ML20151D490
| ML20151D490 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/11/1988 |
| From: | Newson C LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20151D407 | List:
|
| References | |
| PROC-880511-02, NUDOCS 8807250141 | |
| Download: ML20151D490 (19) | |
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9 SHOREHAM NUCLEAR POWER' STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #4-SECONDARY CONTAINMENT CONTROL REVISION NO: 0 DATE:
- I PREPARED BY:
8/!88 REVIEWED BY: [bhI)hs DATE:
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f OPERATING ENGINEER APPROVAL: #
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DATE:
3 / 2///#7 8807250141 080715 PDR ADOCK 05000322 F
PNV MAY 111988 R ORIAT,00 E'!j J
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Centrol EPG Step:
PURPOSE The purpose of this guideline is to:
o.
Protect equipment in the secondary containment, o
Limit radioactivity release to the secondary containment, and either:
o Maintain secondary containment integrity, or o
Limit radioactivity release from the secondary containment.
SNPS PSTG Step:
PURPOSE The purpose of this guideline is to:
o Protect equipment in the secondary containment, o
Limit radioactivity release to the secondary containment, and either:
o
-Maintain secondary containment integrity, or Limit radioactivity rclease from the secondary containment.
o Justification for Differences / Releases N/A l
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PSIG #4 Rev. 0 l
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-f SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Contcinment Control EPG Step:
ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions:
o Differential pressure at or above 0 in, of water An area temperature above the maximum normal operating temperature o
A HVAC cooler differential temperature above the maximum normal operating o
differential temperature o
A HVAC exhaust radiation level above the maximum normal operating radiation level An area radiation level above the maximum normal operating radiation level o
A floor drain sump water level above the maximum normal operating water o
level An area water level above the maximum normal operating water level o
- SNPS PSTG Step:
_ ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions:
o Reactor Building differential pressure at or above 0 in. of water.
A Secondary Containment area terperature above the maximum normal operating o
temperature.
o Reactor Building HVAC exhaust radiation Ir rel above the maximum normal l
operating radiation level.
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Secondary Containment area radiation level above the maximum normal l
operating radiation level, PSTG #4 Rev. 0 i
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3 SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control SNPS PSTG Step LNTRY CONDITIONS (Cont')
o A floor drain sump water level above the maximum normal operating water level.
Justification for Differences / References Deleted "HVAC cooler differential temperature above the maximum normal operating differential temperature" since SNPS woes not have the requisite HVAC coolers or instrumentation necessary to execute this step.
The Shoreham secondary containment is not compartmentalized and therefore does not have areas where water can accumulate other than the lowest elevation of the building (Elevation 8').
Therefore the "area water level" has been deleted since it is not possible for flooding of any portion of elevation 8 to occur prior to-the floor drain sumps reaching their maximum normal operating level.
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PSTG #4 Rev. O Page 3
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o SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control i-EPG Step:
OPERATOR ACTIONS If while executing the following steps secondary containment HVAC exhaust radiation level exceeds.(20 mr/hr (secondary containment HVAC isolation setpoint)):-
Confirm or manually initiate isolation of secondary containment HVAC, o
and Confirm initiation cLf or manually initiate SBGT.
o If while executing the following steps:
o Secondary containment HVAC. isolates, and, Secondary containment HVAC exhaust radiation level is below (20 mr/hr o
(secondary containment HVAC isolation setpoint)],
restart secondary containment'HVAC, defeating high drywell pressure and low RPV water level isolation interlocks if necessary.
Irrespective of the entry condition, execute (Steps SC/T, SC/R, and SC/L]
concurrently.
SNPS PSTG Step:
OPERATOR ACTIONS Notify the Watch Engineer to classify the event per EPIP l-0.
'Ifwhileexecutingthefollowinggtepssecondarycontainmentexhaust radiation levels exceeds 5.4 x 10 CPM as read on PM-29.
o Confirm or manually initiate isolation of RBNVS.
o Confirm initiation of or manually initiate RBSVS, Irrespective of the entry condition, execute Steps SC/T, SC/R, and SC/L concurrently.
PSTG #4 Rev. O Page 4
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control Justification for Differences / References At SNPS,_the Reactor Building Standby Ventilation System (RBSVS) initiates on eny of the following signals:
.y.e i creasure o
Low-Low Reactor Level 5
o 5.4 x 10 CPM in the containment purge lines o
Manual initiation of NSSSS l'ogic o
Closure of either the inlet and/or outlet reactor building isolation valves.
o 35 mR/hr in the refueling level ventilation exhaust.
Without a secondary containment HVAC isolation setpoint for the RBSVS, a suitable high radiation value at thesecondarycogtainmentexhaustwhichmeets the intent of this EPG step was chosen.
5.4 x 10 CPM on PNL-029 is a reasonable value at which to tell the operator to isolate RBNVS and initiate RBSVS. This value was selected because it is the setpoint at which the containment purge / vent valves will be isolated via 1D11-PNL-019. The containment purge / vent valve isolation was calculated so as to remain within 10CFR100 limits for Protective Action Guidelines as per LILCO's commitment to the NRC in responte to TMI action plan (NUREG 0737) item II.E.4.2.
The
-r---d override step is eliminated because the reason behind it is not applicable to Shoreham.
Since Shoreham does not have a Standby Gas Treatment system, and instead has RBSVS, the EPG's intent has to be analyzed. According to the owners Group's explanation of this step, the high drywell pressure / low reacter rater level Interlocks are bypassed, and the secondary containment high radiation interlock is left in place. This is to ensure that if radiation 1svels at-the secondary containment exhaust rose to the initiation setpoint, SBGT would still initiate. Without this interlock, the Shoreham RBSVS system would not automatically re-initiate if operators bypass the hick drywell pressure low reactor level initiation signals. Also,'the Emergency Procedure Guideline requires this step for plants with SBGT since SBGT does not provide algniticant cooiing to the secondary containment during an accident. At Shoreham, RBSVS and emergency chilled water provide extensive cooling to the raa-*^- 5"41 ding during an accident.
In fact, emergency chilled water is cue u vi removing more heat from the secondary containment than normal chilled water.
(Reference - SWEC Calc 19-5.3-1 and System Descriptions 420 and 421).
PSTG #4 Rev. O Page 5
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control Justification for Differences / References For both of these reasons ~(no high radiation isolation and extensive cooling captbility) the Shoreham PSTG will not require restart of the normal ventilation system if RBSVS has initiated.
0 5.4 x 10 CPM:
Tech Spec Table 3.3.7.1-1 Added SNPS Specific Emergency Planning Requirements PSTG #4 Rev. O Page 6
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.SHOREHAM NUCLEAR POWER-STATION j
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Plant Specific Technical Guidelines Secondary Containment Control' L
E EPG Step:
l SC/T:
Monitor and control secondary. containment temperatures.
SC/T 'Operat'e-available area coolers.
SC/T-2 If secondary containment HVAC exhaust radiation level is below [20 mr/hr (secondary containment HVAC isolation cetpoint)], operate available secondary containment HVAC.
SC/T-3 When an area temperature exceeds its maximum normal operating temperature, isolate all
[
]
systems that are discharging into the
[
- 1
)
area except systems required to shut
[
]
down the reactor, assure adequhte core cooling, or suppress a fire.'
l SNPS PSTG Step
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SC/T Monitor and control secondary containmant temperatures.
SC/T-1 Operate available Reactor Building area coolers.
H SC/T-2 Deleted SC/T-3 When an area temperature exceeds its maximum normal operating temperature, isolate'all systems that are discharging into the
- 1 area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire.
. Justification for Differences / References SC/T-2 has been deleted for the sace reason mentioned previously. The purpose of.this step in the guideline is to maximize cooling in the secondary containment.
Since secondary containaent cooling is adequate during RBSVS, thsre is no benefit in directing the operator to restart RENVS.
PSTG #4 Rev. O Page 7
O SHOREHAM NUCLEAR POWER STATION i
j Plant Specific Technical Guidelines i
Secondary Containment Control l
l EPG Ster:
l Execute (Steps SC/T-4 and SC/T-5) concurrently.
SC/T-4 If a primary system is discharging into secondary containment:
SC/T-4.1 Before any area temperature reaches its maximum safe operating temperature, enter (procedure developed frem the RPV Control Guideline) at [ Step RC-1] and execute it concurrently with this procedure.
SC/T-4.2 When an area temperature exceeds its maximum safe operating temperature in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
SNPS PSTG Step:
Execute Steps SC/T-4 and SC/T-5 concurrently.
SC/T-4 If a primary system is discharging into secondary containment:
SC/T-4.1 Before any area temperature reaches its maximum safe operating temperature, enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure, i
SC/T-4.2 When an area temperature exceeds its maximum safe operating temperature in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
Justification for Differences / References N/A PSTG #4 Rev. O Page 8
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control EPG Step:
SC/T-5.
When an area temperature exceeds its maximum safe operating temperature in more than one area, shut down the reactor.
SNPS PSTG Step:
SC/T-5 When sui area temperature exceeds its maximum safe operating temperature in more than one area, shut down the reactor, using SP 22.005.01.
SC/T-6 Continue to reduce area temperatures until below the values of Table 1, Column 1.
Justification for Differences / References Reference added as to how operators are to shutdown the reactor gi'en high temperatures in more than one area.
Added SC/T-6 step as a transition / continuation step. The valiration of this procedure pointed to the need for such a step.
PSTG #4 Rev. O Page 9 1
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O SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control EPG Step:
SC/R Monitor and control secondary containment radiation levels.
SC/R-1 When an area radiation level exceeds its maximum normal operating radiation level, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire.
SNPS PSTG Step:
SC/R Monitor and control secondary containment radiation levels.
SC/R-1 When an area radiation level exceeds its maximum normal operating radiation level, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire.
Justification for Differences / References N/A PSTG #4 Rev. O Page 10
SHOREHAM NUCLEAR POWER STATION' Plant Specific Technical Guidelines Secondary Containment Control EPG Step:
Execute (Steps' SC/R-2 and SC/R-3] cor. currently.
bC/h-2 If a primary system is discharging into secondary containment:
SC/R-2.1 Before any area radiation level reaches its maximum safe operating radiation level, enter (procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this
. procedure.
SC/R-2.2 When an are radiation level exceeds its maximum safe operating radiation level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
SC/R-3 When an area radiation level exceeds its maximum safe operating radiation level in more than one area, shut down the reactor.
SNPS PSTG Step:
Execute Steps SC/R-2 and SC/R-3 concurrently.
SC/R-2 If a primary system is discharging into secondary containment:
SC/R-2.1 Before any area radiation level reaches its maximum safe operating radiation level, enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.
SC/R-2.2 When an are radiation level exceeds its maximum safe operating radiation level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
SC/R-3 When an area radiation level exceeds its maximum safe operating radiation level in more than one area, shut down the reactor, using SP 22.005.01.
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SC/R-4 Continue to reduce area rad levels until below Table 1, j
Column 1.
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t PSTG #4 Rev. O Page 11
y SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control
- Justification for Differences / References R3ference added as to'how opera.rs are to shutdown the reactor given high radiation level in more than one area.
,Addsd SC/R-4 as a transition / continuation step. The validation of this procedure pointed to the need for such a step.
PSTG #4 Rev. O Page 12
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control EPG Step:
SC/L Monitor and control secondary containment water levels.
SC/L-1 When a floor drain sump or area water level is above its maximum normal operating water level, operate available sump pumps to restore and maintain it below its maximum normal operating water level.
If any floor drain sump or area vater level cannot be restored and maintained below its maximum normal operating water level, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire.
SNPS PSTG Step:
SC/L Monitor and control secondary containment water levels.
SC/L-1 When a floor drain sump water level is above its maximum normal operating water level, operate available sump pumps to restore and maintain it below its maximum normal operating water level.
If any floor drain sump cannot be restored and maintained below its maximum normal operating water level, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire, i
If water level on Elevation 8 continues to rise and reaches
+0.5 inches, operate suppression pool pump back only if suppression pool water level can be maintained below the SRV Tail Pipe Limit (Figure H).
Justification for Differences / References Dmleted "or area water level" - N/A to SNPS since SNPS does not have a compartmentalized secondary containment.
Addsd suppression pool pump back to this step. This is the most appropriate tina to tell the operator to initiate this system, since it is before more drcatic actions are specified and after normal actions have proved inadequate.
Th3 reference to +1" is derived from the existing alarm's setpoint.
(1G11*LIS645 A/B).
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PSTG #4 Rev. O Page 13
SHORENAM NUCLEAR POWEP. STATION Plant Specific Technical Guidelines Secondary Containment Control EPG Step:
Execute (Steps SC/L-2 and SC/L-3) concurrently.
SC/L-2 If a primary system is discharging into secondary containment:
SC/L-2.1 Before any area water level reaches its maximum safe operating water level, enter (procedure developed from the RPV Control Gui'deline] at (Step RC-1) and execute it concurrently with this procedure.
SC/L-2.2 When an area water level exceeds its maximum safe operating water level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
SC/L-3 When an area water level exceed, its maximum safe operating water level in more than one area, shut down the reactor.
SNPS PSTG Step:
Execute (Steps SC/L-2 and SC/L-3] concurrently.
SC/L-2 If any system is discharging into secondary containment:
SC/L-2.1 Before Elevation 8 water level reaches 18 in., enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.
SC/L-2.2 When Elevation 8 water level exceeds 18 in., EMERGENCY RPV l
DEPRESSURIZATION IS REQUIRED.
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When Elevation 8 water level exceeds 18 in., shut down the reactor, per SP 29.010.01.
SC/L-4 Continue to reduce floor drain sump levels until below the values of Table 1, Column 1.
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control Justification for Differences / References Brordened the conditional statement to include internal flooding from all cources.
Added SC/L-4 as a transitional / continuation step. The validation of this procedure pointed to the need for such a step.
Msximum safe operating water level - SNPS Probabilistic Risk Assessment, Appandix G, Table G.3-3.
Addsd guidance on how to shutdown the reactor.
PSTG #4 Rev. O Page 15 i
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control TABLE 1 Operating Values of Secondary Containment Parameters Max Normal Max Safe Tcmp-Operating Operating Arta-Description Temperature Temperature (1)
Elevation 8' 104*F 150*F (2)A Elevation 40' and Truck Bay (El. 40' 104'F 152'F El. 63') excluding MCC Room OB1 (3)
MCC Room OB1 (Elevation 40')
104'F 125'F (4)
CRD Master Control / Remote Shutdown 104*F 148'F Panel area and Low Pressure ECCS pipe areas (El. 63')
(5)*
Ilevation 76' excluding Steam Tunnel 104*F 160*F (6)*
Elevation 112', excluding RWCU Rooms 104'F 157'F and MCC Rooms (7)
East MCC Room (Elevation 112')
104*F 125'F (8)
West MCC Room (Elevation 112')
104'F 125'F l
(9)
RWCU Pump Rooms (Elevation 112')
104'F 150*F 1
l (10)
RWCU Heat Exch. Room (Elevation 126')
104'F 150'F 111)*
Northern half of Elevation 150' 104'F 136*F (12)*
Southern half of Elevation 150-104*F 147'F excluding MG Rooms 4
(13)
MG Rooms 111, 112, 113A, 113B (El. 150')
104'F 125'F (14)*
Elevation 175' 104'F 155'F (15)**
Steam Tunnel (Elevation 78')
135'F 215'F This temperature area does not presently have remote temperature monitoring capability in the Control Room.
- The Control Room temperature monitor's scale in this area is below the maximum safe operating temperature listed.
PSTG #4 Rev. O Page 16
SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Secondary Containment Control TABLE l' Operating Values of Secondary Containment Parameters Max Normal Max Safe Rad Operating Operating
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2 _:.
Rad Level Rad Level
'(1)
Elevation 8' 50 mR/hr 6000 mR/hr (2)
Eastern half of Elevation 40' 50 mR/hr 6000 mR/hr (3)
Western half of Elevation.40' 50 mR/hr 6000 mR/hr and Truck Bay (El. 40' - El. 63')
(4)*
CRD Master Control / Remote Shutdown 50 mR/hr 6000 mR/hr Panel (El. 63')
(5)
Low Pressure ECCS Tipe area - East 50 mR/hr 6000 mR/hr (E1. 63')
(6)
Low Pressure ECCS Pipe Area - West 50 mR/hr 6000 mR/hr (El. 63')
(7)
TIP Driva Area (Elevation 78')
50 mR/hr 6000 mR/hr Excluding Room (8)
Equipment Hatch Area (Elevation 78')
50 mR/hr 6000 mR/hr (9) 9: stern half of Elevation 78' 50 mR/hr 6000 mR/hr (10)
Area outside RWCU Pump Rooms (E1. 112')
50 mR/hr 6000 mR/hr (11)
Western half of Elevation 112' 50 mR/hr 6000 mR/hr (12)
Northern half of Elevation 150' 50 mR/hr 6000 mR/hr (13)
Southern half of Elevation 150' 50 mR/hr 6000 mR/hr i
l (14)
Elevation 175' 10 mR/hr 600C mR/hr 6
'-ci 1400 mR/hr 1 x 10 mR/hr The area does not presently have remote radiation monitoring in the Control Room.
NOTE:
The Max Safe Operating Rad Level listed is beyond the scale available for remote monitoring in the Control Room.
l PSTG #4 Rev. O Page 17
w SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines 6
Secondary Containment Control TABLE 1 Operating Values of Secondary Containment Parameters Max Normal Max Safe Operating Operating Secondary Containment Parameter Value
-Value Floor Drain Sump Level A Full N/A Floor. Drain Sump Level B Full N/A Floor Drain Sump Level C Full N/A
' Elevation 8' N/A 18" Elsvation 8' Max. Safe operating value:
SNPS PRA, Appendix G Table G.3-3 l
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PSTG #4 Rev. O Page 18
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