ML20151D593
| ML20151D593 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/13/1988 |
| From: | Newson C LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20151D407 | List:
|
| References | |
| PROC-880713-02, NUDOCS 8807250172 | |
| Download: ML20151D593 (17) | |
Text
'1 l.i C 1 SHOREHAM NUCLEAR POWER STATION PLANT SPECIFIC TECHNICAL GUIDELINES i
PSTG #10 LEVEL / POWER CONTROL REVISION NO: 2 PREPARED BY: g[- DATE: [ !Jo kh REVIEWED BY: b elt
/
5 Nh%C DATE: 6!2d![h OPERATING ENGINEER APPROVAL: #Il , - DATE: 7// [J#
n ..
i (ppf.1J'~ , ;
p,biiis;i i i _.s ji UA'
- F -
8807250172 080715 PDR ADOCK 05000322 F PNU
4 SHOREHAM NUCLEAR POWER STATION
( Plant Specific Technical Guidelines Contingency i 5 Level / Power Control EPG Steps
-If while executing the following steps:
o RPV water level cannot be determined, enter [ procedure developed from Contingency o 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, enter (procedure developed from the RPV Control Guideline] at (Step RC/L].
o 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 containment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
SNPS PSTG Step:
If while executing the following steps:
o RPV water level cannot be determined, enter procedure developed from Contingency l #4.
o A '.1 23. trol rods are inserted to or beyond position 02 or it has been determined that the reactor will remain shutdown under all co-ditions without boron, enter procedure developed from the RPV Control Guideline at Step RC/L.
o 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 containment water level and suppression chamber pressure can be maintained Lelow the Maximum Primary Containment Water Level Limit.
~
^
Differences / References l Maximum Suberitical Banked withdrawal Position: NED Appendir C Calculation C-NFD-200 l
Maximum Primary Containment Water Level Limit: NED Appendix C Cattulation C-NAD-268 l
PSTG #10 Rev. 2 l Page 1
SHOREHAM NUCLEAR POWER STATION Plant-Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Step:
C5-1 Prevent automatic initiation of ADS.
SNPS PSTG Step:
C5-1 Prevent automatic initiation of ADS by placing the ADS Inhibit Switch to INHIBIT.
Juctification for Differences / References Added guidance as to how to prevent automatic initiation of ADS.
PSTG #10 Rev. 2 Page 2
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Step:
C5-2 If:
o Reactor power is above [3% (APRM downscale trip)]
or cannot be determined, and o Suppression pool temperature is above 110', and o Either an SRV is open or opens or drywell pressure is above (2.0 psig (high drywell pressure scram setpoint)),
SNPS PSTG Step:
CS-2 If:
o Reactor power is above 5% or cannot be determined, and o Suppression pool temperature is above 110' F, and o Either an SRV is open or opens or drywell pressure is above 1.69 psig.
Justification f3 Differen_ces/
References:
APRM Downscale Trip: Tech Spec Table 3.3.6-2.
Boron injection Initiation Temperature: NED Appendix C Calculation C-NFD-276 (conservatively specified as the lowest temperature on the curve)
High Drywell pressure scram setpoint: Tech Spec Table 2.2.1-1 PSTG #10 Rev. 2 Page 3
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines
< Contingency i 5 Level / Power Control EPG Step:
C5-2 Then:
(Con't) o If any MSIV is open, bypass low RPV water level pneumatic system and MSIV isolation interlocks and restore the pneumatic supply [to the containment], and o Lower RPV water level, irrespective of any consequent reactor power or RPV water level oscillations, by terminating and preventing all injection into the RPV except from boron injection systems and CRD until either:
o Reactor power drops below [3% (APRM downscale trip)], or o RPV water level reaches [-164 in. (top of active fuel)], or o All SRVs remain closed and drywell pressure remains below (2.0 psig (high drywell pressure scram setpoint)].
SNPS PSTG Step:
C5-2 Then:
(Con't) o If any MSIV is open, bypass low RPV water level pneumatic system and MSIV isolation interlocks and restore the pneumatic supply to the containment, and o Lower RPV water level, irrespective of any consequent reactor power or RPV water level oscillations, by terminating and preventing all injection into the RPV except from boron injection systems and CRD until either:
o Reactor power drops below 5%, or o RPV water level reaches -158 in., or o All SRVs remain closed and drywell pressure remains below 1.69 psig.
Justification for Differences / References l APRM Downscale Trip: Tech Spec Table 3.3.6-2 i
Top of Active Fuel: Tech Spec Figure B 3/4 3-1 1
l High Drywell pressure scram setpoint: Tech Spec Table 2.2.1-1 l
PSTG #10 Rev. 2 Page 4 i
SHOREHAM NUCLEAR POWER STATION
-Plant Specific Technical Guidelines Contingency i 5 Level / Power Control EPG Step:
'If while executing the following steps Emergency RPV Depressurization is required, continue in this procedure at (Step C5-3.1).
If while executing the following step:
o Reactor power is above (3% (APRM downscale trip)) or cannot be determined, and -
o RPV water level is above (-164 in. (top of active fuel)), and o Suppression pool temperature is above (the Boron Injection Initiation Temperature), and o Either an SRV is open or opens or drywell pressure is above
[2.0 psig (high drywell pressure scram setpoint)],
teturn to (Step C5-2].
SNPS PSTG Step:
If'while executing the following steps Emergency RPV Depressurization is required, continue in this procedure at Step C5-3.1.
~
If while executing the following step:
o Reactor power is above 5% or cannot be determined, and o RPV water level is above -158 in., and o Suppression pool temperature is above 110' F, and o Either an SRV is open or opens or drywell pressure is above 1.69 psig return to Step C5-2.
Justification for Differences /
References:
APRM Downscale Trip: Tech Spec Table 3.3.6-2 Top of Active Fuel: Tech Spec Figure B 3/4 3-1 l Boron Injection Initiation Temperature: NED Appendix C Calculation C-NFD-276 l (conservatively specified as the lowest temperature on the curve) l High Drywell pressure scram setpoint: Tech Spec table 2.2.1-1 PSTG #10 Rev. 2 Page 5
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Step:
C5-3 -Maintain RPV water level either: [f7) o If RPV water level was deliberately lowered in (Step C5-2), between (-206 in. (Minimum Steam Cooling RPV Water Level)] and the level to which it was lowered, or o If RPV water level was not deliberately lowered in (Step C5-2), between
(-164 in. (top of active fuel)) and [+58 in. (high level trip setpoint)],
with the following systems:
o Condensate /feedwater o CRD o RCIC with suction from the condensate storage tank defeating low RPV pressure isolation interlocks and high [#3 #4]
suppression pool water level suction transfer logic if necessary.
SNPS PSTG Step:
CS-3 Maintain RPV water level either: [f5) o If RPV water level was deliberately lowered in Step C5-2, between -189 in.
'and the level to which it was lowered, or o If RI'V water level was not duliberately lowered in Step C5-2, between -158
. in, and +56.5 in.,
with the following systems:
o Condensate /feedwater o CRD (#6) l o RCIC with suction from the condensate storage tank defeating low RPV pressure isolation interlocks and low [f2 #3)
CST water level suction transfer logic if necessary.
l PSTG #10 Rev. 2 Page 6
O SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 5 Level / Power Control Justification for Differences / References Altered RCIC bullet to be consistant with SNPS transfer logic design.
.. _vvvitag RPV water level: NED Appendix C Calculation C-NAD-270 Top of Active Fuel: Tech Spec Figure B 3/4 3-1 High Level Trip Setpoint: Tech Spec Table 3.3.3-2 1
Added SNPS Specific Cautionary Guidance regarding 3300 KW Diesel loeding limitation e d' PSTG #10' Rev. 2 Page 7
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 5 Level / Power Control y
EPG-Steg:
C5-3 (o HPCI with suction from the condensate storage }
(Con't) ( tank, defeating high suppression pool water [#3] )
( level suction transfer logic if necessary. ]
[o LPCI with injection through the heat exchangers as )
[ soon as possible; control and mafntain pump flow less ]
[ than the RHR Pump NPSH Limit and [the RHR Vortex Limit.)
SNPS PSTG Step:
C5-3 o HPCI with suction from the condensate storage tank, (Con't) defeating high suppression pool / low CST water level suction transfer logic if necessary.
o LPCI with injection through the heat exchangers as soon as possib3e; control and maintain pump flow less than the RHR Pump NPSH Limit and the RHR Vortex Limit.
Justification for Differences / References RHR Pump NPSH Limits: NED Calculation C-NSD-211 RHR Vortex Limit: NED Appendix C Calculation C-NAD-273 Altered HPCI statement to reflect SNPS specific logic requiremeucs.
l l
PSTG #10 Rev. 2 Page 8
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines
' Contingency # 5 L_evel/ Power Control I
E,PG' Step:
C5-3 If RPV water level was not deliberately lowered in (Step C5-2) and (Con't) RPV vater level cannot be maintained above (-164 in. (top of active fuel)),
maintain RPV water level between (-206 in. (Minimum Steam Cooling RPV Water Level)} and (+58 in. (high level trip setpoint)).
I-If RPV water leven cannot be maintained above (-206 in. (Minimum Steam Cooling RPV Water Level)), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED:
SNPS PSTG Step:
C5-3 If RPV water level was not deliberately lowered in Step C5-2 and RPV (Con't) water level cannot be maintained above -158 in., maintain RPV water level between -189 in, and +56.5 in.
If RPV water level cannot be maintained above -189 in. , EMERGENCY RPV DEPRESSURIZATION IS REQUIRED:
Justification for Differences / References i Top of' Active Fuel: Tech Spec Figure B 3/4 3-1 Minimum Steam Cooling RPV Water Level: NED Appendix C Calculation No. C-NAD-270.
High Level Trip Setpoint: Tech Spec Tabe 3.3.3-2.
PSTG #10 Rev. 2 Page 9 w
e SHOREHAM NUCLEAR POWER STATION l Plant Specific Technical Guidelines 3
Contingency i 5 Level / Power Control EPG Step:
C5-3.1 ' Terminate and prevent all injection into the RPV except from boron injection systems, CRD, and RCIC until RPV pressure is below the Minimum Alternate RPV Flooding Pressure.
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 PSTU Step:
C5-3.1 Terminate and prevent all inj9etion into the RPV except from boron injection systems, CRD, and RCIC 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 5 159 4 216 3 332 2 678 1 Justification for Differences /
References:
Minimum Alternate RPV Flooding Pressure: NED Appendix C Calculation C-NAD-269 t (Numbers rounded to the nearest integer.)
Lowest SRV lifting pressure: Tech Spec 3.4.2.
PSTG #10 Rev. 2 Page 10
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Step:
C5-3.2 Commence and, irrespective of pump NPSH and vortex limits slowly increase injection into the RPV with the following (f7]
systems to restore and maintain RPV water level above
(-164 in. (top of active fuel)):
o Condensate /Feedwater o CRD ,
o RCIC with euction from the condensate storage tank, defeating low Rrv pressure isolation interlocks and high suppression pool water level suction transfer logic if necessary.
(o HPCI with suction from the condensate storage tank, )
( defeating high suppression pool water level suction ]
[ transfer logic if necessary. J (o LPCI with injection through the heat exchangers )
[ as soon as possible. ]
SNPS PSTG Step:
C5-3.2 Commence and, irrespective of pump NPSH and vortex limits slowly increase injection into the RPV with the following (#5) systems to restore.and maintain RPV water level above -158 in.:
o Condensate /Feedwater i
l o CRD o RCIC with suction from the condensate storage tank, defeating low RPV pressure isolation int 2rlocks and low CST level suction transfer logic if necessary, o HPCI with suction from the condensate storage tank, defeating high suppression / low CST level suction transfer logic if necessary.
o LPCI with injection through the heat exchangers as soon as possible.
Justification for Differences /
References:
Top of Active Fuel Tech Spec Figure B 3/4 3-1 Altered HPCI 6 RCIC statements to reflect Shoreham specific logic requirements.
PSTG #10 Rev. 2 Page 11
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Step:
C5-3.2 If RPV water level cannot h. testored and maintained above [-164 in.
(Con't) (top of active fuel)), restore and maintain RPV water level above [-206 in.
(Minimum Steam Cooling RPV Water Level)).
If RPV water level cannot be restored and maintained above [-206 in.
(Minimum Steam Cooling RPV Water Level)), commence and, irrespective of pump NPSH and vortex limits, slowly increase injection into the RPV with the following systems to restore and maintain RPV water level above [-206 in.
(Minimum Steam Cooling RPV Water Level)):
[o RHR service water crosstie ]
[o Fire System )
[o Interconnections with other units ]
[o ECCS keep-full system )
SNPS PSTG Stept C5-3.2 If RPV water level cannet be restored and maintained above -158 in.,
(Con't) restore and maintain RPV water level above -139 in.
If RPV water level cannot be restored and maintained above -189 in.,
commence and, irrespective of pump NPSH and vortex limits, alowly increase injection into the RPV with the following syetems to restore and maintain RPV water level above -189 in.:
o Core Spray bystem o RHR service water crosstie (ultimate coolit g) o Fire main ultimate cooling through IP41-06V-3029 o ECCS conncetions from condensare transfer Justification for Differences / References Top of Active Fuel: Tech Spec Figure B 3/4 3-1 Minitum Steam Cooling RPV Water Level: NED Appendix C Calculation C-NAD-270 Deleted HPCS and "Interconnections with other units" (N/A for SNPS)
R: worded other bulleted items to reflect Shoreham specific nomenclature, t
PSTG #10 Rev. 2 Page 12 1
SHOREHAM N'JCLEAP. POW 2R STA* TON Plant Specific Tichnical Guidelines Continten,cy 0 5 Level /Po' er Control EPG Step:
11 RPV water level cannt: be restored and maintained above [-206 in. (Minitur Steam Cooling RPV Water Level)),
enter [ procedure dev91c<ed from Contingency #6).
C5-3.3 When RPV water level can be maintained above (-206 in.
(Minimum Steam Coolinr -4u Water Level)), return to "Step C5-3).
SNPS PSTG St If RPV water level cann:t be restored and maintained above -189 in., enter procedure developed from Contingency
- 6.
C5-3.3 When RPV water level can be maintained above -189 in.,
return to Step C5-3.
Justification for Differencec/ References Minimum Steam Cooling RPV Water Level: NED Appendix C Csiculation No. C-NAD-270.
PSTG #10' R e '. . 2 Page 13 Ie
9 e
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 5 Level / Power Control EPG Step:
(________________________________________________________
[ If while executing the following step reactor power
[
commences and continues to increase, return to (Step C5-2 )
(________________________________________________________________)
[ ]
(C5-4 When (204 pounds (Hot Shutdown Boron Weight)) of boron }
[ have been injected, restore and maintain RPV water level )
{ between [+12 in. (low level scram setpoint)) and }
[ (+58 in. (high level trip setpoint)). )
[ }
[ If RPV water level cannot be restored and maintained )
[ above_(+12 in. (low level scram setpoint)), maintain }
[
RPV water level above (-164 in. (top of active fuel)). )
[ ]
[ If RPV water level cannot be maintained above (-164 in. ]
[ (top of active fuel)), EMERGENCY DEPRESSURIZATION IS }
[ REQUIRED; return to (Step C5-3.1). }
l PSTG #10 Rev. 2 Page 14
'9 SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Coidelines Contingency i 5 j Level / Power Control k
SNPS PSTG Step:
1 If while executing the following step reactor power commences and continues to increase, return to Step C5-2 C5-4 When 786 gallons of sodium pentaborate have been injected into the vessel, restore and maintain RPV water level between +12.5 in, and +56/5 in.
If RPV water level cannot be restored and maintained above +12.5 in, maintain RPV wat'sr level above -158 in.
If RPV level cannot be mainteined above -158 in. EMERGENCY DEPRESSURIZATION IS REQUIREC; return to Step C5.3-1.
Justification for Differences / References Hot Shutdown Boron Weight: NED Appendix C Calculation No. C-NFD-276 Low Level Scram setpoint: Tech Spec Table 2.2.1-1 High Level Trip setpoint: Tech Spec Table 3.3.3-2 Top of Active Fuel: Tech Spec Figure B 3/4 3-1 PSTG #10 Rev. 2 Page 13
e-SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 5 Level / Power Control EPG Stept C5-5 When [ procedure for cooldown to cold shutdoin conditions}
is entered from [ procedure developed from the aPV Control Guideline] at [ Step RC/P-5), proceed to cold shutdown'in accordance with [ procedures for cooldown to cold shutdown conditions).
SNPS PSTG Step:
C5-5 When SP 22.005.01, Shutdown'From 20% Power, is entered from procedure developed from the RPV Control Guideline at Step RC/P-5, proceed to cold shutdown in accordance with SP 22.005.01, Shutdown From 20% Power.
Justifications for Differences / References Procsdure for cooldown to cold shutdown conditicus: Shoraham Plant Procedure Statuo Listing.
PSTG #10 Rev. 2 Page 16