ML20151D582
| ML20151D582 | |
| 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-880511-06, NUDOCS 8807250169 | |
| Download: ML20151D582 (21) | |
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SHORERAM NUCLEAR POWER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #9 RPV FLOODING REVISION NO: 1 PREPARED BY:
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o SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency #4 RPV Flooding EPG Step:
If while executing the following steps RPV water level can be determined:
If any control rod cannot be determined to be inserted to or beyond e
position [02 (Maximum Suberitical Banked Withdrawal Position)) and it has not been determined that the reactor will remain shutdown under all conditions without boron, enter (procedure developed from Contingency
- 5) and [ procedure developed from the RPV Control Guideline] at [ Step RC/P-4} and execute these procedures concurrently.
If all control rods are inserted to or beyond position [02 (Maximum e
Suberitical Banked Withdrawal Position)) or it has been determined that the reactor will remain shutdown under all conditions witnout boron, enter [ procedure developed from the RPV Control Guideline) at [ Steps RC/L and RC/P-4) and execute these steps concurrently.
SNPS PSTG Step:
If while executing the following steps RPV water level can be determined:
e If any control rod cannot be determined to be inserted to or beyond position 02 and it has not been determined that the reactor will remain shutdown under all conditions without boron, enter procedure developed from Contingency #5 and procedure developed from the RPV Control Guideline at Step RC/P-4 and execute these procedures concurrently.
o If all control rods are inserted to or beyond position 02 or it has been determined that the reactor will remain shutdown under all conditions without boron, enter procedure developed from the RPV Control Guideline at Steps RC/L and RC/P-4 and execute these steps concurrently.
Justification For Differences / References M;xinum Suberitical Banked Withdrawal Position: NED Appendix C Calculation No. C-NFD-200.
PSTG #9 P.e v. 1 Page 1 1
a SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step:
If while executing the following steps primary containment water level and suppression chamher pressure cannot be 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 to the primary containment until primary containment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
SNPS PSTG Stept If while executing the following steps primary containment water level and suppression chamber pressure cannot be 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 to the primary containment until primary contairment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
(Figure M).
Justification for Differences / References Mexigum Primary Containment Water Level Limit:NED Appendix C Calculation No. C-NAD-268
((
j PSTG #9 Rev. 1 Page 2 i
SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step:
C4-1 if any control rod cannot be determined to be anserted to or beyond position
[02 (Maximum Suberitical Banked Withdrawal Position)) and it has not been determined that the reactor will remain shutdown under all conditions without boron, flood the RPV as follows:
If while executing the following steps either all control rods are inserted to or beyond position.[02 (Maximum Suberitical Banked Withdrawal Position))
or it has been determined that the reactor will remain shutdown under all conditions without boron but RPV water level cannot be determined, continue in this procedure at [ Step C4-2].
- SNPS PSTG Step:
C4-1 if any control rod cannot be determined to be inserted to or beyond position 02 and it has not been determined that the reactor will remain shutdown under all conditions without boron, flood the RPV as follows:
If while executing the following steps either all control rods are inserted to or beyond position 02 or it has been determined that the reactor will remain shutdown under all conditions without boron but RPV water level cannot be determined, continue in this procedure at Step C4-2.
Justification for Differences / References Maximum Suberitical Banked Withdrawal Position: NED Appendix C Calculation C-NFD-200.
PStG #9 Rev. 1 Page 3
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Stept C4-1.1 Terminate and prevent all injection into the RPV except from boron injection r
systems and CRD until RPV pressure is below the Minimum Alternate RPV oaing rressure.
If less than (1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure SRV[s] can be opened, continue in this procedure. SNPS PSTG Step: C4-1.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. If no SRV can_be opened, continue in this procedure. Minimum Alternate Number of RPV Flooding Pressure SRVs 84 7 101 6 124 5 <I 159 4 216 3 332 2 678 1 Justification for Differences / References Minitium Alternate RPV Flooding Pressure: NED Appendix C Calculation No. C-NAD-298. '- :- "*" :if ti.g prcosure: Tech Spec 3.4.2 (I NOTE: MARTP Numbers rounded to nearest interger for usability considerations. l l [ i l PSTG #9 Rev. I Page 4 l
t e 1 SHORERAM NUCLEAR POWER' STATION Plant Specific Technical Guioelines Contingency # 4 P RPV Flooding EPG Stept C4-1.2 If at least (3 (Minimum Number of SRVs Required for Emergency Depressurization)] SRVs can be opened, close the MSIVs main steam line drain valves, and 10. RCIC, and RHR steam condensing isolation valves. SNPS PSTG Step: P C4-1.2 If at least 4 SRVs can be opened, close the MSIVs. main steam line 4, drain valves, and RCIC, and RHR steam condensing isolation valves. Justification for Differences / References Minimum Number of SRVs required for Emergency Depressurization: NED Appendix C t Calculation C-NAD-269. IC Deleted from list of systems to isolate (N/A to SNPS). k i l t l i i i PSTG #9 Rev. 1 i Page 5 ... ---...O
f;i SHOREHAM NUCLEAR POWER STATION Plant $)ecli'icTechnicalGuidelines Contingency i 4 RPV Flooding EPG Step: C4-1.3 Commence and, irrespective of pump NPSH and vortex limits, slowly increase' injection into the RPV with the following systems until at least [1 (minimum number. [ #7 ) of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressu u)] SRV[s] [is) open and RPV pressure ir abov~ the Minimum Alternate RPV Flooding Pressure: e Motor driven feedwater pomps, defeat;ng high RPV water level isolation interlocks if necessary. e Condensate pumps v .CRD [e LPCI with injection through the heat exchangers as soon as possible) SNPS PSTG 9(ep: C4-1.3 Commence and, irrepective of pump NPSH and vortex limits, slowly increase injection into the RPV with the following systems until at least 1 SRV is open and i f5 ) RPV pressure is above the Minimum Alternate RPV Flooding Pressure: Minimum Alternate Nr.mber of RPV Flooding' Pressure SRVs 84 7 101 6 124 5 < t 159 4 21e 3 332 2 678 1 e Condensate pumps e CRD LPCI with injection through the heat exchangers as soon as possible e PSTG #9
- t e v. 1 Page 6 u
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 4 RPV Flooding Justification for. Differences / References
- Minimum Alternate RPV flooding pressure:
NED Appendix C Calculation C-NAD-298. (1 Deleted "Motor Driven Feedwater Pumps" from list (N/A to SNPS). Lowsst SRV lifting pressure: Tech, Spec section 3.4.2. PSTG #9 Rev. 1 Page 7
.o SHOREHAM NUCLEAR POWER ST/. TION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: 'C4-1 ' If less than [1 (minimum number of SRVs for which the Minimum (Con Alternate RPV Flooding Pressore is below the lowest SRV lifting pressure)] SRV[s] [is] open or RPV pressure cannot be increased to above the Minimum Alternate RPV Flooding Pressure, commence and, irrespective of pump NPSH and vortex limits, slowly increase injection into the RPV with the following systems until at least [1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)] SRV[s] [is) open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: HPCS, defeating high RPV water level isolation interlocks if e necessary, e LPCS [e RHR service water crosstie ] [e Fire System ] [o Interconnections with other units ] [e ECCS keep-full systems ] SNPS PSTG St'ep: C4-1.3 If no SRV is open or RPV pressure cannot be increased (Con't) to above the Minimum Alternate RPV Flooding Pressure, commence and, irrespective of pump NPSH and vortex limits, slowly increase injection into the RPV with the following systems until at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: Number 87~ Minimum Alternate RPV Flooding Pressure SRVs 84 7 101 6 124 5 'I 159 4 216 3 332 2 678 1 e Core Spray System RHR service water cross ie (Ultimate Cooling) o Fire Main to Ultimate Cooling through IP41-06V-3029 e ECCS Connections from Condensate Transfer e PSTG #9 Rev. 1 Page 8
.. =. SHOREHAM N'JCLEAR P0k'ER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding C4-1.3 (Con't) Justification for Differences / References <1 Minimum Alternate RPV Flooding Pressure: NED Appendix C Calculation C-NAD-298. Lowest SRV Lifting Pressure: Tech Spec Section 3.4.2 Deleted HrCS, reworded LPCS, deleted interconnections to other units and clarified ths others to make them compatible to SNPS. 1. l l l PSTG #9 Rev. 1 Page 9
4 SHOREHAM NUCLFAR POWER STATION Plant Specific Technical Guidelines Continge,ncy # 4 RPV Flcoding 2 If less than (1 (minimum nunber of SRVs tv which the Minimum Alternate RPV Flooding Pres sure is below the lowest SRV lifting pressure)) SRV[s] [is) open or RPV pressure cannot be increased to above the Minimum Alternate RPV Flooding Pressure, enter { procedure developer' f rom Contingency #6] and [ procedure developed from the RPV Control Guideline) at (Step RC/P-4] and execute these procedures concurrently. SNPS PSTG Step: If no SRV is open or RPV pressure canno be increased to above the Minimum Alternate RPV Flooding Pressure, enter procedure developed from Contingency
- 6 and procedure developed from the RFV Control Guideline at Step RC/P-4 and execute these procedures concurrently.
Justification far Differences / References Minimum Alternate RPV Flooding Pressure: NED Appendix Calculation C-NAD-298 Lewest SRV lifting pressure: Tech Spec 3.4.2. PSTG #9 Rev. 1 Page 10
SHOREHAM NUCLEAR POWER STATION Plant Specific T=chnical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-1.4 When at least [1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)) SRV[s] [is) open and RPV pressure is above the Minimum Alternate RPV Flooding Precsure, control injection to maintain at least [1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)) SRV[s] open and RPV pressure above tho. Minimum Alternate RPV Flooding Pressure but as low as practicable. SNPS PSTG Step: C4-1.4 When at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure, control injection to maintain at least 1 SRV open and RIV pressure above the Minimum Alternate KPV Flooding Pressure but as low as practicable. Justification for Difference.-/ References Minimum Alternate RPV Flooding Pressure: NED Appendix C Calculation C-NAD-298. Lowest SRV lifting pressure: Tech Spec 3.4.2 PSTG #9 Rev. 1 Page 11
e SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-1.5 When all control rods are inserted to or beyond position (02 (Maximum Suberitical Banked Withdrawal Position)) or it has been determined that the reactor will remain shutdown under all conditions without boron, continue it. this procedure. SNPS PSTC Step: C4-1.5 When all control rods are inserted to or beyond position 02 or it has been determined that the reactor will remain shutdown under all conditions without boron, continue in this procedure. Justification for Differences / References Mtximum Suberitical Banked Withdrawal Position: Appendix C Calculation C-NFD-200. l l l l l PSTG #9 Rev. 1 Page 12
m SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-2 If at least (3 (Minimum Number of SRVs Required for Emergency Depressurization)) SRVs can.be opened or if a HPCS or motor driven feedwater pump is available for injection, close the MSIVs, main steam line drain valves, and IC, RCIC, and RHR steam condensing isolation valves. SNPS PSTG Step: C4-2 If at least 4 SRVs can be opened, close the MSIVs, main steam line drain valves, and RCIC, and RHR steam condensing isolation valves. Justification for Differences / References Minimum number of SRVs required for Emergency Depressurization: NED Appendix C Calculation C-NAD-269. D31sted reference to HPCS, IC and motor driven feedwater pumps. (N/A to SNPS). t l l i l l l l l PSTG #9 Rev. 1 Page 13 i
.o SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-3 Flood the RPV as follows: C4-3.1 Commence and, irrespective of pumps NPSH and vortex limits, increase injection into the RPV with the following systems until at least (3 (Minimum Number of SRVs Required for Emergency Depressurization)) SRVs aJe open and RPV pressure is not decreasing and is-(75 psig (Minirim RPV Flooding Pressure)) or more above suppression chamber pressura: HPCS, defeating high RPV water level isolation interlock.a if e necessary. Motor driven feedwater pumps, defeating high RPV water level e isolation interlocks if necessary. o LPCS LPCI with injection through the heat exchangers as soon as e
- possible, e
Condensate Pumps o CRD (o RHR service water crosstie ] (o Fire System ) (o Interconnections with other units ] (o ECCS keep-full systems ] [o SLC (test tank) ) (o SLC (boron tank) ] PSTG #9 Rev. 1 Page 14
I SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding SNPS PSTG Step: C4-3 Flood the RPV as follows: C4-3.1 Commence and, irrespective of pumps NPSH and vortex limits, increase injection into the RPV with the following systems until at least 4 SRVs are open and RPV. pressure is not decreasing and is 50 psig or more above suppression chamber pressure: e Core Spray System e LPCI with injection through the heat exchangers as soon as
- possible, o
Condensate Pumps e CRD o RHR service water crosstie (ultimate cooling) Fire Main to Ultimate Cooling through IP41-06V-3029 e o ECCS connections from condensate transfer o SLC (test tank) o SLC (boron tank) Justification for Differences / References Minimum Number of SRVs required for Emergency Depressurization: NED Appendix C Calculation C-NAD-269. Mininum RPV Flooding Pressure: NED Appendix C Calculation C-NAD-269. Dalsted HPCS, Motor Driven Feedwater pumps and interconnections with other units (N/A to SNPS) Changed LPCS to Core Spray System Clarified the alternate injection subsystems as applicable to SNPS. PSTG #9 Rev. 1 Page 15
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding t EPG Step: If less than (3 (Minimum Number of SRVs Required for Emergency Depressurization)) SRV[s] are open or RPV pressure cannot be maintained at least (75 psig (Minimum RPV Flooding Pressure)] above suppression chamber pressure, enter [ procedure developed from Contingency #6) and (procedure developed from the RPV Control Guideline) at (Step RC/P-4) and execute these procedures concurrently. SNPS PSTG Step: -_____________________n If less than 4 SRVs are open or RPV pressure cannot be maintained at least 50 psig above suppress 1?n chamber pressure, enter procedure developed from Contingency #6 and procedure developed from the RPV Control Guideline at Step RC/P-4 and execute these procedures con-currently. Justification for Differences / References l l Minimum Number of SRVs required for Emergency Depressurization: NED Appendix C Calculation C-NAD-269. l Minimum RPV Flooding Pressure: NED Appendix C Lalculation C-NAD-269. PSTG #9 Rev. 1 Page 16 l l
l SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-3.1 When at least [3 (Minimum Number of SRVs Required for Emergency Depressurization)] SRV[s] are open and RPV pressure can be maintained at least [75 psig (Minimum RPV Flooding Pressure)) above suppression chamber pressure, control injection to maintain at least (3 (Minimum Number of SRVs Required for Emergency Depressurization)) SRVs open and RPV pressure at least [75 psig (Minimum RPV Flooding Pressure)) above suppression chamber pressure but as low as practicable. SNPS PSTG Step: C4-3.2 When at least 4 SRVs are open and RPV pressure can be maintained at least 50 psig above suppression chamber pressure, control injection to maintain at least 4 SRVs open and RPV pressure at least 50 psig above suppression chamber pressure but as low as practicable. I f i Justification for Differences / References ( 1 Minimum Number of SRVs required for Emergency Depressurization: NED Appendix C l Calculation C-NAD-269. I Minimum RPV Flooding Pressure: NED Appendix C Calculation C-NAD-269. I L t l PSTG #9 Rev. 1 Page 17
e SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPC Step: .C4-4 When: e RPV water level instrumentation is available, and Temperature [s] [near the cold reference leg instrument vertical runs] e are below 212*F, and e RPV pressure has remained at least (75 psig (Minimum RPV Flooding Pressure)) above suppression chamber pressure for at least [the Minimum Core Flooding Interval) Terminate all injection into the RPV and reduce RPV water level until RPV water level indication is restored. If RPV water level indication is not restored within the Maximum Core Uncovery Time Limit after commencing termination of injection into the RPV, return to [ Step C4-3.1). SNPS PSTG Step: C4-4 When: e RPV water level instrumentation is available, and Temperaturer. near the cold reference leg instrument vertical runs are e below 212'F, and e RPV pressure has remained at least 50 psig above suppression chamber l pressure for at least the. Minimum Core Flooding Interval. I Minimum Core Number of l Flooding Interval SRVs i 47 min. 4 (g i 30 min. 5 l 22 min. 6 17 min. 7 Terminate all injection into the RPV and reduce RPV water level until RPV water level indication is restored. i If RPV water level indication is not restored within the Maximum Core l Uncovery Time Limit (Figure M) af ter commencing termination of injection into the RPV, return to Step C4-3.1. 1 PSTG #9 Rev. 1 Page 18
o, SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding . Justifications for Differences / References Minimum RPV Flooding Pressure: NED' Appendix C Calculation C-NAD-269. Minieum Core Flooding Interval: NED Appendix C Calculation C-NAD-269. Rounded up 4g for conservatism and human factors criteria. - Maximum Core Uncovery Time: NED Appendix C Calculation C-NAD-269. PSTG #9 Rev. 1 Page 19
o-SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 4 RPV Flooding EPG Step: C4-5 Enter [ procedure developed from the RPV Control Guideline) at (Steps RC/L and RC/P-4) and execute these steps concurrently. SNPS PSTG Step: C4-5 Enter procedure developed from the RPV Control Guideline at Steps RC/L and RC/P-4 and execute these steps concurrently. Justification for Differences / References N/A l l l l l I PSTG #9 Kev. 1 Page 20 i .}}