ML20126D951

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Forwards List of Preoperational/Acceptance Testing Items to Be Deferred Past Fuel Load.Lists Tentative Pending Review & Approval of Remaining Test Results by Joint Test Group
ML20126D951
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 12/23/1992
From: William Cahill, Walker R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-92586, NUDOCS 9212280240
Download: ML20126D951 (4)


Text

Log # TXX-92586 File # 914.2 10010 r

r Ref. # 10CFR50.34(b) illELECTRIC Oecember 23, 1992 William J. Cahill, Jr.

Group Vke President U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - Unit 2 DOCKEI NO. 50-446 DEFERRAL OF PRE-0PERATIONAL TESTING Gentlemen:

TU Electric hereby provides a list of pre-operational / acceptance testing to be deferred past fuel load (see Attachment 1 - POST FUEL LOAD DEFERRED TESTING).

In addition, a list ' as also been provided for the portion of the pre-operational / acceptance testing that will require retesting to be deferred ast fuel load (see Attachment 2 - POST FUEL LOAD DEFERRED RETESTING.

These lists are tentative pending the review and approval of remaining test results by the Joint Test Group (JTG).

Upon completion of the JTG review prior to fuel load, modification to these lists, if any, will be provided.

Sincerely, P!hc William J. Cahill, Jr.

By:

Mb Roger't. Walker Manager of Regulatory Affairs for NE0 RSB/

Attachments c-Mr. J. L. Milhoan, Region IV Resident Inspectors, CPSES (2)

Mr. B. E. Holian, NRR C,Q A ; A '

9212280240 921223 PDR ADOCK 05000446 pS *nl A

PDR 400 N, Olive Street LB. 81 Dallas, Texas 75201 l

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i to TXX-92586 Page 1 of 2 i

POST FUEL LOAD DEFERRED TESTING i

i-j 1,

Mixed Bed Demineralizers j

Verify proper flow to the mixed bed demineralizers and determine-j delta P and effectiveness of the demineralizers and filters.

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Delta P. test across one of the three mixed bed demineralizers could not be performed due to potential contamination of that-demineralizer. Normal operating pressure (NDP) and expansion of I

the radiologically controlled area (RCA) to include Unit 2 are j

required. -This mixed bed demineralizer is not required _for safe

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operation of the plant. However, testing is scheduled to be i

complete prior to entry-into Mode 2.

l 2.

Boron Thermal Regeneration System - Loaded Chiller Testing

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Vr'ify flows to and from thermal regeneration demineralizers.

Demineralizer delta P measurements-could not be-taken due to l

potential contamination problems.

NOP and.RCA expansion to include Unit 2 are required. This system is a non-safety related system i

which TV Electric has no immediate plans for making operable. This j

system will.be tested at the earliest convenience for operation, i

3.

Extraction Steam to Auxiliary Steam System i

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Demonstrate ability to supply Unit 1 extraction steam to Unit 2 l

Auxiliary Steam System.

Cross-tie piping t'o Unit 1 could not'be tested with unit operating.

l Normal operating _ temperature (NOT) and NOP are required. This line serves no safety-related function. Testing is scheduled to be j

complete prior to commercial operation.

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4.

Communication Systems i

Demonstrate that the Public Address and Emergency Evacuation Alarm System are audible during the highest expected ambient no he levels.

Communications and Sound Powered Telephone Evacuation Alarm. Test and Audibility of Gatronics Systen have not been completed.

Adequate testing requires normal operating (ground noise.

Testing will commence as soon as practical c vill be completed.

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prict to entry into Mode 2.

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' to TXX-92586 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 d

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 3

been reworked and the remaining testing requires secondary system steam. These valves serve no safety-related function.

Testing is scheduled to be performed as part of power ascension testing.

7.

Reactor Cavity Humidit_y Detectors Demonstrate the proper operation of the humidity detectors and associated annunciators.

These detectors were not available for testing while the reactor vessel head was installed during hot functional.

They will be installed after the reactor head is in place after 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 1

POST FUEL LOAD DEFERRED RETESTING i

1.

Power Operated Relief Valves (PORV) Leak Tightness Demonstrate leak tightness of PORV.

4 PORV leaked during Hot Functional Testing (HFT).

The valve is being reworked; NOP and NOT are required to retest the valve.

Retesting is required to be performed prior to entry into Mode 2 to j

satisfy Technical Specification 3.4.4.

2.

Pressurizer Spray Valve Leakage i

Demonstrate leak tightness of pressurizer spray valve.

4 Pressurizer spray valve leaked during HFT. Valve has been reworked; NDP and NOT are required to retest the valve.

Retesting i

is required to be performed prior to entry into Mode 3 to satisfy Technical Specification 3.4.3.

4 3.

Sampling off Moisture Separator Reheaters (MSRs)

Demonstrate ability to draw samples from MSRs.

i Design modifications have been made to the moisture separator portion of the secondary sampling system.

Secondary plant system must be hot in order to retest.

This_ sampling equipment serves no safety-related function. Testing is scheduled to be complete prior to commercial 'peration.

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 l

stroke time for one main steam isolation valve.

NOP and NOT'are l

required to retest the valve. Retesting is required to be performed prior to entry into Mode 2 to satisfy Technical Specifications 4.3.2.2 and 4.7.1.5.

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