ML20100D289

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Errata to Amends 102 & 104 to Licenses DPR-44 & DPR-56, Respectively,Updating Tech Specs to Reflect Subsequently Issued Amends
ML20100D289
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/18/1985
From:
NRC
To:
Shared Package
ML20100D292 List:
References
NUDOCS 8504020383
Download: ML20100D289 (14)
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Text

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UPDATED TECHNICAL SPECIFICATION PAGES FACILITY OPERATING LICENSE N0. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed updated pages.

Remove Insert 11 11 iii lii vi vi via vii vii 84 84 207 207 I

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j 8504020383 850318 i

PDR ADOCK 05000277 i

P PDR I

PBAPS TABLE OF CONTENTS (Cont'd)

Pace SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMEN"5 3.6 PRIMARY SYSTEM BOUNDARY 4.6 143 A.

Thermal and Pressurization Limitations A

143 B.

Coolant Chemistry B

145 C.

Coolant Leakage C

146 D.

Safety and Relief Valves D

147 E.

Jet Pumos E

148 Recircu'ation Pumps F.

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F 149 G.

Structural Integrity G

149 3.7 CONTAINMENT SYSTEMS 4.7 165 A.

' Primary Containment A

165 B.

Standby Gas Treatment System B

175 C.

Secondary Containment C

176 D.

Primary Containment Isolation valves D

177 3.8 RADIOACTIVE MATERIALS 4.8 203 A.

General A

203 B.

Liquid Effluents B

204 C.

Gaseous Effluents C

208 D.

40 CFR 190 D

216 E.

Radiological Environmental Monitoring E

216a-2 F.-

Solid Radi5 active Waste.

F 216a-5 G.

Mechanic'al Vacuum Pump G

216a-6 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.

Auxiliary Electrical Eculpment A

217 B.

Operation with Inoperable Eculpment B

219 C.

Emergency Service Water System C

221 i

3.10 CORE 4.10 225 A.

Refueling Interlocks A

225 B.

Core Monitoring B

227 C.

Spent Fuel Pool Water Level C

228a D.

Heavy Loads Over Spent Fuel D

228a 3.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.11 233 A.

Main Control Room Ventilation A

233 B.

Alternate Heat Sink Facility B

234 C.

Emergency Shutdown Control Panel C

234 D.

Shock Suppressors, D

234a Amendment No.17, H,102, 11 104, (Updated March 18. 1985 )

s PBAPS TABLE OF CONTENTS(Cont' d)

Pace SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS

- - ~

--_.2.

3.12 RIVERLEV5L' 4.12

237-Al High River Water Level A

237 B.

Low River Water Level B

237 C.

Level Instrumentation C

238 3.13 MISCELLANEOUS RADIOACTIVE MATEhIALS SOURCES 4.13 240a 3.14 FIRE PROTECTION 4.14 240c A.

Water Fire Protection System A

240c B.

CO2 Fire Protection System B

240g C.

Fire Detection C

240i i

D.

Fire Barrier Penetrations D

240j E.

Water Suppression Systems E

240k F.

' Battery Rm. Vent. Flow Detector F

2401 3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240t 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CONTROLS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit Violation 253 l

6.8 Procedures 253 6.9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 l

6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 6.17 Offaite Dose Calculation Manual.

265 6.18 Major Changes to Radioactive Waste Treatment Systems 265 l

Anendment no. U,A7, 77, D, 102, iii 104 (Updated March 18, 1985)

PBAPS Unit 2 LIST OF TABLES Table Title.

Pace 4.2.B Minimum Test and Calibration Frequency, 81 for CSCS 4.2.C Minimum Test and Calibration Frecuency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frecuency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibraticri Freauency 85 for Drywell Leak Detection 4.2.F Minimum Test and Cali.bration Frecuency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frecuency 88 for Recirculation Pump Trip

.3.5.K.2 Operating Limit MCPR Values for 133d Various Core Exposures 3.5.K.3 Operating Limit MCPR Values for 133e Various Core Exposures 4.6.1 In-Service Inspection Program for Peach 15Q Bottom Units 2 and 3 3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations With Double 184 0-Ring Seals 3.7.3 Testable n'enetrations with Testabl e 1A4 Bellows 3.7.4 Primary Containment Testable Isolation 195 Valves 4.8.1 Radioactive Lieuid 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-1 P rogram

4. 8.3 b Reporting Levels, for, Radioactivity 236d-5 by Concentrations in Environmental Sample vi Aniendment No. 37, 44, gd,102 (Updated flarch 18, 1985)

1 PBAPS Unit 2 LIST OF, TABLES Table Title Pace 4.8.3.c Maximum Values for Minimum Detectable 216d-6 Levels of Activity 3.11.D.1 Safety Related Shock Suppressors 234d 3.14.C.1 Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u 3.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements Amendment No. I'G7, 104 vii (Updated!! arch 18, 1985)

TAnf.F. 4. 2. D gg o to

@5.

HINIMlH TEST & CALIBRATION FREOUENCY FOR RADI ATION HONITORING SYSTEMS ii <"n

o. 7, b

Instrument Functional Instrument 2P Instrument Channel s Test Calibration Check (2)

L 50

1) Refuel A ea Exhaust (1)

Once/3 months once/ day g

Honitora - Upscale es

2) Reactor Building Area (1)

Once/3 months once/ day v

I Logic System Functional Test (4) (6)

Frequency

1) Reactor Building Isolation Once/6 months a2 a
2) Standby Gas Treatment Once/6 months Syste'm Actuation e

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RECUIREFENTS

'may be used to estimate

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fl ow.

f. If the requirements of 3.8.B.3.a, 3.8.B.3.b, 3.8.B.3.c, 3.8.B.3.d, or 3.8.B.3.e cannot be met, suspend release of radio-active effluents via this pathway.
g. With less than the minimum I

number of radioactive licuid l

radwaste monitors OPERABLE exert best efforts to return the instruments to I

OPERABLE status within 30 l

days and if unsuccessful explain in the next Semi-annual Radioactive Ef fluent Release Report why the in-operability was not cor-rected in a timely manner.

4.

All licuids shall be 4a. Doses due to licuid processed throuch either ef fluent rel eases to the waste collector filter areas at and beyond the

.and demineralizer, the SITE BOUNDARY shall be fJ oer drain filter, or the projected once per menth fuel pool filter deminer-in accordance with the alizer as appropriate prior methodology and parameters l

to their discharge when in the ODCM.

the projected dose due t

to the licuid effluent 4b. The waste collector releases to unrestricted filter and demineralizer areas, when averaged over and the floor drain filter any month, expeeds 0.12 shall be demonstrated l

mrem to the total body operable once per cuarter, l

or 0.4 mrem to any organ unless utilized to process l

f rom the two reactors at liquid waste during the l

the site. With licuid previous 13 weeks, by waste being discharged analyzing the licuid without treatment as processed throuch the recuired above, prepare appropriate eouipment to and submit to the Com-determine that it meets mission within 21 working the recuirements of days pursuant to Specifi-Specification 3.8.B.1.

cation 6.9.3, a Special The fuel pool fil ter Peport which includes the demineralizer is exempt followine information:

from this recuirement

a. Explanation of why since it is an aJ ternate licuid radwaste was treatment system which is 207 Amen &ient No.102 (Reissued March 18, 1985)

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A

UPDATED TECHNICAL SPECIFICATION PAGES FACILITY OPERATING LICENSE NO. OPR-56 DOCKET NO."50-278 Replace the following pages of the Apoendix "A" Technical Specifications with the enclosed updated pages.

Remove Insert 11 11 iii iii iv iv vi vi via vii vii 84 84

/

/

//[

PBAPS TABLE OF CONTENTS (Cont'd)

Pace

,:M:TINO CONDITIONS FOR OPERATION SURVEILLANCE FIQUIREP'IN"5 3.6 PRIMARY SYSTEM BOITNDARY-4.6 143 A.

Thermal and Pressuriration Limitations A

143 B.

Coolant Chemistry B

145 C.

Coolant Leakage C

146 D.

Safety and Relief Valves D

147 E.

Jet Pumps E

148 F.

Recirculation Pumps F

149 l

G.-

S tructural Integrity G

149 3.7 CONTAINMENT SYSTEMS 4.7

.165 A.

Primary Containment A

165 B.

Standby Gas Treatment System B

175 C.

Secondary Containment C

176 D.

Primary Containment Isolation Valves D

177 3.8 RADIOACTIVE MATERIALS A.

General A

203 B.

Liquid Effluents B

204 C.

Gaseous Effluents C

208 D.

40 CFR 190 D

216 E.

Radiological Environmental Monitoring E

216a-2 F.

Solid Radioactive Waste F

216a-5 G.

Mechanical Vacuum Pump G

216a-6 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.

Auxiliary Electrical Ecuipment A

217 B.

Operation with Inoperable Ecuipment B

219 l

C.

Emergency Service Water System C

221 3.10 CORE 4.10 225 A.

Refueling Interlocks A

225 3.

Core Monitoring B

227 C.

Spent Euel Pool Water Level C

228a D.

Heavy Loads Over Spent Fuel D

22Ba 3.11 ADDITIONAL SAFETY RELA"'ID PLANT CAPABILITIES 4.11 233 A.

Main Control Room Ventilation A

233 B.

Alternate Heat Sink Facility B

234 C.

Emergency Shutdown Control Panel C

234 D.

Shock Suppressors D

234a l

l ii Amendment No. 73, 48,104, 108 (Updated ifarch 18, 1985)

PBAPS,.

' TABLE OF CONTENTS (Cont'd)

Pace SURVEILLANCE LIMITING CONDITIONS FOR OPEPATION REQUIREMENTS 3.12 RIVER LEVEL 4.12 237 A.

High River Water Level A

237 B.

Low River Water Level B

237 C.

Level Instrumentation C

238 3.13 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 4.13 240a 3.14 FIRE PROTECTION 4.14 240c A.

Water Fire Protection System A

240c B.

CO2 Fire Protection System B

240g C.

Fire Detection C

2401 D.

Fire Barrier Penetrations D

240j E.

Water Suppression Systems E

240k F.

Battery Rm. Vent. Flow Detector F

2401 3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240t 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CON *ROLS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit Violation 253 6.8 Procedures 253 6.9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 6.17 Offsite Dose Calculation Manual 265 6.18 Major Changes to Radioactive Waste Treatment Systems 265 l

Amendment No.

JJ,47,7),7$,

iii 104,108 (Updated March 18, 1985)

PBAPS UNIT 3 LIST OF FIGURES Fi=ure Title Page 1.1-1 APRM Flow Bias Scram 'Relati6nship To Normal 16 Operating Conditions 4.1.1 Instrument Test Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test 98 Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution 3.4.2 Required Temperature vs. Concentration for 123 Standby Liquid Control System Solution 3.5.K.1 MCPR Operating Limit vs. Tau, LTA 142 3.5.K.2 MCPR Operating Limit vs. Tau, PTA & P8X8R Fuel 142a 3.5.1.A DELETED 3.5.1.B DELETED 3.5.1.C DELETED 3.5.1.D DELETED 3.5.1.E Kf Factor vs. Core Flow 142d 3.5.1.F MAPLHGR vs. Planar Average Exposure, Unit 3 142e 8X8 PTA Fuel 3.5.1.G DELETED 3.5.1.H MAPLHGR vs. Planar Average Exposure, Unit 3 142g P8X8R Fuel (P8DRB284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, Unit 3 142h P8X8R Fuel (P8DPS299) 3.5.1.J MAPLHGR vs. Planar Average Exposure, Unit 3 1421 P8X8R Fuel (Generic) 3.5.1.K MAPLHGR vs. Planar Average Exposure, Unit 3 142j P8X8Q LTA (P8DQB326) 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatup or 164a Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core operation 164b (Criticality) i 3.6.4 Transition Temperature Shift vs. Fluence 164c 3.6.5 Thermal Power Limits of Specifications 164d 3.6.F.3, 3.6.F.4, 3.6.F.5, 3.6.F.6 and 3.6.F.7 l

3.8.1 Site Boundary And'~ Effluent Release Points 216e t

6.2-1 Mana~gement Organization Chart 244 1

6.2-2 Organization for Conduct of Plant Operation 245 l

i Amendment flo. JA, #7, AE, f3, $2, 77

-iv-pg,194,107 ( Updated flarch 18,198!I) i 1

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-u PBAPS Unit 3 LIST OF TABLES Table

' Title **

Pace 4.2.B Minimum Test and Calibration Frecuency 81 for CSCS 4.2.C Minimum Test and Calibratien Frecuency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibraticn Frecuency 84 for Padiation Monitoring Systems 4.2.E Minimum Test and Calibratien Frecuency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibratien Frecuency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibratien Frecuency 88 for Recirculation Pump Trip

  • 3.5.K.2 Operating Limit MCPR Values for 133d Various Core Exposures 3.5.K.3 Operating Limit MCPR Values for 133e Various Core Exposures 4.6.1 In-Service Inspection Procram for Peach 150 Bettom Units 2 and 3 3.7.1 Primary Centainment Isolation Valves 179 3.7.2 Testable Penetraticns With Double 184 0-Ring Seals 3.7.3 Testable Penetraticns With Testable 184 Bellows 3.7.4 Primary Centainment Testable Isolatien 185 Valves 4.8.1 Radioactive Licuid 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-1 Program 4.8.3.b Reporting Levels for Radioactivity 216d-5 Concentrations in Environmental Samples vi Amendment No. Jy, Jy, 79, ygg (Updated liarch 18, 1985) l

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s PBAPS Unit 3

~

LIST OF TABLES Table Titl e Pace

's 4.8.3.c Maximum Values for Minimum Detectable 216d-6 Levels of Activity 3.11.D.1 Safety Related Shock Suppressors 234d 3.14.C.1 Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u 4.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements l

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l Amendment No. 704, 108 vii (Updated !! arch 18, 1985) l

o TAntz 4. 2.D MINIMIM TEST & CALIDDATION FREOtlENCY FOR RADI ATIOth MONITORING SYSTEMS i FF l$

9 g-Instrument Functional

{g Instrument Channels Test Calibration

-I ns trtunent Check (2)

.l 57:2:

i 2P

1) Refuel Area Exhaust (1)

Once/3 months Once/ day

[g Honi tors - Upscale co *

2) Reactor Building Area (1)

Once/3 months Once/ day G

v Logic System Functional Test (4) (6)

Frequency

1) Reactor Building Isolation Once/6 months

=

7

2) Standby Gas Treatment Once/6 months System Actuation

,

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