ML20151D425
| ML20151D425 | |
| 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, NUDOCS 8807250111 | |
| Download: ML20151D425 (36) | |
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I. MC-1 SHOREHAM NUCLEAR P0k'ER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #2 RPV CONTROL REVISION NO: 1 PREPARED BY: 7 , - DATE: d P IFF hEVlt.WEl> bY: [ hl_1 I e_-_ u% DATE: 3!k [
OPERATING ENGINEER APPROVAL: C T .O DATE: 3/1 7
.,-e 88072501J1 080715
[j/,j 'i t'ldOs., p DR ADOCK 05000322 PNV l l !! .
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- SHOREHAM NUCLEAR POWER STATION
,_ Plant Specific Technical Guidelines RPV Control Guidel,ine EPG St p:
t u tu v a The purpose of this guideline is to:
'o Maintain adequate core cooling, o Shutdown the reactor, and o Cooldown the RPV to cold shutdown conditions ((100'F less than RPV water temperature less than 212'F (cold shutdown conditions))).
PSTC Step:
PURPOSE The purpose of this guf.deline is to:
. :S' cJ qucce core cooling, I e . Shutdown the reactor, and lo Cvuldv.s. Lhe RFV to cold shutdown conditions (Average RPV coolant l temperature less than or equal to 200*F)
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Justification ?or' Differences /
References:
colo snutcovn conditions: Technical Specification Table 1.2 PSTG #2 Rev. 1 Page 1 Y 4** *+--ar=+--*mi-yw+y M-- v r mi--pe-, -ss y-9-m.mm-,.e_ .m- - ,p,g.,g,,.e ,p ,,-g . c. .y , --, w. --_-__ -w-. - -- -
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SHOREHAM NUCLEAR POWER STATION
. Plant Specific Technical Guidelines RPV Control Guideline EPG Step:
, ENTRY CONDITIONS Tho entry conditions for this guideline are any of the following:
o RPV water level below [+12 in. (low level scram setpoint)]
e RPV pressure above [1045 psig (high RPV pressure scram setpoint))
o Drywell pressure above [2.0 psig (high drywell pressure scram setpoint))
o A condition which requires reactor scram, and reactor power a>ove (3% (APRM downscale trip)) or cannot be determined SNPS PSTG Step:
.( AY CONDITIONS Tha Gntry conditions for this guideline are any of the following:
o RPV Water Level below 121 inches i c RPV Pressure above 1043 psig 1
o ,Drywell pressure above 1.69 psig o' A condition which requires a reactor scram, and reactor power above 5%, or cannot be determined.
Justification For Differences /
References:
Low level scram setpoint - Tech. Spec. Table 2.2.1-1 High RPV pressure setpoint - Tech. Spec. Table 2.2.1-1 High Drywell pressure scram setpoint - Tech. Spec. Table 2.2.1-1 APRM Downscale trip - Tech. Spec. Table 3.3.6-2 PSTG #2 Rev. 1 Page 2
e-SHORERAM NUCLEAR POWER STATION
. Plant Specific Technical Guidelines RPV Control Guideline l
EPG Step:
OPERATOR ACTIONS .
RC-1 If reactor scram has not been initiated, initiate reactor scram. .
SNPS PSTG Step:
OPERATOR ACYIONS RC-1 Confirm or place the mode switch to Shutdown
'I Notify the Watch Engineer to classify the Event per EPIP l-0 Justification For Differences /
References:
Specific guidance added on how to initiate a reactor scram Added SNPS specific Emergency Plan Requirements ,
(I PSTG #2 Rev. 1 Page 3
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? SHOREHAM NUCLEAR P0k'ER STATION Plant Specific Technical Guidelines RPV Control Guideline
.EPG Step:
-____________p-____________________
Irrespective of the entry conditions, execute (Steps RC/L, RC/P.
and RC/Q) concurrently.
SNPS PSTG Step:
Irrespective of the entry conditions, execute (Steps RC/L RC/P, and RC/Q) concurrently.
Justification For Differences /
References:
M/A l.
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PSTG #2 Rev. 1 Page 4 l
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline
'EPG Step:
- RC/L Monitor and control RPV water level. [#1)
RC/L-1 Initiate each of the following which should have initiated but did not:
e Isolation .
e ECCS
[e Emergency diesel generator) i
- SNPS PSTG Step
(
RC/L Monitor and control RPV water level. [f1)
RC/L-1 Initiate each of the following which should have initiated but did I not:
6 Group isolations e ECCS o Emergency diesel generators Justification For Differences /
References:
N/A PSTG #2 Rev. 1 Page 5
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline EPG Step:
If while executing the following step:
o Any control rod is not inserted.to or beyond position [02 (Maximum Suberitical Banked Withdrawal P6sition)), and it has not been determined that the reactor will remain shutdown under all conditions without boron enter (procedure developed from CONTINGENCY #5).
o RPV vater level cannot be determined, enter (procedure developed from CONTINGENCY #4).
3 PSTG Step:
!f whO .ating the following step:
o Any control rod is not inserted to or beyond position 02 and it has not been determined that the reactor will remain shutdown under all conditions withc4 bcron, enter CONTINGENCY f5, Level / Power Control.
o RPV water level cannot be determined, enter CONTINGENCY #4, RPV Flooding.
Justification For Differences /
References:
Mtx duotritical Banked Withdraw n Position - NED Appendix C Calculation No.
C-NFD-200 PSTG #2 Rev. 1 Page 6
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guideliaes RPV Control Guideline EPG Step:-
.4 .:.in cacuting the following step primary containment water level and suppression chamber pressure cannot be maintained below the Maximum Primary Containment Vater 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 chtsber pressure can be maintained below the Maximum Primary Containment Water Lsvel. Limit.
SNPS PSTG Step:
If while executing the following step primary containment water level and sun
(~pressionchamberpressurecannotbemaintainedbelowtheMaximumPrimary
- einment Water Level. Limit, (Figure B) then irrespective of whether adequate euro cooling is assured terminate injection into the RPV from sources external to the primary containment until primary containment water level and suppression chtsber pressure can be maintained below the Maximum Primary Containment Water Lovel Limit.
Justification For Differences /
References:
Mtximum Primary Containment Water Level Limit: NED Appendix C Calculation C-NAD-268 PSTG #2 Rev. 1 Page 7
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SHORERAM NUCLEAR P0k'ER STATION Plant Specific Technical Guidelines RPV Control Guideline FPG Step:
RC/L-2 Restore and maintain RPV water level between [+12 in. (low level scram setpoint)) or shutdown cooling RPV water level interlock (whichever is higher) and [+58 in. (high level trip setpoint)) with one or more of the following systems:
o Condensate /feedwater .
e CRD e RCIC with suction from the condensate storage tank, defeating low RPV pressore isolation interlocks and high suppression pool water level suction transfer logic if necessary. (#3 #4) e HPCI with suction from the condensate storage tank, defeating high suppression pool water leval suction transfer logic if necessary.
[#3)
( e HPCS; control and maintain pump flow less than [the HPCS Vortex Limit]. [#5) e LPCS; control and 'taintain pump flow less than the LPCS Pump NPSH Limit and [the LP'.S Vortex Limit).
e LPCI with inject:en through the heat exchangers as soon as possible; contrcl and maintain pump flow less than the RHR Pump NPSH Limit and (the RHR Vortex Limit).
SNPS PSTG Stept RC/L-2 Restore and maintain RPV water level between + 12.5 in, and +56.5 in, with one or more of the following syster--
o Condensate /Feedwater e Centrol Rod Drive [# 6) e RCIC with suction from the CST, defeating low RPV pressure isolation interlocks and overriding low CST water level suction trcnsfer logic if necessary.
[#2) (#3)
PSTG #2 Rev. 1 Page 8
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline e HPCI with suction from the CST, defeating high supprecsion pool / Low CST water level suction transfer logic if necessary.
[f2) e Core Spray system, control and maintain pump flow less than the Core Spray pump NPSH (Figure C) and Vortex Limit (Figure D).
e LPCI with injection through the heat exchangers as soon as possible; control and , maintain pump flow less than the RRR pump NPSH (Figure E) and Vortex Limit (Figure F).
Justification For Differences /
References:
D21eted reference to low level shutdown cooling interlock since it is iient;ral to the low level scram setpoint.
Altered HPCI and RCIC statements to reflect Shoreham specific logic requirements.
( ited reference to HPCS.
SNPS specific caution added to warn operatcr at 3300 KW diesel loading limitation.
Low lovel scram setpoint - Tech Spec Table 2.2.1-1 High level trip setpoint - Tech 8pec Table 3.3.3-2 Low level shutdown cooling fsolation - Tech Spec Table 3.3.3-2 Core Spray NPSH Limits: NED Calculation C-NSD-211 RHR NPSH Limits: NED calculation C-NSD-211 Core Spray /RRR Vor:ex Limits: NED Appendix C Calculation C-NAD-273 i
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PSTG #2 Rev. 1 Page 9 l
t SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/L-2 If RPV water level cannot be restored and maintained above (+12 in.
(Con't) (low level scram setpoint) or shutdown cooling RPV water level interlock, whichever is high!r], maintain RPV water level above (-164 in. (top of active fuel):
SNPS PSTG Step:
RC/L-2 (Cont.) If RPV water level cannot be restored and maintained above +12.5 in.,
maintain RPV water level above -158 in. (Top of Active Fuel).
Justification for Differences / References
. I.nw Level scram setpoint - Tech Spec Table 2.2.2-1 ,
ivp of Active Fuel - Tech Spec Figure B 3/4 3-1 Low Lsvel RPV shutdown cooling interlock - Tech Spec Table 3.3.3-2.
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P PSTG #2 Rev. 1 Page 10 ,
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline EPG Step:
RC/L-2 (Ccnt.) RPV water level control may be augmented by one or more of the following systems:
[e RHR service water crosstie ]
(o Fire system ,
)
[e Interconnections with*other units ]
[e ECCS keep-full systems ]
[e SLC (test tank) )
SNPS PSTG Step:
L-2 (Cont.) RPV vater level control may be augmented by one or more of the following systems:
e RHR Service Water Crosstie (Ultimate Cooling) e Fire Main to ultimate cooling e ECCS connections from Condensate Transfer e SLC (test tank) e SLC (boron tank)
Lt Justificatien for Differences / References Eliainated menu choice which deals with interconnections to other units. SNPS is e single unit facility.
( l PSTG #2 Rev. 1 Page 11
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SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline RC/L-2 (Cont.) If RPV water level can be m,aintained above [-164 in. (top of active fuel)) and the ADS timer has initiated, prevent automatic RPV depressurizaticn by resetting the ADS timer.
SNPS PSTG Step:
RC/L-2
(' 7t.) If RPV vater level can be maintained above -158 in. (Top of Active Is Fuel) and the ADS timer has initiated, prevent automatic RPV depressurization by inhibiting the ADS timer. l<l Justif_tention,for Differences / References Top of Active Fuel - Tech. Spec. Figure B 3/4 3-1 M'thod 2 of "resetting" the ADS timer specified as permitted by EPG Appendix B. (i PSTG #2 Rev. 1 Page 12
-m SHOREHAM N1JCLEAR' POWER STATION Plant Specific Technical Guidelines RPV Control Guideline
-wa e....
If RPV water level cannot be maintained above (-164 in. (top of active fuel)],
enter (procedure developed from CONTINGENCY #1],
SNPS PSTG Step:
If 'tPV watcr level cannot be maintained above -158 in. (Top of Active Fuel) r Contingency #1, Alternate Level Control.
Justification for Differences /
References:
'i Top of Active Fuel - Tech Spec Figure B 3/4 3-1 l
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PSTG #2 Rev. 1 Page 13 b_-
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. i SHOREFAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline
'EPG Step:
RC/L-3 When [ procedure for cooldown to cold shutdown conditions) is entered from [ Step RC/P-5), proceed to cold shutdown in accordance with
[procedire for cooldown to. cold shutdown conditions).
SNPS PSIG Step:
RC/L-3 When SP 22.005.01 is entered from step RC/P-5, proceed to cold shutdown '
in accordance with SP 22.005.01.
' Justification for Differences / References Procedure for cooldown to cold shutdown - Shoreham PJant Procedure Status
- Listing (PPSL).
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PSTG #2 Rev. 1 '
Page 14 r
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C SHOREHAM NUCLEAR POWER STATION Plant Specific T Shnical Guidelines RPV Control Guideline EPG Step:
RC/P Monitor and control RPV pressure.
If while executing the tollowing steps:
e A high drywell pressure ECCS initiation signal ((2.0 psig (drywell pressure which initiates ECCS))) exists, prevent injection from those LPCS a'.d LPCI pumps not required to assure adequate core cooling prict to depressurizing below their maximum injection pressures. '
e Emergency RPV Depres",urization is anticipated and all control rods are inserted to or'oeyond position (02 (Maximum Suberitical Banked Withdrawal Position)), or it has been determined that the reactor will remain shutdown under all conditions without boron, rapidly depressurize the RPV with the main turbine bypass valves.
[#2 #6]
e Emergency RPV Depressurization is required and less than [7 t'
(number of SRVs dedicated to ADS)) SRVs are open, enter (procedure developed from CONTINGENCY $2].
e RPV water level cannot be determined and less than (7 (number of SRVs dedicated to ADS)) SRVs are open, enter (Procedure developed from CONTINGENCY #2).
e RPV water level cannot ti determined and at least (7 (number of SRVs dedicated to ADS)] Sh? are open, enter (procedure developed from CONTINGENCY #4).
SNPS PSTG Step:
l RC/P Monitor and control RPV pressure.
l t .----_--____-_--_----_----_-_--_----
If while executing the following steps:
e A high drywell pressure ECCS initiation signal (1.69 psig) exists, prevent injection from those Core Spray and LPCI pumps not required to assure adequate core cooling prior to depressurizing below their maximum injection pressures.
PSTG #2 Rev. 1 Page 15
e SHOREHAM NUCLEAR POWER STATION
- Plant Specific Technical Guidelines RPV Control Guideline SNPS PSTG Step:
(Con't) e E=ergency RPV Depressurization is anticipated and 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, rapidly depressurize the RPV with the main turbine bypass valves. (f 4) e Emergency RPV Depressurization is required and less than 7 SRVs are open, enter Emerg,ency RPV Depressurization CONTINGENCY #2.
e RPV water level cannot be determined and less than 7 SRVs are open, enter Emergency P.PV Depressurization CONTINGENCY #2.
e RPV water level cannot be determined and at least 7 SRVs are open, enter RPV Flooding, CONTINGENCY #4.
tification For Differences / References e Core Spray vs Low */ressure Core Spray Terminology o Drywell Pressure which initiates ECCS: Tech Spec Table 3.3.3-2 o- Msx Sub-critical Banked Withdrawal Position: NED Appendix C calculation C-NFD-200 e Number of SRV's dedicated to ADS: Tech Spec Section 3.5.1.d.
PSTG #2 Rev. 1 Page 16
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4-SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline EPG Step:
' RC/P-1 If any SRV is cycling. . initiate IC and manually open SRVs until RPV pressure drops to (935 psig (RPV pressure at which all turbine bypass valves are fully open)).
4 SNPS PSTG Step RC/P-1 If any SRV is cycling, manually open SRV's until RPV pressure drops to 930 psig. 'l Justification for Differences / References Deleted Reference to Isolation Condenser (IC) (N/A to SNPS)
RPV Pressure at which all turbine bypass valves are fully open: NED Calculation C-NAD-275. NOTE: This number has taen rounded down to 930 psig 41 frca 932 psig as required by the V & V program (see HED #405).
I PSTG #2 Rev. 1 Page 17
4 SHOREHAM NUCLEAR P0'n'ER STATION Plant Specific Technical Guidelines RPV Control Guideline EPG Step:
If while executing the following steps:
o Suppression pool temperature capnot be maintained below the Heat Capacity Tc=perature Licit, maintain RPV pressure below the limit. [#6) o Suppression pool water level cannot be maintained below the SRV Tail Pipe Level Lwit, caintain RPV pressure below the Limit. [#6) e Steam Cooling is required, enter (procedure developed from CONTINGENCY #3).
.3 PSTG Step:
AI wal.. ca.euting the following steps:
o Suppression pool temperature cannot be maintained below the Heat Capacity Temperature Limit (Figure G) maintain RPV pressure below the Limit. [#4) e- Suppression pool water level cannot be maintained below the SRV Tail Pipe Level Licit, (Figure H) maintain RPV pressure below the Limit. [#4) v...4<4-.4- < r, - n<fferences/ References The Stes: Cooling Contingency has been merged into Contingency #1, SNPS PSTG Heat Capacity Te=perature Limit - NED Appendix C Calculation No. C-NAD-265 SRV Teilpipe Level Limit - NED Appendix C Calculation No. C-NAD-271 PSTG #2 Rev. 1 Page 18
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SHOREHAM NUCLEAR PO'n'ER STATION Plant Specific Technical Guidelines EPG Stept
, -------------..---- ----- i If while executing the following' steps:
e Peron Injection is required, and e The main condenser is available, and e There has been no indication of gross fuel failure or steam line break, open MSIVs, bypassing pneumatic system and low RPV water level isolation interlocks if necessary, to reestablish the main condenser as a heat sink.
SNPS PSTO Step:
If while executing the following steps:
e Boron Injection is required, and e The main condenser is available, and e There has been no indication of gross fuel failure or steam line break,
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open MSIVs, bypassing pneumatic system and low RPV water level isolation interlocks if necessary, to reestablish the main condenser as a heat sink.
-Justification for Differences / References 6, n 4
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PSTG #2 Rev. 1 Page 19
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/P-2 Stabilize RPV pressure at a pressure below [1045 psig (high RPV pressure scram setpoint)) with the main turbine bypass valves.
RPV pressure control may be augmented by one or more of the following systems:
e IC o SRVs only when suppression pool water level is above [4 ft. 9 in. (elevation of top of SRV discharge device)]; open SRVs in the following sequence if possible [M, B G, F. D L K, C A (SRV opening sequence)); if the continuous SRV pneumatic supply is or becomes unavailable, place the control switch for each SRV in the [CLOSE or AUT0) position.
e HPCI with suction from the condensate storage tank.
I#33
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e RCIC with suction from the condensate storage tank.
[#3 f4]
e [0ther steam driven equipment) e RWCU (recirculation mode), bypassing [ regenerative heat exchangers and) filter /demineralizers and, if necessary, defeating SLC and other isolation
- interlocks, o Main steam line drains e RWCU (blowdown mode) if no boron has been injected into the RPV; refer to [ sampling procedures) prior to initiating blowdown.
PSTG #2 Rev. 1 Page 20
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SHORERAM NUCLEAR POWER STATION j Plant Specific Technical Guidelires SNPS PSTG Step:
RC/P-2 Stabilize RPV pressure at a pressure below 1043 psig with the main turbine bypass valves.
RPV pressure control may be augmented by one or more of the following systems:
e SRVs, only when suppression water level is above
-84 in, open SRVs in the following sequence if possible: L. K. B. H, E, A, G. C, F. D J; if the continuous SRV pneumat(c supply is or becomes unavailable, place the control switch for each SRV in the AUTO or CLOSE position.
e HPCI with suction from the condensate storage tank.
[#2) e RCIC with suction from the condensate storage tank.
[f2 #3) e Steam Seal Evaporator e Feedwater System o Steam Jet Air Ejectors e Main Condenser Deserating Steam ;
e P.WCU (recirculat*on mode), bypassing filter /demineralizers and, if necessary, defeating SLC and other isolation interlocks. [f6) <
e Main steam line drains e RWCU (blowdown mode) if no boron has been injected 1 into the RPV; refer to [SP 23.709.01 Section 8.1.3) '
prior to initiating blowdown. [f6) t I
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I PSTG #2 Rev. 1 Page 21
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Justification for Differences / References e High RPV pressure scram setpoint - Tech Spec Table 2.2.1-1 e Deleted Reference to IC (N/A to SNPS) e Elevation of the Top of the SRV Discharge Device:
SWEC Drawing 11600-02-FP-200 NN. NOTE: -84 in. (I represents the lowest level for which the current SNPS Suppression Pool level instrumentation can read from the Control,Roum. See HED #471.
e SRV Opening sequence is determined by attempting to evenly distribute the heat load in the suppression pool. This sequence is determined through Engineering judgement by inspection of the plan view of the SRV T-Quenchers location within the suppression pool.
Reference:
Figure A-1, STP-26.
o Added other steam driven equipment pertinent to SNPS to the bulleted item.
- e. ' Deleted "bypassing regenerative heat exchangers" from the first RWCU bullet. This cannot be done at SNPS. Ref: SWEC drawing 11600.02-FM24A.
e Added the procedural guidance for RWCU (Blowdown Mode).
e Added cautionary statement for 3300 KW concerns PSTG #2 Rev. 1 Page 22
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SHOREHAM NUCLEAR PO'n'ER STATION Plant Specific Technical Guidelines EPG_ Step:
If while executing the following steps the reactor is not shutdown, return to (Step RC/P-2).
SNPS PSTG Step:
If while executing the following steps the reactor is not shutdown, return to [ Step RC/P-2)
Justification for Differences / References N/A PSTG #2 Rev. 1 Page 23
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/P-3 When either:
e All control rods are inserted to or beyond position i.. .....stwom Suberitical Banked Withdrawal Position)), or e It has been determined that the reactor will remain shutdovn under all conditions without boron, or e [280 pounds (Cold Shutdown Boron Weight)) of boron have been injected into the RPV, or e The reactor is shutdown and no boron has been injected into the RPV, depressurite the RPV and maintain cocidown rate below (100*F/hr (RPV cooldown rate LCO)).
If one or more SRVs are being used to depressurire the RPV and the continuous SRV pneumatic supply is or becomas unavailable, depressurite with sustained SRV
. opening.
SNPS PSTG Step:
r.w ir - 3 ...... either:
e All control rods are inserted to or beyond position 02, or e It has been determined that the reactor will remain shutdown under all conditions without boron, or e The entire contenes of the SLC Tank have been <t injected into che RPV, or e The reactor is shutdown and no boron has been injected into the RPV, depressurire the RPV and maintain cooldown rate below 100'F/hr PSIG #2 Rev. 1 Page 24 1
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SHORERAM NUCLEAR POWER STATION Plant Specific' Technical Guidelines P
SNPS PSTG Steps (Con't)
If one or more SRVs are being used to depressurize the RPV and the continuous SRV pneumatic supply is or becomes unavailable, depressurize with sustained ;
SRV opening.
Justification for Differences / References M2x Suberftical Banked Withdrawal Position: NED Appendix C ,
cciculation No. C-NrD-200. !
Cold Shutdown Boron Weight - NED Appendix C Calculation No. [
"D-276/C-NTD-297. 7
- i RPV cooldown rate LCO: Tech Spec section 3.4.6 ;
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PSTG #2 Rev. 1 I 4
Page 25 ,
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e-SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/P When the shutdown cooling RPV pressure intarlock clears, initiate shutdown cooling [using only those RHR pumps not required to maintain RPV water level above (10 in.
(RPV water level shutdown cooling interlock)] by operation in the LPCI mode).
If shutdown cooling cannot be established and further cooldown is required, continue to cool down using one or more of the systems used f,or depressurization.
SNPS PSTG Step:
RC/P-4 When the shutdown cooling RPV pressure interlock clears, initiate shutdown cooling using only those RHR pumps not required to maintain RPV water level above 12.5 in. by
_ C. .- operation in the LPCI mode.
If shutdown cooling cannot be established and further cooldown is required, enter procedure developed for A* ernate Shutdown Cooling SP 29.020.01 ft Justification for Differences / References Procedure for Alternate SD Cooling: SNPS PPSL RPV water level shutdown cooling interlock - Tech Spec Table 3.3.2.
Alternate SD Cooling is called out nere as implied in EPG 4I Appendix B. This is in accordance with the SNPS USAR for a cingle' failure in the Shutdown cooling system.
PSTG #2 Rev. 1 Page 26
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step,:
RC/P-5 When either:
e All control rods are inserted to or beyond position (02 (Maxirum Suberitical Banked Withdrawal Position)], or e It has been determined at the reactor will remain shutdown under all cc- without boron, or e (280 pounds (Cold Shutdown Boron Weight)) of boron have been injected into the RPV, proceed to cold shutdown in accordance with [ procedure for cooldo. , to cold shutdown conditions).
SNPS PSTG Step:
RC/P-5 Whan either:
e All control rods are inserted to or t./ond position 02, or
( -
e It has been determined that the reactor will remain shutdown under all conditions without boron, or e The ei.cire contents of the SLC Tank have been (g injected into the vessel.
proceed to cold shutdown in accordance with SP 22.00,i.01, Shutdown from 20% Power.
Justification for Differences / References wav enkevitical Banked Withdrawal Position - NED Appendix C calculation No. C-NFD-200
.'ald shutdown Boron Weight NED Appendix C calculation No. di C-NFD-276/C-NFD-297 Procedure for cooldown to cold shutdown - From the SNPS PPSL.
PSTG #2 Rev. 1 Page 27
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/Q Monitor and control reactor power.
If while executing the following steps:
e All control rods are inserted to or beyond position (02 (Maximum Suberitical Banked Withdrawal Position)), terminate boron injection and enter
[ scram procedure).
e It has been determinea that the reactor will remain shutdown under all co*nditions without boron, terminate boron injection and enter [ scram procedure),
o The reactor is shutdown and no boron has been injected into the RPV, enter [ scram procedure).
SNPS PSTG Step:
Q Monitor and control reactor power.
If while executing the following steps:
e All control rods are inserted to or beyond position 02, terminate boron injection and enter SP 29.010.01, Emergency Shutdown.
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e It has been determined that the reactor will remain shutdown under all conditions without boron, terminate boron injection and enter SP 29.010.01, Emergency Shutdown, e The reactor is shutdown and no boron has been injected into the RPV, enter SP 29.010.01, Emergency Shutdown.
Justification for Differences / References Mtx suberitical Eanked Withdrawal Position - NED Appendix C Calculation No. C-NFD-200.
Scram Procedure: SNPS PPSL PSTG #2 Rev. 1 Page 28
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/Q1~ [ Confirm or place the reactor mode switch in SHUTDOWN.]
[RC/Q-2 If ARI has not initiated, initiate ARI.]
RC/Q-3 If the main turbine-generator is on-line [and the MSIVs are open], confirm or initiate recirculation flow runback to minimum.
RC/Q-4 If reactor power is above [3% (APRM downscale trip)] or cannot be d,etermined, trip the recirculation pumps.
[RC/Q-5 If ARI has not initiated, initiate ARI.]
Execute [ Steps RC/Q-6 and RC/Q-7] concurrent'v.
SNPS PSTG Step:
c 'RC/Q-1 Confirm or place the reactor mode switch in SHUTDOWN.
RC/Q-2 If ARI has not initiated, manually initiate ARI RC/Q-3 If the M3IVs are open and the main turbine-generator is on-line, confirm or runnack Cl recirculation flow to minimum.
RC/Q-4 If reactor power is above 5% or cannot b; determined, trip the recirculatics. pumps.
Execute [ Steps RC/Q-5 and RC/Q-6} concurrently.
Justification for Differences /
References:
APRM Downscale trip - Tech Specs, table 3.3.6-2.
PSTG #2 Rev. 1 Page 29
- l SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines l
EP1 Step:
RC/Q-6 Before suppression pool temperature reaches [the Boron Injection Initiation Temperature] but only if tne reactor cannot be shu'. down, BORON INJECTION IS REQUIRED; inject boron ira o the RPV with SLC and prevent automatic initirtica of ADS.
SNPS PSTG Step:
RC/Q-5 Before suppression pool temperature reaches 110*F but only if the reactor cannot be shut down; BORON (l INJECTION IS REQUIRED: inject boron into the RPV with SLC and prevent automatic initiation of ADS, by placing the ADS inhibit switch to INHIBIT.
(austification
~ for Differences / References o boton injection Initiation Temperature - NED Appendix C Calcuttion C-NFD-276. NOTE: In order to simplify the step gl the most conservative temperature was utilized as opposed to e curve.
Guidance added on how to "prevent automatic initiation of e'
ADS".
PSTG f. Pav. 1 Page 30
e SH0kERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step; i
RC/Q-6 '
(Cont.) If boron cannot be injected with SLC, inject boron into the RPV by one or more of the following c) ernate methods:
(o CRD ]
[o HPCS }
[o RWCU ] *
[o Feedwater ] *
[o HPCI J
[o RCIC ]
[o Hydro pump)
SNPS PSTG Step:
,/Q-5 If boron cannot be injected with SLC, inject boron (Con't) into the RPV utilizing on alternate method of (i poison injection per SP 25.001.01.
,Justirication for Differences / References S'P 25.001.01: SNPS PPSL 41 l
l l
l PSTG #2 Rev. 1 Page 31
..g SliOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Stept If while executing the following steps SLC tank water level drops to (0% (low SLC tank water level trip)], confirm automatic trip of or manually trip the SLC pumps.
I 1
SNPS PSTG Step:
1 i
If while executing the following steps SLC tank water level drops to 0% manually trip the SLC pumps.
Justification for Differences / References o Dsleted reference to the automatic trip of SLC pumps which is Not Applicable to SNPS: Test Loop Diagram - IC41002.
PSTG #2 Rev. 1 Page 32
SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines EPG Step:
RC/Q-6.1- If boron is not being injected into the RPV by RWCU and RWCU is not isolated, bypass (regenerative heat exchangers and) filter /demineralizers.
RC/Q-6.2 Continue to inject boron until [280 pounds (Cold Shutdown Boron Weight)] of boron have been injected into the RPV.
RC/Q-6.3 Enter [ scram procedure).
SNPS PSTG Step: '
RC/Q-5.1 If RWCU is not isolated, bypass filter /demineralizers.
RC/Q-5.2 Continue to. inject boron until the entire contents of the SLC Tank have been injected into the RPV. 4\
RC/Q-5.3 Enter SP 29.010.01, Emergency Shutdown.
(
- ification for Differences /
References:
RC/Q-5.1 l o Deleted reference to boron injection with RWCU o Daleted reference to bypassing Non-Regenerative Heat Exchangers (NA to SNPS) - SWEC DWG 11600.02-FM24A.
RC/Q-5.2 41 o Cold shutdown Boron Weight - NED Appendix C calculation No.
C-NFD-276/C-NFD-297
! RC/0-5.3 lo Referenced the SNPS Scram Procedure from the SNPS PPSL.
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L l
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PSTG #2 Rev. 1 Page 33
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e SHOREHAM NUCLEAP. P0k'ER STATION Plant Specific Technical Guidelines EPG Step:
RC/Q-7 Insert control rods as follows:
RC/Q-7.1 Reset ARI, defeating ARI logic trips if necessary.
RC/Q-7.2 Insert control rods with one or more of the following methods:
e Deenergize scram solenoids e Ventthesc/amairheader e Reset the scram, defeating RPS logic trips if necessary, drain the scram discharge volume, and initiate a manual scram.
e Open individual scram test switches e Increase CRD cooling water differential pressure
! e Drive control rods, defeating RSCS and Rk'M interlocks if necessary e Vent control rod drive overpiston volumes j SNPS PSTG Step:
l l
RC/Q-6 Insert control rod as follows:
RC/Q-6.l Reset ARI, defeating ARI logic trips if necessary.
RC/Q-6.2 Insert control rods with one or more of the following methods:
e De-energize scram solenoids e Vent the scram air header e Reset the scram, defeating RPS logic trips if necessary, drain the scram discharge volume, and initiate a manual scram.
PSTG #2 Rev. 1 Page 34
e*
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines SNPS PSTG Step:
(Cont.)
e Open individual scram test switches.
e Increase CRD drive water differential pressure.
e Drive control rods, defeating RSCS and RWM interlocks if necessary, e Vent control rod drive overpiston volumes Justification for Differences / References N/A
( ,
PSTG #2 Rev. 1 Page 35
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