ML20023A838
| ML20023A838 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/15/1982 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20023A816 | List: |
| References | |
| RTR-NUREG-0661, RTR-NUREG-661 NUDOCS 8210200068 | |
| Download: ML20023A838 (6) | |
Text
. _ -.
TABLE 3.2.F - SURVEILLANCE INSTRUMENTATION OD
~
DF Minimum No.
>* cf Operable Type CD Instrument Indication Np Channels Instrument and Range Action ***
^
c,___________________________________________________________________________________________
f 2
Reactor Water Level Recorder 0-60" (6) (7)
E' Indicator 0-60" 2
Reactor Pressure Recorder 0-1500 psig (1) (2) (3)
- )
Indicator 0-1200 psig 2
Drywell Pressure Recorder 0-70 psig (1) (2) (3) 3 Drywell Temperature Recorder 0-400*F (1) (2) (3)
Indicator 0-400*F 2
Suppression Chamber Water Recorder 30-230'F (1) (2) (3)
Temperature
- Indicator 30-230*F (9)
Ly 2
Suppression Chamber Water Recorder 0-600 F (1) (2) (3)
Temperature **
Indicator 0-400 F 2
Suppression Chamber Water Recorder 0-2 ft.
(1) (5)
Level Indicator 0-2 ft.
1 Control Rod Position 28 Volt Indicating )
Lights
)
)
(1) (2) (3) (4) 1 Neutron Monitoring SRM,IRM,LPRM
)
0-100%
)
1 Safety-Relief Valve Acoustic or (8)
Position Indication thermocouple Effective when modification associated with this amendment request is complete.
Delete when modification associated with this amendment request is complete.
- Notes'for Table 3.2.F appear on page 78.
p3gpg NOTES FOR TABLE 3.2.F 1)
From and after the dato that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.
2)
From and after the date that one of these parameters is not. indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.
3)
If the requirements of notes (1) and (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4)
These surveillance instruments are considered to be redundant to each other.
5)
In the event that all indications of this parameter are disabled and such indication cannot be restored in six (6) hours, an orderly 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.
6)
With the number of operable channels less than the 5
minimum number of instrumentation channels shown in Table 3.2.F, either restore the inoperable channel to an operable status 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 />.
7)
If this parameter is not indicated in the control room.
either restore at least one inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
8)
If this parameter is not indicated in the control room, either restore at least one channel to operable status within thirty days or be in at least hot shutdown within the next 12-hours.
9)
A suppression Chamber Water Temperature instrument channel will be considered operable if there are at least ten (10) resistance temperature detector inputs operable,and no two (2) adjacent resistance temperature i
detector inputs are inoperable.
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TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION
' Instrument Channel Calibration Frequency Instrument Check 1)
Reactor Level Once/ Operating cycle Once Each Shift.
2)
Reactor Pressure Once/6 months Once Each Shift 3)
Drywell Pressure Once/6 months once Each Shift 4)
Drywell Temperature Once/6 months Ont c Each Shift 5)
Suppression Chamber Water Once/ operating cycle **
On..c Each Day **
Temperature Once/6 months ***
Orace Each Shif t***
6)
Suppression Chamber Water Level Once/6 months Once Each Shift 7)
Control Rod Position NA Once Each Shift 8)
Neutron Monitoring (APRM)
Twice Per Week Once Each Shift 9)
Safety / Relief Valve Position Once/ Operating cycle Once/ Month Indicator (acoustics)
- 10) Safety / Relief Valve Position NA*
Once/ month Indicator (thermocouple)
- 11) Safety Valve Position Once/ operating cycle Once/ month Indicator (Acoustics)
- 12) Safety Valve Position NA*
Once/ month Indicator (thermocouple)
Perform instrument functional check once per operating cycle
- Effective when modification associated with this amendment request is complete.
- Delete when modification associated with this amendment request is complete.
i
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability:
Applicability, Applies to the operating Applies to the primary and status of the primary and secondary containment secondary containment integrity, systems.
Objective:
Objective:
To assure the integrity of To verify the integrity of the primary and secondary the primary and secondary containment system.
containment.
Soecification:
Specification:
- 1. The suppression chamber water level and temperature
- 1. Whenever the nuclear shall be checked once per system is pressurized day.
above atmospheric pressure or work is being done
- 2. Whenever there is in-which has the potential dication of relief valve to drain the vessel, operation (except when the pressure suppression the reactor is being pool water volume and shutdown and torus temperature shall be cooling is being es-maintained within the tablished) or testing following limits except which adds heat to the as specified by 3.7.A.2, suppression pool, the or when inoperability pool temperature shall of the core spray systems, be continually monitored the LPCI and containment and also observed and cooling subsystems is logged every 5 minutes permissible as provided until the heat addition for in 3.5.F.3 and 3.5.F.4.b.
is terminated, a.-Minimum water volume-
- 3. Whenever there is indication 3
122,900 ft of relief valve operation with the local suppression
- b. Maximum water volume-pool temperature reaching 200*F 3
127,300 ft or more, an external visual examination of the suppression chamber shall be conducted be-fore resuming power operation.
- 4. A visual inspection of the sup-
'pression chamber interior, in-cluding water line regions shall be made at each major refueling outage.
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j PBAPS
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE
)
REQUIREMENTS l
l 3.7.A Primary Containment (Cont' d)
I
)
c.
Maximum average suppression pool temperature limits:
1
-(l) During startup/ hot standby and run modes, with the suppression pool temperature greater than 95'F, except l
as permitted below, restore the temperature to less than 95*F within l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in 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 /> and 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 />.
(2) During testing which adds heat to the suppression pool, the pool temperature shall not exceed 105 F. Should the pool temperature axceed 105'F, such testing shall be stopped and the pool temperature must be reduced to below the limit specified in (1) above 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 shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 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 />.
(3) The reactor shall be scrammed from any operating condition if the pool tempera-ture reaches 110'F. Power operation shall not be resumed until the pool temperature is reduced below the limit specified in (1) above.
(4) During reactor isolation conditions, the. reactor pressure vessel shall be depressurized to less than 200 psig at normal cooldown rates if the pool temperature reaches 120*F.
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PBAPS 3.7.A & 4.7.A BASES (Cont'd)
The maximum allowable volume assures the integrity and functional capability of the Suppression Chamber (torus) during postulated LOCA pool swell effects on the torus support system.
The majority of the Bodega tests were run with a submerged length of 4 feet and with complete condensation.
Thus, with respect to downcomer submergence, this specification is adequate.
The maximum temperature at the end of blowdown tested during the Humboldt Bay and Bodega Bay tests was 170 F cnd this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170 F.
Should it be necessary to drain the suppression chamber, this should
}
only be done when there is no requirement for core standby cooling systems operability as explained in basis 3.5.F.
Experimental data indicates that excessive steam condensing loads can be avoided if the peak temperature of the suppression pool water at the quencher discharge is maintained below 200 F during any period of relief valve operation discharging through tee quenchers.
Because of the large volume and thermal capacity of the suppression pool, the volume and temperature changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends.
By requiring the suppression pool temperature to be continually monitored and frequently logged during periods of testing which add significant heat, the temperature trends will be closely followed so that appropriate action can be taken if required.
Logging is not required during inadvertent relief valve operation since during such periods operator action is actively and directly involved in operations relating to controlling torus temperature and monitoring of temperature trends is a natural part of the operations.
Additionally, j
torus temperature is monitored by a recorder during these periods so i
that an historical record is available.
Operating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open.
As a minimum this l
action shall include: (1) use of all available means to close the valve, (2) initiate suppression pool water cooling heat exchangers, e
(3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of
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cnergy insertion to the pool.
1, l
The requirement for an external visual examination following any event i
where potentially high loadings could occur provides assurance that no significant damage was encountered.
Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest etress.
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