View source for TXX-4575, Forwards Deferred MSIV Preoperational Test Status Rept. Initial Deferred Test Status Deficiencies Reported Per Listed Ltrs.Deferrals Granted in Sser 6.Change in Status Result of Unit 2 Heatup from Oct 1984 to Jan 1985

{{Adams
| number = ML20137W255
| issue date = 09/30/1985
| title = Forwards Deferred MSIV Preoperational Test Status Rept. Initial Deferred Test Status Deficiencies Reported Per Listed Ltrs.Deferrals Granted in Sser 6.Change in Status Result of Unit 2 Heatup from Oct 1984 to Jan 1985
| author name = Counsil W
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = TXX-4575, NUDOCS 8510040263
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 8
}}

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Log # TXX-4575 TEXAS UTILITIES GENERATING COMPANY File # 914.2
                   . MMYWAY TOWER e 400 NORTH OUVE STREET. LB. BE e DAM.AS TEXAM WO.        10010 USYANEOS                                September 30, 1985 l        Mr. Harold R. Denton Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET.NOS. 50-445 AND 50-446 DEFERRED PRE 0PERATIONAL TEST STATUS REPORT REF: Letters to Mr. H. R. Denton from B. R. Clements l                    (TXX-4169 dated May 15, 1984; TXX-4182 dated l                   May 29, 1984; TXX-4191 dated June 5, 1984;
!                   TXX-4199 dated June 8, 1984 and TXX-4202 dated June 15, 1984)

==Dear Mr. Denton:==

The purpose of this-letter is to provide the status of certain
'        preoperational tests which were deferred by NRC until after Unit 1 fuel load. The test deficiencies were reported in the referenced letters and deferrals were granted in CPSES Safety Evaluation Report, Supplement No. 6.
.        The change ~in status is as a result of a second plant heatup which was
!        conducted from Octooer 1984 to January 1985 during which certain of these tests were satisfactorily completed. The results of these tests and the current status of each item are indicated in Attachment A.
If you have any questions on this matter, please contact this office.
l Very truly yours,
                                                                          /             fidl W. G. Counsil SDK/grr Attachment p
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1 ATTACHMENT A
: 1. DEFERRED PRE 0PERATIONAL TESTING OF THE MAIN STEAM ISOLATION VALVES (MSIV's)
Deferred Test:  ICP-PT-34-01 Present Test:   ISU-234A DEFERRAL ~ ITEM A:   Demonstrate the MSIV 5 second stroke time TEST RESULTS:     The closure time for each MSIV was less than 5.0 seconds after receipt of a Train A isolation signal.
The closure time for each MSIV was less than 5.0 seconds after receipt of a Train B isolation signal.
No further testing of this item is anticipated.
DEFERRAL ITEM B:     Demonstration of MSIV operability 30 minutes after a loss of air occurrence.
TEST RESULTS:     Each MSIV demonstrated closing operability, upon receipt of an isolation signal, after having been isolated from instrument air for at least 30 minutes.
No further testing of this item is anticipated.
DEFERRAL ITEM C:     Demonstrate MSIV auto timing,   i.e., verify limit switch settings.
TEST RESULTS:     The MSIV auto feature was not tested due to an incomplete design modification. It is our plan     to test the auto timing feature after fuel load (but prior to initial criticality), when the next plant heatup is expected to occur. This testing will be conducted during Mode 4 and will demonstrate the operaDility of the MSIV's prior to Mode 3.
STATUS OF DEFERRAL: This deferral is open pending satisfactory completion of the testing identified in Item C above.
r 1
II. DEFERRED PRE 0PERATIONAL TESTING 0F CONTAINMENT COOLING SYSTEMS Deferred Test:  1CP-PT-45-06 Present Test:   ISU-282A DEFERRAL ITEM A:      Failure of the Containment Cooling System to maintain cooling to the Reactor Vessel Supports.
TEST RESULTS:     The Reactor Vessel Support supply air temperature met the acceptance criteria of less than 88.50F.
No further testing of this it'em is ancticipated.
DEFERRAL ITEM B:      Failure of the containment cooling system to maintain cooling to the Neutron Detector Well Area.
TEST RESULTS:     The return air temperature from each neutron detector well with the exception of SR(N32) and IR(N36) met the requirement of less than 133.50F.
The return temperature from SR(N32) and IR(N36) at azmith 00F reached a maximum of 1430F due to the fact that the temperature detector measures combined neutron detector well and reactor cavity exhaust temperatures. A Technical Specification change request has been initiated requesting that the limit be increased to 1500F. (Refer to TXX-4418)
Procedure OPT-102 will monitor temperatures during the next heatup.
Failure of the Containment Cooling System to
                                    ~
DEFERRAL ITEM C:
maintain cooling to the Pressurizer Compartment.
TEST RESULTS:     The air temperature in the Pressurizer Compartment met the acceptance criteria of less than 118.50F.
No further testing is anticipated.
DEFERRAL ITEM D:      Failure of the Containment Cooling System to maintain cooling to Steam Generator Compartments 1, 2, 3 and 4 areas.
TEST RESULTS:     The air temperature in Steam Generator Ccmpartments 1, 2, 3 and 4 met the acceptance criteria of less than 118.50F.
No further testing of this item is anticipated.
STATUS OF DEFERRAL:   This deferral is considered open pending final approval of the technical specification change request in Item B above.

III. DEFERRED PRE 0PERATIONAL TESTING 0F SAFETY INJECTION SYSTEM CHECK VALVE LEAKAGE Deferred Test:   ICP-PT-57-09 Present Test:    EGT-712A DEFERRAL ITEM A:
                 ~~~~
The following check valves were determined to leak in excess of their acceptance criteria:
1-8949A 1-8956A, B, D ISI-8948A, B, C, D ISI-8905B TEST RESULTS:     The leakage rate of each of the check valves met the acceptance critsria of less than 1 gallon per minute.
No further testing of this item is anticipated.
STATUS OF DEFERRAL:    The Deferred Test Report 84-1-002 has been reviewed and approved by the Station Operations Review Committee.
This deferral is considered complete.
r IV. DEFERRED PRE 0PERATIONAL TESTING 0F TURBINE DRIVEN AUXILIARY FEEDWATER PUMP STEAM SUPPLY LINE CHECK VALVE AND ORAIN P0T LEVEL CONTROL VALVE Deferred Test:  ICP-PT-37-03 Present Test:   ISU-206A
      . DEFERRAL ITEM A:     .The steam line inlet supply drain pot level control valve, ILV-2383, failed to shut after condensate was drained from the steam line piping.
TEST RESULTS:     Valve ILV-2383 operated satisfactorily during 5 consecutive cold quick starts.
DEFERRAL ITEM 8:       The steam line inlet supply check valves, IMS-142 and IMS-143, were damaged during the 5 consecutive cold quick. starts (the disks were eroded and bent).
TEST RESULTS:     The inspection of check valves 1MS-142 and IMS-143 revealed that one of the valves was damaged. A Problem Report was initiated to evaluate this problem and is in Engineering Review at present.
Some retesting and reinspection will probably be required during the post fuel load heatup prior to criticality. This testing is to be performed during Mode 3, prior to entering Mode 2 as required by Technical Specifications.
STATUS OF_ DEFERRAL: This deferral is considered open pending conpletion of the testing identified in Item B above.

V.        DEFERRED PRE 0PERATIONAL TESTING 0F REACTOR COOLANT PUMP SEAL PERFORMANCE Deferred Test:              ICP-PT-49-02, 1CP-PT-55-09 Present Test:                ISU-300A DEFERRAL ITEM A:                     Verification of proper Reactor Coolant Pump seal injection and leakoff flows prior to and after starting of the Reactor Coolant Pumps.
TEST _RESULTS:                 .The RCP seal injection and leakoff flows were within the expected values for initial operation.
No further testing of this item is anticipated.
DEFERRAL ' ' ~ ~
ITEM 8:             Verification of proper Reactor Coolant Pump seal injection and leakoff flows at Reactor Coolant System normal operating system temperature and pressure.
TEST RESULTS:                   The RCP seal injection and leakoff flows were within the expected values for normal Reactor Coolant System temperature and pressure.
No further testing of this item is anticipated.
STATUS OF DEFERRAL: The Deferred Test Report 84-1-004 has been reviewed
                                  '"-~~~
and approved by the Station Operations Review Committee.
This deferral is considered complete.
I

VI. DEFERRED PREOPERATIONAL THERMAL EXPANSION TESTING Deferred Test:  ICP-PT-55-11
             .Present Test:   ISU-008A DEFERRAL' ITEM A:     The foll.owing items required retesting.
: 1) Snubbers
: 2) Springs
: 3) Pipe Whip Restraints
: 4) Pipe Points
: 5) RCP Tie Rods TEST RESULTS:     The following items did not meet th_ acceptance
                             -criteria of ISU-008A.
: 1) Snubbers (4)
: 2) Springs (2)
: 3) Pipe Points (17)
All other items tested satisfactorily. It is our planfto retest these items after fuel load when the next plant heatup is expected to occur.
STATUS OF DEFERRAL: This deferral is considered open pending satisfactory completion of the retesting identified in Item A above.
        ~VII. DEFERRED PREOPERATIONAL CONTROL ROOM AIR BALANCE Deferred Test:  AB-TUSI-001 Present Test:   AB-TUSI-001~
DEFERRAL _ ITEM A:    .Th~e-Control Room air balance could not be completed.
TEST RESULTS:     The design modifications for the Control Room ventilation system are complete. The rebalancing of the system is in progress and is expected to be completed prior to fuel load.
STATUS OF DEFERRAL: This deferral is considered open pending satisfactory completion of the testing identified in Item A above.
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