ML20151D631

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Proposed Tech Specs Table of Contents & Section 2.19
ML20151D631
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/19/1988
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20151D617 List:
References
NUDOCS 8807250185
Download: ML20151D631 (8)
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IfCHNICAL SPECIFICATIONS - TABLES

, TABLE OF CONTENTS ,

TABLE DESCRIPTIOy PfASE ,

i 1-1 RPS LSSS. . . . . . . . . . . . . . . . . . . . . . . . . . . 1 10 '

1-10a ,

2-1 ESFS Initiation Instrumentation Setting Limits. . . . . . . . 2-64 2-64a 2-2 Instrument Operating Requirements for RPS . . . . . . . . . . 2-67 2-67a 2-3 Instrument Operating Requirements for Engineered Safety Features . . . . . . . . . . . . . . . . . . . . . . . 2-68

. 2-68a 2-68b 2-4 Instrument Operating Conditions for Isolation Functions . . . 2-69 2-69a 2-5 Instrumentation Operating Requirements for Other Safety Feature Functions . . . . . . . . . . . . . . . . . . . . . . 2-70 2-7 Fire Detection Zones. . . . . . . . . . . . . . . . . . . . . 2 90

p Halon Area Fire Zones . . . . . . . . . . . . . . . . . . . . 2-90a 2-8 Fire Hose Station Locations . . . . . . . . . . . . . . . . . 2-94 2 95 2-9 RCS Pressure Isolation Valves . . . . . . . . . . . . . . . . 2-2d 2-10 Post-Accident Monitoring Instrumentation Operating Limits . . 2 98 2-98a 2-98b 2-11 Toxic Gas Monitors Operating Limits . . . . . . . . . . . . . 2-100 3-1 Minimum Frequencies for Checks, Calibrations, and Testing of RPS. . . . . . . . . . . . . . . . . . . . . . 3-3 3-4 3-5 36 3-2 Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Features, Instrumentation and Controls. . . 3-7 38 3-9 3-10 3-11 8807250185 as0719 3 12 l

fDR ADOCK 0C000285PDC ,

3-12a l

l iv I

TECHNICAL' SPECIFICATIONS TABLES TABLE OF CONTENTS TABLE DESCRIPTION EAGE 3-3 Minimum Frequencies for Checks, Calibrations, and Testing of Miscellaneous Instrumentation and Controls. . . . . . . . . 3-13 3-14 3-15 3-16 3-16a 3 16b 3-16c 3-4 Minimum Frequencies for Sampling Tests. . . . . ....... 3-18 3-19 3-5 Minimum Frequencies for Equipment Tests . . . . . . . . . . . 3-20 3-20a 3-20b 3-20c 3-20d 3-6 Reactor Coolant Pump Surveillance . . . . . . . . . . . . . . 3-27 3-7 Capsule Removal Schedule. . . . . . . . . . . . . . . . . . . 3-27 3-9 Radiological Environment Monitoring Program . . . . . . . . . 3-66 3-67 3-11 Radioactive liquid Waste Sampling and Analysis. . . . . . . . 3-72 3-73 3-12 Radioactive Gaseous Waste Sampling and Analysis . . . . . . . 3-74 3-75 3-13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . 3 90 5.2-1 Minimum Shift Crew Composition. . . . . . . . . . . . . . . . 5-2 v

.. e TECHNICAL SPECIFICATIONS - TABLES TABLE OF' CONTENTS (ALPHABETICAL ORDER)

BB.LE DESCRIPTION PJ,GE ,

1 I

3-7 Capsul e Removal Schedul e. . . . . . . . . . . . . . . . . . . 3 27 ,

2-1 ESFS Initiation Instrumentation Settina Limits. . . . . . . . 2-64 2 64a 2-7 Fire Detection Zones. . . . . . . . . . . . . . . . . . . . . 2-90 2-8 Fire Hose Station Locations . . . . . . . ........ 2-94 r 2-95 2-7 Halon Area Fire Zones . . . . . . . . . ......... 2 90a 2-4 Instrument Operating' Conditions for Isolation Functions . . . 2-69 2-69a 2-2 Instrument Operating Requirements for RPS . . . . . . . . . . 7 ' .

I it ,

2-3 Instrument Operating Requirements for Engineered  :

Safety Features . . . . . . . . . . . . . . . . . . . . . . . 2-68 2 68a 2 68b !

1 2-5 Instrumentation Operating Requirements for Other Safety '

Feature Functions . . . . . . . . . . . . . . . . . . . . . . 2-70 32 Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Features, Instrumentation and Controls. . . 37  !

3-8 3-9 r 3-10 '

3-11 3-12 l 3 12a  ;

3-3 Minimum Frequencies for Checks, Calibrations, and Testing of Miscellaneous Instrumentation and Controls. . . . . . . . . 3-13 .

3-14 f 3-15 3-16 3 16a 3-16b ;

3-16c j 3-1 Minimum Frequencies for Checks, Calibrations, and Testing of RPS. . . . . . . . . . . . . . . . . . . . . . 3-3  ;

3-4 3-5 l 36 vi

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TECHNICAL SPECIFICATIONS - TABLES

' TABLE OF CONTENTS (ALPHABETICAL ORDER)

Continued TABLE DESCRIPTION PAGE Minimum Frequencies for Equipment Tests . . . . . . . . . . . 3-20

~

3-5 3-20a 3-20b 3-20c 3-20d 3-4 Minimum Frequencies for Sampling-Tests. . . . . ....... 3-18 3-19 >

5.2-1 Minimum Shift Crew Composition. . . . . . . . . . . . . . . . 5-2

'2-10 Post-Accident ltonitoring Instrumentation Operating Limits . . 98 2-98a 2-98b 3 Radioactive Gaseous Waste Sampling and Analysis . . . . . . . 3-74 3-75 3-11 Radioactive Liquid Waste Sampling and Analysis. . . . . . . . 3-70 3-73 3-9 Radiological . Environment Monitoring Program . . . . . . . . . 3-66 3-67 2-9 RCS Pressure Isolation Valves . . . . . . . . . . . . . . . . 2-2d 3-6 . Reactor Coolant Pump Surveillance . . . . . . . . ..... 3-27 1-1 RPS LSSS. . . . . .-. . . . . . . . . . . . . . . . . . . . . 1-10 1-10a-3-13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . 3-90 2-11 Toxic Gas Monitors Operating Limits . . . . . . . . . . . . . 2-100 i:

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1 TECHNICAL SPECIFICATIONS - FIGURES TABLE OF CONTENTS PAGE WHICH FIGURE- DESCRIPTION TABLE FOLLOWS 1-1 LTMLP Safety Limits 4 Pump Operations. . . . . . . . . . . . . 1-3 2: ' Axial Power Distribution LSSS for 4 Pump Operation ..... 1-3 1-3 .TMLP LSSS 4 Pump Operation. . . . . . . . . . . . . . . . . . 2-6 1A RCS Press-Temp Limits Heatup. . . . . . . . . . . . . . . . . 2-7a 2-1B RCS - Press-Temp Limits Cooldown. . . . . . . . . . . . . . . . 2-7a 2-3 Predicted Radiction Induced NDTT Shift. . . . . . . . . . . . 2-7a 2-10 Spent Fuel Pool Region 2 Storage Criteria . . . . . . . . . . 2-38a 2-4 .PDIL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-57e 2-5 Allowable Peak Linear Heat Rate vs Burnup . . . . . . . . . . 2-57e 2-6 ~ LC0 for Excore Monitoring of LHR. . . . . . . . . . . . . . .

2-57e 2-7 LC0 for DNB Monitoring. . . . . . . . . . . . . . . . . . . . 2-57e 2-8 Flux Peaking-Augmentation Factors . . . . . . . . . . . . . . 2-57e 2-9 FT,F A

T X Y and Core Power Limitations . . . . . . . . 2-57e viii

)

s ATTACHMENT B Justification and No Significant Hazards Consideration

.This proposed change to Appendix A of Operati ng License DPR-40 is an editorial improvement to the. Table of Contents of the Technical Specifications. Cur-rently, the Fort Calhoun Station (FCS) Technical Specifications do not contain a listing of their tables and figures in the Table of Contents. The addition of such listings makes the FCS Technical Specifications more user friendly, allowing an individual to more easily locate information contained in tables and figures. Due to the number of tables contained in the FCS Technical Specifications, two listings of tables have been provided. One listing is in numerical order while the other is in alphabetical order by table title. Add-itionally, a correction is made to an internal reference listed in Section 2.19(4)b. This section references Section 5.9.2a for reporting requirements, Section 5.9.2 was revised in Amendment 99, combining Sections 5.9.2a and 5.9.2b into a new Section, 5.9.2. This internal reference was inadvertently overlooked.

No Sianificant Hazards Considerations The proposed changes do not involve significant hazards based on the following information:

Will the change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The subject changes do not involve a material alteration of equipment or a change in operational methods. The proposed changes do not alter any inputs or methodologies. utilized in safety analyses for FCS. The subject changes are editorial in nature only.

Will the change create the possibility of a new oc different kind of accident from any accident previously evaluated?

No. The subject changes do not involve a material alteration of equipment or a change in operational metieds. The proposed changes do not alter any inputs or methodologies utilized in safety analyses for FCS. The subject changes are editorial in nature only.

Will the change involve a significant reduction in a margin of safety?

No. The subject changes are editorial in nature and augment the table of contents of the Technical Specifications. The addition of listing of tables and figures allow Technical Specification users to more easily locate information. No Technical Specification bases have been modified.

For the stated reasons, Omaha Public Power District does not believe the proposed changes to the Technical Specifications involve any significant hazards.

J

,y . .

2.0 LIMITING CONDITIONS FOR OPERATION 2.19 Fire Protection System (Continued)

(3) The provisions set forth in Section 2.19(2) do not apply to time periods during which Containment Integrated Leak Rate Tests are being performed.

(4) Fire suppression water system shall be operable, except during system testing,_ jockey pump maintenance or training (not to exceed 7 consecutive days) with both fire pumps, each with a minimum capacity j of 1800 gpm, with their discharge aligned to the fire suppression header and automatic initiation logic for each fire pump.

a. With less than the above required equipment:

(i) restore the inoperable equipment to operable status within 7 days.

(ii) if equipment is not restored to operable status within 7 days, prepare and submit. a report to the Nuclear Regulatory Commission, pursuant to Section 5.9.3.i of the Technical Specifications, within the next 30 days, outlining the plans and procedures to be used to provice for the loss of the system and the cause of the malfunction,

b. With no fire suppression water system operable:

(i) establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(ii) notify Section(theJiu4 ear Regulatory 5.9.2.xof Commission, the Technical pursuant to Specifications, outlinind-~t he cause of the malfunction, the actions taken, and the plans and schedule for restoring "he system to operable status.

(iii) If (i) above cannot be ful filled, place reactor in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following thirty (30) hours.

(5) The sprinkler system in the Diesel Generator Rooms, the sprinklers above the steam driven auxiliary feedwater pump, the sprinkler / spray nozzle system in the compressor room, and the deluge system in the personnel corridor between fire areas 6 and 20 shall be operable except during system testing. If inoperable:

a. Within one hour establisly a continuous fire watch with backup fire ext.inguishira aq"YL iur tnose areas in which reaundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

AmendmentNo.38,53,gg 2-91

ATTACHMENT B Justification and No Significant Hazards Consideration This proposed change to Appendix A of Operating License DPR-40 is an editorial improvement to the Table of Contents of the Technical Specifications. Cur-rently, the Fort Calhoun Station (FCS) Technical Specifications do mot contain a listing of their tables and figures in the Table'of Contents. The addition of such listings makes the FCS Technical Specifications more user friendly, allowing an individual to more easily locate information contained in tables and figures, Due to the number of tables contained in the FCS Technical Specifications, two listings of tables have been provided. One listing is in numerical order while the other is in alphabetical order by table title. Add-itionally, a correction is made to an internal reference listed in Section

'2.19(4)b. This.section references Section 5.9.2a for reporting requirements, Section 5.9.2 was revised in Amendment 99, combining Sections 5.9.2a and 5.9.2b into a new Section, 5.9.2. This internal reference was inadvertently overlooked.

No. Sianificant Hazards Considerations The proposed changes do not involve significant hazards based on the following information:

Will the change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The subject changes do not involve a material alteration of equipment or a change in operational methods. The proposed changes do not alter any

. inputs or methodologies utilized in safety analyses for FCS. The subject cr.anges are editorial in nature only.

Will the change create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The subject changes do not involve a material alteration of equipment or a change in operational methods. The proposed changes do not alter any inputs or methodologies utilized in safety analyses for FCS. The subject changes are editorial in nature only.

Will the change involve a significant reduction in a margin of safety?

No. The subject changes are editorial in nature and augment the table of contents of the Technical Specifications. The addition of listing of tables and figures allow Technical Specification users to more easily locate information. No Technical Specification bases have been modified.

For the stated reasons, Omaha Public Power District does not believe the proposed changes to the Technical Specifications involve any significant hazards.

J

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