ML20127B733
| ML20127B733 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/08/1993 |
| From: | William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-93011, NUDOCS 9301130090 | |
| Download: ML20127B733 (5) | |
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N M Log # TXX-93011 File # 914.2 10010 P.ef. # 10CFR50.34(b)
TUELECTRIC January 8, 1993 Willlem J. Cahill, Jr.
Group Vre frtsident U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - Unit 2 00CKET NO. 50-446 DEFERRAL OF PRE-0PERATIONAL TESTING REF:
TU Electric letter logged TXX-92586 from William J. Cahill, Jr.
to the U.S.N.R.C dated December 23, 1992 Gentlemen:
Per the telephone conversation between the NRC and TO Electric on January 6, 1993, 10 Electric hereby provides a revised description of the pre-operational / acceptance testing to be deferred past fuel load.
These revised lists supersede the information provided in the referenced letter.
A revised list has been provided of pre-operational / acceptance testing to be deferred past fuel load (see Attachment 1 - POST FUEL LOA 0 DEFERRED TESTING).
In addition, a revised list has also been provided for the portion of the pre-operational / acceptance testing that will require retesting to ba deferred past fuel load (see Attachment 2 - POST FUEL LOAD DEFERRED RETESTING). The schedule for performing the deferred testing / retesting ensures that systems required to prevent, limit, or mitigate the consequences of postulated accidents will be tested prior to the systems being required operable and ensures that the safety of the plant will not be dependent on the performance of untested systems, structures, and components.
120057 9301130090 930100 g
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TXX-93011 Page 2 of 2 No additional deferrals are anticipated at this time. However, upon completion of the review and approval of remaining test results by the Joint Test Group (JTG) prior to fuel load, additional modifications to these lists, if any, will be provided.
)h William J. Cahill, Jr.
By:
44 Roger D. Walker Manager of Regulatory Affairs for NEO RSB/
Attachments c-Mr. J. L. Milhoan, Region IV Residentinspectors,CPSES(2)
Mr. B. E. Holian, NRR
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4 to TXX-93011 Page 1 of 2 POST FUEL LOAD DEFERRED TESTING 1.
Mixed Bed Demineralizers Verify proper flow to the mixed bed demineralizers and determine delta -
P and effectiveness of the demineralizers and filters.
Delta P test across one of the three mixed bed demineralizers could-not be performed due to potential contamination of that demineralizer.'
Normaloperatingpressure(NOP)andexpansionoftheradiologically-controlled area (RCA) to include Unit 2 are required. This mixed bed-domineralizer is not required for safe operation of the plant.
However, testing is scheduled to be complete prior to entry into Mode 2.
2.
Boron Thermal Regeneration System - Loaded Chiller Testing Verify flows to and from thermal regeneration demineralizers and the -
piping vibration response.
Demineralizer delta P measurements could not he taken due to potential contamination problems. -NOP and RCA expansion to~ include Unit 2-are required.
This system is a non-safety related system which' TU Electric has no immediate. plans for making operable. This system will be tested prior to utilizing the system for-its intended purpose at which time the lines will also be looked at for vibration response.
~ 3.
Extraction Steam to Auxiliary Steam System Monitor the Unit 2 extraction steam piping-to Auxiliary Steam System for thermal expansion.
Extraction steam piping did not reach normal operating temperature (NOT)duringHotfunctionTesting(HFT). NOT is required. This line serves no safety-related. function.
Testing is scheduled to. be complete prior to commercial operation.-
4.
Communication Systems Demonstrate that the.Public_ Address and Emergency Evacuation Alarm System are audible during the highest expected ambient noise _ levels.
Evacuation Alarm Test and Audibility of Gatroitics System have not been completed.- The' system will have been verified functional; prior:to fuel load. Completion of; testing requires normal operating background-noise.
Testing will - commence :as ! soon' as practical ' and will----be completed prior to entry into Mode 2.
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Attachment I to TXX-93011 Page 2 of 2 5.
Fuel Pool Cooling and Cleanup System 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.
.6.
Steam Dump Valves Demonstrate the proper operation of the steam dump valves.
~
Steam dump valves did not operate properly during HFT.
Valves have been reworkeo and the remaining testing requires secondary system steam. These valves serve no safety-related function. Valve stroke time testing is scheduled to be performed prior to entry into Mode 2.
7.
Reactor Cavity Humidity--Detectors Demonstrate the proper operation of the humidity' detectors and associated annunciators.
The replacements for the defective detectors were not available for testing while the reactor vessel head was installed during HFT. They will be installed af ter the reactor head is in place af ter fuel load.
These detectors. serve no safety-related function.
Testing is scheduled to be complete prior to entry into Mode 2.
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' to TXX-92586 Page 1 of 1 POST FUEL LOAD DEFERRED RETESTING 1.
PowerOperatedReliefValves(PORV)LeakTightness.
Demonstrate leak tightiess of PORVs.
PORVs leaked during Hot functional Testing (HFT)..The valves have been modified to install spacer rings in accordance.with a Westinghouse Field Change notice to correct the leakage problem. NOP and NOT are required to retest the valves. Retesting is required to be completed-prior to' entry into Mode 2 (Technical Specification 3.4.4 applies).
2.
Pressurizer Spray Valve Leakage Demonstrate leak rate of pressurizer spray valve.
Pressurizer spray valve leaked higher than expected during HFT. Valve has been reworked; NDP and NOT are required to retest the valve.
Retesting it scheduled to be complete prior to entry into Mode 2.
3.
Sampling off Mo -ture Separator Reheaters (MSRs)
Demonstrate ability to'iraw samples-from MSRs.
Design modifications have been made to the moisture separator portion _-
of the secondary sampling system.
Secondary plant systems must be hot--in order to retest.
This sampling equipment serves no. safety-related function.
Testing is scheduled-to be complete prior to commercial operation.
4 Main Steam Isolation Valve Test Verify the proper _ stroke time.for. Main Steam Isolation Valve.
Pre-operational test data was inconclusive in demonstrating proper stroke time for one main steam isolation valve due to measuring and test equipment problems.
NOP and' NOT are required to retest the L valve. _ Retesting will be -performed expeditiously in Mode 3 when conditions permit.
Retesting is-required: to be. complete. prior to:
entry into Mode 2 to satisfy Technical Specifications 4.3.2.2 and
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