ML18040A826

Proposed Tech Specs,Allowing Alternate Method of post-accident Drywell Gaseous Sampling & Providing Relief for Unnecessarily Restrictive Action Statement on Drywell Oxygen Analyzer

ML18040A826
Person / Time
Site:	Susquehanna
Issue date:	02/09/1987
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17146A708	List: ML17146A707 ML18040A825 ML18040A826
References
NUDOCS 8702180499
Download: ML18040A826 (20)

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%N t$ 0' a> ~ v TABLE 3.3.7.5-1 AQ) xc ~ Ill ACCIDENT MONITOR I NG INSTRUMENTATION QIQI 4 OO Olu' MINIMUM APPLICABLE "QOO,

,'au< y

~ *REQUIRED NUMBER CHANNELS OPERATIONAL

XI c=

INSTRUMENT OF CHANNELS OPERABLE ACTION CONDITION

l. Reactor Vessel Steam Domp Pressure 2 1 l

80 1 2

2. Reactor Vessel Mater Level 2 1 80 l1, 2

3. Suppression Chamber Mater Level 2 1 80 1, 2

4. Suppression Chamber Mater Temperature 8, 6 locations 6, 1/location 80 1, 2

5. Suppression Chamber Air Temperature 2 1 80 .1, 2

6. Primary Containment Pressure 2/range 1/range 80 1, 2

7. Drywe)1 Temperature 2 1 80 1, 2

8. Orwell Gaseous Analyzer

a. Oxygen 24 'ba, e2- 1P, 2II M', 2II 9.

10.

b. Hydrogen Safety/Relief Valve Position Indicators Containment High Radiation 1/valve" 2

1/val ve*

1 82 80 81 1, 2 1, 2

,

ll. Noble gas monitors"*

a. Reactor Bldg. Vent 81 1, 2 and *""

b. SGTS Vent 81 1, 2 and "*"

'1

c. Turbine Bldg. Vent 1 2

12. Neutron Flux 80 1, 2

~Acoustic monitor.

• • Mid-range and high-range channels O "*"When moving irradiated fuel in the secondary containment.

C)

IISee Special 74 Test Exception 3. 10. 1

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TABLE 4.3.7.5-1 ACCIDENT HONITORING INSTRllMEHTATION SURVEILLANCE RE UIREHEATS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATIOH

l. Reactor Vessel Steam Dome Pressure " H R

2. Reactor Vessel Water Level H R

3. Suppression Chamber Mater Level H R

4. Suppression Chamber Mater Temperature'.

H R Suppression Chamber Air Temperature M R

6. Primary Containment Pressure H R

7. Drywell Temperature H R

8. Drywell Oxygen/Hydrogen Analyzer~ H Q*

9. Safety/Relief Valve Position Indicators H R

10. Containment High Radiation H R ll. Noble gas monitors

a. Reactor Bldg. Vent

b. SGTS Vent H R

c. Turbine Bldg. Vent H R

12. Neutron Flux M R

(~e coy the peeplee e/ +<ee~ eel~)

or hydrogen ana yzer~ use sample gas containing:

a. Nominal zero volume 'percent hydrogen, balance nitrogen.

b. Nominal thirty volume percent hydrogen, balance nitrogen.

• "CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an .

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TABLE 3.3.7.5-1 ACCIDENT HOHI TOR ING IHSTRUHENTATION MINIHlJH APPLICABLE REQUIRED NUHBER CHANNELS OPERATIONAL INSTRUHENT OF CHANNELS OPERABLE ACTION CONDITIONS

1. Reactor Vessel Steam Dome Pressure 80 1, 2

2. Reactor Vessel Water Level 80 1, 2

3. Suppression Chamber Mater Level 80 1, 2

4. Suppression Chamber Mater Temperature 8, 6 locations 6, 1/location 80 1, 2

5. Suppression Chamber Air Temperature 2 1 80 1, 2

6. Primary Containment Pressure 2/range 1/range 80 1, 2

7. Drywell Temperature 2 1 80 1, 2

8. Orwell Gaseous Analyzer

a. Oxygen W 82 1,¹ 2¹ cS:A

b. Hydrogen 2 82 1,¹ 2¹

9. Safety/Relief Valve Position Indicators 1/val ve" 1/valve" 80 1, 2

10. Containment High Radiation 81 1, 2 ll. Noble gas monitors*"

a. Reactor Bldg. Vent 81 1, 2 and"""

b. SGTS Vent 81 2 and%**

c. Turbine Bldg. Vent 1 81 1, 2 and"""

12. Primary Containment Isolation Valve Position 1/valve 1/valve 80 1, 2

13. Neutron Flux 80 1, 2 "Acoustic monitor.

""Hid-range and high-range channels.

• • • When moving irradiated fuel in the secondary containment.

¹See Special Test Exception 3. 10. 1.

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CA CA TABLE 4.3.7.5-1 tll C

ACCIOENT HONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS CHANNEL CHANNEL IRSTRUHEHT CHECK CALIBRATION Reactor Vessel Steai Oome Pressure R

2. Reactor Vessel Mater Level R

3. Suppression Chamber Mater Level R

4. Suppression Chamber Mater Teimperature R

5. Suppression Chamber Air Temperature R

6. Primary Containment Pressure R GP

7. Orywell Temperature a R C

8. Orywell Oxygen/Hydrogen Analyzer ~ qA Ca) 9. .Safety/Relief Valve Position Indicators R

10. Containment High Radiation R**

Noble gas monitors a.. Reactor Bldg. Vent R

b. SGTS Vent R

c. Turbine Bldg. Vent R

12. Primary Containment Isolation Valve Position NA

13. Neutron Flux R (lsg,f gyt fgc, )ref (cHlh+4 l~A+ wA~ocif ER

• For hydrogen analyzer P use sample gas containing:

a. Nominal zero volume percentt hydrogen, balance nitrogen.

b. Nominal thirty volume percent hydrogen, balance nitrogen.

• "CHANNEL CALIBRATION shall consist of an electronic for range decades above 1O R/hr and a one point calibration calibration of the channel, not including the detector, check of the detector below 1O R/hr>>th an installed or portable gamma source.

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C CA AD TABLE 3.3.7.5-1 m

ACCIDENT HONITORING INSTRUMENTATION INSTRUHENT

~ REQUIRED NUMBER OF CHANNELS HINIHUM CHANNELS OPERABLE ACTION APPLICABLE OPERATIONAL CONDITION

~

Reactor Vessel Steam Domo Pressure 2 l

80 1, 2

2. Reactor Vessel Mater Level 80 )lq 2

3. Suppression Chamber Mater Level 2 1 80 1, 2

4. Suppression Chamber Mater Temperature 8, 6 locations 6, 1/location 80 1 2 Suppression Chamber Air Temperature 2 1 80 .1, 2

6. Primary Containment Pressure 2/range 1/range 80 1, 2

7. Drywell Temperature 2 1 80 1, 2

8. Drywell Gaseous Analyzer

a. Oxygen 288 1 I'III 82 lP, 1H 2h'8,

b. Hydrogen 82 2II'.

2k'/valve"

9. Safety/Relief Valve Position Indicators 1/valve" 80 2

10. Containment High Radiation 1 81 1 2

11. Noble gas monitors""

a. Reactor Bldg. Vent 81 1, 2 and *"*

b. SGTS Vent 81 1, 2 and "**

'1

c. Turbine Bldg. Vent 1 2

12. Neutron Flux 80 1 2 "Acoustic monitor.

"*Hid-range and high-range channels O ""*Mhen moving irradiated fuel in the secondary containment.

DSee Special Test Exception 3. 10.1 CD HThe preplanned alternate method of monitoring this parameter, once implemented, is considered a valid "channel" to meet this requirement.

TABLE 4.3.7.5-l ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMEATS CHANNEL CHANHEL INSTRUMENT CHECK CALIBRATION

1. Reactor Vessel Steam Dome Pressure R

'.

Reactor Vessel Mater Level R

3. Suppression Chamber Mater Level R

4. Suppression Chamber Mater Temperature R

5. Suppression Chamber Air Temperature R

6. Primary Containment Pressure R

7. Drywell Temperature R

8. Drywell Oxygen/Hydrogen Analyzers *

9. Safety/Relief Valve Position Indicators R

10. Containment High Radiation RA%

11. Noble gas monitors

a. Reactor Bldg. Vent

b. SGTS Vent

c. Turbine Bldg. Vent M

12. Neutron Flux M

!

or hydrogen ana yzer~(but not the preplanned alternate method), use sample'as containing':

a. Hominal zero volume'percent hydrogen, balance nitrogen.

b. Nominal thirty volume percent hydrogen, balance nitrogen.

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

8If the preplanned alternate method is being utilized, an appropriate CHANNEL CHECK and an appropriate CHANNEL CALIBRATION shall be performed at the listed frequencies.

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TABLE 3.3.7.5-1 ACCIDENT HONITORING INSTRUHENTATION HINIHUM APPLICABLE REQUIRED NUHBER CHANNELS OPERATIONAL INSTRUHENT OF CHANNELS OPERABLE ACTION CONDITIONS C

1. Reactor Vessel Steam Dome Pressure 80 1, 2 M

2. Reactor Vessel Mater Level 80 1, 2 tO

3. Suppression Chamber Mater Level 80 1, 2

4. Suppression Chamber Water Temperature 8, 6 locations 6, 1/location 80 1, 2

5. Suppression Chamber Air Temperature 2 1 80 1, 2

6. Primary Containment'Pressure 2/range 1/range 80 1, 2

7. Drywell Temperature 2 1 80 1, 2

8. Drywell Gaseous Analyzer

~

a. Oxygen 2yy 82 l,f 28

b. Hydrogen 2kTI 1H 82 1,8 28

9. Safety/Relief Valve Position Indicators '1/va1 ve" 1/val ve* 80 1, 2

10. Containment High Radiation 2 81 1, 2

11. Noble gas monitors"*

a. Reactor Bldg.- Vent 81 1 2 and*"*

b. SGTS Vent 81 and*A'4

c. Turbine Bldg. Vent 1 1 81 2 and

12. Primary Containment Isolation Valve Position 1/valve 1/valve 80 1, 2

13. Neutron Flux 1 80 1, 2

• Acoustic monitor.

"*Hid-range and high-range channels.

"*"When moving irradiated fuel in the secondary containment.

gSee Special Test Exception 3.10.1.

HThe preplanned alternate method of monitoring this parameter, once implemented, is considered a valid

" channel" to meet this requirement..

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TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Reactor Vessel Steam Dome Pressure H "'R

2. Reactor Vessel Mater Level H R

3. Suppression Chamber Mater Level H R

4. Suppression Chamber Mater Temperature H R

-5. Suppression Chamber Air Temperature H R

6. Primary Containment Pressure M R

l. Drywell Temperature R

8. Drywell Oxygen/Hydrogen Analyzer g H QA'

9. -Safety/Relief Valve Position Indicators

10. Containment High Radiation H R*A'

11. Noble gas monitors

a. Reactor Bldg. Vent H

b. SGTS Vent M

c. Turbine Bldg. Vent

'

H R

12. Primary Containment Isolation Valve Position H NA

13. Heutron Flux H R "For hydrogen analyzer,(but not the preplanned alternate method), use sample gas containi'na; I

a. Hominal zero volume percent hydrogen, balance nitrogen.

-b. Nominal thirty volume percent hydrogen, balance nitrogen.

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

glf the preplanned alternate method is being utilize'd, an appropriate CHANNEl CHECK and an appropriate CHANNEL CALIBRATION shall be performed at the listed freauencies.

SSES-FSAR recombiners are located approximately midway between the pedestal and containment wall.

The suppression chamber recombiners both have structures located close to two. of the recombiner ports. Both recombiners have a 42 1-1/2 inch diameter diaphragm slab support column approximately feet from the suction, and a 24 inch beam approximately 6 inches from the 26 inch high discharge.

The hydrogen recombiner is a natural convection, flameless, thermal reactor-type hydrogen/oxygen recombiner. The initiation time for the recombiners is prior to 1.2 days, post-LOCA as shown in Figures 6.2-49, 6.2-50 and 6.2-51. The heat-up time is approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Therefore, recombiner heat-up will begin approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to operation. The recombiner heats a continuous stream of containment atmosphere to a temperature sufficient for recombination of the hydrogen and oxygen,to form water.

The recombination unit consists of an inlet preheater section, a heater-recombination section, and a mixing chamber. The air is drawn into the unit by natural convection via the inlet louvers and passes through the preheater section, which 'consists of a shroud placed around, the central heaters to take advantage of heat conduction through the walls. In this area the temperature of the inlet air is raised. This accomplishes the dual function of increasing the system efficiency and of evaporating any moisture droplets which may be entrained in the air. The warmed air then passes through the flow orifice which has been specifically sized to regulate the airflow through the unit.

After passing through the orifice plate, the air flows vertically upward through the heater section, where its temperature is raised to the range of 1150-1400 F, causing recombination of H2 and 02 to occur. The recombination temperature is approximately 1135~8. The heater section consists of five banks of electric heaters stacked vertically. Each bank contains 60 individual U-type heating elements.

Next, the air rises from the top of the heater section and flows into the mixing chamber, which is at the top of the unit. Here, the hot air is mixed with the cooler containment air to discharge it back into the containment at a lower temperature.

containment air enters the mixing chamber through the The cooler lower part of the upper louvers located on three sides of the unit."

Table 6.2-18 gives the design characteristics of the hydrogen iecombiner.

Rev. 36, 07/85 6.2-71

EO" 200-103 Reiision 0 Page 17 of 33 PC/P-4 IF: 0 H2 CONCENTRATION > 3% BY VOLUME OR 24 HOURS HAS ELAPSED SINCE 1.72 PSIG SIGNAL, THEN: START H2 RECOMBINERS IAW OP-273"001 RUN DW COOLERS IN SLOW IAW ES-234-001 This step becomes effective when read and remains effective until flowchart exited. Ignition of combustible gases (hydrogen and oxygen) could result in significant containment pressure transients, leading to containment failure. This Will not occur if containment hydrogen concentration is maintained below 4%.

Therefore, start hydrogen recombiners at 3% concentration. Run drywell coolers in slow to avoid pockets with high hydrogen concentrations. Start both systems also after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has elapsed from receipt of LOCA signal to counteract buildup of combustible gas due to radiolysis. Secure hydrogen recombiners prior to initiating containment sprays.

pc/p-5 REDUCE PC PRESSURE USING:

(PC/P-1) o SBGT IAW ON-234-001, ONLY WHEN DW AND SUPP CHAMBER TEMP < 212 F o RPV DEPRESSURIZATION AND COOLDOWN IAW RPV CONTROL o ES"234-001, BYPASSING DRYWELL COOLING'OGIC ISOLATIONS Reduce containment pressure using listed procedures. These procedures account for 1.72 psig isolations. Initiate RPV depressurization and cooldown'in accordance with E0-200-102, RPV Control, performed concurrently with this procedure.

Use SBGT only if primary containment temperatures are below 212~F:

If temperature is above 212 F, steam may be admitted to containment. Continued use of SBGT would eventually reduce containment's non-condensible air mass and prevent using drywell sprays.

pc/p-e BEFORE DW OR SUPP CHAMBER PRESSURE REACHES 0 PSIG,

-

TERMINATE PRESSURE REDUCTION This step becomes effective when read and remains effective until flowchart exited. It gives appropriate time to stop pressure reduction, whatever means employed (i.e. SBGT or sprays). Stop pressure reduction at this point to prevent containment failure on negative pressure.

0 RRC LIMITS EXPERIMENT FLAMMABLE PETONABL AIR NON-FLAMMABLE

$ % O~

20 Figure 1. COMBUSTION CHARACTERISTICS OF H> IN AIR AND STEAM

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C NONFLAMMABLE 40 COMBUSTIBLE . 0 30 02 AIR INERT RAOIOLYSIS METAL-WATER RECOMBINATION Figure 2 MITIGA TION OF DEGRADED CORE EN VIRONMENTBY RECOMBINATION

4 TOTAL RADIOLYSIa 150 4

W 4

4, 4 '100 IL R

8 4.

X O~yy e~ Priul~eed S

(Ih-<<le)

METALWATER REACTION PlUS INITIALHYDROGEN 10 20 TIME AFTER LOCA IDAYSI Rev. 35 07 84 SUSCNEHANNA STEAN ELECTRIC STATION UNITS 1 AND 2 FINAL SAFETY ANALYSN REPORT INTEGRATED PRODUCTION OF HYDROGEN VS. TIME AFTER LOCA FIGURE 6. 2-4.8

I 8

C1 N CCI I

C IV~JAXO p N3008OAHLNBQBBdBWllOA Rev. 35 07/84~

SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT HYDROGEN CONCENTRATION IN THE.DRYNELL VS. TIME AFTER LOCA (SHORT TERM)

BOURS "6'2-50

I 1? F 1 ~ ATTACQIENT 6 I COIIThISKHT HYOROGEN MONITOR I

A continuous.'fndication of hydrogen concentration in the containment atjaosphcrc shall be provided in the control rooa. Hcasurcacnt capability shall bc provided over the range of 0 to 10K hydrogen concentration under both positive and negative aablent pressure.

Cha s to Prevfous R ufreaents and Guidance Regulatory Gufde 1.9>, Rev. 2 was referenced in the October 30, 1979 letter as the guide for the design and qualification crfterfa for the contafnecnt hydrogen monitor. However, there have been aany changes aade to this proposed revision and ft has not yet been sade ffw.'.. Therefore, the appropriate sections of ttw latest version of Regulatory Guide 1.97 have been added to this letter (Appendix A) and, therefore, this fs to be considered a ncw rcqufreeent.

The f~ltaentatfon date has been changed due to cqufpoent procurcacnt probleas.

The new fepleaentation schedule is intended to allow licensees enough tiae to coeplete design modifications with a afnfaua nueber of plant shutdowns.

Clarification (1) . Design and qual ifIcitfon crfterfa are outlined fn Appendix A.'2)

Ttw continuous fr.)ication of hydrogen concentration Is not required during noraal operation.

lf an fndfcatfon fs not available at all tfees, continuous indicatfon and recording shall be functioning within 30 afnutes of the initiation of safety infection.

(3) Ttw accuracy and placeeent of the hydrogen eonftors shall be provided and

)ustified to be adequate for their intended functfon.

Tt:: wqufrccwnt applies to alt operatfng reactors and all applicants for operating licenses.

I lceentatfon For operating reactors, desfgn aodfffcatfons should be coapleted by January 1, 1982.

Operating license applicants with an operating license date before January 1, 1982 est have design changes coapleted by January 1, 1982, whereas those applicants with license dates past January 1, 1982 aust have all design oodfff-catfons coapletcd before they can rccefve their operating license.

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