|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
[Table view] |
Text
F
.tittad: SP Numbar: 29.015.02 (Section hard)
Revision: C
~
(Plant Manager) Date Effective:
~ STATION BLACKOUT EMERGENCY PROCEDURE S77 j* [
3 L
1.0 SY11PTOMS
1.1 Lose of both normal and reserve station power.
1.2 Failure of all Emergency Diesel G2nerators to re-energize any of the emergency AC buses.
2'. 0 ~ AUTOMATIC ACTIONS:
2.1 Reactor Scram 2.2 Main Turbine Trip 2.3 NSSSS Isolation
- 2. 4 - 125V AC Uninterruptible Power Supplies (UPS #1 & 2) switch to 125V DC batteries.
3.0 IMMEDIATE ACTION:
3.1 Initiate SP29 919 01 Emergency Shutdown.
3.2 Enter. SP29.923 91 (Level Control) as necessary to maintain <C reactor water level betweem 29"-59".
CAUTION: HPCI and RCIC are the only means available to restore reactor water level.
3.3 Enter SP 29 923 95 (RPV Depressurization) as necessary to Itduce and maintain RPV pressure at 199#-159#.
CAUTION: Depressurization should not result in a cooldown rate in excess of 199'F/ER.
3.4 Notify the system operator that a station blackout exists.
~_
['N
,jn.!.. . . r - [8*3 % y
~n ' ,
$b - '*i'
. $' ,3c # 55, p e107230270 e10720 f /;2 [6 $DRADOCK 05000322 PDR ,
t- t 4.0 SUBSEQUE'IT ACT10t!S (C
- 4. -1 Stabilize _ plant conditions by performing the following:
4.1.1 Secure the HPCI pump if the RCIC pump is available to maintain RPV level.
-NOTE: If the RCIC pump trips en high.RPV level (58.75"), the trip throttle valve must be reset by running 1E51*MOV-944 to the full close position and then slowly re-open.
4.1.2 Adjust RCIC pump speed to maintain RPV level between-29"-59~. Do not reduce spr.ed below 2259 RPM.
4.1.3 Cy;1e SRV's as necessary to maintain RPV presau t between 1998-1599 NOTE: - Steps 4.2, 4.3, and 4.4 should be perforoad con-currently.- If AC power is rcetored to any of the emergency AC buses, refer to SP 29 915.91, Loss of Off-site Power.
, '4. 2 - . Verify the following equipment starts:
4.2.1 thin Turbine Emergency Lube Oil Pump .
4.2.2 Hydrogen Seal Oil Em.'rgency Lube Oil Pump 4.2.3 RFP Turbine A Emergency Lube Oil imp 4.2.4 RFP Turbine B Emergency Lube Oil Pump _
4.2.5 MG Set 1A Emergency Lube Oil Pump 4.2.6 MG Set IB Emergency Lube Oil Pump
~
4.3 . Start'the_ Emergency Diesel Generators from the Control Room to re-energize the emergency AC buses.
'4.3.1 If the Emergency Diesel Generators will not start from the Control Room, proceed to the Diesel Cenerator Rooms and perform the following:
NOTE: Preferred starting sequence is 191, then 192, then 193.
4.3.1.1 Verify DC control power breakers in control cabinet 1R43*PNL-DG1 (2, 3) are closed.
SP 29 915.92 Rev. C
/ / Page 2
- p 4r m.r- - - ,-g p-yr=-y , w , . 3ge-y-- - w <iw. -%y- w- w
4.3.1.2 Placs tha moda esisctor in local and dsprass <C th2 etart pushbutton for at lanat 3 escends.
4.3.2 _ If the emergency diesels are running, but the buses are not energized, proceed to the Switchgear Rooms'and locally close the diesel generator tie breakers.
4.4 ' .1Line-up the RHR heat- oxc'nangers for steam condensing by performing the following:
4.4.1 Manually close the following valves:
4.4.1.1- IP41*29V-9997A (B), RHR Hx Service Water inlet.
4.4.1.2 1E11*MOV-933A (E), RHR Ex Shell Side inlet.
4.4.1.3 1E11*MOV-935A (B),' RRR Ex Shell Side Outlet.
4.4.2 Connect a 21/2 inch fire hose between hose reel supply
~ valve IM43-93V-(Later) and RHR Hx -Flush Connection
' 1P41*92V-3991A (B).
4.4.3 > .tianually open the following valves:
-4.4.3.1 . 1E11*MOV-955A (B) and 1E11*MOV-956A (B) RHR Hx
- Vents.
4'.4.3.2 1E11*MOV-914A (B) RHR Hx Drain to Suppression Pool.
4.4.3.3 - 1E11*MOV-934A (B) RHR Ux Service Water Outlet.
~
4.4.3.4' 1E11*MOV-949 RHRS Steam Inlet Valve.
4.4.3.5 1P41*$2V-3991A (B) RHR Hx Flush Connection.
4.4.3.6 - 1H43-93V-(Later) Fire Water to Hose ' Reel.
-4.4.4 Start the diesel driven fire pump, IM43-P-958, if
- not running due to low header pressure.
I 4.4.5 Manually open IE11*PCV-997A (B) to lower RRR Hx Water Level to es3/4-level.
j 4.4.6 Slowly open IE11*PCV-993A (B) to raise RRR Hx Steam Pressure'to re125 psig.
CAUTION: Do not exceed 499*F or 459 psig at the shell.
side of 6he RHR heat exchanger.
SP 29.P15 92 Rev. C l: / -/ Page 3 I
- -r p-4 -,e sm ,, .--~ ,:,_-,,-,- m, --
,~w,--v-,.c, ye-,y--+-s,-w-,-c. ew,*-,, meym --
, 4.4.7 Adjust RHR lix lsval for ths nsetacary amount of stema <C candInsing rcquired to maintain RPV pressure c' t.25 psig.
~4.4.8 Maintain RCIC pump suction from the CST until level falls to 10,000 gallons.
4.5 Isolate all non essential DC loads to prolong battery life.
4.6 Contact the local fire department to draft from the intake canal to the fire connection at the Northwest corner of the warehouse.
4.7 If AC power can not be restored and the DC batteries approach complete discharge, perform the following:
4.7.1 Connect a fire hose from the fire header to the ultimate cooling water connection IP41-96V-3929.
,, 4.7.2 Close IP41-MOV-039A. _
'4.7.3 Open IP41-06V-3929, IP41-MOV-033C, and '
lEll-MOV-937A.
4.7.4 Secure the RCIC pta.p, open all SRV's, and fill the RPV to the highest level of available indication. ,
4.8 Implement the Emergency Plan and consult Plant Staff for further actions.
5.0 FINAL CONDITIONS:
5.1 All sources of electrical power have been depleted.
5 The emergency plan has been implemented.
5.3 - The core can be maintained covered with water but containment integrity is not assured.
'6.0 DISCUSSION:
l 6.1 This procedure provides information and instructions for actions in the event off-site power is lost and all emergency diesel generators fail to start and no method of restoring AC power can be accomplished for an extended period of time.
6.2 If at aay time during-the performance of this procedure AC power can be restored by Jan method (off-site, diesels, portable generators, etc.),
proceeding to SP29 915 91 will previde the necessary information and instructions to place the plant in a safe condition.
SP 29 015.62 Rev. C
/ / Page 4
~
6,3 Due t3 th] ralichil~ty cf.the diOOG1 g:nerscors, Off-sito cystem <C
, ict rcannectitna cnd avail bility cf portable alcetrical gsnsrcting
,, cquipment, o tet:1 lees of powar for th2 cxtcadad time covarad by thic procedure is highly unlikely.
6.4 Early RPV depressurization and utilization of the RHR Heat Exchangers for steam condensing will result in suppression pool and drywell temperatures and pressures remaining below design limitations until well af ter battery depletion.
6.5 The time available in which to restore A* power before injecting seawater into the RPV is determined by the battery depletion rate. This time can be significantly increased by securing non-essential DC equipment and lighting and by using RCIC until the red battery is depleted and then transferring to HPCI to maintain RPV level until the blue battery is exhausted. The CST should be utilized as long as available before shif ting suction to the suppression pool. This will result in slower rates of containment temperature and pressure rise and avoid failure of the HPCI/RCIC turbines due to high lube oil temperatures.
l SP 29 915.02 Rev. C
/ / Page 5 i
(
.