ML20151D597
| ML20151D597 | |
| 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-880511-07, NUDOCS 8807250174 | |
| Download: ML20151D597 (9) | |
Text
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SHOREHAM NUCLEAR POWER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG fil PRIMARY CONTAINMENT FLOODING REVISION NO: 1 i
PREPARED BY:
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DATE:
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REVIEWED BY:
OPERATING ENGINEER APPROVAL:
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8807250174 880715 MM 11 GBB
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding EPG Step If while executing the following steps:
Primary containment water level and suppression chamber pressure cannot be o
maintained below the Maximum Primary Containment Water Level Limit, then irrespective of whether adequate core cooling is assured terminate injection into the RPV from sources external t,o the primary containment until primary containment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
.RPV water level can be restored and maintained above (-164 in. (top of active
-o fuel)], enter (procedure developed from the RPV Control Guideline] at (Step RC/L).
SNPS PSTG Step:
If while executing the following steps:
Primary containment water level and suppression chamber pressure cannot be o
maintained below the Maximum Primary Containment Water Level Limit, (Figure B) then irrespective of whether adequate core cooling is assured terminate injection into the RPV from sources external to the primary containment until primary containment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
RPV water level can be restored and maintained above -158 in., enter procedure o
developed from the RPV Control Guideline at Step RC/L.
Justification for Differences / References M2ximum Primary Containment Water Level Limit: NED Appendix C Calculation C-NAD-268
- op of Active Fuel: Tech Spec l'igure B 3/4 3-1 PSTG #11 Rev. 1 Page 1
'i SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 6 Primary Containment Flooding EPG Step:
C6-1 Initiate SPMS.
.SNPS PSTG Step:
C6-1 None Justification for Differences / References SNPS does not have a Suppression Poo1~ Makeup System.
l l
PSTG #11 Rev. 1 Page 2
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding EPG Step
'C6-2 Operate the following systems:
o HPCS with suction from the condensate storage tank when available, o
LPCS; operate one LPCS with suction from the condensate storage tank
[or fire system] only when the other LPCS is operating with suction from the suppression pool, o
Condensate /Feedvater o
CRD o
RCIC with suction from the condensate storage tank only, defeating low RPV pressure isolation interlocks and high suppression pool water level suction transfer logic if necessary.
o LPCI with suction from sources external to the primary containment
[only.] [if possible).
[o RHR service water crosstie
]
[o Fire System
)
[o Interconnections with other units
]
[o ECCS keep-full systems
]
[o Other primary containment fill systems
]
Execute [ Steps C6-3 and C6-4] concurrently.
PSTG #11 Rev. 1 Page 3
- o SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding
.SNPS PSTG Step:
C6-2 Operate the following systems:
' Core Spray System; operate one core spray pump with suction from the o
condensate storage tank only when the other core spray pump is operating with suction from the suppression pool.
o Condensate /feedwater o
CRD RCIC with suction from the condensate storage tank only, defeating low o
RPV pressure isolation interlocks and low CST level suction transfer logic if necessary.
RHR service water crosstie (Ultimate Cooling) o o
Fire Main to Ultimate Cooling et o
ECCS Connections from Condensate Transfer Execute Steps C6-3 and C6-4 concurrently.
Justification for Differences / References Deleted HPCS, Interconnections with other units, and other primary containment fill systcms (N/A to SNPS).
Reworded RCIC system statement to reflect Shoreham specific interlocks.
Deletsd the step to use LPCI for filling the containment (N/A to SNPS).
Clarified the descriptions of the alternate injection subsystems to be Shoreham specific.
PSTG fil Rev. 1 Page 4
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SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding
-EPG Step:
.C6-3 When-primary containment water level reaches [26 ft. 3 in. (elevation of the bottom of the lowest recirculation piping)], then irrespective of the offsite radioactivity release' rate vent the RPV, defeating isolation interlocks if necessary, until RPV water level reaches [-164 in. (top of active fuel)) with one or more of the following:
o Flood vent valves o
MSIVs o
Main steam line drains o
HPCI steam line o
RCIC steam line o
IC tube side vents o
RHR SNPS PSTG Stept C6-3 When primary containment water level reaches Elevation 65 ft. 6 in., then irrespective of the offsite radioactivity release rate vent the RPV, defeating isolation interlocks if necessary, until RPV water level reaches
-158 in, with one or more of the following:
o MSIVs o
Main steam line drains
~
HPCI steam line o
o RCIC steam line o
RHR steam condensing o
RPV nced "ent to Drywell Equipment Drain Tank PSTG #11 Rev. 1 Page 5
SHORERAM NUCLEAR' POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding Justification for Differences / References Elsystion of the bottom of the lowest recirculation piping:
SWEC Drawings 11600.02-53.31-3 and 53.31-4 Top of Active Fuel: Tech Spec Figure B 3/4 3-1 Dalsted Flood vent valves and IC tube side vents (N/A to SNPS)
Added RPV Head Vent as alternate means of venting the RPV.
1 l
PSTG fil Rev. 1 Page 6
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 6 Primary Containment Flooding EPG Stept C6-4 When primary containment water level reaches (83 ft. 5 in. (elevation of top of active fuel)], maintain primary containment water level between [83 f t. 5' in. (elevation of top of active fuel)] and the Maximum Primary Containment Water Level Limit with the following systems taking suction from sources external to the primary containment only when required:
o HPCS o
LPCS o
Feedwater/ Condensate o
CRD o
LPCI o
Head spray
[o RHR service water crosstie
}
[o Fire system
)
[o Interconnections with other units
)
[o ECCS keep-full systems
)
[o Other primary containment fill systems
]
SNPS PSTG Step:
C6-4 When primary containment water level reaches Elevation 122 ft, maintain primary containment water level between Elevation 122 ft. and the Maximum Primary Containment Water Level Limit (Figure B) with the following systems taking suction from sources external to the primary containment only when required:
o Core Spray System o
Feedwater/ Condensate o
CRD o
LPCI o
Head spray PSTG #11 Rev. 1 Page 7
7 SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contir.gency # 6 Primary Containment Flooding SNPS PSTG Step:
(Con't) o RHR service water crosstie (ultimate cooling)
I'I
- .. ::.l.. to Ultimate Cooling o
ECCS connections from condensate transfer Justification for Differences / References Elovation of top of active fuel:
SWEC drawing 11600.02-FM-1E and Tech Spec Figure B 3/4 1.
Maxinum Primary Containment Water Level Limit: NED Appendix C Calculation No. C-NAD-268 D21sted HPCS, Interconnections with other units and other primary containment fill systsms (N/A to SNPS).
R; worded the alternate injection subsystems to reflect SNPS specific systems.
PSTG #11 Rev. 1 Page 8