Similar Documents at Salem |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 1999-09-10
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18102B6681997-10-0101 October 1997 Rev 8 to Inservice Testing Manual for Pumps & Valves Program. ML18106A8291997-09-0404 September 1997 Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl ML18102A7941997-01-21021 January 1997 Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem ML18102A7931997-01-21021 January 1997 Event Classification Guide,Technical Basis, Salem Generating Station ML18102A6661996-11-19019 November 1996 Rev 2 to Pse&G Simulation Facility Certification Program. ML20115B7791996-07-0303 July 1996 Final Draft, Hope Creek Event Classification Guide, Sections 1-9 ML18101B1141995-11-14014 November 1995 Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9 ML20091M9911995-10-15015 October 1995 Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary ML18101A6911995-05-31031 May 1995 Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995 ML18101A7711995-05-11011 May 1995 Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan. ML20134K0831995-02-27027 February 1995 Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan, ML18101A6751995-02-16016 February 1995 Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection. ML18101A6761995-02-16016 February 1995 Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response. ML18101A5381995-01-27027 January 1995 Revised Salem Generating Station Event Classification Guide. ML18101A2111994-08-17017 August 1994 Revised Salem Event Classification Guide. ML18101A6771994-07-11011 July 1994 Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination. ML20147B1601994-04-23023 April 1994 Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation ML18100A8081994-01-0707 January 1994 Rev 30 to Salem Generating Station Event Classification Guide. ML20147B1491993-11-0202 November 1993 Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation ML18100A4201993-06-15015 June 1993 Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures. ML18100A3771993-05-0505 May 1993 Rev 27 to Salem Generating Station Event Classification Guide. ML18100A3661993-04-27027 April 1993 Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6 ML20147B1171993-04-13013 April 1993 Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program ML18096B3251993-02-26026 February 1993 Integrated Scheduling Program. ML18096B2911993-02-10010 February 1993 Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18 ML20147B1021993-01-21021 January 1993 Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process ML20135B6521992-12-29029 December 1992 Rev 0 to Loss of Overhead Annunciator Sys ML20147B1371992-12-22022 December 1992 Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca ML20147B2051992-09-21021 September 1992 Rove Time Keeping Procedure ML18096A9601992-08-28028 August 1992 Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan. ML18100A3151992-07-28028 July 1992 Rev 1 to Process Computer Maint & Mod Control Program. ML18096B3191992-07-17017 July 1992 Rev 8 to Salem Nuclear Generating Station Odcm. ML20147B1691992-05-0707 May 1992 Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications ML18096A6791992-04-30030 April 1992 Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan. ML18096A4421992-01-15015 January 1992 Rev 17 to Salem Generating Station Event Classification Guide ML18096A3211991-10-0404 October 1991 Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages ML18096A1431991-06-28028 June 1991 Rev 12 to Salem Generating Station Event Classification Guide. ML18095A9661991-05-30030 May 1991 Artificial Island Salem Event Classification Guide, Rev 11 ML18096A1191991-05-28028 May 1991 Rev 2 to NFU-0039, Salem Reactor Physics Methods. ML18095A9391991-05-16016 May 1991 Revised Replacement Pages to Facility Inservice Testing Program 1999-09-10
[Table view] |
Text
'/
I' STARTUP PROCEDURE 90.6,Rev. 2 UNIT NO. 2 COOLDOWN CAPABILITY OF CHARGING AND LETDOWN SUP 90.6, Rev. 2 Salem Unit 2
STARTUP PROCEDURE 90.6 COOLDOWN 'CAPABIDITY OF CHARGING AND LETDOWN __ _
1.0 OBJECTIVES 1.1 The objective of this test is to determine the capability of the charging and letdown system to cooldown the reactor coolant system with the steam generators isolated and one reactor coolant pump in operation
- SUP 90.6, Rev. 2 Salem Unit 2
- REFERENCES 2.1 2.2 FSAR Salem Unit 2 Technical Specifications 2.3 Salem Operating Instructions EI I-4.0, "Safety Injection Initiation", Rev. 1 OI II-1.3.1, "RCP Operation", Rev. 1 OI II-3.3.1, "Establishing Charging, Letdown and Seal Injection Flow", Rev. O.
2.4 Westinghouse Precautions Limitations and Setpoints, Rev. 7, August, 1979.
2.5 SUP 90.0 Special Tests Sequence Document 2.6 SUP 70.5 RCS Flow Measurement.
Salem Unit 2 SUP 90.6, Rev. 2 0 PREREQUISITES
. 3.1 The low power physics testing is complete (SUP's 80.3, 80.4, 80.5, B0.6) 3.2 Brush Recorders are set up to record the plant parameters outlined in paragraph 8.2.
3.3 A trend block containing the address points shown in paragraph 8.3 has been established on the P-250.
3.4 The P-250 is operational with a dedicated analog recorder acting as a saturation meter.
3.5 The test engineer has briefed all personnel involved in the conduct of the test.
3.6 SUP 70.5 RCS Flow Measurement (Ref *. 7.7) has been completed.
3.7 Station QA has been notified of the start of the test.
3.8 The control room has* been cleared of non-essential personnel .
Salem Unit 2 SUP 90.6, Rev. 2 4.0 INITIAL CONDITIONS 4.1 The reactor is shutdown and borated to ensure adequate shutdown margin, with the shutdown banks withdrawn, (Mode 2).
4.2 All four reactor coolant pumps are in operation.
4.3 Steam Generator level being maintained at approximately 33% with the Auxiliary Feedwater System.
4.4 Reactor Coolant System pressure and level ender automatic control at approximately 2235 psig and 22% level.
- 4. 5 Reactor Coolant System temperature being controlled at approximately 54.7°F by steam dump to the condenser under automatic pressure control, (Steam Generator pressure at approximately 1005 psig) , or alternatively with atmospheric steam dump if the condenser is unavailable.
4.6 Steam Generator chemistry is adjusted within normal specification such that Steam Generator blowdown can be isolated when the steam generators are isolated.
4.7 Normal charging and letdown in service and under automatic control .
- Salem Unit 2 SUP 90.6, Rev. 2
ENVIRONMENT CONDITIONS
- 5. l No special environmental conditions are required for the conduct of this te.st.
6.0 ACCEPTANCE CRITERIA 6.l The'effect of charging and letdown variations on Tavg has been determined.
7.0 SPECIAL TEST EQUIPMENT 7.l Three Brush 260 (or equivalent) chart recorders, connected per section 8.0.
Cal. Date' Recorder No.
l 2.
3 SUP 90.6, Rev. 2 Salem Unit 2 DAT1' COLLECTION 8.1 All data acquired as a result of performance of this procedure shall be recorded at the appropriate step, on the Check Off Sheets or affixed as appropriate.
to monitor the 8.2 Two Brush Recorders will be utilized and connected as shown following test parameters.
Inst. Monitorins: Rans:e Recorder 1 RCS Flow Loop 21 0-10%
Channel No. 1 FT 414 RCS Flow Loop 22 0-10%
Channel No. 2 FT 424 RCS Flow Loop 23 0-10%
Channel No. 3 FT 434 RCS Flow Loop 24 o-10%
Channel No. 4 FT 444 Pressurizer Pressure 16-2400 Channel No. 5 PT 474 Pressurizer Level 0-100%
Channel No. 6 LT 461 Recorder 2 Monitorins:
Channel No. 1 RCS Charging Flow Channel No. 2 RCS Letdown Flow 3 Charging Temperature Channel No.
4 Letdown Hx Outlet Temp.
Channel No.
Channel No. 5 Regen. HX Outlet Temp.
Channel No
- 8.3 'rhe reactivity computer chart recorders will be connected as of the.special test program.
8.3.l Recorder #l Channel A Channel B p-computer output in the remainder N-41 excore detector current 8.3.2 Recorder #2 Channel A Loop 21 T c TE 413 B 510-610 Channel B Loop 21 Th TE 413 A 510-610 8.3.3 Recorder #3 Channel A Loop 22 Tc TE 423 B 510-610 Channel B Loop 22 Th TE 423 A 510-610 8.3.4 Recorder #4 Channel A Loop 23 Tc TE 433 B 510-610 Channel B Loop 23 Th TE 433 A 510-610 8.3.5 Recorder lt5 Channel A Loop 24 Tc TE 443 B 510-610 Channel B Loop 24 Th TE 443 A 510-610 SUP 90.6, Rev. 2 Salem Unit 2 B.4 Two P-250 trend blocks will be set up to monitor the following computer points.
(Additional points may be added as required by the test engineer)
~ Address Parameter 1 P0480A Pressurizer Pressure 2 L0480A Pressurizer Level 3 T0400A RCS Loop 21 Avg Temperature 4 F0400A RCS Loop 21 Flow 5 T0420A RCS Loop 22 Avg Temperature 6 F0420A RCS Loop 22 Flow 7 T0440A RCS Loop 23 Avg Temperature 8 F0446A RCS Loop 23 Flow 9 T0460A RCS Loop 24 Avg Temperature 10 F0460A RCS Loop 24 Flow 11 P0400A Steam Generator 21 Pressure 12 L0400A Steam Generator 21 Narrow Range Level 13 P0420A Steam Generator 22 Pressure 14 L0420A Steam Generator 22 Narrow Range Level 15 P0440A Steam Generator 23 Pressure 16 L0440A Steam Generator 23 Narrow Range Level 17 P0460A Steam Generator 24 Pressure 18 L0460A Steam Generator 24 Narrow Range Level 19 N0031A Source Range Channel 1 20 N0032A Source Range Channel 2 21* T0126A Regen Hx Charging Outlet Temperature 22 T0127A Regen Hx Letdown Outlet Temperature 23 T0140A VCT outlet Temperature 24 F0128A Charging Pump Discharge Header Flow 25 F0134A Non-Regen Hx Letdown Outlet Flow 26 T0185A Seal Return Temp 27 F0134A Letdown Flow 28 T0145A Non-regen Hx Letdown Outlet Temp.
29 T0482A Pressurizer Surge Line Temp 30 T0122A Excess Letdown Hx Outlet Temp.
31 P0142A Charging Pump Discharge Pressure 32 P0135A N. Regen. Hx Outlet Pressure 33 P0139A VCT Pressure 34 F0483A(or Y) Pressurizer Spray Flow 35 F0484A(or Y) Pressurizer Spray Flow 36 U0091A Average Incore T/C 8.5 The following data (as applicable) shall be recorded on each strip chart and computer listing.
a) Unit number b) Date c) Procedure number d) Parameter scale and range e) Chart speed f) Name o~ person recording data g) Recorder IO number h) Time mark for start qf test Salem Unit 2 SUP 90.6, Rev. 2
8.6 Record Operator participation in the test on Appendix A.
9.0 PRECAUTIONS 9.1 Before beginning, and while the test is conducted, perform shutdown margin calculations, as directed by the Test Engineer.
9.2 The boron concentration in the pressurizer should not be less than the con-centration in the Reactor Coolant loops by more than 50 ppm. Use pressurizer spray to equalize concentration before the test.
9.3 Both source range channels should be in operation and monitored closely during the conduct of this test, (15 minute intervals) . Any unexplained increase in counts by a factor of*two is grounds for test termination.
9.4 Makeup flow to the .RCS must be at the same boron concentration as that required for shutdown.
9.5 The RCS should be sampled for boron concentration once toward the end of the 30-minute period of maximum letdown and charging and shutdown margin verified.
9.6 Observe the differential. pressures between Steam Generators. and maintain llP
< 100 psid to avoid safety.injection. If it determined that Steam Generator pressure control is unsatisfactory to maintain this limit, then defect the S/G llP input to SI actuation per Appendix A of SUP 90.0 (ref. 2.4).
9.7 Do not use excess letdown unless absolutely necessary.
9.8 When changing charging and letdown*flows, always reverify RCP seal injection flow is about 8 gpm per pump
- Salem Unit 2 SUP 90.6, Rev. 2
-a-
INSTRUCTIONS 10.l If the reactor coolant system Tavg is above 547°F, reduce it by manually increasing steam dump to the condenser.
10.2 Prepare all charts and computer listing per paragraph 8.4.
10.3 Start chart recorders and intiate P-250 trending.
10.4 Shutdown reactor coolant pumps 21, 22 and 24 in accordance with OI II-1.3.l. Ensure That the pressurizer spray valves are closed and in manual control.
10.5 Isolate all four steam generators by closing main steam isolation valves and Auxiliary Feedwater valves, 21-24AF21 10.6 Isolate Steam Generator blowdown if it is presently in operatio~. by closing valves 21-24 6B-4 10.7 Increase charging flow and letdown to the maximum allowable, (150 gpm letdown}. Start additional charging pumps as ne~essary. Bypass the letdown ion exchangers by directing three-way valve 2CV21 to the VCT.
10.8 Continue maximum letdown and charging for a 30-minute period and then reduce letdown and charging to the minimum, (45 gpm} . Continue recording data, marking this point on chart recorder traces and trend typewriter printout .
- 10.9 NOTE: Toward the end of the 30-minute period a boron analysis of the RCS should be done to verify adequate shutdown margin.
After running with minimum letdown and charging for a 30-minute period, stop the recorders. Restore the letdown line to normal.
'* NOTE: The test engineer may elect to run longer than 30 minutes if desired to obtain sufficient data.
CAUTION: Perform a shutdown margin calculation at the lowest temperature reach during the test.
10.10 Stop trend printer and recorder.
10.11 Open MSIV bypass valves and then the MSIV's when the steam generator pressure and steam header pressure are approximately equal.
NOTE: Control secondary side pressure using the atmospheric dump valves until all MSIV's are open.
10.12 Start reactor coolant pumps 21, 22 and 14 in accordance with OI II-1.3.l, "RCP Operation". Re-establish steam pressure control using the condenser steam dump if
Salem Unit 2 SUP 90.6, Rev. 2 10.13 On Data Sheet 5.1, using recorded data, calculate the average ra~e of temperature change for the 30-minute periods of maximum and minimum letdown and charging. Also record the maximum rate of change observed and the period this rate was sustained.
10.14 Record the names of Unit 2 licensed operators participating in or observing the test in Appendix B, as appropriate.
10.15 Retrieve and attach chart recordings and P-.250 printouts per paragraph 8.1 - 8.3.
10.16 Generate a plot.of temperature vs. time for each of the two cases .
SUP 90.6, Rev. 2 Salem Unit 2 11.0 TEST COMPLETION 11.l Comments 11.2 Changes to SPM 11.3 Signature Date T/C Date S/S QA/QC Date STA Date SUP 90.6, Rev. 2 Salem Unit 2
DATA SHEET 5.1 Maximum Letdown and Charging Charging Flow ______gpm Letdown Flow ______gpm
_ _ _ _ _ _ _ _oF Average Temperature Change over the 30-minute period.
Avg. change ?F Max rate _ _ _ _ _ _ _°F/Hr.
Rate of Temperature Change .5 ------hr observed Sustained _ _ _ _ _ __.:min.
Minimum Letdown and Charging Charging Flow _ _ _ _ _gpm Letdown Flow _ _ _ _ _gpm
- Average Tempe~ature Change ---..,.----~
OF over the 30-minute period.
Avg. change OF Max rate _ _ _ _ _ _ _°F/Hr.
Rate of Temperature Change .5 -------hr observed
'* Sustained _ _ _ _ _ _....;min.
Calculated by Reviewed by Salem Unit 2 SUP 90.6, Rev. 2
APPENDIX A .
SRO's Participating In Test SRO's Observing Test Salem Unit 2 Page l of 2 SUP 90.6, Rev. 2
APPENDIX A (cont.)
RO's Participation In Test RO's Observing Test Salem Unit 2 Page 2 of 2 SUP 90.6, Rev. 2