Text

Amends 104 & 108 to Licenses DPR-44 & DPR-56,respectively, Revising Tech Specs to Permit Continued Operation of Reactor Water Cleanup Sys W/Isolation of Filter Demineralizer
	ML20107D495
Person / Time
Site:	Peach Bottom
Issue date:	02/07/1985
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20107D499	List: ML20107D495; ML20107D502;
References
	DPR-44-A-104, DPR-56-A-108 NUDOCS 8502220416
	Download: ML20107D495 (35)
	v • d • e

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION o

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WASHINGTON. D. C. 20555

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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 c

PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. DPR-44 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al.(thelicensee)datedNovember 10, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

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7 P

_ Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

(

FOR THE NUCLEAR REGULATORY COPHISSION L

h

. Stolz, Chief Ope ating Reactors Branc No. 4 D ision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 7,1985 d

ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277

- Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

c Remove insert 1-i 1.1 11 111 iii vi vi vii 38 38 39 39 42 42 44 44 62 62 63 63 73 73 83 83 84 84*

91 91

0verleaf page provided to maintain document completeness.

L

_ =. -

PBAPS TABLE OF CONTENTS Page No.

1.0 DEFINITIONS 1

LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1 FUEL CLADDING INTEGRITY 2.1 9

1.2 REACTOR COOLANT SYSTEM INTEGRITY 2.2 29 C

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.0 APPLICABILITY 4.1

, 34 3.1 REACTOR PROTECTION SYSTEM 4.1 35 3.2 PROTECTIVE INSTRUMENTATION 4.2 57 3.3 REACTIVITY CONTROL 4.3 99 A.

Reactivity Limitations A

99 B.

Control Rods B

101 c.

C.

Scram Insertion Times C

103 D.

Reactivity Anomalies D

105 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 115 A.

Normal Operation A

115 B.

Operation with Inoperable Components B

116 C.

Sodium Pentaborate Solution C

117 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 124 A.

Core Spray and LPCI Subsystems A

124 B.

Containment Cooling Subsystem (HPSW)

B 127 C.

MPCI Subsystem C

128 D.

RCIC Subsystem D

130 E.

Automatic Pressure Relief Subsystem E

131 F.

Minimum Low Pressure Cooling System F

132 Diesel Generator Availability f

G.

Maintenance of Filled Discharge Pipe G

133 H.

Engineered Safeguards Compartments H

133 Cooling and Ventilations I.

Average Planar LNGR I

133a J.

Local LNGR J

133a K.

Minimum Critical Power Ration (MCPR)

K 133b

' Amendment No. 104

_g, O

b.

4 PBAPS TABLE OF CONTENTS (Cont'd)

Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMEN'IS

]

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 i'

D.

Safety and Relief Valves D

147 E.

Jet Pumps E

148 C

l F.

Recirculation Pumps 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 i

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.

Airborne Effluents C

206 l

D.

Mechanical Vacuum Pump D

209a 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.

Auxiliary Electrical Equipment A

217 B.

Operation with Inoperable Equipment B

219 C.

Emergency Service Water System C

221 3.10 CORE 4.10 225 A.

Refueling Interlocks A

225 B.

Core Monitoring B

227 l

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

(

l A.

Main Control Room Ventilation A

233 l

B.

Alternate Heat Sink Facility B

234 C.-

Emergency Shutdown Control Panel C

234 l

D.

Shock Suppressors D

234a 3.12 RIVER LEVEL 4.12 237 l

A.

High River Water Level A

237 B.

Low River Water Level B

237 C.

Level Instrumentation C

238 Amendment No. 17.33 D,104 l

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M PBAPS TABLE OF CONTENTS (Cont'd)

Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 4

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

Water Fire Protection System A

240c C

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 CONTROLS 243 i

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 i

iii Amendment No. 77,$7,7f,7f, i

1 04 i

+..e.

P2APS LIST OF TABLES Table Title Page 4.2.B Minimum Test and Calibration Frequency 81 for CSCS 4.2.C Minimum Test and Calibration Frequency 83 for Control Rod Blocks Actuation j

4.2.D Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems i

4.2.E Minimum Test and Calibration Frequency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibration Frequency 86

.for Surveillance Instrumentation 4.2.G

Minimum Test and Calibration Frequency 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 Insoection Program for Peach 150 i

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 Penetrations with Testable 184 Bellows 3.7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive Liquid Waste Sampling and 210 Analysis 4.8.2 Radioactive Gaseous waste Sampling and 211 Analysis C

3.ll.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

- 240v Surveillance Requirene,nts g

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Amendment No..J, Jp, pp,104 d

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Table 3.1.1 (Cont'd) y REACTOR PROTECTION SYSTEM.(SCRAM) INSTRUMElfrATION REQUIREMElfr

=

(

-Minimum No.

Modes in which Number of a

of Operable Function Must be Instrument

' ?,

Instrument Trip Level Operable Channels Action 2-Channels Trip Function Setting Provided (1)

?

per Trip Refuel Startup Run by Desqin System (1)

(7) y 2

High Water Level

<50 Gallons X(2)

X X

4 Instrument A

2*

in Scram Discharge Channels E

Instrument Volume 2

Turbine Condenser

>23 in. Hg.

X(3)

X 4 Instrument A or C Low Vacuum Vacuum Channels 2

Main Steam Line

<3 X Normal Full X X

X 4 Instrument A

,g High Radiation Power Background Channels I

4 Main Steam Line

<10% Valve X(3)(6) X(3)(6) X(6) 8 Instrument A

Isolation Valve Elosure Channels Closure 2

Turoine Control 500<P<R50 pelg X(4) 4 Instrument A or D I

Valve Fast Closure Control Oil Pres-Channels f

sure Between Fast I

Closure Solenoid and Disc Dump j

Valve i

l 4

Turbine Stop (10% Valve X(4)

R Instrument A or D i

j Valve closure Elosure channels I

4 I

l 1

n n

t PBAPS NOTES FOR TABLE 3.1.1 1.

There shall be two operable or tripped trip systems for each function.

If the minimum number of operable sensor channels for a trip system cannot be met, the affected trip system shall be placed in the safe (tripped) condition, or the appropriate actions listed below shall be taken.

A.

Initiate insertion of operable rods and complete

]

Ansertion of all operable rods within four hours.

B.

Reduce power level to IRM range and place mode switch in the start up position within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C.* Reduce turbine load and close main steam line isolation ~

valves within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D.

Reduce power to less than 30% rated.

2.

Permissible to bypass, in refuel and shutdown positions of the reactor mode switch.

3.

Bypassed When reactor pressure is less than 600 psig.

4.

Evoassed When turbine first stage pressure is less than 120 neig or less than 10% of rated.

5.

IRM's are bypassed When APRM's are onscale and the reactor mode switch is in the run position.

6.

The design permits closure of any two lines without a scram being initiated.

7.

When the reactor is suberitical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be operable:

A.

Mode switch in shutdown B.

Manual scram C.

High flux IRM d

D.

Scram discharge instrument volume high level 8.

Not' required to be operable When primary containment integrity is not required.

9.

Not required to be operable When the reactor Dressure vessel head is not bolted to the vessel.

Amendment No. -1),104.

4 TABLE 4.1.1 (Cont'd) g REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS no 5.

?.

P.

Group (?)

Functional Test'

~

Minimum Frequency (3)

E High Water Level in Scram A

Trip Channel and Alarm Every 1 month.

Discharge Instrument Volume h

Turbine Condenser Low Vacuum (6)

B2 Trip Channel and Alarm (4)

Every 1. month (1).

Main _ Steam Line High Radiation B1 Trip Channel and Alarm (4)

Once/ week.

Main Steam Line Isolation A

Trip Channel and Alarm Every 1 month (1).

e Valve Closure D

e Turbine Control Valve A

Trip Channel and Alarm Every 1 month.

EHC Oil Pressure Turbine First. Stage Pressure A

Trip Channel and Alarm Every 3 months (1).

Permissive Turbine Stoo Valve Closure A

Trip Channel and Alarm Every 1 month (1).

Reactor Pressure Permissive (6)

B2 Trip Channel and Alarm (4)

Every 3 maonths.

x

TABLE 4.1.?

REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS

,5-5 Instrument Channel Group (1)

Calibration (4)

Minimum Frequency (2)

'5 IRM High Flux C

Comparison to APRM on Maximum frequency once Controlled Shutdown per week.

APRM High Flux Output Signal B1 Heat Balance Twice per week.

Flow Bias Signal B1 With Standard Pressure Every refueling outage.

Source LPRM Signal B1 TIP System Traverse Every 6 weeks.

a High Reactor Pressure B2 Standard Pressure Source Once per Operating cycle.

I High Drywell Pressure B2 Standard Pressure Source Once per oper6tihg cycle.

Reactor Low Water Level B2 Pressure Standard Once per operating cycle.

High Water Level in Scram A

Water Column Every refueling outage.

Discharge Instrument Volume Turbine Condenser Low Vacuum B2 Standard Vacuum Source Once per operating cycle.

Main Steam Line Isolation A

Note (5)-

Note (5)

Valve Closure Main Steam Line High Radiation B1 Standard Current Source (3)

Every 3 months.

Turbine First State Pressure A

Standard Pressure Source.

Every 6 months.

Permissive i

n n

TA!LE 3.2.A g

INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMEIR ISOLATION 5

6 5 Minimum No.

== cf Operable Number,o.f Instrument

? Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2) g, Trio System (1) a 2

Main Steam Line

< 200 deg. F.

4 Inst. Channels B

~

Leak Detection High Temperature 1

Reactor Cleanup

< 300% of Rated 2 Inst. Channels C

System High Flow Flow 1

Resctor Cleanup

- 200 deg. F 1 Inst. Channel E

l System High l

m Temperature Y

1 A-

i PBAPS 4

NOTES FOR TABLE 3.2.A f

1.

Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.

2.

If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action liste.d below shall be taken:

c A.

Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.

C.

Isolate Reactor Water Cleanup System.

D.

Isolate. Shutdown Cooking.

E.

Isolate Reactor Water Cleanup Filter Demineralizers unless the following-provision is satisfied.

The RWCU Filter Demineralizer may be.used (the isolation j

- overridden) to route the reactor water to the main condenser or waste surge tank, with the high temperature trip inoperable for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F.

3.

Instrument setpoir,t corresponds to 177.7" above top or active fuel.

4.

Instrument setpoint corresponds to 129.7" above top of active fuel.

5.-

Two required'for each steam line.

i 6.-

These signal also start SBGTS and initiate secondary containment isolation.

7.

-Only required in Run Mode (interlocked with ' Mode Switch).

f 8.

At a radiation level of 1.5 times the normal rated power background, an alarm will be tripped in the control room to.

alert the control room operators to an increase in the main

! steam line tunnel radiation level.

9; In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a

-period not to exceed 30 minutes to permit' restoration of the ventilation flow.

During the 30-minute period, an operator 4

shall observe control room indications of the duct temperature so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.

- Amendment No. % 104_.

INSTRUMENTATION THAT TIk k CONTROL ROD BLOCKS Minimum No.

Instrument Trip Level Setting Number of Instrument Action I

.I of Operable Channels Provided Instrument by Design Channels Per

& Trip System lD 4

APRM Upscale (Flow

~<(0.66w+47-0.666w) x 6 Inst. Channels (10)

Biased)

FRP-a MFLPD (2)

' *M 4

APRM Upscale (Startuo (12%

6 Inst. Channels (10)

U

Mode)

~

a#

' g 4

.APRM Downscale

>2.5 indicated on 6 Inst. Channels (10) scale s

1 (7)

Rod Block Monitor

~<(0.66w+41-0.66Aw)x 2 Inst. Channels (1)

(Flow Biased)

FRP i

MFLPD (2)

I (7)

Rod Block Monitor 12.5 indicated on 2 Inst. Channels t' l )

1 Downscale scale L

6 IRM Downscale (3)

>2.9 indicated on 8 Inst. Channels (10) l P

scale

~

l 6

IRM Detector not in (8)

R Inst. Channels (10)

Startuo Position 6

IRM Upscale

<108 indicated on R Inst. Channels (10) scale 2 (5)

SRM Detector not in (4) 4 Inst. Channels (1)

I Startup Position 2 (5)(6)

SRM Upscale

<10 counts /sec.

4 Inst. Channels (1) i 1

Scram Discharge

~<25 gallons 1 Inst. Channel (9) l Instrument Volume High Level A

m.

r

.g TABLE 4.2.C

{

MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION

$n x

Instrument Functional Instrument

?

Instrument Channel Test Calibration Check 3

f b

1)

APRM - Downscale (1) (3)

Once/3 months once/ day l

g 2)

APRM - Unscale (1) (3)

Once/3 months Once/ day 3)

IRN - Upscale (2) (3)

Startup or Control Shutdown (2) 4)

IRM - Downscale (2) (3)

Startup or Control Shutdown (2) 5)

RBM - Upscale (1) (3)

Once/6 months Once/ day 6)

RBM - Downscale (1) (3)

Once/6 months Once/ day 7)

SRM - Upscale (2) (3)

Startuo or Control Shutdown (2) 8)

SRM - Detector Not in Startup (2) (3).

Startup or Control Shutdown (2)

Position 9)

IRM - Detector Not in Startuo (2) (3)

Startup or Control Shutdown (2)

Position co 10)

Scram Discharge Instrument Volume Quarteriv.

Once/ Operating Cycle NA

- High Level Logic System Functional Test (4) (6)

Frecuency (1)

System Logic Check.

Once/6 months 9

A

i

[

g 1

e TABLE 4.2.D i

5

{

g MINDENt TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS 4

Ir.strtunent Channels Instrument Functional Calibratkon

{

Instrument Test Check (2) l l-1)

Refuel Area Exhaust Monitors - Upscale (1)

Once/3 months once/ day 1

2)

Reactor' Building Area Exhaust Monitors (1)

Once/3 months Once/ day

{

- Upecale r

3)

Off-Gas Radiation Monitors (1)

Once/3 months Once/ day g

i e,

8 Imeic System Functional Test (4) (6)

Frequency 4

4 l

1)

Asactor Building Isolation Once/6 months t

l 2)

Standby Gas Treatment System Actuation once/6 months 3)

Steam Jet Air Ejector Off-Gas Line 1

Isolation Once/6 months d.

i i

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PBAPS i

3.2 BASES (Cont'd)

Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below R50 psig.

The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe than the loss of feedwater analyzed in section 14.5 of the FSAR therefore, closure of the Main Steam Isolation valves for thermal transient protection when not in RUN Mode is not required.

The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping.

Tripping of this instrumentation results in actuation of HPCI isolation valves.

/

Tripoing logic for the high flow is 1 out of 2 logic.

Temperature is monitored at four (4) locations with four (4) temperature sensors at nach location.

Two (2) sensors at each location are powered by "A" DC control bus and two (2) by "B" DC control bus.

Each pair of sensors, e.g.,

"A",or "B" at each location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves.

The trip settings of < 100% of design flow for high flow and 200 degrees F for high temperature are such that core uncovery is prevented and fission product release is within limits.

The RCIC high flow and temperature instrumentation are arranged the same as that for the HPCI.

The trip setting of < 100% for high flow and 200 degrees F for temperature are based on the same' criteria as the HPCI.

1 The Reactor Water Cleanup System high flow instrumentation is arranged similar to that for the HPCI System.

The trip settings are such that core uncovery is prevented and fission product release is maintained l

within limits.

The high temperature instrumentation downstream of the non-regenerative heat exchanger is provided to protect the ion exchange resin in the domineralizer from damage due to hiqh temperature.

Such damage could impair the resins' ability to remove impurities from the primary coolant and possibly result in the release of previously captured impurities back into the coolant in large concentrations.

The instrumentation which initiates CSCS action is arranged in a dual bus system.

As for other vital instrumentation arranged in this fashion, the Specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed.

An exception to this is when logic functional testing is being performed..

[

The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the fuel i

cladding integriAy safety limit.

The trip logic for this function is 1 out of nt e.g., any trip on one of 6 APRM's, 8 IRM's, or 4 SRM's will result in a rod block.

The minimun instrument channel requirements assure sufficient instrumentation to assure the single failure criteris is met.

The minimum instrument channel requirements for the RBM cay be reduced by one for maintenance, testing or calibration. This t ime period is only 3% of the operating time in a month and does,not sigiificantly increase the risk of preventing an inadvertent contrcl rod withdrawal.

Amendment No.

7#./N.79,104 __

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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. DPR-56 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 10, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;-

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense. and security or to the health and safety of the public; and g

E.

The issuance of this amendment is in accordance with 10 CFR Part 53 of the Comission's regulationc and all applicable requirements have been satisfied.

2.

Accordingly, the license is. amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

_ _, Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.108, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This lic,ense &mendment is effective as of its date of issuance.

c FOR THE NUCLEAR REGULATORY C0tNISSION ihn F. Stolz, Ch rating Reactors Branch No. 4 ivision of Licensing

Attachment:

Changes to the Technical Specifications

~Date of Issuance: February 7,1985 l

ATTACHMENT TO LICENSE AMENDMENT NO.108 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain.a vertical line indicating the area of change.

Remove Insert i '

i

-ii 11 iii 11:

vi vi vii 38 38 39 39 42 42

-44 44 62 62 63 63 63a 73 73 83 83 84 84*

91 91

0verleaf page provided to maintain document completeness.

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+

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^

PBAPS TABLE OF CONTENTS Page No.

1.0 DEFINITIONS 1

LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1 FUEL CLADDING INTEGRITY 2.1 9

1.2 REACTOR COOLANT SYST'M INTEGRITY 2.2 29 E

(

SURVEILLANCE

. LIMITING CONDITIONS FOR OPERATION REQUIREMENTS

~

3.0 APP.LICABILITY 4.1 34 3.1 REACTOR PROTECTION SYSTEM 4.1 35 3.2 PROTECTIVE INSTRUMENTATION 4.2 57 3.3 REACTIVITY CONTROL 4.3 99 A.

Reactivity Limitations A

99 B.

Control Rods B

101 C.

Scram Insertion Times C

103 D.

React'ivity Anomalies D

105 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 115 A.

Normal Operation A

115 B.

Operation'with Inoperable Components B

116 C.

Sodium Pentaborate Solution C

117 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 124 A.

Core Spray and LPCI Subsystems A

124 B.-

Containment Cooling Subsystem (RPSW)

B 127 C.

HPCI: Subsystem C

128 D.

RCIC Subsystem D

130 E.

Automatic Pressure Relief Subsystem E

131 F.

Minimum Low Pressure Cooling System F

132

(

Diesel Generator Availability G.

Maintenance of ?illed Discharge Pipe G

133 E.

Engineered Safeguards Compartments H

133 Cooling and Ventilations I.

Aterage Planar LHCR I

133a J.

Local LECR J

133a K.

Minimum Critical T ower Ration (MCPR)

K 133b

-i-Amendment No. M.,

108 s-

. ~ -..

..,,e-,

.,--,,,~.,-.-,-,m,.-

--.,.w--,---,

PBAPS TABLE OF CONTENTS (Cont'd)

Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 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 c

E.

Jet Pumps E

148 F.

Recirculation' Pumps F

149 G.

Structural Integrity G

149 3.7 CONTAI.NMENT 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.

Airborne Effluents

.C 206 l --

D.

Mechanical Vacuum Pump D

209a 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.

Auxiliary Electrical Equipment A

217 B.

Operation with Inoperable Equipment B

219 C.

Emergency Service Water System C

221

.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 d

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 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 Amendment No. 15, 48, 108

T.

PBAPS TABLE OF CONTENTS (Cont'd)

Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 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 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 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

~'

(

Amendment No. -#,.47,7),7J, 111 108

-~-

,w,.

PBAPS LIST OF TABLES Table Title Page 4.2.B Minimum Test and Calibration Frequency 81 for CSCS 4.2.C Minimum Test and Calibration Frequency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration Frequency 85 fo'r Drywell Leak Detection 4.2.F Minimum Test and Calibration Frequenuy 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frequency 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 150 Bottom Units 2 and 3 3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations With Double 184 O-Ring Seals 3.7.3

' Testable Penetrations with Testable 184 Bellows 3.7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive Liquid Waste Sampling and 210 Analysis 4.8.2 Radioactive Gaseous Waste Sampling and 211 d

Analysis 3.ll.D.1 Safety Related Shock Suppressors 234d 3.14.C.1 Fire Detectors 240m 3.15 Seismic Monitoring Inst:umentation 240u -

4.15 Seismic Monitoring Instrumentation 240v Surveillance Requirements

~VI-Amendment No.

Q, y, 7),

108

4 i

(Unit 3)

Table 3.1.1 (Cont'd) liEACTOR PROTECTION SYSTEM (SCRAM) [NSTRUMElfrATION REQUIREMEM Minimum No.

Modes in which Number of i

of Operable Function Must be Instrument I

Instrument Trip Level-Operable Channels Action S

Channels.

Trip Function Setting Provided (1) per Trip.

Refuel Startup.Run by Desgin

, E System (1)

(7) j.

T l'*

2 High Water Level

<50 Gallons X(2)

X X

4 Instrument A

Qu in Scram Discharge Channels

3.. ?"

Instrument Volume I

,,o 03 2

Turbine Condenser

>23 in. Hg.

X(3)

X 4 Instrument A or C Low Vacuum Vacuum Channels

+

2 Main Steam Line

<3 X Normal Full X

X X(14) 4 Instrument k

,g High Radiation Power Background Channels i

4 Main Steam Line

<10% Valve X(3)(6) X(3)(6) X(6) 8 Instrument A

l

' Isolation Valve Dlosure Channels

}

Closure 2

Turbine Control 500<P<R50 psig X(4) 4 Instrument A or D Valve Past Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid and Disc Dump i

Valve i

i 4

Turbine Stop (10% Valve X(4)

G Instrument A or D l

Valve Closure

'Ulosure Channels i

1 l:

n kI::

1}

.t n

m.

4 PBAPS NOTES FOR TABLE 3.1.1 1.

There shall be two ooerable or trioned trip systems for each function.

If the minimum number of operable sensor channels for a trip system cannot be met, the affected trip system

)

shall be placed in the safe (tripped) condition, or the appropriate actions listed below shall be taken.

A.

Initiate insertion of operable rods and complete insertion of all operable rods within four hours.

/

B.

Reduce oower level to IRM range and place mode switch in the, start up position within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C.

Reduce turbine load and close main Oteam line isolation valves within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D.

Reduce power to less than 30% rated.

2.

Permissible to bypass,.in refuel and shutdown positions of the reactor mode switch.

3.

. Bypassed when reactor pressure is less than 600 osig.

4.

Evoassed when turbine first stage pressure is less than 220 osig or less than 30% of rated.

5.

IRM's are bypassed when APRM's are onseale and the reactor mode switch is in the run position.

6.

The design permits closure of any two lines without a scram being initiated.

7.

When the reactor is suberitical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be onorable:

A.

Mode switch in shutdown B.

Manual scram C.

High flux IRM D.

Scram discharge instrument volume high level.

8.

Not required to be operable when primary containment j

integrity is not required.

~

9.

Not required to be operable when the reactor pressure vessel i

head is not bolted to the vessel.

L Amendment No. ;),108 l e.

ee-----*-

e

- m

4 l

TABLE 4.1.E (Cont'd) g REACTOR PROTECTION SYSTEM (SCRAM) INSTRIMEIR FUNCTIONAL TESTS MINIMIM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS 1

e I

s a

n

{-

g:

Group (?)

Functional Test-Minimum. Frequency (3)-

f.

15 i

,, High Water Level in Scram A

Trip Channel and Alarm Every 1 month.

l PA Discharge Instrument Volume Turbine Condenser Low Vacuum (6)

R2 Trip Channel and Alarm (4)

Every 1, month (1).

m Main Steam Line High Radiation B1 Trip channel and Alarm (4)

Once/ week.

Main Steam Line Isolation A

Trip Channel and Alarm Every 1 month (1).

,1s Valve closure Y

Turbine Control Valve A

Trip Channel and Alarm Every 1 month.

EHC Oil Pressure

. Turbine First Stage Pressure A

Trip Channel and Alarm Every 3 months (1).

Permissive l

Turbine Stop Valve closure A

Trip Channe'l and Alarm Every 1 month (1).

Reactor Pressure Permissive (6)

B2 Trip-Channel and Alarm (4)

Every 3 months.

i-q s

4

,t I

TABLE 4.1.*Jt, REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION i

MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS

s j

Instrut.cnt Channel Group (1)

Calibration (4)

Minimum Frequency (2) j y

)

4 IRM High Flux C

Comparison to APRM on Maxi. mum frequency once Controlled Shutdown per week.

j APRM High Flux j-Output Signal 81 Heat Balance Twice per week.

i Flow Blas Signal B1 With Standard Pressure Every refueling outage.

j Source

]

LPRM Signal B1 TIP System Traverse Every 6 weeks.

g High Reactor Pressure B2 Standard Pressure Source Once per operating cycle.

l High Drywell Pressure B2 Standard Pressure Source Once per operating cycle.

i Reactor Low Water Level B2 Pressure Standard Once per operating j

cycle.

l High Water Level in Scram A

Water Column.

Every refueling outaqe.

Discharge Instrument Volume l_

' Turbine Condenser Low Vacuum B2 Standard Vacuum Source Once per operatinq cycle.

I Main Steam Line Isolation A

Note (5)

Volve Closure j

Main Steam Line High Radiation-B1 Standard Current Source (3)

E'very 3 months.

Turbine First State Pressure A

Standard Pressure Source.

Every 6 months.

Parmissive

[

~

n

\\

TA"LE 3 *2.A 9-INSTRUMEPrfATION THAT INITIATES PRIMARY CONTAINMElff ISOIATION Y-l'

y Minimum No.

" cf Operable Number of Instrument g

Instrument Instrument Trip Level Setting Channels ~ Provided Action Chant.els per By Design (2)

Trio System (1)

. - w

!. *g 2

Main Steam Line

< 200 deg. F.

4 Inst. Channels B

j Leak Detection High Temperature.

1 Reactor Cleanup

< 300% of Rated 2 Inst. Channels C

System High Flow Plow 1

Reactor Cleanup

< 200 deg. F 1 Inst. Channel E

l Synstem High l

1 Temperature u

I 4

Ii i

i lil' I

l

'6 e

i 6

O

PBAPS 4

i i

NOTES FOR TABLE 3. 2. A 1.

Whenever Primary Containment integrity is required by Section 3.7, there 'shall be two operable or tri.pped trip systems for each function.

2.

If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken:

c A.

Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Initiate an orderly load reduction and have Main Steam Lines isolated within.eight hours.

C.

Isolate Reactor Water Cleanup System.

D.

Isolate Shutdown Cooking.

E.

Isolate Reactor Water Cleanup Filter Demineralizers unless che following provision is satisfied.

The RWCU Filter Demineralizer may be-used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high' temperature trip inoperable for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , prov~ided the water inlet temperature is monitored once per hour and

~

confirmed to be below 180 degrees F.

3.

Instrument setpoint corresponds to 177.7" above top or active fuel.

4.

Instrument setpoint corresponds to 129.7" above top of active fuel.

~

5.

Two required'for each steam line.

6.

These signals also start SBGTS and initiate secondary containment isolation.

7.

Only required in Run Mode (interlocked with Mode Switch).

g 8.

At a radiation level of 1.5 times the normal rated power g

L background, an alarm will be tripped in the control room to "

l~

' alert the control room operators to an increase in the main steam line tunnel radiation level.

9.

In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a period not to exceed 30 minutes to permit' restoration of the l

ventilation flow.

During the 30-minute period, an operator shall observe control room indications of the duct

!~

temperature so in the event of rapid increases (indicative of a steam line break)-the operator shall promptly close the main-steam line isolation valves.

Amendment No.

$7,' 108.

- ~. - - -, -, _ - - - -..

PBAPS

.l NOTES FOR TABLE 3. 2. A (Cont.)

10. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels after completion of the test program, and within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor power levels below 20% rated power.

d imendment. No.19$,108

-63a-

?.

~

TABLE 3.2.C,

INSTRIMENTATION THAT INITIATES CONTROL ROD BLOCKS g' Minimum No.

Instrument Trip Level Setting Number of Instrument Action g cf Operable Channels Provided g Instrument by Design g Channels Por

" Trip System

~~

4 APRM Upscale (Flow

<(0.66w+42-0.666w) x 6 Inst. Channel's (10)

~

Biased)

FRP j$

MPLPD,(2),

$lO

-4 APRM Upscale (Startup 112%

6 Inst. Channels (10)

Mode)

'4 APRM Downscale

>2.5 indicated on 6 Inst. Channels (10) i

,,a scale 1 (7)-

Rod Block Monitor

~(0.66w+41-0.66Aw)x 2 Inst. Channels (1).

e (Flow Biased)

PRP gj MPLPD.(2)

,i.

1 (7)

Rod Block Monitor 12.5 indicated on 2 Inst. Channels (1)

Downscale scale 6

IRM.Downscale (3)

>2.9 indicated on R Inst. Channels (10) scale i

6 IRM Detector not in (R)

R Inst. Channels (10) l Startup Position 6

IRM Upscale 1108 indicated on R Inst. Channels (10) scale

[

~2 (5)

SRM Detector not in' (4) 4 Inst. Channels (1)

Startup Position 2 (5)(6)

SRM Upscale 110 ~ counts /sec.

4 Inst. Channels (1) 1 Scram Discharge 125_ gallons 1 Inst. Channel (9) l Instrument Volume High Level i

l

e g{

TABLE 4.2.C MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL R00 BLOCKS ACTUATION

,+ =

1"z Instrument Functional Instrument Instrument Channel Test Calibration Check i

1)-

APRM - Downscale (1) (3)

Once/3 months once/ day o

2)

APRM - Upscale (1) (3)

Once/3-months once/ day 3)

IBM - Upscale (2) (3).

Startup or Control Shutdown (2) 4)

IRM - Downscale (2) (3)

Startup or Control Shutdown (2) i 5)

RBM - Upacale (1) (3)

Once/6 months Once/ day 6)

RBM - Downscale (1) (3)

Once/6 months Once/ day i

7)

SRM - Upscale (2) (3)

Startup or Control Shutdown (2) j 8)

SRM - Detector Not in Startup (2). (3)

Startup or Control Shutdown (2)

Position 1

i 9)

IRM - Detector Not,in Startup (2) (3)

Startup.or Control Shutdown (2)

Position 10)

Scram Discharge Instrument Volume Quarterly Once/ Operating Cycle NA

=

- High Levek Logic System Functional Test (4) (6)

Frequency (1)

System Loq1c Check Once/6 months.

t 8

1.'

e i

/

I ru n

M.

TABLE 4.2.D MINIDRIN TEST AND CALIBRATION FREQUENCY FOR RADIATION MONI'IDRING SYSTEMS Instrumment Channels Instrussent Functional Calibration Instrument Test check (2) 1)

Refuel Area Exhaust Monitors - Upscale (1)

Once/3 months once/ day i

2).meactor Building Area Exhaust Monitors (1)

Once/3 months Once/ day

- Upecale I

'o 3)

Off-Ges Radiation Monitors (1)

Once/3 months Once/ day I Logic System Functional Test (4) (6)

Frequercy 1) menctor Building Isolation Oncc/6 months 2)

Standby Gas Treatment System Actuation Once/6 months 3)

Steam Jet Air Ejector Off-Gas Line Isciati:n Once/6 months

~:-

A m

PBAPS 3.2 pASES (Cont'd)

Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drons below R50 psig.

The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe thgn the loss of feedwater analyzed in section 14.5 of the FSAR: therefore, ciosure of the Main Steam Isolation valves for thermal transient protection when not in RUN Mode is not reauired.

The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam pioing.

Tripoing of this instrumentation results in actuation of HPCI isolation valves.

Tripping logic for the high flow is 1 out of 2 logic.

Temperature is monitored at four (4) locations with four (4) temperature sensors at each location.

Two (2) sensors at each location are powered by "A" DC control bus and two (2) by "B" DC control bus.

Each pair of sensors, e.g., "A" or "B" at each-location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves.

The trip settings of j,100% of design flow for high flow and 200 degrees F for high temperature are such that core uncovery is prevented and fission product release is within limits.

Th'e RCIC high flow and temperature instrumentation are arr0nged the same as that for the HPCI.

The trip setting of j,100% for high flow and 100 degrees F for temperature are based on the same' criteria as the HPCI.

The Reactor Water Cleanup System high flow instrumentation is arranged 1

similar to that for the HPCI System.. The trip settings are such that core uncovery is prevented and fission product release is maintained within limits.

The high temperature instrumentation downstream of the non-regenerative heat exchanger is provided to protect the ion exchange resin in the domineralizer from damage due to hiqh temperature.

Such damage.could impair the resins' ability to remove impurities from the primary coolant and possibly result in the release of previously captured impurities back into the coolant in large concentrations.

The instrumentation which initiates CSCS action is arranged in a dual bus system.

As for other vital instrumentation arranged in this fashion, the Specification preserves the effectiveness of the system even during' periods when maintenance or testing is being performed.

An exception to this is when logic functional testiny is being performed.

The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the fuel-cladding integriAy safety limit.

The trip logic for this function is 1 out of na e.g., any trip on one of 6 APRM's, 8 IRM's, or 4 SRM's will result in a rod block.

The minimun instrument channel requirements assure sufficient

~

instrumentation to assure the single failure critoria is met.

The 6

minimum instrument channel requirements for the RBM may be reduced by i -

.one for maintenance, testing or calibration. /Riis time period is only 1% of the operating time in a month and does not significantly increase tho' risk of preventing an inadvertent control rod withdrawal.

Amendment No. 7f, $7, 77,108.

_. _ _ _,_

ML20107D495

Text

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