ML20151D419
| ML20151D419 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/13/1988 |
| From: | Newson C LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20151D407 | List:
|
| References | |
| PROC-880713, NUDOCS 8807250109 | |
| Download: ML20151D419 (16) | |
Text
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MC-1 SHOREHAM NUCLEAR P0k'ER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #1 INTRODUCTION AND OPERATOR PRECAUTION REVISION NO: 1 e
DATE:
6/Jo /r5 PREPARED BY:
d!8d!88 REVIEk'ED BY:
, (J 7. MhM DATE:
7 // /k OPERATING ENGINEER APPROVAL: Mw DATE:
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SHOREHAM KVCLEAR POWER STATION Plant Specific Technical Guidelines INTRODUCTION Ths Shoreham PSTG's have been developed utilizing Revision 4 of the BWR Owners Group's Emergency Procedure Guidelines.
The PSTG's are written to show in sufficient detail, the flow of information from its analytic base to its use as a technical guidsline.
The format of the PSTG's shows each BWROG EPG step, the corresponding PSTG step (including Shoreha= specific systems, components, data, etc.), and a justification for any differences between the two.
References are provided and are drawn from the following source documents:
o Shoreham Technical Specifications Shoreham Safety Analysis Report o
o As-built plant drawings o
Nuclear Engineering Department Calculations (using the above source documents) o Currently Approved Shoreham Station Procedures fNs o
Shoreham Probalistic Risk Assessment s
Tha PSTGs will form the technical bridge between the Shoreham specific design and the Owners Group's EPG's, and provide the necessary audit trail to ceet the requirements of NUREG-0S99. Together with the Writer's Guide, the PSTGs will be utilized to develop symptom oriented, Human Factored, Emergency Operating Procedures for the Shoreham Nuclear Power Station.
The following symptomatic Plant Specific Technical Guidelines have been developed from the BWROG EPGs:
o RPV Control Guideline o
Primary Containment Control Guideline o
Secondary Containment Control Guideline o
Radioactivity Release Control Guideline PSTG #1 Rev. 1 PaF0 1
e SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Tha RPV Control Guideline maintains adequate core cooling, shuts down the reactor, and cools down the RPV to cold shutdown conditions.
This guideline is entered whsnever low RPV water level, high RPV pressure, or high drywell pressure occurs, or whenever a condition which requires reactor scram exists and reactor power is above thz APRM downscale trip or cannot be determined.
The Primary Containment Control Guideline maintains primary containment integrity and protects equipment in the primary containment with respect to the consequences of all machanistic events. This guidelipe is entered whenever suppression pool temperature, drywell temperature, drywell pressure, suppression pool water level, or primary containment hydrogen concentration is above its high operating limit or suppression pool water level is below its low operating limit. Suppression pool, and drywell, temperatures are determined by plant-specific procedures for determining bulk cuppression pool water temperature,.drywell atmosphere average temperature, respectively.
Tha Secondary Containment Control Guideline protects equipment in the secondary containment, limits radioactivity release to the secondary containment, and either naintains secondary containment integrity or limits radioactivity release from the escondary containment. This guideline is entered whenever a secondary containment temperature, radiation level, or water level is above its maximum normal operating value or secondary containment differential pressure reaches zero.
C*heRadioactivityReleaseControlGuidelinelimitsradioactivityreleaseintoareas
.tside the primary and secondery containments.
This guideline is entered whenever
'offsite radioactivity release rate is above tha't which requires an Alert.
. Table 1 is a list of the abbreviations used in the guidelines.
At various points throughout these guidelines, operator precautions are noted by the symbol:
If1 Ths number within the box refers to a numbered "Caution" contained in the Operator Procautions section.
These "Cautions" are brief and succinct red flags for the oporator.
At verious points within these PSTGs, limits are specified beyond which certain actions are required. While conservative, these limits are derived from engineering analvaan utilizing best-estimate (as opposed to licensing) models. Consequently, thesa limits are generally not as conservative as the limits specified in a plant's Techrical Specifications. This is not to imply that operation beyond the Technical Sp=cliications is recommended in any emergency.
Rather, such operation is required cnd is now permitted under certain degraded conditions in order to safely mitigate the consequences of those degraded conditions. The limits specified in the PSTGs establish the boundaries within which continued safe operation of the plant can be essured.
PSTG #1 Rev. 1 Page 2
e e
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines At other points within these PSTG's, defeating safety system interlocks and initiation logic is specified. This is aise required in order to safely mitigate the consequences of degraded. conditions, and it is generally specified only when conditions exist for which the interlock or logic was not designed.
Bypassing other intorlocks may also be required due to instrument failure, etc., but these interlocks cannot be identified in advance and are therefore not specified in the PSTGs.
Tha entry conditions for these PSTGs are symptomatic of both emergencies and events which may degrade into emergencies.
The guidelines specify actions appropriate for both. Therefore, entry into procedures developed from these guidelines is not conclusive that an emergency has occurred.
Each procedure developed from these PSTGs is entered whenever any of its entry conditions occurs, irrespective of whether that procedure has already been entered or is presently being executed.
The procedure is exited and the operator returns to non-emergency procedures when either of the exit condicions specified in the procedure is satisfied or it is determined that an emergency no longer exists.
For extmple, the procedure developed from the RPV Control Guideline specifies cooldown to cold shutdown conditions by various methods and exit after the shutdown cooling interlocks have cleared, but entry into this procedure does not require any cooldown if it can be determined that an emergency no longer exists prior to establishing the dicions required to co=mence the cooldown as specified in the procedure. After a
,.ocedure developed from these guidelines has been entered, subsequent clearing of all entry conditions for that procedure is not, by itself, conclusive that an cmsrgsney no longer exists.
PSTG #1 Rev. 1 Page 3
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines TABLE I PSTG ABBREVIATIONS ADS Automatic Depressurization System APRM Average Power Range Monitor
.aI Alternate Rod Insertion CRD Control Rod Drive CS Core Spray ECCS Emergency Core Cooling System HPCI High Pressure Coolant Injectica UVAC Heating, Ventilating and Air Conditioning LCO Limiting Condition for Operation LPCI Low Pressure Coolant Injection HSIV Main Steamline Isolation Valves NPSH Net Positive Suction Head RBSVS Reactor Building Standby Ventilation System RENVS Reactor Building Normal Ventilation System RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal RPS Reactor Protection System RPV Reactor Pressure Vessel Rod Sequence Control Syss?m asts ot'rti Reactor Water Cleanup RWM Rod Worth Minimizer SLC Standby Liquid Control SRV Safety Relief Valve PSTG #1 Rev. 1 Page 4
SHOREHAM NUC' LEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #1 An RPV water level instrument may be used to determine RPV water level only when al
...,.o..citzons are satisfied for that instrument:
1.
The temperatures near all the instrument runs are below the RPV Saturation Temperature.
2.
For each of the instruments in the following table, the instrument reads above the Minimum Indicated Level or the temperatures near all the instrument reference leg vertical runs are below the Maximum Run Temperature.
Maximum Run Minimum Temperature (*F)
Indicat'd Instrument Range (in.)
[ Fuel Zone
-317 to -17 376 NA
-305
)
3.
For each of the following instruments, the instrument reads above the Minimum Indicated Level associated with the highest temperature near an instrument reference leg vertical run:
.. arrow Range (0 to 60 in.)
o.
Highest Drywell Run Minimum Temperature ('F) Between Indicated Low High Level (in.)
286 0
286 350 5
350 450 14 450 550 26 1
PSTG #1 Rev. 1 Page 5
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-SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Steps (Con't)
CAUTION (1 b.
Wide Range (-150 to +60 in.)
Highest Drywell Run Minimum Temperature ('F) Between Indicated Low High Level (in.)
128
-150 128 250
-140 25s 350
-131 350 450
.20 450 550
-107 c.
Shutdown Range (-17 to +383 in.)
Highest Drywell Run Minimum Temperature ('F) Between
. Indicated Low High Level (in.)
150 10 150 250 23 250 350 41 350 450 65 450 550 98
'SNPS PSTG Step:
CAUTION #1 An RPV water level instrument may be used to determine RPV water level only when all the following conditions are satisfied for that instrument:
' 1 '. - ~The temperatures near all the instrument runs are below the RPV Saturation Temperature.
(RPV Saturation Curve - Figure A) 2.
For each of the instruments in the following table, the instrument reads above the Minimum Indicated Level or the temperatures near all the instrument reference leg vertical runs are below the Maximum Run Temperature.
PSTG fl Rev. 1 Page 6
r; SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions SNPS PSTG Step:
(Con't)
CAUTION #1 Maximum Run Minimum Temperature (*F)
Indicated Instrument Range (in.)
Fuel Zone A & B
-310 to -110 NA 328
-302.7 Wide Range A 6 B
-150 to 60 NA 132
-121.0 Narrow Range A 6 B 0 to 67 NA 207 7.2 3.
For each of the following instruments, tne instrument reads above the Minimum Indicated Level associated with the highest temperature near an instrument reference leg vertical run:
a.
Shutdown Range (0 to 400 in.)
Highest Drywell Run Minimum f'-
Temperature (*F) Between Indicated
(
Low High Level (in.)
100 9.5 100 150 20.8 150 200 36.1 200 250 54.3 250 300 75.5 300 350 99.6 350 450 158.2 450 550 248.7 b.
Upset Range (0 to 180 in.)
Highest Drywell Run Minimum Teeperature ('F) Between Indicated Lov High Level (in.)
150 0
150 200 19.8 200 250 43.3 250 300 70.8 300 350 102.0 350 400 137.4 400 550 Useless PSTG #1 Rev. 1 Page 7
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Justification for Differences / References RPV Saturation Temperature: Derived from ASME steam tables, Properties of Saturated Storm and Saturated Water.
Wster Level Instrument Data: NED Appendix C Calculation No. C-NAD-274.
+
f PSTG #1 Rev. 1 Page 8
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #2
[Hseted Reference leg instruments) may not be used to determine RPV water level during rapid RPV depressurization below 500 psig.
SNPS PSTG Step:
Nons
'~
Justification For Differences /
References:
Th2 Shoreham Nuclear Power Station does not utilize heated reference leg instrueertation.
(FSAR Section 5).
i PSTG #1 Rev. 1 Page 9
r SHOREHAM NUCLEAR POWER SIATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #3 Oparating HPCI or RCIC turbines below [2200 rpm (minimum turbine speed limit per
.aor canuel)J may~ result in unstable system operation and equipment damage.
SNPS PSTG Stepj_
CAUTION #2 Opsrating HPCI or RCIC turbines below 2200 rpm may result in unstable system opsration and equipment damage.
Justiticativn For Differences /
References:
Minimum turbine speed per turbine vendor manual - Station Procedures 23.202.01 and 23.119.01 Terry Turbine Manuals:
1E41-1, IE51-1 PSTG fl Rev. 1 Page 10
GHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #4 Elevated suppression chamber pressure may trip the RCIC turbine on high exhaust crassure.
SNPS PSTG Step:
CAUTION #3 Elevated suppression chamber pressure may trip the RCIC Turbine on high exhaust pressure.
Just_ification,For Differences /
References:
N/A POTG f1 Rev. 1 Page 11 Q
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #5 If HPCS is taking suction from the suppression pool and suppression pool temperature axeseds the HPCS Pucp NPSH Limit, the pump may be damaged and become inoperable.
SNPS PSTG Step:
None Justification For Differences /
References:
The Shoreham Nuclear Power Station is a BWR 4 and does not have a HPCS.
(FSAR Section 6.3)
PSTG i'l Rev. 1 Page 12
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #6 Cooldown rates above [100'F/hr (RPV cooldown rate LCO)} may be taquired to accomplish this step.
SNPS PSTG Step:
CAUTION #4 Cooldown rates above 100'F/hr may be required to accomplish this step.
Justification For D'.fferences/
References:
RPV cooldown rate LCO - Shoreham Technical Specification section 3.4.6.
'l PSTG fl Rev. 1 Page 13
SHOREHA!! NUCLEAR P0k'ER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
CAUTION #7 A r pid increase in injection into the RPV may induce a large power excursion and rssult in substantial core damage.
SNPS PSTG Step:
CAUTION #5 A rapid increase in injection into the RPV may induce a large power excursion and rcsult in substantial core damage.
Justification For Differences /
References:
N/A l
l PSTG fl Rev. 1 i
Page 14 l
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SHOREHAM NUC1. EAR POWER STATION Plant Specific Technical Guidelines Operator Precautions EPG Step:
None SNPS PSTG Step CAUTION #6 If a (equipment name) is started with its associated Emergency Diesel Generator Lord greater than [KW value] KW, then 3300 KW may be exceeded.
l# I Equipment Name KW Value
[
CRD Pump 3050 KW RHR Pump 2250 KW Hydrogen Recombiner 3150 KW Drywell Cooling System 3200 KW RWCU Pu=p 3250 KW RBCLCW Pump 3200 KW Justification for Differences / References This SNPS specific caution has been added as a result of the derating of the TDI Emergency Diesel Generators to 3300 KW.
Its purpose is to alert operators that by starting a piece of equipment not normally required during design basis cvents may cause diesel loading to exceed 3300 KW, Thi caution will be inserted before each step in which operation of equipment may be called for during a design basis accident. The equipment must be powered by ezergency buses and not be already included on the Bus Program Logic.
Extnples of equipment which falls into this category are CRD pumps, RWCU pumps, Hydrogen Recombiners and Drywell Coolers. Additional equipment may be preceded by c ca.ution at the discretion of the Operating Engineer.
Equip 3ent vs KW Value SNPS SAR Section 8.3 (Table 8.3.1-1)
SP 29.015.01, Loss of Offsite Power PSTG fl Rev. I Page 15
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