ML20066C049

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Proposed Tech Specs Re Surveillance Requirement 4.6.G & Associated Bases on Structural Integrity
ML20066C049
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1990
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20066C047 List:
References
NUDOCS 9101090157
Download: ML20066C049 (13)
v • d • e


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i ATTACHMENT 2 2

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l PEACH BOTTOM ATOMIC POWER STATION 4

UNITS 2 AND 3 i

Docket Nos. 50-277.

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1,1 cense Nos. DPR-44 DPR-56 4

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TECHNICAL SPECIFICATION CHANGES r

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Unit 2 Unit 3 i

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-150 150 161 161 162 162 163 163 9101090157 901231 POR ADOCK 05000277

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i Unit 2 PBAPS-LIST OF TABLES i

Table Title Page A'

4.2.B Minimum Test and Calibration frequency 81-i for CSCS i

4.2.C Minimum Test and Calibration frequency 83 for Control Rod Blocks Actuation

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4.2.0 Minimum Test and Calibration frequency

- 84 j

l for Radiation Monitoring Systems j

4.2.E Minimum Test and Calibration frequency 85 for Drywell Leak Detection J

4.2.f Minimum Test and Calibration frequency 86:

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for Surveillance Instrumentation u,

4.2.G Minimum Test arid Calibration frequency

'. 88 i

I for Recirculation Pump Trip 133d 5

3.5 K.2 DELETED-1 i

3.5.K.3 DELETED

. 133d.

4.6.1 DELETED

- 150 l

3.7.1 Primary Containment Isolation Valves 179 4

3.7.2 Testable Penetrations with Double 184 0-Ring Seals i

3.7.3 Testable Penetrations with Testable 184 Bellows I

3.7.4 Primary Containment Testable-Isolation 185

-l Valves j

4.8.1 Radioactive Liquid Waste Sampling and -

216b !

Analysis f

4.6.2 Radioactive Gaseous Waste Sampling and' 216c-1 i

Analysis-4.8.3.a Radiological Environmental Monitoring-216d-1 Program i

4.8.3.b Reporting' Levels-for-Radioactivity-by 216d ;

t Concentrations _in Environmental Sample

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PBAPS Unit 3

' LIMIT'ING CONDITION POR OPERATION SURVEILLANCE REQUIREMENTS 3.6.G Structural Integrity 4.6.G Structural Integrity The structural integrity of 1.

Inservice inspection of ASME the primary system boundary Code Class 1, 2, and 3 shall be maintained at the components shall be level required by the performed in accordance original acceptance standards with Section XI throughout the life of the of the ASME Doller and station.

The reactor shall Pressure Vectel Code and-be maintained in a Cold applicable Addenda as Shutdown condition until required by 10 CFR each indication of a defect Part 50, Section 50.55a(g),

has been investigated and except where relief evaluate,

has been granted by the Commission pursuant to 10 CPR Part 50, Section 50.55a(g)(6)(1) and (a)(3).

2. The Augmented Inservice Inspection Program for piping shall be performed in accordance with the staff positions on schedule, methods, personnel and sample expansion as provided by M3C Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.
3. Nothing in the ASME Boller and Pressure Vessel Code l

shall be construed to supersede l

the requirements of any Technical Specification.

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Unit 2 4.

PBAPS i

3.6.G & 4.6.G Bases S_tructural Integrity The inspection programs for ASME Code Class 1, 2 and 3 components ensure that integrity of these components will be maintained at an acceptable level throughout the life of the plant.

The Inservice Inspection Program was developed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1970 Edition, except where accessibility for inspection was not provided and where it was impractical to modify the original design.

The Inservice Inspection Program for ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR Part 50.55a(g) except where specific written i"

relief has been granted by the NHC pursuant to 10 CPR Part 50.o' 5a(g)(6)(1) and (a)(3).

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s Unit 3 P8APS Ll!! Of TABLES Table Title Page 4.2.8 Minimum Test and Calibration frequency 81 for CSCS 4.2.C Minimum Test and Calibration Frequency 83 for Control Rod Blocks Actuation 4.2.0 Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration frequency 85 for Drywell Leak Detection 4.2.F Minimum lest and Calibration frequency 86-for Surveillance Instrumentation 4.2.G Minimum lest and Calibration frequency 88 for Recirculation Pump Trip 3.5.K.2 DELETED 133d 3.5.K.3 DELETED 133d 4.6.1 DELETED 150 l

3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations with Double 184 0-Ring Seals 3.7.3 Testable Penetrations with Testable 184 Bellows

!. 7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive liquid Waste Sampling and 216b-1 Analysis 4.8.2 Radioactive Gaseous Waste Sampling and 216c-1 Analysis 4.8.3.a Radiological Environmental Monitoring 216d-l Program 4.8.3.b Reporting Levels for Radioactivity 216d-5 Concentrations in Environmental Samples

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PBAPS Unit 3 "L'IMITING CONDITION POR OPERATION SURVEILLANCE REQUIREMENTS l

3.6.G Structural Integrity 4.6.G Structural Integrity The structural integrity of

1. Inservice inspection of ASME the primary system boundary Code Class 1, 2, and 3 shall be maintained at the components shall be level required by the performed in accordance original acceptance standards with Section XI throughout the life of the of the ASME Boiler and station.

The reactor shall Pressure Vessel-Code and

.i be maintained in a Cold applicable' Addenda as-Shutdown condition until required by 10 CPR each indication of a defect Part 50, Section 50.55a(g),

has been investigated and except where relief i

evaluated.

has been-granted-by the Commission i

pursuant to 10.CPR Part 50, Section 50.55a(g)(6)(1) andL(a)(3).

2. The Augmanted-Inservice Inspoetion Program for' piping shall be performed in accordance 1

with.the staff positions-Ron schedule, methods, personnel and sample expansion as provided by~NRC Generic Letter 88-01 orz in

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accordance'with alternate 3

measures approved;by i

the NRC staff.

1

-3.'Nothing in1 the ASME Boiler 3

and Pressure Vessel _ Code.

shall be construed to supersede the. requirements of any Technical Specif1tation, i

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Unit 3 s

.s PBAPS 3.6.G & 4.6.0 Bases Structural Integrity The inspection programs for ASME Code Class 1, 2 and 3 components ensure that integrity of these components will be maintained at an acceptable level throughout the life of the plant.

The Inservice Inspection Program was developed in accordance with Section XI of the ASME Boller and Pressure Vessel Code 1970 Edition, except where accessibility for inspection was not provided and where it was impractical to modify the original design.

The Inservice Inspection Program for-ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CPR Part 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CPR Part 50.55a(g)(6)(1) and (a)(3).

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