Letter Sequence Other |
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Results
Other: ML20137L000, ML20206T655, ML20206T679, ML20206T705, ML20206T726, ML20206T748, ML20206T776, ML20206T792, ML20206T817, ML20206T843, ML20206T847, ML20206T875, ML20206T899, ML20206T913, ML20206T921, ML20206T931, ML20206T937, ML20206T949, ML20206T966, ML20206T981, ML20206T986, ML20206U003, ML20212B914, ML20262E700, ML20262E704, NLS8400108, Forwards Second 10-yr Inservice Insp Plan, NLS8600021, Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components, NLS8600248, Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes
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MONTHYEARML20206T9131978-10-23023 October 1978
Rev 5 to Surveillance Procedure 6.3.16.1, Reactor Equipment Cooling - Pump Operability Test
Project stage: Other
ML20206T9861981-08-28028 August 1981
Rev 0 to Surveillance Procedure 6.4.1.8, Control Rod Drive Hydraulic Control Unit Accumulator Leakage Test
Project stage: Other
NLS8400108, Forwards Second 10-yr Inservice Insp Plan1984-04-0303 April 1984
Forwards Second 10-yr Inservice Insp Plan
Project stage: Other
ML20206U0031984-07-23023 July 1984
Rev 13 to Nuclear Performance Evaluation Procedure 10.9, Control Rod Scram Time Evaluation
Project stage: Other
ML20100M8071984-11-28028 November 1984
Draft Rev 9 to QA Policy for Calvert Cliffs Nuclear Power Plant
Project stage: Draft Other
ML20206T9371984-12-0606 December 1984
Rev 10 to Surveillance Procedure 6.3.18.2, Svc Water Motor Operated Valve Operability Test
Project stage: Other
ML20206T9311984-12-0606 December 1984
Rev 6 to Surveillance Procedure 6.3.18.1, Svc Water Pump Operability Test
Project stage: Other
ML20206T8751985-01-0303 January 1985
Rev 11 to Surveillance Procedure 6.3.12.2, Diesel Generator Starting Air Compressor Operability
Project stage: Other
ML20262E7001985-04-25025 April 1985
Flow Diagram:Circulating,Screen Wash & Service Water Systems. Sheet 1 of 5. Actual Rev STATUS:N14
Project stage: Other
ML20262E7041985-04-26026 April 1985
Flow Diagram:Circulating,Screen Wash & Service Water Systems. Sheet 2 of 5. Actual Rev STATUS:N07
Project stage: Other
ML20206T9661985-05-0202 May 1985
Rev 13 to Surveillance Procedure 6.3.19.1, Standby Gas Treatment Operability Test
Project stage: Other
ML20129J6611985-07-12012 July 1985
Submits Revised Inservice Testing Relief Requests RV-03 Re Reactor Recirculation Loops a & B Discharge Bypass Valves, Reflecting Current Pipe Configuration & RP-05 Re HPCI Test Method & Updated Request Index
Project stage: Request
ML20206T7761985-08-18018 August 1985
Rev 11 to Surveillance Procedure 6.3.8.4, Standby Liquid Control Manual Initiation Test Tank to Reactor Vessel
Project stage: Other
ML20206T8171985-09-13013 September 1985
Rev 12 to Surveillance Procedure 6.3.10.2, Instrument Line Flow Check Valve Test
Project stage: Other
ML20137L0001985-10-31031 October 1985
Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components
Project stage: Other
ML20206T7481985-11-21021 November 1985
Rev 15 to Surveillance Procedure 6.3.6.1, RCIC Test Mode Surveillance Operation
Project stage: Other
ML20206T8431985-12-11011 December 1985
Rev 0 to Surveillance Procedure 6.3.10.16, Check Valves in Cooling Sys of Diesel Generators Integrity Verification
Project stage: Other
ML20206T9211986-01-16016 January 1986
Rev 12 to Surveillance Procedure 6.3.16.2, Reactor Equipment Cooling Motor Operated Valve Operability Test
Project stage: Other
NLS8600021, Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components1986-01-17017 January 1986
Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components
Project stage: Other
ML20206T7051986-01-30030 January 1986
Rev 18 to Surveillance Procedure 6.3.4.1, Core Spray Test Mode Surveillance Operation
Project stage: Other
ML20154A5251986-02-12012 February 1986
Forwards Request for Addl Info Re Inservice Testing Program, Based on Review of 840615,850522 & 0722 Ltrs Describing Second 10-yr Inservice Testing Program.Response Requested within 45 Days
Project stage: RAI
ML20206T8471986-03-0606 March 1986
Rev 17 to Surveillance Procedure 6.3.12.1, Diesel Generator Operability Test
Project stage: Other
ML20206T9491986-03-0606 March 1986
Rev 15 to Surveillance Procedure 6.3.18.3, Svc Water Surveillance Operation
Project stage: Other
ML20206T7261986-03-13013 March 1986
Rev 21 to Surveillance Procedure 6.3.5.1, RHR Test Mode Surveillance Operation
Project stage: Other
ML20206T9811986-04-24024 April 1986
Rev 17 to Surveillance Procedure 6.3.20.1, RHR Svc Water Booster Pump Flow Test & Valve Operability Test
Project stage: Other
ML20211A1361986-04-28028 April 1986
Trip Rept of 860415-16 Site Visit for Pump & Valve Inservice Testing Program Working Meeting Re Questions Resulting from Program Review.List of Attendees,Questions Serving as Agenda for Meeting & Responses to Questions Encl
Project stage: Meeting
ML20211A0891986-05-30030 May 1986
Forwards Contractor Summary of 860412 & 16 Meetings at Facility Re to Recipient Requesting Addl Info on Second 10-yr Inservice Testing Program.Correction Made on Page 2 of Summary
Project stage: Meeting
ML20206T8991986-06-0505 June 1986
Rev 3 to Surveillance Procedure 6.3.12.8, Diesel Generator Fuel Oil Transfer Pump Flow Test
Project stage: Other
ML20206T7921986-06-0505 June 1986
Rev 1 to Surveillance Procedure 6.3.9.1, MSIV Accumulator Functional Test
Project stage: Other
ML20206T6551986-06-12012 June 1986
Rev 13 to Surveillance Procedure 6.3.2.1, Automatic Depressurization Sys Manual Valve Actuation
Project stage: Other
ML20206T6791986-06-12012 June 1986
Rev 23 to Surveillance Procedure 6.3.3.1, HPCI Test Mode Surveillance Operation
Project stage: Other
ML20206T6381986-06-30030 June 1986
Forwards Response to W Long 860212 Request for Addl Info Re Inservice Testing Program & 860415-16 Meetings Re Open Items.Surveillance Procedures,Including Procedure 6.3.2.1, Also Encl
Project stage: Meeting
NLS8600248, Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes1986-07-30030 July 1986
Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes
Project stage: Other
ML20212B9141986-07-31031 July 1986
Vols I & II of Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program
Project stage: Other
ML20148C9481988-01-13013 January 1988
Forwards Safety Evaluation of Util Second 10-yr Inservice Testing Program Submitted w/860730 Ltr.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable.Technical Evaluation Rept Also Encl
Project stage: Approval
ML20151H8461988-04-13013 April 1988
Forwards Response to Anomalies Identified in NRC 880113 SER Re Facility Inservice Testing Program.Reactor Equipment Pumps Will Be Tested in Accordance W/Section Xi.Util Evaluating Need for Any Relief Request in Performing Test
Project stage: Request
ML20151L3111988-07-29029 July 1988
Forwards Revised & New Relief Requests & Program Corrections to Second 10 Yr Inservice Testing Program.Addl Review of Program Identified Need for Further Changes to Program Including Rev of Existing Relief Requests
Project stage: Request
1986-01-16
[Table View] |
Text
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SURVELLLANCE PROCEDURE 6.3.10.2 INSTRUMENT LINE FLOW CHECK VALVE TEST I.
PURPOSE A.
To ensure that all installed Harotta excess flow check valves function properly and meet their specifications on closed leakage (0.2 gpm to 0.7 gpm).
II.
DISCUSSION A.
The Marotta excess flow check valves are installed in the instrument lines to prevent uncontrolled leakage from the process line during a postulated condition when the instrument line breaks between the check valve and the instrument.
Leakage tests are performed to demonstrate that the leakage is within the Technical Specification requirements.
III.
REFERENCE MATERIAL A.
I & C Instruction Manual 105, Marotta Excess Flow Check Valve.
IV.
PREREQUISITES A.
Reactor vessel pressure holding at approximately 1000 psig.
V.
LIMITATIONS A.
Technical Specifications Section 4.7.D.I.b.2)d).
1.
Section 4.7.D.1.b.2)d) - At least once per operating cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.
B.
Administrative Limits.
1.
All discrepancies shall be recorded in the Shift Supervisor's log.
2.
All testing shall be coordinated with the Control Room Operator.
VI.
PRECAUTIONS A.
Since the vessel is at 1000 psig, all valves should be opened and closed slowly.
B.
If very little or no flow through the check valve, check the Clearance Order book to see if the penetration isolation valve micht be tagged closed for some reason.
C.
The test apparatus should be held to prevent any whipping action and the free end pointed away from any person or equipment.
P R; vised By/Date Reviewed By/Date Date Rev Procedure Page 1 Of D. King 8/27/85 R. Brungardt 9/11/85 f.jg-gy' 12 6.3.10.2 1
Pages L
D.
Vessel pressure indication will be lost if not on proper level control before certain instruments are valved out (see notes in procedure).
E.
Be aware that the water may contain large amounts of radioactive contaminants.
F.
Vessel level indication will be lost when certain instruments are valved out (see notes in procedure).
C.
Be aware that the reference leg (s) for LT-61 (LI-86) will probably be lost during the test.
Have backfilling equipment available before taking this inctrument out of service.
H.
CRD differential pressure indication will be lost when certain instru-ments are valved out (so noted in procedure).
I.
Recirculation pump differential pressure and flow indication will be lost when certain instruments are valved out (so noted in procedure).
VII. TEST EQUIPMENT A.
One gallon plastic containers marked at
.2,
.3,
.4,
.5,
.6, and.7 gallon.
B.
Stopwatches.
C.
Test apparatus.
.tII.
PROCEDURE Note:
1.
Attachment "A" is written such that all instruments (with the exception of Steps 4., 6.,10., and 19) can be valved out before starting to test or can be valved'out one section at a time. If there is enough help available it would reduce testing time by i'aving one crew valving the instruments out, another crew (s) testing the check valves, and another crew valving the instru-ments back in.
2.
Each section lists instruments that can be valved back in after certain check valves are tested.
All instruments (with the exception of steps and/or parts of Steps 2., 13., 1$., and 19.)
can be valved in af ter testing of all check valves is complete or after each section of the check valves is tested, whichever is most convenient.
A.
Instrument Line Flow Check Valve Test.
1.
Obtain permission and signature from the Shift Supervisor before starting the test.
2.
Inform the Control Room Operator of the test.
3.
Contact Health Physics if water is suspected to contain radio-activity.
Proc dure Number 6.3.10.2 Date 6L A '2.f Revision 12 Page 9
Of 1
Pages
4.
Valve the instruments OUT (one section at a time or all allowable sections if so desired) as specified in the Valve Out (a) section of the applicable steps in Attachment "A" and initial Attachment "A".
5.
Perform the following test for each excess flow check valve as listed on Attachment "B".
a.
Verify that the required instrumente are valved out (as per Attachment "A") for the check valves to be tested.
b.
Perform valving operations and attach test apparatus as per the Can Test (b) section of the applicable step (s) in Attachment "A".
Hold the free end of apparatus to ensure it will discharge into c.
a bucket and slowly open the valve.
d.
After the check valve has been seated (as ' indicated by a reduced flow), catch the flow in a marked plastic container for 60 seconds.
Note: If the level is within the indicated limits on the container, record the value on the data sheet and initial the test point'.
If the amount is less than.2 or greater than.7 gallon, cycle the test valve a few times trying to seat the check valve. Repeat the test.
The procedure is written to test through the drain valves where possible.
There may be cases where not enough flow can be obtained through the drain valve. If this happens, try testing through the rack isolation valve that is listed on Attachment "B".
Perform valving operations and remove test apparatus as per the e.
Can Test (b) section of the applicable step (s) in Attachment "A".
6.
Valve the instruments IN (one section at a time or all allowable sections if so desired) as specified in the Valve In (c) section of the applicable steps in Attachment "A" and initial Attachment "A".
7.
After the testing is completed notify the Shift Supervisor.
8.
Verify that the racks have been returned to normal, date, and initial Attachment "A".
IX.
ATTACHMENTS A.
Instrument Valving List Data Sheets.
i B.
Check Valve Test Data Sheets.
C.
Instrument Rack Locations.
Procedure Number 6.3.10.2~
Date G-Q_W Revision 12 Page 3
Of 3
Pages r
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