ML20084B177

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Proposed Tech Specs Reflecting Editorial Correction to Proposed Amends Re Incorporation of New Requirements of 10CFR20
ML20084B177
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/23/1995
From:
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20084B168 List:
References
NUDOCS 9505310159
Download: ML20084B177 (6)
v • d • e


Text

. l ATTACHMENT 2 TO TXX 95147 Supplemental changes to LAR 94 004 Incorporation of the New Requirements of 10 CFR Part 20 (20.1001 20.2402)

Pages 9 of 13 and 10 of 13 from TXX 95045 i

i 1

l 9505310159 950523 PDR ADOCK 05000445 P PDR

' ' /1/tA;^wT 3 7* 7M~ f904/.1 Py 1 # 13 AMIMISTRATIVE CONTROLE STARTup REPORT (Continued)

The initial Startup Report shall address each of the startup tests identified in I Chapter 14 of the Final Safety Analysis Report and shall include a description t of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and spectTications. Any corrective actions that were required to obtain satis-factory operation shall also be described. Any additional specific details required this report.

in license conditions based on other comitments shall be included in Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the acceptability of changes and/or modifications.

Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or comencement of commercialis power whichever earliest. operation, or (3) 9 months following initial criticality, If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or comencement of commercial operation), supplementary reports shall be sub- T mitted at least every 3 months until all three events have been completed. 4 ANNUAL REPORTS

  • 5 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each j The initial initial report shall be submitted prior to March I of the year foi criticality. ,

Reports required on an a m91 ha*4e shall i ~

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nual basis of he n on, utilit *^'**

and other greater than~100 s Q. er ( uding cg_ntractors) receiving A ,#"# O f""/

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oband the $ associated # D x T - ~ ' D f according to work a functions ** e.g., re M tons'an ~ /

surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20% of l

the individual total dose need n Jot accounted for. In the aggre-I

-Q eg received from external gate, sourcesat should least 805 of to be assigned the totalk l

ic inajor work functions;pec i  !

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  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are commen to all units at the station.

p "This tabulation supplements the requirements of 10 CFR N .

qv COMANCHE PEAK - UNITS 1 AND 2 6-18 g;, ;

. . - - = = . _ - - _ -. - . - - - - - -

& est 3 To 7XX ~ 9y045 47 /O o8 /3 AfBifNISTRATfVr mayans s ,

SpfCIAL rep M I 6.9.2 In additten to the applicable reporting requirements of Title 10. Code of Federal Regulattens, soecial reports shall be submitted to the Regional Admin-1strator of the Regional 6ffice of the NRC within the time period specified for each l report. 4 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, .

Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level;
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety;
c. All REPORTABLE EVENT 5;
d. Records of surveillance activities, inspections, and calibrations required by the Technical Specifications. Technical Requirements Manual, and Fire protection Report, except as explicitly covered in
  • gg Specification 4.10.3;

)* e. Records of changes made to the procedures required by De # " **

f. ...... .. ........... .~...
g. Records of sealed source and fission detector leak tests and results; and
h. Records of annual physical inventory of all sealed source material  !

of record. '

I 6.10.3 The following records shall be retained for the duration of the unit  !

Operating Liceness i

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; I
b. Records ef new and irradiated fuel inventory, fuel transfers, and i assembly bu
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c. Records of : %t.a . y..... P all indivi e z._.-;s Miette G  !

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I ynonMac;a uns requies lON FetNQO- '

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d. Records of gase sa igu a na eased a the  !
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$gpppW COMANCHE PEAK - UNIT 5 1 Ale 2 6-22 Unit 1 - Amendment No. 1 i )

1 i

O e ATTACHMENT 3 TO TXX 95147 Miscellaneous Editorial Corrections

l 4% cam.,# -3 to Tx x- 4 5 /4 7

.f%% i d$2-- m RASES l Er m 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................ 33/4!5-f 3/4.5.4 REFUELING WATER STORAGE TANK.............................. B 3/4J5-2 3/4.6 CONTAINMENT SYSTEMS ,

3/4.6.1 PRIMARY CONTAINMENT....................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

8 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE............................................. B B 3/4 7-1 3/4 7-3 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

3/4.7.3 COMPONENT C0OLING WATER SYSTEM............................ B 3/4 7-4 3/4.7.4 STATION SERVICE WATER SYSTEM.............................. B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK........................................ B 3/4 7-5 3/4.7.6 FL000 PROTECTION.......................................... B 3/4 7-5 j 3/4.7.7 CONTROL ROOM HVAC SYSTEM.................................. B 3/4 7-5 '

3/4.7.8 PRIMARY PLANT VENTILATION SYSTEM - ESF FILTRATION UNITS... B 3/4 7-6 l 3/4.7.9 SNUBBERS.................................................. B 3/4 7-6 3/4.7.10 AREA TEMPERATURE M0NITORING............................... B 3/4 7-7 3/4.7.11 UPS HVAC SYSTEM....'....................................... B 3/4 7-8 3/4.7.12 SAFETY CHILLED WATER SYSTEM............................... B 3/4 7-8 3/4.7.13 MAIN FEEDWATER ISOLATION VALVE PRESSURE /

TEMPERATURE LIMIT......................................... B 3/4 7-8 g 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.B.1, 3/4.5.2, and 3/4.5.3 A.C. SOURCES, D.C. SOURCES, and DNSITE POWER DISTRIBUTION............................. B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES . . . . . . . . . . . . . . . . . . . B 3/4 8-3/4.9 REFUELING OPERATIONS .

3/4.9.1 B0RON CONCENTRATION....................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................... B 3/4 9-1 3/4.9.3 DECAY TIME.... ........................................... B 3/4 B 3/49-1 9-1 3/4.9.4 CONTA1104ENT BUILDING PENETRATIONS.........................

3/4.9.5 C0PtquM I CAT ! 0NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.6 REFUELING MACHINE.........................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS................... B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............. B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and IRRADIATED FUEL STORAGE .............................. B 3/4 9-3 xii Unit 1 - Amendment No. B. 1 '

COMANCHE PEAK - UNITS 1 AND 2

kqtlNO mow +- 3 To TXX-95 W7 mg 2 sep_

EMERGENCY CORE C0OLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves  ;

are in the indicated positions with power to the valve operators  !

removed:

Valve Nn=her Valve Function Valve Position 8802 A & B SI Pump to Hot Legs Closed j 8808 A, B, C, D Accum. Discharge Open*

8809 A & B RHR to Cold Legs Open

)

i 8835 SI Pump to Cold Legs Open 8840 RHR to Hot Legs l Closed 8806 SI Pump Suction from RWST Open 8813 SI Pump Mini-Flow Valve Open i

b. At least once per 31 days by verifying that each valve (manual,  ;

power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

1

c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the l pump suctions during LOCA conditions. This visual inspection shall be performed:
1) For all accessible areas of the containment prior to establish- ,

ing CONTAINMENT INTEGRITY, and

2) At least once daily of the areas affected within containment by containment entry and during the finsi entry when CONTAINMENT INTEGRITY is established. i
d. At least once per 18 months by:
1) Verifying interlock action of the RHR system from the Reactor i Coolant System to ensure that with a simulated or actual l Reactor Coolant System pressure signal greater than or equal to 442 psig the interlocks prevent the valves from being opened.
  • Surveillance Requirements covered in Specification 4.5.1.

COMANCHE PEAK - UNITS 1 AND 2 3/4 5-4 Unit 1 - Amendment No. 4,40 Unit 2 - Amendment No. 26 ue_-.- - _-- -- - - . . . - . _ _ - . _ . . _ _ - __ _ _ _ _ . _ . . . . - - - - - - - - - ._ , _ _- . . + - - , . - . - - ... +

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