ML20151D562
| ML20151D562 | |
| 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-880713-01, NUDOCS 8807250161 | |
| Download: ML20151D562 (6) | |
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.SHOREHAM NUCLEAR POWER STATION PLANT SPECIFIC TECHNICAL GUIDELINES PSTG #7 EMERGENCY DEPRESSURIZATION REVISION NO: 2 PREPARED BY:
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 2 Emergency RPV Depressurization uu s.=g; C2-1 When either: [f2 f6) Any control rod cannot be determined to be inserted to or beyond o position (02 (Maximum Suberitical Banked Withdrawal Position)) and it has not been determined that the reactor will remain shutdown under all conditions without boron and all injection into the RPV except from boron injection systems, CRD, and RCIC has been terminated and prevented, or All control rods are inserted to or beyond position [02 (Maximum o Suberitical Banked Withdrawal Position)) or it has been determined that the reactor will remain shutdown under all conditions without boron, SNPS PSTG Step: C2-1 When either: [ #4 ) c Any control rod cannot be determined to be inserted to or beyond position 02 and it has not been determined that the reactor will remain l shutdown under all conditions without boron and all injection into the RTV except from boron injection systems, CRD, and RCIC has been terminated and prevented, or o 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, Justification For Differences / References haxacuu suberitical Banked Withdrawal Position: NED Appendix C Calculation No. C-NFD-200. PSTG #7 Rev. 2 Page 1
V e: SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 2 Emergency RPV Depressurization EPG Stept -C2-1.1 If a high drywell pressure ECCS initiation signal ((2.0 psig (drywell pressure which initiates ECCS))) exists, prevent injection from those LPCS and LPCI pumps not required to assure adequate core tooling. C2-1.2 Initiate IC. C2-1,3 If suppression pool water level is above (4 ft. 9 in. (elevation of top of SRV discharge device)): o Open all ADS valves, If any ADS valve cannot be opened, open other SRVs until [7 (number of o SRVs dedicated to ADS)) valves are open. SNPS PSTG Step: C2-1.1 If 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. C2-1.2 If suppression pool water level is above -84 in.: o Open all ADS valves, If any ADS valve cannot be opened, open other SRVs until 7 valves are o open. Justification for Differences / References Icolation Condenser step deleted. (N/A to SNPS) Drywell pressure which initiates ECCS: Tech Spec Table 3.3.3-2. Top of SRV discharge device: SWEC Dwg. No. 11600.02-FP-200NN Number of SRVs dedicated to ADS: Tech Spec Section 3.5.1.d. Although the top of the SRV discharge device is at -144 inches. -84 inches is the bottom of the range for the suppression pool water level instrumentation in the Control Room. PSTG #7 Rev. 2 Page 2
o SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 2 Emergency RPV Depressurization EPG Stept C2-1.4 If less than [3 (Minimum Number of SRVs Required for Emergency Depressurization)) SRVs are open (and RPV pressure is at least 50 psig (Minimum SRV Reopening Pressure) above suppression chamber pressure), rapidly depressurize the RPV, defeating isolation interlocks if necessary, using one or more of the following: o Main condenser o RHR (steam condensing mode) o [0ther steam driven equipment] o Main steam line drains o HPCI steam line o RCIC steam line o Head vent o IC tube side vent If RPV water level cannot be determined, enter (procedure developed from Contingency f4]. SNPS PSTG Step C2-1,3 If less than 4 SRVs are open and RPV pressure is at least 50 psig above suppression chamber pressure, rapidly depressurize the RPV, defeating isolation interlocks if necessary, using one or more of the following: o Main condenser o RHR (stsam condensing mode) o Feedwater o Main steam line drains o HPCI steam line o RCIC steam line o Head vent If RPV water level cannot be determined, enter procedure developed from Contingency #4. PSTG #7 Rev. 2 Page 3
SHOREHAM NUCLEAR POWER STATION i Plant Specific Technical Guidelines Contingency i 2 Emergency RPV Depressurization Justification for Differences / References Minimum Number of SRVs Required for Emergency Depressurization: NED Appendix C 1 t Calculation No. C-NAD-269. Minirum SRV Reopening Pressure: NED Appendix C Calculation No. C-NAD-271.
- b Dsisted "IC tube side vent". N/A to SNPS.
t C i h i 1 PSTG #7 Rev. 2 Page 4
e. SHOREHAM NUCLEAR' POWER STATION Plant Specific Technical Guidelines , Contingency # 2 Emergency RPV Depressurization EPG Stept C2-2 When either: o All control rods are inserted to or beyond position (02 (Maximum Suberitical Banked Withdrawal Position)), or o it has been determined-that the reactor will remain shutdown under all conditions without boron, or (280 pounds-(Cold Sherdown Boron Weight)) of boron have been injected o into the RPV, or The reactor is shutdown and no boron has been injected into the RPV, o enter [ procedure developed from the RPV Control Guideline) at (Step RC/P-4]. SNPS PSTG Step: C2-2 When eithers o All control rods are inserted to or beyond position 02, or o It has been determined that the reactor will remain shutdown under all conditions without boron, or The entire contents of the SLC tank have been injected into the RPV, or o The reactor is shutdown and no boron has been injected into the RPV, o enter procedure developed from the RPV Control Guideline at Step RC/P-4. Justification for Differences / References Max. Suberitical Banked Withdrawal Position: NED Appendix C Calculation No. C-NFD-200 Roworded statement dealing with the Cold Shutdown Boron Weight to require the entire contents be injected. This is conservative and justified since with enriched sodium penteborate the entire contents of the tank is less than 1500 gal. PSTG #7 Rev. 2 Page 5}}