D562
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/11/1993
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20056D533 List:
References
GGNS-PCOL-93-09, GGNS-PCOL-93-9, GNRO-93-00097, GNRO-93-97, NUDOCS 9308170076
Download: ML20056D562 (11)
v • d • e


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Attechmznt 3 to GNRO-93/00097 .i l

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MARK-UP OF TECHNICAL SPECIFICATION PAGES +

i ACCIDENT MONITORING INSTRUMENTATION (GGNS PCOL-93/09) ,

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TABLE 3.3'.7.5-l' ACCIDENT MONITORING _ INSTRUMENT 4T10d ,

APPLICABLE- MINIMUM OPERATIONAL REQUIRED NUlWER CHANNELS INSTRUMENT CONDITIONS OF CHANNELS OPERABLE ACT1011  :

J. 1. - Reactor Vessel Pressure 1,23 2 1 80 7 2.. Reactor Vessel Water Level 1.2,3,4,5 2 1 82

3. Suppression Pool Water level 1, 2, 3 2 1 _80 f 4. Suppression Pool Water Temperature 1. - 2, 3 6, 1/ sector 6, 1/ sector 80 i swell / Containment Differential Pressure 1, 2, 3 2 1 ~i 80
6. Drywell Pressure' 1, 2, 3 2 1 80 ,
7. Drywell and Control Red Drive Cavity Temperature 1, 2, 3 2 (each) 1 (each) 80
8. Containment Hydrogen Concentration As lyzer and Monitor 1, 2, 3 2 1 83
9. Drywell' Hydrogen Concentration Analizer and Monitor. 1, 2, 3 2 1 83 R 10. - Contelament Pressure (wide and narrow range) .

I, 2, 3 2 (each) I (each) 80 A .11. Containment Air Temperature 1, 2, 3 2 1 80

- 5 I 12. Safety / Relief Valve Iall Pipe Pressure Switch -

c _ Position Indicators- 1, 2, 3 1/ valve 1/ valve _80 k 13. Containsant/Drywell Area Radiation Monitors 1, 2, 3.-4, 5 2 2

81 ,

' 14. Containment ventilation Exhaust Radiation liar 1,2,3,4.5 1 1 8

/ 15. -Offbsandmassestosieg..

Em st Radiation MonitorVentilation I.2.3.4.5 1 1 8 16.fFuelHandlingArea.vont11ationExhaust _

d A Radiation Monitor-I.2.3.4,5 1 'l 81 ,

17. (Turbine sieg. ventilation Exhaust Radiation ~

L Monitor 1,23 1 1 81'

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$tandby Gas Treatment System A & 8 Exhaust o 18.

Radiation Monitors

  • 8 1/each 1/each jfach for containment and dryell. -- _

(,F L*When its assectated train o" the standby gas treatment system is reautred operable (Ref. 3.6.6.3))%

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TABLE 4.3.7.5-1 i

ACCIDENT MONITOR.ING INSTRUMENTATION SURVEILLANCE REQUIREMENT 5 CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Reactor Vessel Pressure M R
2. Reactor Vessel Water Level M R
3. Suppression Poci Water Level M R b} 4 ,5uppression Pool Water Temperature M R
5. TDrywell/ Containment Differential t
  • 1 (Pressure N M '
6. Drywell Pressure R)

M R

7. Drywell and Control Rod Cavity '.mperature M R B. Con 3' ent Hydrogen Concentration Ana' e- and Monitor NA M*
9. Drywell Hydrogen Concentration Analyrar and Monitor NA M*
10. Containment Pressure -

M R

11. Containment Air Temperature . M R
12. Safety /Relie' Valve Tail Pipe Pressure Switch Position Indicators M 4 13.

.R -

Containment /Drywell Area Radiation k Monitors M R**

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14. Containment Ventilation Exhaust '

diation Monitor M A 0 -o Ventilation

15. kQhaust Radiation MonitorF ff gas and M Radwaste Bldg.

A iy/16.kiationMonitor/

Q Fuel Handiing AreaM Ventilation Exhaust A G._ ^

17. ( Turbine Bldg. Ventilation Exhaust #

(RadiationMonitor-M Aj

) > 18. Tanoby Gas Treatment System A & B Exhaust Radiation Monitors M A k "Using sample gas containing:

a. One volume percent hydrogen, remainder nitrogen.
b. Four volume percent hydrogen, remainder nitrogen.

"The CHANNEL CALIBRA110N shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R'/hr with an installed or portable gama source.

GRAND GULF-UNIT 1 3/4 3-76

, REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 For the following safety / relief valves:

a. The safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than those satisfying the safety valve fun tion requirement shall be OPERABLE with the specified lift setting __ an
b. he safety /reitef tail-pipe pressure switches for each safety / relief alve shall be OPERABLE.

Number of Valves Function Setooint* (esia) Be/eM 8 Safety 1165 i 11.6 psi 6 Safety 1180 i 11.8 psi 6 Safety 1190 1 11.9 psi 1 Relief 1103 i 15 psi 10' Relief 1113 i 15 psi 9 Relief 1123 15 psi APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With the safety and/or relief valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than Il0*F, take action to close the stuck open relief valve (s); if suppression pool average water temperature F or greater, place the reactor mode switch in the Shutdown c.(Hi15:n: er mere ::fety/r:1i fTil:-pip: Dr:ssvre swii.cr.e; tr.eperibie, i

r-utcr: the inep:r:ble switch (45) te OPEP/BLE ;tetus within 7 d:ys cr b; in l 4L i n s t 40T SHUTOC".'" wit.. . n on. n.u m uvo. , .uw .u ww anw w.m . Mn  ;

the fellettir,c M ha ra

d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REOUIREMENTS 7 L 4.4.2.1. %1 tail-pip: presesre switch for eech ;&fety/rulief u h . ih&H -be l y*=wtrat:d OPERASLE" with th; setpciat verified te b. 30 2 5 p iv by l Jerfe m r.ce vi i.

The lift setting pressure shall correspond to ambient conditions of the

' valves at nominal operating temperatures and pressures.

ff-"dnitial opening of IB21-F051B is 1103 + 15 psto due to low-low set function.'

A channel may De placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> foT kondition. required surveillance without placing the trip system in the tripped GRAND 3ULE-UNILC N WM

REACTOR COOLANT SYSTEM i REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS i

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a. CHANNEL FUNCTIONAL TEST at least once per 92 days, and a l
b. CHANNEL CALIBRATION at least once per 18' months.*

4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE" by performance of a: I

a. CHANNEL TUNCTIONAL TEST, including calibration of the trip unit, at least once per 92 days. l.
b. CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of the entire system at least once per 18 months.

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_o l The provisions of Specification 4.0.4 are not applicable provided the ' )I surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor. steam pressure is

__ adequate to' perform the test.

. A channel may be placed in an inoperable status for up.to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for j required surveillance without piccing the trip system in the tripped .i

. condition.  !

GRAND GULF-UNIT 1 3/4 4-6 Amendment No.105

Attcchm:nt 4 to GNRO-93/00097 d

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u INFORMATIONAL COPY OF PROPOSED TECHNICAL SPECIFICATION PAGES ACCIDENT MONITORING INSTRUMENTATION (GGNS PCOL-93/09) i I

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Attachment 4 to GNR0-93/00097l-TABLE 3.3.7.5-1 -

ACCIDENT MONITORING INSTRUMENTATION APPLICABLE MINIMUM ,

OPERATIONAL REQUIRED NUMBER CHANNELS INSTRUMENT. CONDITIONS OF CHANNELS OPERA 8LE ACTION.

1.. Reactor Vessel' Pressure 1, 2, 3 2 1- .80

2. Reactor Vessel Water Level 1, 2,'3, 4, S 2 1 82 3
3. -Suppression Pool Water Level 1,2,3 2 1 80-
4. Suppression' Pool Water Temperature 1, 2, 3 6,1/ sector 6,1/ sector 80-5.- Deleted
6. Drywell Pressure 1,2,3 2 1 80
7. - Drywell 'and ' Control Rod Drive Cavity Temperature 1,2,3 2 (each) 1 (each) 80
8. Containment Hydrogen Concentration Analyzer and Monitor 1,2,3 2 1 83
9. Drywell Hydrogen Concentration Analyzer :and Monitor' 1, 2, 3 - 2 1 83
10. Containment Pressure (wide and narrow range) 1, 2, 3 2 (each) 1 (each) 80
11. Containment Air Temperature .1, 2, 3 2 1 80
12. ~ Deleted .
13. . Containment /Drywell ' Area. Radiation Monitors 1,2,3,4,5 2' 2' 81-
14. Deletad
15. Deleted
16. Deleted
17. Deleted-
18. Deleted

.#Each for. containment'and.drywell.

GRAND' GULF-UNIT-c1 -3/4 3-74 Amendment. No. 403'-

- __- __-- - . . . . - . . . _ - - . - - - . . . . . . - - . . . - . - . . - - . . - - . . .. .. . . - . . . , - . . . - . . . . . - . . ~ . - . . .

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Attachment'4 to GNRO-93/00097 '

. TABLE 4.3.7.5-1 j ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .

CHANNEL CHANNEL l INSTRUMENT CHECK CALIBRATION

1. Reactor Vessel Pressure M R L.
2. Reactor Vessel Water Level M R 3
3. Suppression Pool Water Level M R  !
4. Suppression Pool Water Temperature M R  !

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5. Deleted l i
6. Drywell Pressure M R l
7. Drywell and Control Rod l

Cavity Temperature- M R f l

8. Containment Hydrogen Concentration Analyzer' and Monitor _ NA M*

L 9. .Drywell Hydrogen Concentration Analyzer and Monitor NA M* .

10. Containment Pressure M R' ,

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11. Containment Air Temperature M -R  :
12. Deleted  !-
13. Containment /Drywell Area Radiation ~

Monitors M R** j l

14. Deleted ,
15. Deleted j
16. Deleted
17. Deleted  :
18. Deleted  ;

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  • Using sample gas containing:- I l

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a. One volume percent hydrogen,; remainder nitrogen.  !

-b. FourLvolume: percent hydrogen. remainder. nitrogen.-  !

~ **The CHANNEL CALIBRATION shall consist of-an electronic calibration' of the1 channel; not including the detector, for range decades above 10R/hr and a-one point calibration check of the detectcr below 10R/hr with an installed or portable gamma source.-

GRAND GULF-UNIT 3/4 3-76: Amendment No.. q r

Attachment 4 to GNRO-93/00097 1

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES .

LIMITING CONDITION FOR OPERATION 1

3.4.2.1 For the following safety / relief valves:

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a. The safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than those satisfying the safety valve function requirement shall be OPERABLE with the specified lift ,

settings

b. Deleted l Number of Valves Function Setooint* (osio) 8 Safety 1165 i 11.6 psi 6 Safety 1180 1 11.8 psi 6 Safety 1190 1 11.9 psi 1 Relief 1103 1 15 psi '

10' Relief 1113 i 15 psi 9 Relief 1123 1 15 psi APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With the safety and/or relief valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '
b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 110*F, take action close the stuck open relief valve (s); if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position. J l
c. Deleted 8 l
d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status 1 within 7 days; otherwise be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and  !

in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  ;

SURVEILLANCE REQUIREMENTS

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4.4.2.1.1 Deleted l

  • The lift setting pressure shall correspond to ambient conditions of the ,

valves at nominal operating temperatures and pressures.  !

  1. Initial opening of IB21-F051B is 1103115 psig due to low-low set GRAND GULF-UNIT 1 3/4 4-5 Amendment No. 105 _

Attachment 4 to GNR0-93/00097

. REACTOR COOLANT SYSTEN

. SURVEILLANCE REQUIRENENTS (Continued) 4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE ** by performance of a:

a. CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least once per 92 days,
b. CHANNEL CALIBRATION, LOGIC SYSTEN FUNCTIONAL TEST and simulated automatic operation of the entire system at least once per 18 months.
    • A channel may be placed in an inoperable status for up'to.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for

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required surveillance without p1 acing the trip system in the-tripped condition.

GRAND GULF-UNIT 1 -3/4 4-6 -Amendment No. M5

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. REFERENCES i

.1)- NUREG-1434. Revision 0 of the Improved Standard Technical

. Specifications. l;

2) NUREG-0578 " Status of Short term Recomment.ations" .;
3) Letter L. F. Dale (MP&L) to H. R. Denton (NRC) " Regulatory Guide 1.97 - f (Rev. 2) Position Report on Accident Monitoring Instrumentation" (AECM-85/0059"
4) Letter L. F. Dale (MP&L) to H. R. Denton (NRC) " Response to. Request for  !

Additional Information on MP&L's Position Report on Regulatory Guide  :

1.97 (Rev. 2)  !

5) Letter L. L. Kintner (NRC).to 0. D. Kingsley (SERI) dated . .

January . 12, 1987 " Conformance to Regulatory Guide 1.97, Revi.clon 2" ij

6) NED0-31466 " Technical Specification Screening Criteria Application and Risk Assessment" i

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