TXX-4647, Forwards Table Providing Description of FSAR Amend 57

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Forwards Table Providing Description of FSAR Amend 57
ML20138P352
Person / Time
Site: Comanche Peak  
Issue date: 12/20/1985
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Noonan V
NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
References
TXX-4647, NUDOCS 8512260070
Download: ML20138P352 (4)


Text

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Log # TXX-4647 ile # 10010 TEXAS UTILITIES GENERA'IING COMPANY SKYWAY TOWER e 400 NORTH OtJVE trlFREET. L.B. 8 8. DALLAS. TEXA8 7S301 M Eff.f3 MAS December 20, 1985 Director of Nuclear Reactor Regulation

Attention: Mr. Vincent S. Noonan, Director

-Comanche Peak Project Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445'AND 50-446 FSAR AMENDMENT 57 DESCRIPTION

Dear Mr. Noonan:

Attached is a table providing the description of Amendment 57 (dated December 20, 1985) to the CPSES FSAR.

Very truly yours,

/

N W. G. Counsil JWA/grr Attachment

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5 AD - J. Knight (1tr only)

A EB (BALLARD)

EICSB (ROSA)

PSB (GA.%DlILL) a invasion or rExas urstrrrEs ELECTNrC COMPAN" RSB (BERLINGER)

FOB (BENAH0YA)

CPSES/FSAR AMENDMENT 57 DESCRIPTION Section Description of Change IA(B)

Revise wording per NP.C request in discussion regarding Reg. Guide 1.44.

3.98 Removes reference to use of specific tables to define the acceptance criteria for maximum allowable deflection during steady state vibration testing.

T3.118-5 Update tables to reflect latest EQ information.

EQR T4-1 Update tables to reflect latest EQ information.

EQR T5-1 Update tables to reflect latest EQ information.

EQR T5-2 Update tables to reflect latest EQ information.

5.2 Update ASME Code Addenda for reactor coolant pipe.

Correct methodology for computing containment sump "1 gpm leak rate".

Revise 1 gpm leak alarm test description.

T5.2-1 Update ASME Code Addenda for reactor coolant pipe.

T6.2.4-5 Minor changes to test arrangements for a few isolated valves.

7.4 Update to Alternate Shutdown description.

T7.4-2 Update table to reflect change to Alternate Shutdown description.

7.6 Update to the description of the RCS low temperature overpressure interlocks.

F7.6-5 Update figure to reflect changes to.

the description of the RCS low temperature overpressure interlocks.

y CPSES/FSAR Section-Description of Change 9.1 Delete the use of poly bags with new fuel assemblies.

2 Update water chemistry tables.

+-

T9.2 T9.3 Revise to lower sampling rate to meet delay time requirements for N16 decay.

10.4-Revise' silica specification.

Update Auxiliary Feedwater System

+

description.

T10.4 Update water chemistry tables.

12.5 Provides editorial correction.

13.1 Provide update to organization to-reflect new management appointments and personnel changes.

F13.1-2 Revised to reflect new management appointments.

13.6 Provides update to site security organization.

14.2 Revise wording to refer to Table 17A-1.

15.0 Adds the phrase "except as noted".

4 15.2 Provides new accident analyses for loss of non-emergency power, loss of normal feedwater, and feedwater i

system pipe break.

T15.2-Revised to reflect changes to Section 15.2.

.F15.2 Revised to reflect changes to Section 15.2.

j 15.6 Provides clarification to the air volume in the control room.

p,

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i CPSES/FSAR

. Section Description of Change 9

~ 17.1 Provides reference to' Table 17A-1.

Provides editorial changes requested

-by NRR QA Program Reviews.

F17.1-6 Revised to reflect changes to organization and new management appointments.

T17A

' Adds diesel generator intake air flexible connectors to Table 17A-1.

Adds Note B on Sheet 21.

Update Table 17A-2 to reflect changes in Table 17A-1.

LQ212 Corrects methodology for computing containment sump "I gpm leak rate".

- Q491 Revised due to CPSES no longer being lead plant for hafnium control rods.

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.-