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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
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
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
. - - - _ - _--_ -
1: -
ha',mi t'cdd:-' SP Numbar 29.023.04 (Szeticn Hetd)
__ Approved: Revision C (Plant Manager)
Effective Date LEVEL RESTORATION EMERGENCY PROCEDURE d6 h5
-1.0 ~ PURPOSE The purpose-of this procedure is to restore RPV w ter level to above top of
' active fuel.
2.0 ENTRY CONDITIONS Enter this procedure from 29.923.91 (Level Control) or 29.923.92 (Cooldown) when RPV. water level cannot-be maintained above tcp of activel fuel (TAF).
NOTE TAF = +6" as-read on fuel zone instrumentation:
-3.0 OPERATOR ACTIONS .
3.1 Lineup for injection and start pumps in two or more of the
- following normal injection subsystems:
3.1.1 Condensate 3.1.2. CS A ,
3.1.3 'CS'B 3.1.4 LPCI A 3.1.5 LPCI B 3.2 If-less than two normal injection subsystems (Paragraph 3.1) en
.be lined up, commence lining up as many of the Alowing
. alternate injection subsystems as possible:
cet i N 37,e es, g
.prW
., f,,/gi- 8107230264 810720'; -..-
PDR ADOCK 05000322. .
A- PDR. . . . .
Ll
A % .d-.,,, - - . . . - ,
, 3.2.1 Service water / rec ~ ire loop ultimate cooling water
~
crossties valves IP41-MOV-033A, MOV-0335. MOV-033C, and MOV-033D.
3.2.2 ECCS connections from the Condensate Transfer System 3.2.3 SLC (test tank) per SP 2?.123.01, Standby Liquid Control 3.2.4 SLC (boron task) per SP 23.123.91, Standby Liquid Control CAUTION IF RPV water level cannot be determined and at least one subsystem with at least one pump running is:
- 1. lined up for injection proceed to 29.023 05 (Rapid RPV Depressurization)
- 2. not lined up for injection proceed to Step 3.7.4, (Core Cooling Wirkout Injection).
3.3 Monitor RPV pressu.e and water level -
3.3.1 Continue in this procedure at the step indicated in the following table:
NOTE If n_ . ..se the RPV water level tre.nd reverres or RPV pressure changes region, return to step 3~.a.1.
Table 1 RPV PRESSURE REGION 333 333 to 100 100 HIGH INTERMEDIATE LOW RPV LVL INC. 3.4 3.5 3.6 RPV LVL DEC. 3.7 3.8 3.4 RPV level increasing and RPV pressure creater than 333 psig (High Region).
3.4.1 ENTER SP29 023.91, Level Control at Step 3.3.
SP 29.023.04 Rev. C
/ / Page 2 N' , . . . _ . _
3.5 .RPV leval increasing end RPV pressure batween 333 and 100 psig (intermediata ragion).
CAUTION Do not depressurize the RPV below 100 psig unless motor driven pumps . sufficient to maintain RPV water level are running and available for injection.-
t,
.3.5.1 If. HPCI and RCIC are available and RPV water level increases to +12.5", proceed to SP29.923 91 (Level Control) Step 3.3.
' 3. 5. 2 ' If HPCI and RCIC are not available and RPV pressure is increasing, proceed to SP29.923 95 (Rapid RPV-Depressurization).
.3.5.3' If HPCI and RCIC are not available and RPV pressure is not increasing, proceed to SP29 923.91 (Level Control) step 3.3. ,
3.6 1RPV level increasing and RPV pressure 100 psig (low region).
. 3.6.1 Determine RPV pressure.
3.6.2- :If lev pressure is increasing, proceed to SP29.923.95
- (Rapid RPV Depressurization).
3.6.3 If RPV pressure is not~ increasing, proceed to SP29 923 91, (Level Control) step 3.3.
L 3. 7. RPV level decreasing and RPV pressure greater than 333 psig (Intermediate /High region).-
~
3.7.1 5 If HPCI and'RCIC are not operating, restart HPCI per SP 23.292 91, High Pressure Coolant Injection i
and/or RCIC per SP'23.119 91, Reactor Core Isolation
! Cooling (RCIC) System.
l i 3.7.2 If CRD is not operating but at least 2 injection
! subsystems are lined up for injection with pumps running,
- proceed to SP29.923 95 (Rapid RPV Depressurization).
3.7.3 If CRD is not operating and no normal injection subsystem
"' is lined up for injection with at least one pump running, i
start pumps in alternate injection subsystems which are lined up for injection.
l
~3.7.4 When RPV , water level drops to +6" on the fuel zone instrumentation (TAF), perform the following.
b 1 -p i
l SP 29 923.b. Aev. C
/ / Page 3
- i
l 3.7,4.1 If CRD 'is not cparating and na normal inj2ctica er alternrte injsetion sub2ystem is lintd up for-injection with at least one pump running, I perforn core cooling without injection as follows.
' 3.7.4.1.1 When RPV water level drops to later (2/3 core height) or if RPV water level cannot be determined, open I one SRV. j 3.7.4.1.2 As RPV pressure decreases, open additional SRV's as required by the following table. I TOTAL NUMBER OF RPV PRESSURE (psig) SRV's OPEN above 899 1 between 800 and 599 . 2 between 599 and 350 3 between 359 and 259 4 between 250 and 175 5 L between 175 and 125 6 below 125 7
~
. 3.7.4.1.3 When a normal injection or alternate injection subsystem is lined up for injection with at least one pump running . proceed to SP 29.923 95 (Rapid RPV Depressurization).
l 3.7.4.2- If the-RPV water level drops to +6" on the fuel-zone indicator (TA?) and CRD is operating or a normal injection system is lined up for injection with a pump running or an alternate injection system is lined up for injection with pump running proceed to SP29 923 95 (Rapid RPV Depressurization).,
s SP 29.923 94 Rev. C
/ / Page 4 i
. 3.8 -RPV lev 21 decrenming and RPV prascura lema then 100 psig (low rsginn).-
3.8.1 If no normal injection system is lined up for injection with at least one punp running, start pumps in alternate
' injection subsystems which are lined up for injection and perform the following.
3.8.1.1 If RPV pressure is increasing, proceed to SP29 923.95 (Rapid RPV Depressurizat h n).
'3.8.1.2 If RPV' pressure is aot increasing and RPV water level drops to +6" on fuel zone instrumentation (TAF), perform Corg Cooling Without Level Restoration as follows.
3.8.1.2.1 Open all ADS valves.
CAUTION Observe NPSH requirements for the core spray pumps as indicated, when taking a suction on ths Suppression Pool.
SUPPRESSION POOL PUMPS MAXIMUM TEMPERATURE MINIMUM LEVEL
- CS Later Later NOTE 1Cooldown ratea greater than 199'F/Hr may be required'to L accomplish this~ step.
t -.-
3.8.1.2.2 If all of the ADS valves cannot be
, opened, open other SRV's until 7 valves are open.
3.8.1.2.3 Operate Core Spray subsystems with suction from the Suppression pool.
3.8.1.2.4 When at least one core spray subsystem is operating with suction from ti.e Suppression Pool and RPV l
pressure is less than 299 psig, L terminate injection into the RPV from sources external to the primary containment.
o :;
' SP 29.923.94 Rev. C
/ / Page 5
3.8.1.2.5 .If RPV water 1sv21 is restored to
+6" (TAF) on the fuel zone instrumentation, proceed to SP 29.923.91 (Level Control) at paragraph 3.3.
'49 ' REFERENCES 4.1 'SP 29 923 95 Rapid RPV Depressurization 4.2 SP'29.923 91 Level Control-4.3 SP 23.292 91 High Pressure Coolant Injection 4.4 SP 23.119 91 Reactor Core Isolation Cooling (RCIC) System
-4.5 SP 23.196.91 Control Rod Drive 14.6 SP 29.923.99 RPV Flooding 4.7 SP 23.293.91 Core Spray System 4.8 SP 23.123.91 Standby Liquid Control 4.9 SP 23.294.91 Low Pressure Coolant-Injection 4.19' SP 23.193 91 Condensate System 4.11 SP 23.195 91 Condensate Storage and Transfer System 4.12 SP 23.199.91 Feedwater System f
l~
c O
l r.
I l SP 29 923 94 Rev.C[
/ / Page 6.
L = e
, . . . . -. . - . , . , . . . . ....-.--,_,,m,,,_.m.
_._,,,~.....m,. , ., ._
.m. . _ _ . -
