ML20151D447
| ML20151D447 | |
| 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-880511-01, NUDOCS 8807250123 | |
| Download: ML20151D447 (52) | |
Text
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.' MC-1 SHOREHAM NUCLEAR POWER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #3 PRD!ARY CONTAINMENT CONTROL REVISION NO: 1 r*
PREPARED BY: 8, .
DATE: / [9 h" O '_ : jf f/ 7, hirurtw DATE: /d[8N OPERATING ENGINEER APPROVAL: u ;_ DATE: F/, /W 8807250123 080715 PDR ADOCK 05000322 F PNU MAY 111980 n:ny]Q" y arg ,
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SHOREHAM NUCLEAR POWER STATION l Plant Specific Technical Guidelines Primary Containment Control i
EPG Step:
...anner r
i The purpose of this guideline is to: -
o Maintain primary containment integrity, and o Protect equipment in,the primary containment.
SNPS PSTG Step:
( POSE The purpose of this guideline is to:
o Maintain primary containment integrity, and a
Protect equipment in the primary containment.
Justification For Differences /
References:
N/A PSTG #3 Rev. 1 Page 1
SHOREHAM NUCLEAR POWER STATION
, Plant Specific Technical Guidelines Primary Containment Control.
EPG Step:
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
o Suppression pool temperature above [95'F (most limiting suppression pool temperature LCO))
o Drywell temperature above [135*F (drywell temperature LCO or maximum normal operating temp'erature, whichever is higher))
o Containment *<cperature above [90'F (containment temperature LCO)]
o Drywell pressure above [2.0 psig (high drywell pressure scram setpoint))
o Suppression pool water level above [12 ft. 6 in. (maximum suppression pool water level LCO))
o Suppression pool water level below [12 ft. 2 in. (minimum suppression pool water level LCO))
o Primary containment hydrogen concentration above [2% (high hydrogen alarm setpoir.t))
SNPS PSTG Step:
ENTM CONDITIONS The entry conditions for this guideline are any of the following:
o Suppression pool temperature above 90*F o Drywell temperature above 145'F o Drywell pressure above 1.69 psig
'o Suppression pool water level above + 6 in.
o Suppression pool water level below - 6 in. 'b o Primary containment hydrogen concentration above 4%
PSTG #3 Rev. 1 Page 2
l SHOREHAM NUCLEAR POWER STATION Plant Specific Technica1' Guidelines Primary Containment Control
. Justification for Differences / References Host limiting suppression pool temperature LCO:
Drywell temperature LCO: Tech Spec Section 3.6.1.7 Deleted reference to "Containment Temperature" which only applies to Mark III containments (SNPS is a }Mrk II containment)
High drywell pressure scram setpoin,t - Tech Spec Table: 2.2.1-1 Min / Maximum Suppression Pool water'1evel LCO: Tech Spec Section 3.6.2.1 High hydrogen alarm setpoint: SWEC Drawing 11600.02-7.67-149 i
PSTG #3 Rev. I-Page 3
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. l SHOREHAM NUCLEAR POWER STATION l Plant Specific Technical Guidelines Primary Containment Control EPG Step:
OPERATOR ACTIONS Irrespective of the entry condition, execute (Steps SP/T, DW/T, CN/T, PC/P. SP/L, and PC/H] concurrently. .
SNPS E0P Step Irrespective of the entry condition, execute Steps SP/T, D'n'/T, PC/P, SP/L, and PC/H concurrently.
Notify they Watch Engineer to classify the Event per EPIP 1-0 Justification for Differences / References Deleted CN/T since it only applies to Mark III containments.
Added SNPS Specific Emergency Plan requirements PSTG #3 Rev. 1 Page 4
s SHOREHAM NUCLEAR POWER STATION
-Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/T Monitor and control suppression pool temperature below [95'F (most limiting suppression pool temperature LCO)] using available suppression pool cooling.
When suppressio:. pool temperature cannot be maintained below [95*F (most limiting suppression pool temperature LCO)):
SP/T-1 Operate all available suppression pool cooling (using only those FHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode).
SP/T-2 Before suppression pool temperature reaches [the Boron injection Initiation Temperature), (Figure N) enter [ procedure developed from the RPV Control Guideline) at [ Step RC-1) and execute it concurrently with this procedure.
SNPS PSTG Step:
( !T Monitor and contrcl suppression pool temperature below 90*F using available suppression pool cooling. [#6)
When suppression pool temperature cannot be maintained below 90*F.
SP/T-1 Operate all available suppression pool cooling using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode.
SP/T-2 Before suppression pool temperature reaches the 110' F, enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.
Justification for Differences /
References:
Most limiting suppression pool temperature LCO - Tech Spec Section 3.6.2.1 Loron Injection Initiation Temperature - NED Appendix C Calculation No. C-NFD-276 In order to simplify this procedure the most conservative Boron Injection Initiation #1 Terperature from the NED calculation was chosen. This eliminates the use of another grcph while still maintaining the most conservative portion of it.
PSTG #3 Rev. 1 Page 5
SHORE' LAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Steg:
SP/T-3 When suppression pool temperature and RPV pressure cannot be maintained below the Heat Capacity Temperature Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
SNPS PSTG Step:
SP/T-3 When suppression pool temperature and RPV pressure cannot be maintained below the Heat Capacity Temperature Limit, (Figure G)
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
bustification for Differences / References Hect Capacity Temperature Limit - NED Appendir C Calculation No. C-NAD-265 PSTG #3 Rev. 1 Page 6
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SHORENAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
.. 6c.
oi.o control drywell temperature below (135'F (drywell temperature LC0 or maximum normal operating temperature, whichever is higher)] using available drywell cooling.
When drywell temperature e,annot be maintained below (135'F (drywell temperature LCO or maximum
- normal operating temperature, whichever is higher)]: (#1)
DW/T-1 Operate all available drywell cooling, defeating isolation interlocks if necessary.
""DS PSTG Step:
DW/T Monitor and con' trol drywell temperature below 145'F using availabic drywell cooling.
When drywell temperature cannot be maintained below 145'F:
(#1)
. DW/T-1 Operate all available drywell cooling, defeating isolation interlocks if necessary. (#6)
Justdffcation for Differences / References Drywell Temperature LCO: Tech Spec Section - 3.6.1.7 PSTG #3 Rev. 1 Page 7
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
If while executing the following steps drywell sprays have been initiated and drywell pressure drops below (2.0 psig (high drywell pressure scram setpoint)),
terminate drywell sprays. ,
SNPS PSTG Step:
If while executing the following steps drywell sprays have been initiated and dryvell pressure drops below 1.69 psig, terminate drywell sprays.
(,, _____ ______________ _ _____
Justification for Differences / References High drywell pressure scram setpoint - Tech Spec Table 2.2.1-1 PSTG #3 Rev. 1 Page 8
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
DW/T-2 Before drywell temperature reaches [340*F (maximum temperature at which ADS qualified or drywell design temperature, whichever is lower)] but only if [ suppression pool water level is below (17 ft.
2 in. (elevation of bottom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water )] and] drywell temperature and pressure are within the Drywell Spray Initiation Limit. [ shutdown recirculation pumps and drywell cool,ing fans and) initiate drywell sprays (using only those RHR pumps'not required to assure adequate core cooling by continuous operation in the LPCI mode).
SNPS PSTG Step DW/T-2 Before drywell temperature reaches 340'F but only if suppression pool water level is below Elevation 50 ft. and drywell temperature and pressure are within the Drywell Spray Initiation Lim:Ir, j, (Figure I) enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure, shut down recirculation pumps and drywell cooling fans and initiate drywell sprays using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode.
Justification for Differences / References Hiximum temperature at which ADS is qualified /drywell design temperature:
Shoreham Environmental Qualification Report (EQR) -
Figure D-1, June 1981 (340'F)
Shoreham Technical Specification Section 5.2.2. (340'F)
Elevation of bottom of internal suppression chamber to drywell vacuum breakers less vecuum breaker opening pressure in feet of water: SWEC Drawing 11600.02-FK15B and Tech Spec Section 4.6.4.b.3.a.
50.75 Ft. - 0.25 psi (2.31 ft. H 0/ psi) = 50.17 ft.
2 Drywell Spray Initiation Limit - NED Appendix C Calculation No. C-NAD-263.
sd statement from DW/T-3 to enter RPV Control prior to initiating Drywell Sprays <1
.e DW/T-3).
PSTG #3 Rev. 1 Page 9
SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
DW/T-3 When drywell temperature cannot be maintained below [340*F (maximum te.,perature at which ADS qualified or drywell design temperature, whichever is lower)), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter (procedure developed from the RPV Control Guideline) at [ Step RC-1) and execute it concurrently with this procedure. .
SNPS PSTG Step:
DW/T-3 When drywell temperature cannot be maintained below 340'F, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
{b
' stification for Dif f erences:
Maximum temperature at which ADS is qualified /drywell design temperature:
Shoreham EQR, Figure D-1, June 1983 (340*F)
Shoreham Tech Spec Section 5.2.2 (340'F)
D21sted statement directing operator to enter RPV Control. This was moved to DW/T-2 # 3' l prior to initiating Drywell Sprays. This is justified for the following reasons:
l continued critical operation with recirculation pumps secured is not permitted by the SNPS Technical Specifications (LCO 3.4.1.1), and initiation of drywell sprays during critica'l operation is not in accordance with standard operating practices for l trcnsients/ accidents. The net affect on the intent of this procedure section is not altered, although entry into RPV Control will be permitted earlier than the Guideline i intended.
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l PSTG #3 Rev. 1 Page 10 I
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
CN/T Monitor and control con:ainment temperature below [90'F (containment temperature LCO)), using available containment cooling.
When containment temperature cannot be maintained below [90'F (containment
- emperature LCO)): [#1)
CN/T-1 Operate all avai,lable containment cooling.
If while executing the following steps suppression pool sprays have been initiated and suppression chamber pressure drops below [2.0 psig (high drywell pressure scram setpoint)], terminate suppression pool sprays.
CN/T-2 Before containment temperature reaches (185'F (containment design temperature)], but only if suppression chamber pressure is above
[2.0 psig (Mark III Containment Spray Initiation Pressure Limit)],
initiate suppression pool sprays using only those RHR pumps not
~
required to assure adequate core cooling by continuous operation in the LPCI mode.
CN/T-3 When containment temperature cannot be maintained below (185'F (containment design temperature)], EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter (procedure developed from the RPV Control Guideline) at (Step RC-11) and execute it concurrently with this procedure.
-S'NPS PSTG Step:
N/A Justification for Differences / References Stops in the EPG with the prefix CN/ are only applicable to Mark III containments.
SNPS is a Mark II containment.
PSTG #3 Rev. 1 Page 11
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u SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/P Monitor and control primary containment pressure below (2.0 psig (high
..;: pr;;r_rc scram setpoint)) using the following systems:
o Containment pressure control systems; use (containment pressure control system operating procedures).
o SBGT (and drywell purge); use (SBGT and drywell purge operating procedures). ,.
When primary containment pressure cannot be maintained below (2.0 psig (high drywell pressure scram setpoint)):
,SNPS PSTC Stept PC/P Monitor and control primary containment pressure below 1.69 psig by venting
, the primary containment in accordance with 23.425.01, Section 8.2.6.
When primary containment pressure cannot be maintained below 1.69 psig:
Justification for Differences / References The purt se of Step PC/P is to maintain primary containment pressure below 1.69 psig using the normal operating procedures and systems. SP 23.425.01 includes the nscessary guidance on venting a pressure rise in the primary containment prior to its r6ad.iua 1.03 psig. With this noted in the PSTG, the need for the first bullet item is satisfied, and the second bulleted item is eliminated since SNPS doet, not have a Stendby Gas Treatment System. The SNPS equivalent to SBGT, Reactor Building Standby Ventilation System (RBSVS), is only operated during an emergency condition, and does not include the capability for primary containment venting in its normal mode of operation.
High drywell pressure scram setpoint: Tech Spec Table: 2.2.1-1 RBSYS Design Basis: FSAR Section 6.2 PSTG #3 Rev. 1 Page 12 i _.
' '. ' )i 1 SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
If while executing the following steps suppression pool sprays have been initiated and suppression chamber pressure drops below [2.0 psig (high drywell pressure scram setpoint)], terminate suppression pool sprays.
SNPS PSTG Step:
If while executing the following steps suppression pool sprays have o'een initiated and suppression chamber pressure drops below 1,69 psig, terminate suppression
(- pool sprays.
Justification for Differences / References High Drj .t1 pressure scram setpoint: Tech Spec. Tablo 2.2.1-1
(
PSTG #3 Rev. 1 Page 13
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SHOREHIM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
L PC/P-1 Before suppression chamber pressure reaches [the Pressure l Suppression Pressure} [13.8 psig (Suppression Chamber. Spray l, $,
l Initiation Pressure)), but only if (suppression chamber pressure l 1s above 2.0 psig (Mark III Containment Spray Initiation Pressure Limit)) (suppression pool water level is below 24 ft. 6 in.
(elevation of suppressicn pool spray nozzles)], initiate a suppression pool sprays [using only those RER pumps not required to assure adequate core cooling by continuous operation in the LPCI mode).
SNPS PSTG Step
?C/P-1 Before suppression chamber pressure reaches 9 psig but only if
. suppression pool water level is below Elevation 50 ft., initiate suppression pool sprays using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode.
Justification for Differences / References For Step PC/P-1.the applicable parameter for a Mark II containment is the containment is the Suppression Chamber Spray Initiation Pressure. Pressure Suppression pressure cpplies to Mark III containments in this particular step, and therefore has been deleted.
Deleted reference to Mark III limits which are N/A to SNPS.
Prossure Suppression Pressure: NED Appendix C Calculation No. C-NAD-267 Suppression Chamber Spray Initiation Pressure: NED Appendix C Calculation No.
( C-NAD-272 Elovation of suppression pool spray nozzles: SWEC Drawing No. 11600.02-FP-200NN PSTG #3 Rev. 1 Page 14
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SHOREHAM NUCLEAR P0'n'ER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
If while executing the following steps drywell sprays hsve been initiated and drywell pressure drops below
[2.0 psig (high drywell pressure scram setpoint)],
terminate drywell sprays. .
SNPS PSTC Step:
If while executing the following steps drywell sprays have
( been initiated and drywell pressure drops below 1.69 psig, terminate drywell sprays.
Justification for Differences /
References:
High drywell pressure scram setpoint: Tech Spec Table 2.2.1-1 PSTG #3 Rev. 1 Page lj P
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/P-2 When suppression chamber pressure exceeds (13.8 psig (Suppression l' Chamber Spray Initiation Pressure)) but only if (suppression pool water level is below [17 ft. 2 in. (elevation of bottom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)) and) drywell temperature and pressure are within the Drywell Spray Initiation Limit, [ shut down recirculation pumps and drywell cooling fans and) initiate drywell sprays [using only those RER pumps not required to assure adequate core cooling by continuous operation in the LPCI mode).
SNPS PSTG Step:
PC/P-2 When suppression chamber pressure exceeds 9 psig but only if suppression pool water level is below Elevation 50 ft. and ,drywell temperature and pressure are within the Drywell Spray Initiation
('__ Limits, (Figure 1) shut down recirculation pumps and drywell cooling fans and initiate drywell sprays using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode.
Justification for Differences / References Suppression Chamber Spray Initiation Pressure: NED Appendix C Calculation No. C-NAD-272 Elcyction of bottom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water: see Step DW/T-2.
Drywell Spray Initiation Lielt: NED Appendix C Calculation No. C-NAD-263 PSTG #3 Rev. 1 Page 16
SHOREHAM NUCLEAR POWER STATION P1 o tic Specific Technical Guidelines Priccry Containment Control EPG Step:
PC/P-3 When suppression chamber pres , cannot be maintained below the Pressure Suppression Pressure, LMERGENCY RPV DEPRESSURIZATION IS REQUIRED. .
SNPS PSTG Step:
PC/P-3 When suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure, (Figure J) EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
(
Justification fcc Differences / References Pressure Suppression Pressure - NED Appendix C Calculations No. C-NAD-267.
PSTG #3 Rev. 1 Page 17
,e- + *- y g 9 + p. _ . - -..,., p .---
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SHOREHAM NUCLEAR POWER STATION Plane Specific Technical Guidelitjes Primary Containment Control PC/P-4 Before suppression chamber pressure reaches (the Primary Containment Pressure Limit), then irrespective of the offsite radioactivity release rate, vent the primary containment, defeating isolaelen interlocks if necessary, to reduce and maintain pressure below (the Primary Containment Pressure Limit) as follows:
SNPS PSTC Step:
( PC/P-4 Before suppression chamber pressure reaches 60 psig then irrespective of the offsite radioactivity release rate, vent the primary containment, defeating isolation interlocks if necessary, to reduce and maintain pressure below the Primary Containment Pressure Limit as follows:
Justification for Differences /
References:
Primary Containment Pressure Limit: NED Appendix C Calculation No. C-NAD-303.
l' 3" PSTG #3 Rev. 1 P ge 18
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SHOREHAM NUCLEAR POWER STATloN Plant Specific Technical Guidelines Primarv Containment Control EPG Step:-
--~ o if suppression pool water level is below (26 ft.-9 (con't) in. (elevation of the bottom of the suppression chamber vent)), vent the suppression chamber in accordance with (procedure for primary containment venting].
o if suppression pool water is=at or above (26 ft. 9 in.
(elevation 'of the bottom of the suppression chamber vent)),
or if the suppression chamber cannot be vented, vent the drywell in accordance with (procedure for containment venting).
SNPS PSTG Step:
PC/P-4 o if suppression pool water level is below Elevation 57 ft.,
(Con't) vent the suppression chamber in accordance with SP 23.418.01,
(,, Section 8.2.1.
o if suppression pool water level is at or above Elevation 57 ft. or if the suppression chamber cannot be vented, vent the drywell in accordance with SP 23.418.01, Section 8.2.1.
.Justifica lon for Differences /Eeferences Elsvation of the bottom of the suppression chamber vent - SP 84.654.03 penetration X-29 and Xs-22, i
Shoreham specific venting guidance added.
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l-PSTG #3 Rev. 1 Page 19
'SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/P-5 When suppression chamber pressure exceeds (the Primary Containment Pressure Limit), then irrespective of the offsite radioactivity release rate or whether adequate core cooling is assured, vent the primary containment, defeating isolation interlocks if necessary, to reduce and maintain pressure below (the Primary Containment
-Pressure Limit) *as follows:
o If suppression pool water level is below (26 ft. 9 in.
(elevation of the bottom of the. suppression chamber vent)),
vent the suppression chamber in accordance with (procedure for primary containment venting).
o If suppression pool water level is at or above (26 ft. 9 in.
(elevation of the bottom of the suppression chamber vent)),
or if the suppression chamber cannot be vented, vent the drywell in accordance with (procedure for primary concainment
. k' venting).
i SNPS PSTG Step:
None I
justificationforDifferences/ References Tha purpose of this step is to permit venting the containment utilizing systems nacsssary for mai-taining adequate core cooling. This step is not applicable to SNPS 4}
since the method of venting the Shoreham containment (through the RBNVS) has ao offect on adequate core cooling. Step PC/P-4 will have the operator vent at the appropriate time, i
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i PSTG #3 R e.v . 1 l Page 20 l
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SHOREHAM NUCLEAR F0WER STATION Plant Specific Technical Guidelines Primary Containt.ent Control EPG Step:
PC/P-6 When suppression chamber pressure cannot be maintained below (the Primary Containment Pressure Limit), then irrespective of whether adequate core cooling is assured o (If suppression pool water level is below 24 ft. 6 in.
(elevation of suppression pool spray nozzles),) initiate suppression pool spray.
o If (suppres'sion pool water level is below (17 ft. 2 in.
(elevation of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water )) and) drywell temperature and pressure are within the Drywell Spray Initiation Limit, (shut down recirculation pumps and drywell cooling fans and) initiate drywell sprays.
SNPS PSTG Step:
PC/P-5 When suppression chamber pressure cannot be maintained below 60
(" psig, then irrespective of whether adequate core cooling is assured:
o If suppression pool water level is below Elevation 50 ft.,
initiate suppression pool splays, o If suppression pool water level is below Elevation 50 ft. and drywell temperature and pressure are within the Drywell Spray Initiation Limit, (Figure I) shut down recirculation pumps and drywell cooling fans and initiate drywell sprays.
Justification for Differences / References Elevation of suppression pool spray nozzles: SWEC Drawing 11600.02-FP-200NN.
Elevation of bottom of internal suppression chamber to drywell vicuum breakers less vacuum breaker opening pressure in feet of water: (see Step DW/.*-2).
i The Primary Containment Pressure Limit - NED Appendix C Calculatt.c No. C-NAD-303.
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l PSIG #3 Rev. 1 Page 21 i , . _ - . _- _ _ _ _
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/L Monitor and control suppression povi ei or level.
~
If wEiIe~execuIiEg~ tee ~fo1Iow1Eg~sIeps PIiEary~ConIainEent FIaodIng is required, enter [ procedure developed from Contingency #6).
SP/L-1 Maintain suppression pool water level between [12 ft. 6 in.
(maximum suppression pool water level LCO)) and [12 ft. 2 in.
(minimum suppre'ssion pool water level LCO)); refer to [ sampling procedure) prior to discharging water; [ suppression pool makeup may be augmented by SPMS).
If SPMS has been initiated, maintain suppression pool water level between [23 ft. 9 in. (SPMS initiation setpoint plus suppression pool water level increase which results from SPMS operation)) and *
[19 ft. 11 in. (minimum suppression pool water level LCO)).
If suppression pool water level cannot be maintained above [12 ft.
2 in. (minimum suppression pool water level LCO)), execute [ Step SP/L-2].
If suppressior, pool water level cannot be maintained below [12 ft.
6 in. (maximum suppression pool water level LCO)) ([23 f t. 9 in.
(SPMS initiation setpoint plus suppression pool water level increase which results from SPMS operation)) if SPMS has been initiated), execute [ Step SP/L-3).
cyPS PSTG Step:
3P/L Monitor and control suppression pool water level.
~ ~ ~
' ~ ~
If whiIe~execuIiEg~the folIowing sIeps~PriEary~ConIaInEent FIoodIng Is~ required, cntor procedure developed from Contingency #6.
SP/L-1 Maintain suppression pool water level between + 6 in and - 6 in.;
refer to SP 23.708.01 prior to discharging water. Refer to SP 23.203.01, Appendix 12.7, prior to adding water, j If suppression pcol water level cannot be maintained above
- 6 in., execute Step SP/L-2.
If suppression pool vater level cannot be maintained below
+ 6 in. , execut.e Step SP/L-3.
PSTG #3 Rev. 1 l Page 22 i
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-SHOREHAM NUCLEAR POWER STATION
, Plant Specific Technical Guidelines Primary Containment Control Justification for Differences / References H:x/ Minimum suppression pool water level LCO-Tech Spec Section 3.6.2.1.
Plcnt specific suppression pool letdown procedure referenced.
All reference to SPMS deleted. SPMS is a Mark III specific system and not applicable to SNPS.
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, PSTG #3 Rev. 1 l Page 23 l
e SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Stept SP/L-2 SUPPRESSION POOL WATER LEVEL BELCR (12 ft. 2 in. (minimum suppression pool water 1svel LCPj}
Execute (Steps SP/L-2.1 and SP/L-2.2) concurrently.
SP/L-2.1 Mainta'in suppression pool water level above the Heat Capacity Level Limit.
If suppression pool water level cannot be caintained above the Heat Capacity Level Limit. EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter (procedure developed from the RPV Control Guideline) at (Step RC-1) and execute it concurrently with this procedure.
SP/L-2.2 Maintain suppression pool water level above (6 ft. O in.
(elevation of the top of the HPCI exhaust)).
( If suppression pool water level cannot be maintained s_
above (8 ft. O in. (elevation of the top of the HPCI exhaust)), secure HPCI irrespective of whether adequate core cooling is assured.
SNPS raiu step:
SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW - 6 in.
Execute Steps SP/L-2.1 and SP/L-2.2 concurrently.
SP/L-2.1 Maintain suppression pool water level above the Heat Capacity Level Limit.
If suppression pool water level cannot be maintained above the Heat Capacity Level Limit, (Figure L)
EHERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.
PSTG #3 Rev. 1 Page 24
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4 SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control SNPS PS1C Step:
SP/L-2.2 Maintain suppression pool water level above - 42 in. 'b If suppression pool water level cannot be maintained above -'42 in., secure HPCI irrespective of whether adequate core cooling is assured.
Justification for Differences / References Mininum suppression pool water level LCO: Tech Spec Section 3.6.2.1.
Elevation of the top of.the HPCI exhaust: SWEC Drawing' 11600.02-FP200NN.
Hast Capacity Level Limit: NED Appendix C Calculation No. C-NAD-266.
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PSTG #3 Rev. 1 Page 25
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE [12 ft. 6 in. (maximum suppression pool water level LCO)] ([23 ft. 9 in. (SPMS initiation setpoint plus suppression pool water level increase which results from SPMS operation)] if SPMS has been initiated)
Execute (Steps SP/L-3.1, SP/L-3.2, and SP/L-3.3] concurrently, SNPS PSTG Step:
SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE + 6 in.
f
( ________________________________
Execute (Steps SP/L-3.1, SP/L-3.2, and SP/L-3.3] concurrently.
Justification for Differences / References Maximum suppression pool water level LCO: Tech Spec Section 3.6.2-1.
Sections dealing with SPMS deleted (NA to SNPS).
.i PSTG #3 Rev. 1 Page 26
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/L-3.1 Maintain suppression pool water level below the SRV Tail Pipe Level Limit.
If suppression pool water level cannot be maintained below the SRV Tail Pipe Level Limit, enter (procedure developed from the RPV Control Guideline) at (Step RC-1]
and execute it concurrently with this procedure.
If suppression pool water level and RPV pressure cannot be maintained below the SRV Tail Pipe Level Limit but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD.
If suppression pool water level and RPV pressure cannot be restored and maintained below the SRV Tail Pipe Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
(
SNPS PSTG Step:
SP/L-3.1 Maintain suppression pool water level below the SRV Tail Pipe Level Limit (Figure H).
l If suppression pool water level cannot be maintained below the SRV Tail Pipe Level Limit, enter' procedure
- developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.
If suppression pool water level and RPV pressure cannot be maintained below the SRV Tail Pipe Level Limit but only if adequete core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD.
If suppression pool water level and RPV, pressure cannot be restored and maintained below the SRV Teil Pipe Level Limit. EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
stification for Differences / References bRV Tail Pipe Level Limit: NED Appendix C Calculation No. C-NAD-271 PSTG #3 Rev. 1 L Page 27
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, SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/L-3.2 Maintain suppression pool water level below (17 ft. 2 in. (elevation of bottom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)].
If suppression pool water level cannot be maintained below (17 ft. 2 in. (elevation of bottom of internal supprepsion chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)):
o Terminate drywell sprays, o If adequate core cooling is assured, terminate injection into the RPV from sources externsi to the primary containment except from boron injection systems and CRD.
SNPS PSTG Step:
SP/L-3.2 Maintain suppression pool water level below Elevation 50 ft.
If suppression pool water level cannot be maintained
. below Elevation 50 ft.:
o Terminate drywell sprays.
o If adequate core cooling is assured, terminate injection into the RPV from sources external to the l primary containment except from boron injection l
systems and CRD.
I l
Justification for Differences / References Elevatica of bottom of internal suppression chamber to drywell vacuum breakers less v:cuum breaker opening pressure in feet of water. (See Step DW/T-2)
PSTG #3 Rev. 1 l Page 28
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
SP/L-3.3 Maintain primary containment water level below the Maximum Primary Containment Water Level Limit.
If primary containment water level cannot be maintained below the Maximum Primary Containment Water Level Limit, terminate injection into the RPV from sources external to the Primary containment irrespective of whether adequate core cooling is assured.
SNPS PSTG Step:
SP/L-3.3 Maintain primary containment water level below the Maximum Primary Containment Water Level Limit, (Figure B).
k' If primary containment water level cannot be maintained below the Maximum Primary Containment Water Level Limit, terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is assured.
Justification for Differences /Referencec hsximum Primary Containment Water Level Limit - NED Appendix C Calculation No. C-NAD-268.
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PSTG #3 Rev. 1 Page 29 L
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:-
PC/H Monitor and control hydrogen and oxygen concentrations.
wn11e executing the following steps:
o The hydrogen or oxygen monitoring system is or becomes unavailable, sample the drywell and suppression chamber for hydrogen and oxygen in accordance with (sampling procedure].
o Dryvell or suppressibn chamber hydrogen concentration cannot be determined to be below 6% and drywell or suppression chamber oxygen concentration cannot be determined to be below 5%,
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed form the RPV Control Guideline] at (Step RC-1] and execute it concurrently with this procedure; secure and prevent operation of hydrogen mixing systems and recombiners and, irrespective of the offsite radioactivity release rate, vent and purge the primary containment in accordance with (Steps PC/H-4.]
through 4.4] until drywell and suppression chamber hydrogen concentrations can be determined to be below 6% or dryvell and suppression chamber exygen concentrations can be determined to be below 5%.
SNPS_PSTG Step,:
PC/H donitor and control hydrogen and oxygen concentrations, by placing the H /0 Analyzers in service.
2 2 If while executing the following steps:
o The hydrogen or oxygen monitoring system is or beccmes unavailable, request Radiochemistry sample for hydrogen and
- yg:n.
PSTG #3 Rev. 1 Page 30
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control SNPS PSTC Steps (Con't) o Drywell or suppression chamber hydrogen concentration cannot be determir.ed to be below 6% and drywell or suppression chamber
oxygen concentration cannot be determined to be below 5%,
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure; secure and prevent operation '
of recombiners and, irrespective of the offsite radioactivity release rate, vent and purge the primary containment in accordance with Steps PC/H-4.1 through 4.4 until drywell and suppression chamber hydrogen concentration can be determined to be below 6% or drywell and suppression chamber oxygen concentrations can be determined to be below 5%.
Justification for Differences / References Added guidance as to how to monitor H and 0 I" * "**i"**"**
2 2 C.ingsystemsarethedrywellandsuppressionchambersprays.sted There "hydrogen is little mixing systems"l f cn nce that sprays could possibly cause ignition of the containment atmosphere. '
Th2refore, it is inappropriate to tell the operator to secure Drywell and Suppression pool sprays in this override, as Sections DW/T or PC/P of the Primary Containment Control Guideline may require sprays at this point.
Drywall atmosphere mixing system: FSAR Section 6.2.5.2.1.
PSTG #3 Rev. 1 Page 31
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Centainment Control EPG Step:
PC/H-1 When drywell or suppression chamber hydrogen concentration reaches (0.5% (minimum detectable hydrogen concentration)),
but_only if the offsite radioactivity release rate is expected to remain below the offsite release rate LCO, vent and purge the primary containment, defeating isolation interlocks if necessary, to restore and maintain drywell and suppression chacber hydrogen concentrations below (0.5%
(minimum detectable hydrogen concentration)) as follows:
SNPS PSTG Step:
( PC/H-1 When drywell or suppression chamber hydrogen concentration reaches 0.5%, but only if the offsite radioactivity release race is expected to remain below the offsite release rate LCO, vent and purge the primary containment, to restore and maintain drywell and suppression chamber hydrogen concentration below 0.5% as follows:
Justification for Differences / References Deleted "defeating isolation interlocks if necessary" because this cannot be dcne in the context of this step. In order to defeat the interlocks mentioned here, it would require bypassing RBSYS initiatit logic which is not the intent of this step. Bypassing interlocks will be perm 16ted at a later time, when the guid211ne allows the bypass of high radiation interlocks.
Minin 1 detectable hydrogen concentration: SP 44.654.04 PSTG #3 Rev. 1 Page 32
Os SHOREHAM NUCLEAR POWER STATION '
Plant Specific Technical Guidelines Primary Containment Control EPG Stept If while executing the following steps the offsite radioactivity release rates reaches the offsite release rate LCO, isolate the primary containment vent and purge.
SNPS PSTG Step:
If while executing the following steps, 1Dll-PNL-19 signals a high alarm condition, isolate, or confirm, the isolation of the containment vent valves.
Justification for Differences / References Included the necessary guidance for the operating crew to be able to determine when the offsite release rate LCO is reached. 1D11-PNL-19isthecontaigment ')-
..n. -......i enich is set to isolate containment vent valves at 5.4 x 10 CPM.
PSTG #3 Rev. 1 Page 33
A SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/H-1.1 Refer to [ sampling procedure).
PC/H-1.2 .If suppression pool water level is below [26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)], vent the suppression chamber in accordance with [ procedure for primary containment venting).
If suppression pool water level is at or above [26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)) or if the suppression chamber cannot be vented, vent the drywell in accordance with [ procedure for primary containment venting).
I
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PC/h-1.3 If the suppression chamber or drywell can be vented:
o If drywell oxygen concentration is below 5%,
initiate and maximize the drywell nitrogen purge flow, o If drywell oxygen concentration is not below i 5%, initiate and maximize the drywell air
. purge flow.
PFTG #3 Rev. 1 Page 34
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Gm**elines Primary Containment Control SNPS PSTG Step:
PC/H-1.1 Refer to Section 8.2.6 of SP 23.425.01 to assess whether Radiochemistry Authorization is required prior to venting.
PC/H-1.2 If suppression pool water level is below Elevation 57 ft.',. vent the suppression chamber in accordance with SP 23.425.01, Section 8.2.6.
If suppression pool water level is at or above Elevation 57 ft., or if the suppression chamber cannot be vented, vent the drywell in accordance with SP 23.425.01, Section 8.2.6.
PC/H-1.3 If the suppression chamber or drywell can be vented, contact Radiochemistry and request saiv.i42 eaten to begin nitrogen purge. Maximize
['- nitrogen purge licw to the drywell after et authorization is received.
Justification for Differences / References PC/H-1.1 was expanded to clearly indicate that the following steps are not to be perfermed outside the normal administrative controls of station procedures.
PC/H-1.2 was altered to match the existing station procedures on venting the primary containment. The seccnd bullet item in PC/H-1,3 was deleted because thero is no means at SNPS to add air to the primary containment under normal cdainistrative procedures. Since this particular procedural step is explicitly stated to not require operators to take extraordinary measures, the adjustments made cre justified. PC/H-1.3 was altered to delete the conditional action based en Oxygen Concentration. This is unnecessary since an air purge is not permitted.
- Elcyction of the bottom of the suppression chamber vent: SP 84.654.03, penetration X-29.
PSTG #3 Rev. 1 Page 35
4:
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
Execute [ Steps PC/H-2 and PC/W-3] concurrently.
SNPS PSTG Step:
Execute Steps-PC/H-2 and PC/H-3 concurrently.
-[
h Justification for Differences / References N/A 1
i J
PSTG #3 Rev. 1 Page 36 l
SHOREHAM N11 CLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/H-2 Monitor and control hydrogen and oxygen concentrations in the drywell.
PC/H-2.1 When drywell hydrogen concentration reaches (1%
(minimum hydrogen concentration for recombiner operation or minimum detectable hydrogen concengration, whichever is higher)) but only if drywel,1 hydrogen concentration is below (6%
(maximum hydrogen concentration for recombiner operation or 6%, whichever is lower)) or drywell oxygen concentration is below [5% (maximum oxygen concentration for recombiner operation or 5%,
whichever is' lower)), place hydrogen recombiners in service taking suction directly on the drywell and cperate the drywell hydrogen mixing system.
'S PSTG Stept
('x PC/H-2 Monitor and control hydrogen and oxygen concentrations in the drywell.
PC/H-2.1 When drywell hydrogen concentration reaches 0.5%
but only if drywell hydrogen concenctation is below 6% or dryvell oxygen concentration is below 5%
- place the hydrogen recombiners in service taking
> - suction directly on the drywell. (#6)
Justification for Differences / References The Rockwell Hydrogen Recombiner can recombine hydrogen and oxygen even when concontrations of hydrogen are below the minimum detectable level, since the electric heaters will provide the necessary thermal requirements even though the recction is not necessarily self sustaining (
Reference:
Rockwell manual T48-1).
Minicum detectable hydrogen concentration: SP 44.654.04.
Maxitum Hydrogen and Oxygen concentration for recombir.er operation: Vendor 3:nual Rockwell Hydrogen recombination system. T48-1, -2, -3, -4.
D21sted instructions to operate "drywell hydrogen mixing systems" since as described in Appendix B. "The mixing systems referred to in this guideline are
- cr-driven fans, dampers, and duct work..." SNPS has no su-h system, aeference: FSAR Section 6.2.5.2.1 Addsd cautionary guidance for EDG 3300 KW concern.
PSTG #3 Rev. 1
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Stept PC/H-2.2 When drywell hydrogen concentration reaches [6%
(maximum hydrogen concentration for recombiner operation or 6%, whichever is louer)) and drywell oxygen, concentration reaches [5% (maximum oxygen concentration for recombiner operation or 5%,
whichever is lower)), secure any hydrogen recombiner taking suction on the drywell.
PC/H-2.3 Continue-in this procedure at [ Step PC/H-4).
S EPG Stept PC/H-2.2 When drywell hydrogen concentration reaches 6% ar.d dryvell oxygen concentration reaches 5%. eccure any hydrogen recombiner taking suction on the dryvell.
FC/H-2,3 Continue in this procedure at Step PC/H-4.
Justification for Differences / References Maxitum hydrogen concentration for recombiner operation - Vendor manual, Rockwell Hydrogen Recombination System. T48-1, 2, 3, 4.
l PSTG #3 Rev. I rwnJn
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e SHORERAM NL' CLEAR POWER STATION s
Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/H-3 Monitor and control hydrogen and oxygen concentrations in the suppression chamber.
PC/H-3.1 When suppression chamber hydrogen concentration reaches [1% (minimum hydrogen concentration for recombiner operation or minimum detectable hydrogen concentration, whichever is higher)) but only xf suppre'ssion chamber hydrogen cor. centration is below
[6% (maximum hydrogen concentration for recombiner operation or 6%, whichever is lower)) or suppressf on chamber oxygen concentration is below (5% (maximum oxygen concentration for recombiner operating or 5%, whichever us lower)), place hydrogen recombiners in service taking suction directly on the suppression chamber.
SNPS PSTG Stept PC/H-3 Monitor and control hydrogen and oxygen concentrations in the suppression chamber.
PC/H-3.1 When suppression chamber hydrogen concentration reaches 0.5% but only if suppression chamber hydrogen concentration is below 6% or suppression
! chamber oxygen concentration is below 5%, place hydrogen recombiners in service taking suction directly on the suppression chamber. (#6) l ~ Jus?$fication f_or, Differences / References
- see Ster PC/H-2.1 i
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PSTG #3 Rev. 1
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SHORERAM NUCLEAR POWER STATION Plant Specific Technical Guidelines 3
Primary Containment Control EPG Step:
PC/H-3.1 If no hydrogen recombiner can be placed in service taking suction directly on the suppression chamber but only if the drywell hydrogen concentration is below [6% (maximum hydrogen concentration for recombiner operation or 6%, whichever is lower)),
or dryvell oxygen concentration is below [5%
+ (maxim,um oxygen concentration for recombiner operation or 5%, whichever is lower)), place hydrogen recombiners in service taking suction indirectly on the suppression chamber by way of the drywell.
SNPS PSTG Step:
PC/H-3.1 If no hydrogen recombiner can be placed in servi'ce taking suction directly on the suppression chamber
(' (Con't) but only if the dryvell hydrogen concentration is below 6% or drywell oxygen concentration is below 5%, place hydrogen recombiners in service taking suction indirectly on the suppression chamber by way of the drywell.
[ustificationforDifferences/ References M:xitum hydrogen / oxygen concentration for recombiner operation - Vendor Manual.
Rockwell Hydrogen recombination system. T48-1, 2, 3, 4.
PSTG #3 Rev. I rwvvve _
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step PC/H-3.2 When suppression chamber hydrogen concantration reaches [6% (maximum hydrogen concentration for recombiner operation or 6%, whichever is lower))
and suppression chamber oxygen concentration reaches [5% (maximum oxygen concentration for recombiner operation or 5%, whichever is lowor)),
secure all hydrogen recombiners taking suction directly on the suppression chamber.
SNPS PSTG Step:
PC/H-3.2 When suppression chamber hydrogen concentration reaches 6% and suppression chamber oxygen
(, concentration reaches 5%, secure all hydrogen recombiners taking suction directly on the suppression chamber.
Justification for Differences / References Mtximum hydrogen / oxygen concentration for recombiner operation - Vendor manual, hockwell Hydrogen Recombination System, IT48-1, 2, 3, 4.
PSTG #3 Rev. 1 Pane 41
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
l'.'h:n drywell or suppression chamber hydrogen concentration reaches 6% and drywell or suppression chamber oxygen concentration is above 5%,] EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter (procedure ??7 eloped from the RPV Control Guideline) at (Step RC-1] and execute it concurrently with this procedure; secure hydrogen mixing systems and, irrespective of.the offsite radioactivity release rate, vent and purge the primary containment, defeating isolation interlocks if ne~cessary, to restore and maintain drywell and suppression chamber hydrogen concentrations below 6% or drywell and suppression chamber oxygen concentrations below 5% as follows:
SNPS PSTG Step:
PC/H-4 When drywell or suppression chamber hydrogen concentration #$b reaches 6% and drywell or suppression chamber oxygen concentration is above 5% EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concorrently with this procedure; and, irrespective of the offsite radioactivity release rate, vent and purge the primary containment, defeating isolation interlocks if necessary, to restore and maintain drywell and suppression chamber hydrogen concentrations below 6% or drywell and suppression chamber oxygen concentrations below 5% as follows:
.inerification for Differences / References
~' '
---. fer cecuring the hydrogen mixing systems has been deleted beu.a. at SNPS these a : the drywell and suppression pool sprays. Since the enly reason the EPGs specify securing the mixing systems was to remove possible d2flagration ignition sources, there is no reason to secure sprays at SNPS.
Further, later H e ntr 1 guidaace (Step PC/H-4.1) will specify when to initiate 2
spreys.
PSTG #3 Rev. 1 Page 42 _ _ _ .
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control
'EPG Step:
If while executing the following steps suppression pool or drywell sprays have been initiated and:
o Suppression chamber p.ressure drops below [2.0 psig (high drywell pressure scram setpoint)), terminate suppression pool sprays.
o Drywell pressure drops below [2.0 psig (high drywell pressure scram setpoint)),
terminate drywell sprays. '
w..PS PSTG Step:
If while executing the following steps suppression pool or drywell sprays have been initiated and:
o Suppression chamber pressure drops below 1.69 psig terminate suppression -
pool sprays.
o Drywell pressure drops below 1.69 psig terminate drywell sprays.
Justification for Differences /Refereness N/A PSTG #3 Rev. 1 Page 43
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,' w 'SHOREHAM NUCLEAR' POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step PC/H-4.1 If suppression pe91 water level is belev l24 ft. 6 in. (elevation.oi suppression pool sprar oorales)],
initiate suppretsion pools sprays insing only those RHk pumps not required to assure adegaste core cooling by continuous operation the LPCI mode).
SNPS PSTG Step: ,
PC/H-4.1 If supprestion pool water level is below Elevatica 50 ft., initiate suppression pool sprays using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode.
Justification for Differences / References Elevation of suppression pool spray nozzles: SWEC Drawing 11600.02-FP-200NN.
PSIG f3 Rev. 1 Page 44
'. SHOREHAM NUCLEAR P0k'ER STATION Plant Specific Technical Guf.delines Primary Conta.inment Control ,
r EPG Stept ,
ve/u-4.2 If suppression pool water level is below (26 ft. 9 in. (elevation of the bcttom of the suppression chamber vent)), vent the suppression chamber in accordance with [ procedure for primary containment venting).
Ifsu[pressionpoolwaterlevelisatorabove(26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)) or if the suppression -
chamber cannot be vented, vent the drywell in ;
accordance with (procedure for primary containment venting).
SNPS PSTG Step PC/H-4.2 7f suppression pool water level is below Elevation j 37 ft., vent the suppression chambe: ' recordance with SP 23.418.01, Sectiot. 8.2.1. ;
If suppression pool vater level is at or above Elevation 57 ft., or if the suppression chseber cannot be vented, vent the drywell in accordance with 57 23.418.01, Section 8.2.1.
I Justification for Differences / References Elevation of the bottom of the suppressi::n chamber vent - SP 84.654.03, pot... .Livn X-29 and XS-22.
ll PSTG #3 Rev. 1 Page 45 ,
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical'Guidel'ines Primary Containment Control EPG Step:
PC/H-4.3 If the suppression chamber or drywell can be vented, initiate and maximize the dryvell purge flow.
SNPS PSTG Step: ,'
PC/H-4.3 If the suppression chamber or drywell can be vented, initiate and maximize the drywell purge flow through all available purge valves defeating isolation interlocks if necessary.
- S tifica *.ic, far Differences / References The step has been altered to include the necessary guidance to get air into the containment during conditions which would otherwise preclude opening the purge velves.
PSTG #3 Rev. 1 Page 46
SHOREHAM NUCLEAR POWER STATION 7 Plant Specific Technical Guidelines Primary Containment Control l
EPG Step: 1 1
PC/H-4.4 If (suppression pool water level is below (17 ft. 2 in. (elevation of bcttom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)) and) drywell temperature and pressure are within the Drywell Spray Initiation Limit, (shut down i recireplation pumps and drywell cooling fans and) l initiate drywell sprays (using only those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode).
SNPS PSTG Step:
PC/H-4.4 If suppression pool water level is below Elevation 50 ft, and drywell temperature and pressure are within the Drywell Spray Initiation Limit (Figure I), shut down recirculation pumps and drywell cooling fans and initiate drywell sprays using only those RHR pumps not required to assure adequ s core cooling by continuous operation in the Lasl mode.
Justification for Differences / References Elsvation of bottom of internal suppression chamber to drywe.'.1 vacuum breakers less vacuum breaker opening pressure in feet of water - see DW/T-2.
PSTG #3 Rev. 1 Page 47
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,' SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
!H-> When drywell or suppression chamber hydrogen concentration cannot be restored and maintained below 6% and drywell or suppression chamber oxygen concentration cannot be restored and maintained below 5%, then irrespective of whether adaquate core cooling is assured:
SNPS PSTG Step:
PC/H-5 When drywell or suppression chamber hydrogen concentration cannot be restored and maintained below 6% and drywell or suppression chamber oxygen concentration cannot be restored and meintained below 5%, then irrespective of whether adequate core cooling is assured:
I -
l Justification for Differences / References N/A i
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PSTG #3 Rev. 1 Page 48
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,' SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
7f while executing the following steps st,spression pool or drywell sprays have been initiated and:
o Suppression chamber pressure drops below (2.0 psig (high drywell pre m re scram secpoint)), termintte stir;aession pool sprays, o Drywell pressure d. ops below (2.0 psig (high drywell pressure scram setpoint)],
terminate drywell sprays.
'"PS PSTG Step:
If while executing the following steps suppression pool or drywell sprays have been initiated and:
o Suppression chember presr Jrops below 1.69 psig, terminate sur , ion pool sprays.
o Drywell pressure drops below 1.69 psig, terminate drywell sprays.
. Justification for Differences / References High dryvell pressure scrarr setpoint - Tech Spec table: 2.2.1-1 l
! PSTG #3 Rev. 1 Page 49
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
PC/H-5.1 If' suppression pool water level is below (24 ft.
6 in. (elevation of suppression pool spray '
nozzles)], initiate suppression pool sprays.
SNPS PSTG Step: .
PC/H-5.1 If suppression pool water level is below Elevation 50 ft., initiate suppression pool sprays.
Justification for Differences / References
_g ~"svation of suppression pool spray nozzles: SWEC drawing 11600.02-FP-200NN.
\
-se ~
1 PSTC #3 Rev. 1 Page 50
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Primary Containment Control EPG Step:
- /U-5.2 If (suppression pool water level is below (17 ft.
2 in. (elevation of bottom of internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)) and) drywell temperature and pressure are within the Drywell Spray Initiation Limits, (shut down recir-culation pumps and drywell cooling fans and) initiate drywell sprays.
SNPS PSTC Step:
PC/H-5.2 If suppression pool water level is below Elevation 50 ft., and drywell temperature and pressure are within the Drywell Spray Initiation Limit (Figure I) shut-down recirculation pumps and drywell cooling fans and initiate drywell sprays.
i sos.........t. for Differences / References Elsvetion of bottom of internal suppression chamber to drywell vacuum breakers lsss vacuum breaker opening pressure in feet of water. (See DW/T-2)
PSTG #3 Rev. 1 Page 51
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