Text

Amends 12,12 & 2 to Licenses NPF-37,NPF-66 & NPF-72, Respectively,Revising Tech Specs to Allow one-time Extension to 32 Months for Interval for Performing 18-month Instrument Surveillance
	ML20236V092
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	11/25/1987
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20236V096	List: ML20236V092;
References
	NPF-37-A-012, NPF-66-A-012, NPF-72-A-002 NUDOCS 8712040084
	Download: ML20236V092 (54)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION n

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COWiONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-37 l

1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated September 3,1987, 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 1; 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 Commission's regulations; i

)

D.

The issuance of this amendment will not be inimical to the common 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 Commission'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. NPF-37 is hereby amended to read as follows:

s712040004 % 2jg4 I

D PDR ADOCK PDR P

e e 1 (2) Technical Specifications l

The Technical Specifications' contained in Appendix A as revised through Amendment No.12 and the Environment Protection Plan contained in Appendix B, both of which are attached hereto,'are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and'the' Environmental Protection Plan.

3.

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

.FOR THE NUCLEAR REGULATORY COMMISSION h-A ter I

Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: November 25, 1987 l

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c cuooq'o, UNITED STATES 8'

NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-66 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated September 3,1987, complies with the standards j

i 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 Commission; j

i 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 j

conducted in compliance with the Comission's regulations; 1

D.

The issuance of this amendment will not be inimical to the common 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 1

have been satisfied.

i 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. NPF-66 is hereby amended to read as follows:

.. (2) Technical Specifications The Technical Specifications contained in Appendix (NUREG-1113),

as revised through Amendment No. 12 and revised by' Attachment 2 to NPF-60, and.the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the 1

Environmental Protection Plan.

3.

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

FOR THE NUC R REGULATORY COMMISSION

[a2Ag b M

FcY Daniel R. Muller, Director Project Directorate III-2 Division of Pcactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 25, 1987 1

i l

l

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,1 ATTACHMENT TO LICENSE AMENDMENT NOS. 12 AND 12 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN-50-454 AND STN 50-455 Revise Appendix A as follows:

}

Remove Pages Insert Pages 3/4 2-9 3/4 2-9 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-11 3/4-3-11 3/4 3-12 3/4 3-12 3/4 3-34

-3/4 3-34 3/4 3-35 3/4 3-35 j

3/4 3-36 3/4 3-36 i

3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-42 3/4 3-42 3/4 3-52 3/4 3-52 3/4 3-55 3/4 3-55 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-67 3/4 3-67 l

3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-69 3/4 3-70 3/4 3-70 3/4 4-12 3/4 4-12 3/4 4-20 3/4 4-20 3/4 4-20 a 3/4 4-41 3/4 4-41 3/4 5-2 3/4 5-2 1

l l

l E

l POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) q b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that' the combination of F and RCS total flow rate are restored to H

within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and Identify and correct the cause of the out-of-limit condition prior c.

to increasing THERMAL POWER above the reduced THERMAL POWER limit j

required by ACTION a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of F and indicated RCS AH total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region of acceptable operation defined by Specification 3.2.3 prior to exceeding the fol-I lowing THERMAL POWER levels:

1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal 75% of RATED THERMAL POWER, and' 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

I SURVEILLANCE REQUIREMENTS l

l 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

N 4.2.3.2 The combination of indicated RCS total flow rate and F " shall be determined to be within the region of acceptable operation of 0 Specification 3.2.3:

I Prior to operation above 75% of RATED THERMAL POWER after each fuel a.

loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the most recently obtained value of F btained per Specification 4.2.3.2, is assumed to exist.

H, 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.*

l 1

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months.

The measurement instrumentation shall be calibrated within seven days prior to the performance of the calorimetric flow measurement.

Prior to the precision heat balance measurement, at least two of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.

The specified 18 month interval may be extended to 32 months for Cycle 1 onl*,.

l BYRON - UNITS 1 & 2 3/4 2-9 AMENDMENT NO. 12

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I TABLE 4.3-1 (Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

- These channels also provide inputs to ESFAS. The Operational Test Frequency i

for these channels in Table 4.3-2 is more conservative and, therefore, i

controlling.

The specified 18 month interval may be extended to 32 months for Cycle 1 only.

1. Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED l

THERMAL POWER. Adjust excore channel gains consistent with calorimetric j

power if absolute difference is greater than 2%.

The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFF2RENCE above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(Sa) Initial plateau curves shall be measured for each detector.

Subsequent plateau curves shall be obtained, evaluated and compared to the initial

[

curves.

For the Intermediate Range and Power Range Neutron Flux channels i

the provisions of Specification 4.0.4 are not applicable for entry into l

MODE 2 or 1.

,l (5b) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector.

Subsequent discriminator bias curves shall be obtained, evaluated and i

compared to the initial curves.

I l

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provi-l sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

l (8) With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.

l (9) Surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant l

conditions by observation of the permissive annunciator window.

Surveil-lance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

BYRON - UNITS 1 & 2 3/4 3-12 AMENDMENT N0. 12 l

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o TABLE 4.3-8 (Continued) j TABLE NOTATIONS

The specified 18 month interval may be extended to 32 months for Cycle 1 only.

h (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate-that automatic isolation of this pathway and control room alarm annunciation occur if any of.the following conditions exists:

Instrument indicates measured levels above the Alarm / Trip'Setpoint, a.

or a

b.

Circuit failure (monitor loss of communications - alarm only, detector I

loss of counts, or monitor loss of power), or c.

Detector check source test failure, or j

d.

Detector channel out-of service, or e.

Monitor loss of sample flow.

1 (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

Instrument indicates measured levels above the Alarm Setpdint, or a.

b.

Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or Detector check source test failure, or c.

d.

Detector channel out-of-service, oc e.

Monitor loss of sample flow.

1 (3) The initial CHANNEL CALIBRATION shall be performed using one or more of i

the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and i

measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

1 (4) CHANNEL CHECK shall consist of verifying indication of flow during periods l

of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days or, which continuous, periodic, or batch releases are made.

l i

1 BYRON - UNITS 1 & 2 3/4 3-61 AMENDMENT NO. 12 i

L__m_____.__.___.______.____.________.-_______...______.___

ICE MNR AI RLU OLQ FIE ER SV ERS DUI OS S

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\\

TABLE 4.3-9 (Continued)

TABLE NOTATIONS l

At all times.

- During WASTE GAS HOLDUP SYSTEM operation.

All instruments required for Unit 1 or. Unit 2 operation.

1. The specified 18 month interval may be extended to 32 months for Cycle 1 only.

l (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

Instrument indicates measured levels above the Alarm / Trip Setpoint, a.

or b.

Circuit failure (monitor loss of communications alarm only, detector loss of counts, or monitor loss of power), or Detector check source test failure, or c.

f d.

Detector channel out of-service, or l

e.

Monitor loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

Instrument indicates measured levels above the Alarm Setpoint, or a.

b.

Circuit failure (monitor loss of communications alarm only, detector loss of counts, or monitor loss of power), or Detector check source test failure, or c.

d.

Detector channel out-of-service, or e.

Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

BYRON - UNITS 1 & 2 3/4 3-70 AMENDMENT NO. 12 l

l a

REACTOR COOLANT SYSTEM i

3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION

)

1 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

i APPLICABILITY:

MODES 1, 2, and 3.

ACTICN:

l l

With one or more PORV(s) inoperable because of excessive seat leakage, a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise be in at least HOT STANDBY l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j b.

With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status j

or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD l

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With both PORV(s) inoperable due to causes other than excessive seat c.

leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore each of the PORV(s) to OPERABLE status or close their associated block valve (s) and remove pow (r from i

the block valve (s) and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i

in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With one or more block valve (s) inoperable, wit' o 1 hour:

)

1) restore the block valve (s) to OPERABLE status or close the block i

valve (s) and remove power from the block valve (s), or close the PORV and remove power from its associated solenoid valve; and 2) apply the ACTION of b. or c. above, as appropriate for the isolated PORV(s).

The provisions of Specification 3.0.4 are not applicable.

e.

SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5,'each PORV shall be demonstrated OPERABLE at least once per 18 months by:

Performance of a CHANNEL CALIBRATION #, and l

a.

b.

Operating the valve through one complete cycle of full travel.

4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b. or c. of Specification 3.4.4.

The specified 18 month interval may be extended to 32 months for Cycle 1 only.

l BYRON - UNITS 1 & 2 3/4 4-12 Amendment No.12 1

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

l The Containment Atmosphere Particulate Radioactivity Monitoring System, l

a.

b.

The Containment Floor Drain and Reactor Cavity Flow Monitoring i

System, and f

The Containment Gaseous Radioactivity Monitoring System.

c.

l APPLICABILITY:

MODES 1, 2, 3, and 4.

j ACTION:

I With a. or c. of the above required Leakage Detection Systems inoperable, a.

operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required Gaseous or i

i Particulate Radioactivity Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With b. of the above required Leakage Detection Systems inoperable be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With a. and c. of the above required Leakage Detection Systems inoperable:

c.

1)

Restore either Monitoring System (a. or c.) to OPERABLE status within 1

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 3)!

Perform a Reactor Coolant System water inventory balance at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SitVTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

Containment Atmosphere Gaseous and Particulate Monitoring System-a.

performance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, BYRON - UNITS 1 & 2 3/4 4-20 AMENDMENT N0.12

)

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS-f SURVEILLANCE REQUIREMENTS (Continued) b.

Containment Floor Drain and Reactor Cavity Flow Monitoring System-t performance of CHANNEL CALIBRATION'at least once per 18 months,# and

.l -

Verify the oil separator portion of the containment floor drain c.

collection sump has been filled to the level of the overflow to the containment floor drain unidentified leakage collection weir box once-per 18 months, following refueling, and prior to initial'startup.

i I

l i

The specified 18 month interval may be extended to 32 months for Cycle l'only.

l BYRON - UNITS 1 & 2 3/4 4-20a AMENDMENT NO.12

O

'e I

l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS I

.l 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV a.

actuation channel, but excluding valve operation, within 31 days I

prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; b.

Perf ormance of a CHANNEL CALIBRATION on.the PORV. actuation channel at least once per 18 months #; and i

Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months c.

when the PORV is being used for overpressure protection.

J 4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for co1d ot; aressure protection l

as follows:

f i

a.

For RHR suction relief valve 87088:

1)

By verifying at least once per 31 days that RHR RCS Suction Isolation Valve RH8702A is open with power to the valve operator remcVed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that RH8702B is open.

b.

For RHR suction relief valve 8708A:

1)

By verifying at least once per 31 days that RH8701B is open with power to the valve operator removed, and 2)

By verifying at least once per 1? hours that RH8701A is open.

l c.

Testing pursuant to Specification 4.0.5.

i 4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per i

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

I l

i i

Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

The specified 18 month interval may be extended to 32 months for Cycle 1 only.

l.

BYRON - UNITS 1 & 2 3/4 4-41 Amendment No.12

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 70 gallons by verifying the boron concentration of the accumulator solution, and At least once per 31 days when the RCS pressure is above 1000 psig c.

by verifying that the MCC compartment is open and tagged out of service.

i

4. 5.1. 2 Each accumulator water level and pressure channel shall be demonstrated OPERABLE at least once per 18 months # by the performance of a l

CHANNEL CALIBRATION.

l l

l i

The specified 18 month interval may be extended to 32 months for Cycle 1 only.

l BYRON - UNITS 1 & 2 3/4 5-2 Amendment No.12

aun

/

q'o 8

g UNITED STATES NUCLEAR REGULATORY COMMISSION o

74 y

WASHINGTON, D. C. 20555 COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-456 i

BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATIflG LICENSE i

Amendment No. 2' License No. NPF-72 i

1.

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

L A.

The application for amendment by Commonwealth Edison Company L.

(the licensee) dated September 3,1987, complies with the standards j

and requirements of the Atomic Energy Act of 1954, as amended'(the i

Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.

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

)

Concission; 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; y

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.

1 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. NPF-72 is hereby amended to read as follows:

1 i

. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 2 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license..The licensee shall i

operate the facilit) in accordance with the Technical l

Specifications and the Environmental Protection Plan.

f 3.

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

FOR THE NUC AR REGULATORY COMMISSION fAM b' for l

Daniel R. Muller, Director i

4 Project Directorate III-2 Division of Reactor Projects - III, l

IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: November 25, 1987 I

1 l

i

O 3

ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO NPF-72 DOCKET NO. STN-50-456 j

l l

Revise Appendix A as follows:

i 1

l Remove Pages Insert Pages 1

j 3/4 2-9 3/4 2-9 1

3/4 3-9 3/4 3-9 3/4' 3-10 3/4' 3-10 3/4 3-11 3/4.3-11 3/4 3-12 3/4 3-12 1

l 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-42 3/4 3-42 3/4 3-52 3/4_ 3-52 3/4 3-55 3/4 3-55 3/4 3-62 3/4 3-62 3/4 3-63 3/4 3 3/4 3-69 3/4 3-69 3/4 3-70 3/4 3-70 3/4 3-71 3/4 3-71 3/4 3-72 3/4 3-72 1

3/4 4-12 3/4 4-12 3/4 4-20 3/4 4-20 3/4 4-41 3/4 4-41 3/4 5-2 3/4 5-2

i POWER DISTRIBUTION LIMITS I

LIMITING CONDITION FOR OPERATION ACTION (Continued) b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of F and RCS total flow rate are restored to H

within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and Identify and correct the cause of the out of-limit condition prior c.

to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of F and indicated RCS

)

H total flow rate are demonstrated, through incore flux mapping and f

RCS total flow rate comparison, to be within the region of acceptable q

operation defined by Specification 3.2.3 prior to exceeding the fol-lowing THERMAL POWER levels:

j 1

1.

A nominal 50% of RATED THERMAL POWER, 1

2.

A nominal 75% of RATED THERMAL POWER, and l

3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

l SURVEILLANCE REQUIREMENTS I

4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The combination of indicated RCS total flow rate and F shall be deter-q mined to be within the region of acceptable operation of Specification 3.2.3:

i Prior to operation above 75% of RATED THERMAL POWER after each fuel a.

loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenthemostrecentlyobtainedvalteofFfH, btained per Specification 4.2.3.2, l

is assumed to exist.

l 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.*

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months.

The measurement instrumentation shall be calibrated within seven days prior to the performance of the calorimetric flow measurement.

Prior to the precision heat balance measurement, at least two of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.

The specified 18 month interval may be extended to 32 months for cycle 1 only.

BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AMENDMENT NO. 2 w_-___----__.

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TABLE NOTATIONS

With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

- These channels also provide inputs to ESFAS.

The Operational Test Frequency for these channels in Table 4.3-2 is more conservative and, therefore, controlling.

The specified 18 month interval may be extended to 32 months for cycle 1 only.

1. Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are -

not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

l (Sa) Initial plateau curves shall be measured for each detector.

Subsequent plateau curves shall be obtained, evaluated and compared to the initial curves.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(5b) With the high voltage setting varied as recommended by the manufacturer,-an initial discriminator bias curve shall be measured for each detector.

Sub-sequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.

(6) Incore - Excore Calibration, above 75% of PATED THERMAL POWEP.

The provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator vindow.

(9) Surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

Surveil-lance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

(10) Setpoint verification is not applicable.

(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.

BRAIDWOOD - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 2

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TABLE 4.3-8 (Continued) j TABLE NOTATIONS

The specified 18 month interval may be extended to 32 months for cycle 1 only.

l i

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

i Instrument indicates measured levels above the Alarm / Trip Setpoint, a.

or b.

Circuit failure (monitor loss of communications alarm only, detector

{

loss of counts, or monitor loss of power), or l

1 c.

Detector check source test failure, or d.

Detector channel out-of-service, or i

e.

Monitor loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

i Instrument indicates measured levels above the Alarm Setpoint, or a.

b.

Circuit failure (monitor loss of communications alarm only, detector loss of counts, or monitor loss of power), or c.

Detector check source test failure, or d.

Detector channel out of-service, or e.

Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that i

participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods i

of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on i

days on which continuous, periodic, or batch releases are made.

l l

BRAIDWOOD - UNITS 1 & 2 3/4 3-63 AMENDMENT NO. 2

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TABLE 4.3-9 (Continued) 1 i

TABLE NOTATIONS l

At all times.

- During WASTE GAS HOLDUP SYSTEM operation.

All instruments required for Unit 1 or Unit 2 operation.

l

1. The specified 18 month interval may be extendea to 32 months for cycle 1 only.

l (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1 Instrument indicates measured levels above the Alarm / Trip Setpoint, a.

or b.

Circuit failure (monitor loss of communications - alarm only, detector-loss of counts, or monitor loss of power), or l

c.

Detector check source test failure, or d.

Detector channel out-of-service, or e.

Monitor loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

Instrument indicates measured levels above the Alarm Setpoint, or a.

b.

Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or q

Detector check source test failure, or c.

d.

Detector channel out-of-service, or e.

Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of 1

the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its-intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

BRAIDWOOD - UNITS 1 & 2 3/4 3-72 AMENDMENT NO. 2 l

I s

l a

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES 1

LIMITING CONDITION FOR OPERATION l

3.4.4 All power-operated relief valves (PORVs) aad their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

1 ACTION:

With one or more PORV(s) inoperable because of excessive seat leakage, a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3 b.

With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status j

or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following-72 hours or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With both PORV(s) inoperable due to causes other than excessive seat-c.

leakage, within I hour either restore each of the PORV(s).to. OPERABLE status or close their associated block valve (s) and remove power from the block valve (s) and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , d.

With one or more block valve (s) inoperable, within 1 hour:

1) restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s), or close the PORV and remove power from its associated solenoid valve; and 2) apply the l

ACTION of b. or c. above, as appropriate for the isolated PORV(s).

1 The provisions of Specification 3.0.4 are not applicable.

e.

l SURVEILLANCE REQUIREMENTS I

4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV l-shall be demonstrated OPERABLE at least once per 18 months by:

Performance of a CHANNEL CALIBRATION,# and a.

l b.

Operating the valve through one complete cycle of full travel.

4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b. or c. of Specification 3.4.4.

The specified 18 month interval may be extended to 32 months for cycle 1 only.

gj BRAIDWOOD - UNITS 1 & 2 3/4 4-12 AMENDMENT NO. 2

o REACTOR COOLANT SYSTEM 1

l 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE l

LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall i

be OPERABLE:

J L

The Containment Atmosphere Particulate Radioactivity Monitoring System, l

a.

l b.

The Containment Floor Drain and Reactor Cavity Flow Monitoring System, and i

c.

The Containment Gaseous Radioactivity Monitoring System.

1 APPLICABILITY:

MODES 1, 2,'3, and 4.

ACTION:

With a or c. of the above required Leakage Detection Systems inoperable, a.

operation may continue for up to 30 days provided grab samples of the 1

containment atmosphere are obtained and analyzed for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

)

b.

With b. of the above required Leakage Detection Systems inoperable be in at

)

least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With a and c, of the above required Leakage Detection Systems inoperable:

c.

1)

Restore either Monitoring System (a. or c.) to OPERABLE status within.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 1

2)

Obtain and analyze a grab sample of the containment atmosphere for gaseous and particulate radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and j

3)

Perform a Reactor Coolant System water inventory balance at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD l

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 1

4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

Containment Atmosphere Gaseous and Particulate Monitoring System-a.

i performance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment Floor Drain and Reactor Cavity Flow Monitoring System-performance of CHANNEL CALIBRATION at least once per 18 months,# and l

c.

Verify the oil separator portion. of the' containment floor drain collection sump has been filled to the level of the overflow to the containment floor drain unidentified leakage collection weir box once l

per 18 months, following refueling, and prior to initial startup..

1

The specified 18 month interval may be extended to 32 months for cycle 1 cnly.

BRAIDWOOD - UNITS 1 & 2 3/4 4-20 AMENDMENT NO 2.

l l

1 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 'Each PORV shall be demonstrated OPERABLE by:

a.

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; I

b.

Performance of a CHANNEL CALIBRATION on the PORV actuation channel' at least once per 18 months;# and Verifying the PORV isolation valve is open at least'once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months c.

when the PORV is being used for overpressure protection.

4.4.9.3.2 Each RHR suction relief-valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure protection as follows:

a.

For RHR suction relief valve 8708B:

1)

By verifying at least once per 31 days that RHR RCS Suction Isolation Valve RH8702A is open with power to the valve operator removed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that RH8702B is open, b.

For RHR suction relief valve 8708A:

1)

By verifying at least once per 31 days that RH87018 is'open with power to the valve ~ operator removed, and j

2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that RH8701A is open.

c.

Testing pursuant to Specification 4.0.5.

4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

I a

Except when the vent pathway is provided with a valve which is locked, taaled, or otherwise secured in the open position, then verify these valves open at least once per 31' days.

i

The specified 18 month interval may be extended to 32 months for cycle 1 only.

BRAIDWOOD - UNITS 1 & 2 3/4 4-41 AMENDMENT NO. 2 l

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days and'within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 70 gallons by verifying the boron concentration of the accumulator solution, and At least once per 31 days when the RCS pressure is above 1000 psig c.

by verifying that the MCC compartment is open and tagged out of ;

service.

4.5.1.2 Each accumulator water level and pressure channel shall be demonstrated OPERABLE,at least once per 18 months #.by the performance.of a CHANNEL CALIBRATION.

l j

i

The specified 18 month interval may be extended to 32 months.for cycle 1 only.

BRAID'400D - UNITS 1 & 2 3/4 5-2 AMENDMENT NO. 2 r

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ML20236V092

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