ML19332E808

Discusses Deferral of Preoperational Testing of Sampling Sys,Primary Plant Ventilation,Safeguards Bldg Ventilation, Auxiliary Feedwater Sys,Fuel Pool Cooling & Cleanup Sys, Safety Injection & Response Time Testing of MSIVs

ML19332E808
Person / Time
Site:	Comanche Peak
Issue date:	12/06/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89824, NUDOCS 8912130004
Download: ML19332E808 (3)

Text

.- - . -- -

j' Log # TXX-89824 P9

~ ~

File # 914.2

- .- 10010 ,

C C

~

Ref. # 10CFR50.34(b).

nlELECTRIC December 6. 1989 OnTeN??"$a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 ,

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)  :

DOCKET NOS. 50-445 AND 50-446 DEFERRAL OF PRE 0PERATIONAL TESTING

-REF: TV Electric Letter TXX-89460 from W. J. Cahill, Jr. to the NRC dated July 14, 1989 Gentlemen:

t As a supplement to the referenced letter, TV Electric is providing a list of l the preoperational testing items that it has requested to defer past fuel load

!- (see attachment " POST FUEL LOAD DEFERRED RETEST").

This list is tentative pending the completion of TU Electric's review of the

. preoperational test program. Upon completion of th:s review, a list of additional deferred testing items, if any, will be provided.

Sincerely,

{

J. 7,r/

William J. Cahill, Jr.

RSB/bjh Attachment c - Mr. R. D. Martin, Region.IV Resident Inspectors, CPSES (3)

Mr. J. H. Wilson, OSP-NRC 8912130004 991206 PDR A ADOCK 05000445 PDC po30

' \

400 North Olive Street LB81 Dallas, Texas 75201

-4 i y

Attachment to TXX-89824 Page 1 of 2 POST FUEL LOAD DEFERRED RETEST  ;

1. Sampling Systems Demonstrate the secondary and process sampling systems provide sa'nples for analysis within the design requirements for flow rates, temperatures and pressures.

' Numerous design changes which occurred on the sampling systems during and following the preoperational test required additional verification of the system operation. All testing which can be performed prior'to hot, pressurized operation is scheduled to be completed prior to fuel load.

Those tests which required pressure and temperature (flow path verifications and sample cooler performances) will be performed prior to entry into Mode 2.

2. Primary Plant Ventilation Demonstrate proper operation of the ventilation fans and filters, and verify adequate air flow to areas served.

The filter. testing can not be performed until after installation of the charcoal in the charcoal absorber housing. Charcoal installation will be ,

deferred until extensive painting and cleaning in the areas is completed. ,

The required charcoal loading and testing will be completed prior to entry into Mode 4 and will satisfy Technical Specification 3.7.8.

3. Safeguards Building Ventilation Demonstrate the ventilation system will maintain the temperature in the

! Main Steam Isolation Valve area within design requirements at normal operating temperature.

i The equipment necessary to verify system operability was not available l

during preoperational testing. The MSIV area temperatures will be verified to satisfy the design requirements at normal operating temperatures prior to entry into Mode 2.

4. Auxiliary Feedwater System Demonstrate that the turbine-driven pum) is capable of delivering flow to the steam generators within the accepta)1e time after an initiating signal.

A design change to the steam admission valves requires retesting the response time of the turbine-driven auxiliary feedwater pump. This testing will be completed in Mode 3 in order to comply with Technical Specification 3.7.1.2.

1 I

.4 Attachment b TXX-89824 Page 2 of 2 j 1

5. Fuel Pool Cooling and Cleanup System I A. Verify proper actuation and operation of the pump in the spent fuel pool skimmer loop and verify correct flows in the loop.

The reactor cavity skimmer pump can not be tested for flow until the reactor cavity is flooded. This pump is rated non-nuclear safety and is not needed until the first refueling outage. The flow-rate of the pump will be verified during the first refueling outage.

B. Verify vibration level for piping and components arewithin acceptable  !

limits.

Modifications to pipe supports in the spent fuel pool can not be performed until the fuel is loaded into the reactor vessel.

Completion of these modifications will require reverification of the piping vibration levels. These modifications and the subsequent pipe vibration testing is scheduled to be completed after fuel load and prior.to Mode 2 entry.

6. Safety Injection Demonstrate check valve operability for valves 1-8841A,1-8818A, B, C, and D.

Maintenance was performed on these valves following the completion of the hot ft.nctional tests. The required post-maintenance test satisfies the L preoperational testing as well as Technical Specification 4.4.5.2.2. This testing will be completed prior to entering Mode 2,

7. Response Time Testing of Main Steam Isolation Valves Reverify the response times for the MSIV's.

Maintenance performed on the MSIVs since the completion of the hot functional testing requires that the MSIV response times be reverified.

This will be performed in Mode 3 and will satisfy Technical Specifications 3.7.1.5.

. . . . . - - , . . - - . - - . . . - .