Text

Rev 26 to Selected Licensee Commitments Manual. with Update Instructions
	ML20196C921
Person / Time
Site:	Mcguire, McGuire
Issue date:	11/14/1998
From:	Crane K; DUKE POWER CO.
To:	;
References
	PROC-981114, NUDOCS 9812020119
	Download: ML20196C921 (92)
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,-~s November 14, 1998

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To: All Holders of the Selected Licensee Commitments Manual Please find attached a revision to the subject manual. Your copy of the SLC manual should be revised as follows:

Remove these pages: Insert these pages:

List of Effective Pages List of Effective Pages Revision 25 Revision 26 Table of Contents Table of Contents 16.7-3 16.7-3 16.7-4 16.7-4 16.7-7 16.7-7 16.7-11 16.7-11 16.8-1 16.8-1 16.8-4 16.8-4 16.9-12 16.9-12 Table 16.9-4 Table 16.9-4 16.9-15 m 16.9-15

16. 9-MT I 7 750 16.9-17 16.10-1.1 16.10-1.2

/ Pages 16.15-1 through

( ,/ 16.15-71 Questions or problems should be directed to Kay Crane, McGuire Regulatory Compliance at extension 4306.

b Kay L. Crane,

~lcGuire Regulato_7 Compliance

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9812020119 981114 7 PDR ADOCK 05000369h P PDR ;,;

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TABLE OF CONTENTS iG SECTION 16.0 TITLE PAGE SELECTED LICENSEE COMMITMENTS 16.1

16.1 INTRODUCTION

16.1-1 26.2 APPLICABILITY 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS 16.4-0 16.5 COMMITMENTS REl ATED TO REACTOR COOLANT SYSTEM 16.5-0 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6-0 (NON-ESF SYSTEMS) 16.7 COMMITMENTS RELATED TO INSTRUMENTATION 16.7-1 16.7-1 ATWS MITIGATION SYSTEM 16.7-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8-0 16.9 COMMITMENTS RELATED TO AUXILIARY SYSTEMS 16.9-1 16.10 DELETED (ITS IMPLEMENTATION)

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( j 16.11 RADIO 1/0GICAL EFFLUENT CONTROLS 16.1 l-I w-16.15 RELOCATED ITEMS FROM ITS IMPLEMENTATION 16.15-1 l

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McGuire Nuclear Station l

('S Selected Licensee Commitments l List of Effective Pages

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Page Revision Date LOEP Tab List of Effective Pages 26 Tab 16.0 16.0-1 4/96 16.0-2 4/96 Ipb 16.1 1 16.1-1 1 1

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1121 INSTRUMENTATION '

16.7-2 SEISMIC INSTRUMENTATION

O COMMITMENT:

a. The seismic monitoring instrumentation shown in Table 16.7-

2A shall be OPERABLE.

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, APPLICABILITY:

i At all times.

1 i REMEDIAL ACTION:

l a. With one or more seismic monitoring instruments j inoperable for more than 30 days, prepare and submit a 1 Special Report to the Commission within the next 10 days

, outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.

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1 TESTING REQUIREMENTS:

l a. Each of the above seismic monitoring instruments shall be ,

demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL 2

TEST operations at the frequencies shown in Table 16.7-2B.

b. Each of the above accessible seismic monitoring instruments

!. actuated during a seismic event greater than or equal to j' 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the seismic event. Data shall be retrieved from accessible actuated instruments and analyzed to determine the magnitude of the vf.bratory ground motion. Data i retrieved from the triaxial time-history accelerograph shall include a post-event CHANNEL CALIBRATION obtained by actua-F tion of the internal test and calibrate function immediately

!. prior to removing data. CHANNEL CALIBRATION shall be l performed immediataly after insertion of the new recording i media in the triaxial time-history accelerograph recorder.

! A Special Report shall be prepared and submitted to the Commission, with a copy to Director, Office of Nuclear Reactor Regulation, attent ion: Chief, Structural and Geotechnical Engineering Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 10 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

O 16.7-3 11/98

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REFERENCES:

N/A BASES:

16.7-2 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that l l sufficient capability is available to promptly dettermine the !

i magnitude of a seismic event and evaluate the respcuse of those features important to safety. This capability is required to j permit comparison of the measured response to that used in the

! design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974.

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M INSTRUMENTATION 4

16.7-3 METEOROLOGICAL INSTRUMENTATION COMMITMENT j

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a. The meteorological monitoring instrumentation channels shown in Table 16.7-3A shall be OPERABLE.

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! APPLICABILITY:

1

, . At all times.

REMEDIAL ACTION:

! a. With one or more required meteorological monitoring j channels inoperable for more than 7 days, prepare and 1 '

submit a Special Report to the Commission within the next 10 days outlining the cause of the malfunction and j the plans for restoring the channel (s) to OPERABLE j status.

TESTING REQUIREMENTS 2

a. Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the 3-

's CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 16.7-38.

4 4-j REFERENCEss N/A i

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16.7-4 LOOSE-PART DETECTION SYSTEM ;

1 COMMITMENT:

a. The Loose-Part Detection System shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2 REMEDIAL ACTION:

a. With one or more required Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission within the next 10 days outlining the cause of the malfunction and the plans for restoring the channels (s) to OPERABLE status.

TESTING REQUIREMENTS:

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(,) a. One of the three channels associated with the reactor lower vessel area (channel 1, 2 or 3), One channel associated with the reactor upper vessel area (channel 4, 5, or 6), and one channel associated with each steam generator (channel 8, 9, or 10 for SG-A, channel 12, 13 or 14 for SG-B, channel 16, 17 or 18 for SG-C, channel 20, 21 or 22 for SG-D) of the Loose-Part Detection System shall be demonstrated operable by performance of:

1. A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2. An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and

3. A CHANNEL CALIBRATION at least once per 18 months.

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REFERENCES:

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. 16.8 Electrical Powe_r Systems.

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- ELECTRICAL EQUIPMENT PROTECTION DEVICES 16.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES

1. COMMITMENT i -

The containment penetration conductor overcurrent protective devices shown in Table 16.8-1 shall be maintained in compliance with the reautrements of McGuire Technical Specification 16.15-3 8.4.1', ELECTRICAL EQUIPMENT

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' PROTECTIVE DEVICES.

BASES:

1 The tables listed in this commitment were relocated from the McGuire Technical Specifications with the approval of the U.S. Nuclear Regulatory Commission.

- Any additions, deletions, or revisions to the table are considered a change in a commitment and shall be performed pursuant to the Compliance Control of Selected Licensee Commitments Section Manual Procedure. Being a commitment, l these tables.ca.n only be changed using the 10 CFR 50.59 evaluation process as

i. described in the previously mentioned procedure.

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I p General:

, 1.

Cranes or other heavy equipment that~have the potential to touch or affect any or all of the four buslines as they are moved in or !

out of the switchyard, or anywhere within the switchyard where they could touch or affect the buslines. !

l APPLTCABILTTY! Modes 1 through 6 REMEDIAL.ACTTON Restore equipment to normal operating conditions and/or alignments as soon as possible.

TERTING REOUIREMENTS:. None REFERENCF&

McGuire FSAR, Chapter 8 McGuire Technical Specifications and Bases, Nuclear System Directive 409, Nuclear Generation Department / Power Delivery Department Switchyard Interface Agreement Nuclear System Directive 502, Corporate Conduct of Operations in the Switchyard MCC 1535.00-00-0006, SAAG File 208: McGuire Units 1 and 2 PRA Risk significant SSCs for the Maintenance Rule NSAC-203 (EPRI), Losses of Off-Site Power at U. S. Nuclear Power Plants through 1993.

MC-801-02 One Line Diagram, 230/525KV Switchyard 480/277 AC Load Centers (Rev 21)

(s

\ MC-802-01 One Line Diagram, 230/525KV Switchyard 125V DC System (Rev 27)

BASIS; From the probabilistic risk assessment of McGuire Units 1 and 2, it may be concluded that it is important to minimize the risk of a loss of offsite power (LOOP) event, and it is important to be able to restore offsite power following a LOOP event. The identified risk significant activities are a result of an engineering review to determine those systems or actions that are significant to help maximize the availability and reliability of offsite power. The activities are combinations or alignment and design considerations and good practices, as well as lessons learned from past industry events that have been initiators of or contributors to LOOP events.

This SLC was created to provide a method of fracking the switchyard systems for the purposes of supporting WPM 60? (Maintenance Rule Assessment of Equipment out of Servicen and 10 CFR 50.65 (Requirements for Monitoring the Effectiveness of Maintenance at Fuc3 ear Power Plants.)

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O 16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS l i !'

16.9-6 FIRE DETECTION INSTRUMENTATION l' 1 COMMITMENT

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As a minimum, the fire detection instrumentation for each fire detect' ion zone I

! shown in Table 16.9-3 shall be OPERABLE.

- APPLICABILITY: Whenever equipment protected by the fire detection instrument l is required to be OPERABLE.

REMEDIAL ACTION:

i

(^ a. -With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in Table 16.9-3 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within the next I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hotirs or monitor the containment air temperature at least once per

! hour at the locations given in Technical Specification 3.6.5.1SR or l 3.6.5.2SR O b. With more t'han one-half of the Function A fire detection instruments

.Q in any fire zone shown. in Table 16.9-3 inoperable, or with any

. Function B fire detection instruments shown in Table 16.9-3 in-operable, or with any two or more adjacent fire detection instru- i

, ments shown in Table 16.9-3 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a !

l fire watch patrol to inspect the zone (s) with the inoperable i instrument (s) at least once per hour, unless the instrument (s) is 3 located inside the containment, then inspect.that containment zone i at least once per.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature )

i at least once per hour at the locations given in' Technical Specifi-cati on 4. 6.1. 5.1 or 4. 6.1. 5. 2. With any Annulus Fire detection

. instrumentation listed in Table 16.9-3 inoperable do the following:

1 l.

i Within'one hour, perform a fire watch patrol of the annulus and, 11 Perform the following:

!' 1) Perform an hourly fire watch by verifying that at least j' one adjacent zone is operable OR

, 2) If no adjacent zones are operable then perform a fire watch patrol of the annulus at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , thereafter.

O.

16.9-12 11/98

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'u Table 16.9-4 STANDBY SNUTDOWN SYSTEM C0ttf1DNENT REMEDIAL ACTION STATEENTS tith one or more of the following ISS components inoperable Verify operability UI of fire detectors and suppression systems (if installed) in the following areas:

EL 716 EE-XX EE-XX EL 733 EE-KX EL 750. Control Room Battery Cable Turbine Driven Motor Driven Containment Other Room Rooms AW Pump A W Pump Actions

.. Diesel Generator X X X X X X X X (2) (3),(4)

L Diesel starting 24-Volt battery I X X X bank and charger X X X X (2) (3),(4)

Standby ' makeup pump and water supply X X X 250/125 V battery bank and associated charger X X X (2) (4)

Steam Turbine Driven Auxiliary Feedwater Pump Solenoid "C" X Instrumentation Reactor Coolant Pressure X Pressurizer Level X X X X X (2)

Steam Generator Level X (2)

Incere Temperature X X X X X (2)

(2)

OTES: (1) suppression 11 fire detection and/or suppression systems are inoperable, then the REMEDIA1. *CTION statement (s) of the applicable fire detecti selected Licensee Comatteent(s) shall be complied with.

(2)

Monitor contairment air temperature at least once per hour at the locations specified in Specification 3.6.5.1SR or 3.6.5.2SR in lieu of verification of operability of systems inside containment.

(3)

(4) With this component inoperable, verify operability of of f-site power and one' emereeney diesel menerator-With this component inoperable, then denoted areas of both units are affected. .

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1 16.9 AIIXfT.T ARY SYSTTIMS l g .

b FIRE PROTECTION SYSTEMS 16.9-7 STAND 5Y SHUTDOWN SYS'1 tim COMMITMRNT The Standby Shutdown System (SSS) shall be operable.

L APPLICABILITY: MODES 1,2, and 3. l REMEDIAL ACTION 1 NOTI!: ' Die SRO should ensure that security is notified l'0 niifiUtes prior to declaring the SSS inoperable, immediately upon discovery of the SSS inoperability, Security must be notified to implement compensatory measures within 10 minutes of the discovery.

a. With one or more of the following SSS components inoperable, declare the SSS l

inoperable, comply with Action C. of this commitment and within I hour verify the l OPERABILITY of fire detection and suppression systems (ifinstalled) in areas as identified in Table 16.9-4 and as appropriate, perform the actions identified in notes 3 and 4 of the table. SSS components are:

~ SSS Diesel Generator l [V _ SSS Diesel starting 24-Volt battery bank and charger

_ Standby makeup pump and water supply

_ SSS 250/125V battery bank and associated charger

_ Steam Tbrbine Driven Auxiliary Feedwater Pump I ;

_ CAPT Solenoid "C" SA48 '

_ Instrumentation Reactor Coolant Pressure Pressurizerlevel -

Steam Generator Level '

Incore Temperature

b. With the totalleakage from UNIDENTIFIED LEAKAGE, IDENTIFIED LEAKAGE and reactor coolant pump seal leakoff greater than 26 gpm, declare the Standby Makeup Pump and the Standby Shutdown System inoperable; and

c. With the Standby Shutdown System inoperable for more than 7 days, prepare and submit a report to the Commission within the next 30 days outlining the cause of the inoperability, corrective actions being taken, and plans for restoring the system to OPERABLE status.

d. If equipment which constitutes inoperable component of SSS is located inside containment, then repairs shall be effected at the first outage which permits containment access.

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! c. The Standby Makeup Pump water supply shall be demonstrated OPERABLE by:

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'(') i Verifying at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that IDENTIFIED LEAKAGE, UNIDENTIFIED LEAKAGE, and Reactor Coolant Pump Seal leakoff do not exceed a tctal of 26 gpm.

l 11 Verifying at least once per 7 days:

l 1) That the requirements of Technical Specification 3.7.13.1SR are met and the boron concentration in the storage pool is greater than or equal to the minimum boron concentration specified in the Core Operating Limits Report, or

2) That the refueling water storage tank is capable of being aligned to the Standby Makeup Pump.

iii Verifying at least once per 92 days that the Standby Makeup Pump i

develops a flow of greater than or equal to 26 gpm at a pressure l greater than or equal to 2485 psig.

d. The Standby Shutdown System 250/125-Volt Battery Bank and its associated charger shall be demonstrated OPERABLE:

l i At least once per 31 days by verifying:

1

1) That the electrolyte level of each battery is above the i plates, and

2) The total battery terminal voltage is greater than or equal to 258/129 volts on float charge.

ii At least once per 92 days by verifying that the average specific l gravity is greater than or equal to 1.200.

b(_,/ iii At least once per 18 months by verifying that:

1) The batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration, and

2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

e. The Steam Turbine Driven Auxiliary Feedwater Pump and associated components shall be demonstrated OPERABLE at least once per 18 months by

, verifying that the "C" solenoid is capable of being deenergized to open l

valve SA48ABC to provide steam supply to the turbine driven auxiliary feedwater pump.

f. Standby Shutdown System instrumentation shall be demonstrated OPERABLE by performance of testing requirements in Table 16.9-5.

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16.15 CTS RELOCATED ITEMS

'16.15-3.1'2.1 BORATION SYSTEMS FLOW PATH - SHUTDOWN I'

COMMITMENT:

As a minimum, one of'the following boron injection flow paths shall be OPERABLE l 'and capable of being powered from an OPERABLE emergency power source:

a. A flow path from a boric acid tank via a boric acid transfer pump and a charging pump to the Reactor Coolant System if the boric acid storage tank ]

I in SLC 16.15-3.1.2.5a. is OPERABLE, or 1 l

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b. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in SLC 16.15-3.1.2.5b. is OPERABLE.

APPLICABILITY: MODES 5 and 6.

REMEDIAL ACTION:

1 1 With none of the above flow paths OPERABLE or capable of being powered from an

[ OPERABLE energency power source, suspend all operations involving CORE '

ALTERATIONS or positive reactivity changes.

TESTING REQUIREMENTS

16.15-4.1.2.1 At least one of the above required flow paths shall be f'(* '

L demonstrated _ OPERABLE:

a. At least once pet 7 days by verifying that the temperature of the heat

!. traced portion of the flow path is greater than or equal to 65 degrees F l I

l when a flow path from the boric acid tanks is used, and

b. At'least once per 31 days by' verifying that each valve (manual, power operated, or automatic) in the flow path'that is not locked, sealed, or otherwise secured in position, is in its correct position.

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l BASES:

I

! The Boron Injection System ensures that negative reactivity control is available

! during each mode of facility operation. The components required to perform this

! function include: '(1) borated water sources, (2) charging pumps, (3) separate L flow paths, (4) boric acid transfer pumps, (5) associated Heat Tracing Systems, j s.

.and (6) an emergency power supply from OPERABLE diesel generators.

With the RCS temperature below 200'F, one Boron Injection System is acceptable

.without ' single failure consideration on the basis of the stable reae.tivity condition of the reactor and the additional restrictions prohibiting CORE j: ALTERATIONS and positive reactivity changes in the event the single Boron

! Injection' System becomes inoperable.

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16-15.1 1I/98 I

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The OPERABILITY of one Boron Injection System during REFUELING ensures that this

!--[] system is available for reacti*tity control while in MODE 6.

SLC 16.15-3.1.2.1 requires at least one boron injection flow path to be OPERABLE in MODES 5 and 6. This SLC requires that each valve (manual, power operated, or automatic) in the flow path that is not-locked, sealed, or otherwise secured in position be verified to be in its correct position every 31 days.

For automatic valves and power operated valves which are OPERABLE and have an OPERABLE emergency power source, these valves may be repositioned as required to support other plant operations if the valves will move to their proper position on demand to establish the Boration Flow Path.

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16.15 CTS RELOCATED ITEMS I 16.15-3.1.2.2 - ~ BORATION SYSTEMS FLOW PATH - OPERATING COMMITMENT':' I At least two # of the following three boron injection flow paths shall be OPERABLE:

a. The' flow path from a boric acid tank via a boric acid transfer pump and a charging pump to the Reactor Coolant System, and

b. Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3, and 4.

REMEDIAL ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the

! Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and berated to a SHUTDOWN MARGIN equivalent to at least 1% delta k/k at 1 2000F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I TESTING REOUIREMENTS:

16.15-4.1.2.2 At least two of the above required flow paths shall be ,

demonstrated OPERABLE: I

~ a. At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path from the boric acid tanks is greater than f- or equal to 650F when it is a required water source;

,(

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b. At least once per 31 days by verifying that each valve (manual, power l operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;

-c. At least once per 18 months during shutdown by verifying that each

' automatic valve in the flow path actuates to its correct position on a Safety Injection test signal; and

d. At least once per 18 months by verifying that the flow path required by SLC 16.15-3.1.2.2a. delivers at least 30 gpm to the Reactor Coolant System,

.Only one boron injection flow path is required to be OPERABLE whenever the l

j temperature of one or more of the RCS cold legs is less than or equal to 300*F.

BASES:

!' The Boron Injection System ensures that negative reactivity control is available

! during each mode of facility operation. The components required to perform this ,

function include: (1) borated water sources, (2) charging pumps, (3) separate !

flow paths, (4) boric acid transfer pumps, (5) associated Heat Tracing Systems, and (6) an emergency power supply from OPERABLE diesel generators, t With the RCS average temperature above 200*F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an l; assumed failure renders one of the flow paths inoperable. The boration j L

capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from I expected operating conditions of 1.3% delta k/k after xenon decay and cooldown l- ,

16-15.3 i 11/98 h

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to 200*F. The maximum expected boration capability requirement occurs at EOL I from full-power equilibrium xenon conditions. '

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16.15 - CTS RELOCATED ITEMS

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( 16.15-3.1.2.3 - BORATION SYSTEMS CHARGING PUMP - SHUTDOWN COMMITMENT:

One' charging pump in the boron injection flow path required by SLC 16.15-3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 5 and 6.

REMEDIAL ACTION:

With no charging pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

TESTING REOUIREMENTS:

16.15-4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying a differential pressure across the pump of greater than or equal to 2380 psid is developed when tested pursuant to ITS 5.5.8.

BASES.

The Boron Injection System ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include: (1) borated water sources,

,-s (2) charging pumps, (3) separate flow paths, (4) boric acid transfer

[ pumps, (5) associated Heat Tracing Systems, and (6) an emergency power y supply from OPERABLE diesel generators.

With the RCS temperature below 200*F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE below 300'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV. Allowing two Centrifugal Charging pumps to operate simultaneously for 5 15 minutes increases the margin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted during pump swap.

For the 15 minute period during which simultaneous Centrifugal Charging pump operation is allowed, the safety margins as related to the mass addition analysis are not appreciably reduced. Improved Technical Specification 3.4.12 requires two PORVs to be operable during this period of operation, thus a mass addition transient can be relieved as required assuming the two PORVs function properly.

The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

Two charging pumps may be operable and operating for less than or equal to 15 minutes to allow swapping charging pumps.

,f V] 16-15.5 II/98 L - .

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SLC 16.15-3.1.2.3 required one charging pump in the boration flow path l g '

of SLC 16.15-3.1.2.1 to be OPERABLE and capable of being powered from an OPERABLE emergency power source. SLC 16.15-3.1.2.3 is applicable in MODES 5 and 6.

The ACTION statement requires ' suspend all operations involving CORE ALTERATIONS or positive reactivity changes.' The intent is that L

specific evolutions or operations that involve positive reactivity changes (fuel movement, dilutions, control rod movements or sustained NC' temperature changes adding positive reactivity) not continue if the conditions described above do not exist. There are operations (e.g.

swapping ND trains, swapping KC trains, some testing) that can result in temperature oscillations that have insignificant effects on shutdown margin and can continue.

l l Operational or testing activities that result in NC temperature swings of 20 degrees F about an initial value have been judged not to constitute positive reactivity changes as intended in SLC 16.15-3.1.2.3 when in MODE 5. There must be at least 500 ppm of boron beyond the required Shutdown Boron Concentration for this interpretation to remain i valid. This interpretation should not be used to establish sustained NC l_ system heatups or cooldowns that result in sustained positive reactivity I additions.

I REFERENCES Nuclear / Reactor Engineering Memo to File R.F. 4.0.1, August 23, 1994 *NC Temperature Swings affect on Shutdown Margin as per SLC 16.15-3.1.2.3".

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l 16.15 - CTS RELOCATED ITEMS A \

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\v / 16.15-3.1.2.4 BORATION SYSTEMS CHARGING PUMPS - OPERATING COMMITMENT:

At least two # charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

REMEDIAL ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and berated to a i

SHUTDOWN MARGIN equivalent to at least 1% delta k/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l TESTING REQUIREMENTS:

16.15-4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying a differential pressure across each pump of greater than or equal to 2380 psid is developed when tested pursuant to ITS 5.5.8.

BASES:

The Boron Injection System ensures that negative reactivity control is available

,, during each mode of facility operation. The components required to perform this

( ) function include: (1) borated water sources, (2) charging pumps, (3) separate

(,,/ flow paths, (4) boric acid transfer pumps, (5) associated Heat Tracing Systems, and (6) an emergency power supply from OPERABLE diesel generators.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE below 300*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV. Allowing two Centrifugal Charging pumps to operable simultaneously for < 15 minutes increases the margin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted during pump swap.' For the 15 minute period during which simultaneous Centrifugal Charging pump operation is allowed, the safety margins as related to the mass addition analysis are not appreciably reduced. Improved Technical Specification 3.4.12 requires two PORVs to be operable during this period of operation, thus a mass addition transient can be relieved as required assuming the two PORVs function properly.

'A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 300 F.

Two charging pumps may be operable and operating for 5 15 minutes to allow swapping charging pumps.

\ ~J l 16-15.7 l1/98 l

I 16.15 - CTS RELOCATED ITEMS

,m

( 16.15-3.1.2.5 - BORATED WATER SOURCE - SHUTDOWN COMMITMENT:

As a minimum, one of the following berated water sources shall be OPERABLE:

a. A Boric Acid Storage System and at least one associated Heat Tracing System wi*h:

1. A minimum contained berated water volume as presented in the Core Operating Limits Report,

2. A minimum boron concentration as presented in the Core Operating Limits Report, and

3. A minimum solution temperature of 65'F.

b. The refueling water storage tank with:

1. A minimum contained berated water volume as presented in the Core Operating Limits Report,

2. A minimum boron concentration as presented in the Core Operating Limits Report, and

/m $

3. A minimum solution temperature of 70 F.

APPLICABILITY: MODES 5 and 6.

REMEDIAL ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

TESTING REQUIREMENTS:

16.15-4.1.2.5 The above required berated water source shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1. Verifying the boron concentration of the water,

2. Verifying the contained berated water volume, and

3. Verifying the boric acid storage tank solution temperature when it is the source of berated water.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water >= 70 F.

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( 16-15.8

~

L' 1I/98

('] BASES:

The Boron Injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this i function include: (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, (5) associated Heat Tracing Systems, and (6) an emergency power supply from OPERABLE diesel generators. !

The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1% delta k/k af ter xenon decay and cooldown f rom 200 *F to 140 *F. The minimum borated water volumes and concentrations required to maintain shutdown margin for the Boric Acid Storage system and the Refueling Water Storage Tank are presented in the Core Operating Limits Report.

The Technical Specification LCO value for the Boric Acid Storage Tank and the ,

Refueling Water Storage Tank minimum contained water volume during Modes 5 and 6 i is based on the required volume to maintain shutdown margin, an allowance for l unusable volume and additional margin e- follows: )

i Boric Acid Storage Tank Requirements fc: Maintaining SDM - Modes 5 & 6 I

Required volume for maintaining SDM presented in the COLR l Unusable volume (to maintain full suction pipe) 4,199 gallons Additional margin 4,100 gallons Refueling Water Storage Tank Requirements for Maintaining SDM - Modes 5 & 6 Required volume for maintaining SDM Presented in the COLR Unusable volume (to maintain full suction pipe) 16,000 gallons t ) Additional margin 23,500 gallons L)

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

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! '16.15 - CTS RELOCATED ITEMS-g 16.15-3.1.2.6'- BORATED WATER SOURCES'- OPERATING

< COMMITMENT:

As a minimum, the following borated water source (s) .shall be OPERABLE es required by SLC.16.15-3.1.2.2:

(- a. A Boric Acid Storage System and at least one associated Heat Tracing System I. withs.

I'

1. A minimum contained borated water volume as presented in the Core Operating Limits Report,

2. t. minimum boron concentration as presented in the Core Operating' Limits Report, and 3

3. ' A minimum solution temperature of 65 F.

'b. The refueling water storage tank with:

1. A minimum contained berated water volume as presented in the Core Operating Limits Report.

i ..

2. A minimum boron concentration as presented in the Core Operating Limits Report,

3. A minimum solution' temperature oi 70*F, and

4. A. maximum solution temperature of 100*F.

APPLICABILITY: MODES 1, 2, 3 and 4.

REMEDIAL ACTION:

a. With the Boric Acid Storage System inoperable and being used as of the above required berated water sources, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the i

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and berated to a SHUTDOWN MARGIN equivalent to at least 1%

~.

. delta k/k at 200 F; restore the Boric Acid Storage System to OPERABLE

!- status within the next 7 days or be in COLD SHUTDOWN within the next 30

' hours.

k, b. With the refueling water storage tank inoperable, restore the tank to I

OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or 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 , !

L j t-l TESTING REQUIREMENTS:

16.15-4.1.2.6 Each berated water source shall be demonstrated OPERABLE:

, a. At least once'per 7 days by: l i

U l( 16 15.10 11/98 I

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

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l 1. Verifying the boron concentration in the water, fs

( 2. Verifying the contained berated water volume of the water source, and l

l 3. Verifying the Boric Acid Storage System' solution temperature when it is l the source of berated water.

) b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature is greater l than 70 F or less than 100'F.

BASES:

l The Boron Injection system ensures that negative reactivity control is available l during each mode of facility operation. The components required to perform this

! function include: (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, (5) associated Heat Tracing Systens, and (6) an emergency power supply from OPERABLE diesel generators.

The minimum borated water volumes and concentrations required to maintain shutdown margin for the Boric Acid Storage System and the Refueling water Storage Tank are presented in the Core Operating Limits Report.

The Technical Specification LCO value for the Boric Acid Storage Tank and the Refueling Water Storage Tank minimum contained water volume during Modes 1-4 is based on the required volume to maintain shutdown margin, an allowance for l unusable volume and additional margin as follows.

Boric Acid Storage Tank Requirements for Maintaining SDM - Modes 1-4 f

, Required volume for maintaining SDM presented in the COLR

, Unusable volume (to naintain full suction pipe) 4,199 gallons l Additional margin 6,470 gallons l Refueling Water Storage Tank Requirements for Maintaining SDM - Modes 1-4 Required volume for maintaining SDM Presented in the COLk Unusable volume (to raintain full suction pipe) 16,000 gallons Additional margin 23,500 gallons The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

l I

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components, i i

i (o 16-15.11 31/9g

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16.15-3.1.3.3 - ROD POSITION INDICATION SYSTEM-SHUTDOWN l j

{

COMMITMENT: I One rod position indicator (excluding demand position indication) shall be OPERABLE and capable of determining the control rod position within - 12 steps for each shutdown or control rod not fully inserted.

APPLICABILITY: MODES 3*, 4* and 5*.

REMEDIAL ACTION:

With less than the above required position indicator (s) OPERABLE, immediately open the Reactor Trip System breakers.

BASES:

OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod l alignment and insertion limits.

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With the Reactor Trip System breakers in the closed position.

l rs e 1 (y 16-15.12 '

11/98

1 16.15 - CTS RELOCATED ITEMS 16.15-3.3.3.1 - RADIATION MONITORING FOR PLANT OPERATIONS COMMITMENT:

The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY: As shown.in Table 3.3-6.

REMEDIAL ACTION:

a. With a radiation monitoring channel Alarm / Trip Setpoint exceeding the value shown'in Table 3.3-6, adjust the Setpoint to within the limit within-4 hours or declare the channel inoperable.

b.' With one or more radiation monitoring channels inoperable, take the action shown in' Table 3.3-6.

c. The provisions of SLC 16.2.3 are not applicable.

TESTING REQUIREMENTS:

16.15-4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations for the modes and at the frequencies y shown in Table 4.3-3.

BASES:

The OPERABILITY of the radiation monitoring inst rumention for plant operations ensures that: (1) the associated action will. be initiated with the radiation

level monitored by each channel or combinatic. thereof reaches its Setpoint, (2) the'specified coincident logic is maintained, and (3) sufficient redundancy is maintained to permit.a channel to be out-of-service for testing or maintenance.

The radiation monitors for plant operations sensos radiation levels in'. selected plant systems and locations and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.

16-15.13 11/98

L TABLE 3.3-6 I RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS MINIMUM CHANNELS CHANNELS APPLICABLE ALARM / TRIP t MONITOR TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION

1. Containment Atmosphere 1 1 1, 2, 3, 4 ***

26 '

Gaseous Radioactivity-High (Low Range-EMF-39)

2. Spent Fuel Pool 1 1 **

s 1.7 x 10 4 30 Radioactivity-High pCi/ml '

(EMF-42)

3. Criticality- 1 1 s 15 mR/hr 28 Radiation Level (2 EMF-4)

4. Gaseous Radioactivity- N.A. I 1, 2, 3, 4 N.A. 29 RCS Leakage Detection (Low Range - EMF-39)

5. Particulate N.A. 1 1,2,3,4 N.A. 29 Radioactivity- "

RCS Leakage Detection (Low Rangc - EMF-38) l 16-15.14 11/98

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TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS MINIMUM CHANNELS CHANNELS APPLICABLE ALARM / TRIP MONITOR TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION

6. Control Room Air 1 per station 2 per All s 3.4 x 10 4 27 Intake Radioactivity- station pCi/ml High (EMF-43aand43b)

TABLE NOTATION With fuel in the fuel storage areas or fuel building.

With irradiated fuel in the fuel storage areas or fuel building.

- - - Must satisfy the requirements of McGuire Selected Licensee Commitment 16.11-6.

ACTION STATEMENTS ACTION 26 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge valves are maintained closed.

ACTION 27 - With the number of operable channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolate the Control Room Ventilation System outside air intake which contains the i inoperable instrumentation.

ACTION 28 - With less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel pool area. Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.

ACTION 29 - Must satisfy the ACTION requirement for Specification 3.4 15 ACTION 30 - With less than the minimum channels OPERABLE requirement, operation may continue provided the Fuel Handling Ventilation Exhaust System requirements of Specification 3.7.12 are met.

16-15.15 11/98

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TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT <

OPERATIONS SURVE!LLANCE REQUIREMENTS ANALOG CHANNEL MODES - :

CHANNEL CHANNEL OPERATIONAL REQUIRING MONITOR CHECK CALIBRATION TEST SURVEILLANCE

1. Containment Atmosphere Gaseous S R Q 1, 2, 3, 4 Radioactivity-High (Low Range-EMF-39)

2. Spent Fuel Pool . Ventilation S R Q Radioactivity-High (EMF-42)

3. Criticality-High .

S R Q Radiation Level (IEMF-17)

4. Gaseous Radioactivity-RCS Leakage S R Q 1, 2, 3, 4 ;

Detection (Low Range-EMF-39)

5. Particulate Radioactivity- S R Q 1, 2, 3, 4 RCS Leakage Detection (Low Range-EMF-38)

6. Control Room Air Intake S R Q All '

Radioactivity-High (EMF-43a and EMF-43b)

TABLE NOTATION

- With fuel in the fuel handling area.

- - With irradiated fuel in the fuel handling area.

16-15.16 11/98

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16.15 - CTS RELOCATED ITEMS O\

16.15-3.3.3.2 - MOVABLE INCORE DETECTORS l

COMMITMENT:

The Movable Incore Detection System shall be OPERABLE with:

a. At least 75% of the detector thimbles, l

l

b. A minimum of two detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for:

a. Recalibration of the Excore Neutron Flux Detection System,

b. Monit.oring the QUADRANT. POWER TILT RATIO, or i

c. Measurement of Fo(Z) or F" Delta H l l

REMEDIAL ACTION: ,

1 With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of SLC

. 16.2.3 are not applicable.

TESTING REQUIREMENTS:

i 16.15-4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE 1 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by normalizing each detector output when required for:

I

a. Recalibration of the Excore Neutron Flux Detection System, or j 1

b. Monitoring the QUADRANT POWER TILT RATIO, or l l

c. Measurement of Fo(Z) or F" Delta H BASES:

l The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core.

.The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring Fo(Z) or F" Delta H a full incore flux map is used. 1 i Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in !

l' recalibration of the Excore Neutron Flux Detection System, and full incore flux !

maps or symmetric incore thimbles may be sued for monitoring the QUADRANT POWER t TILT RATIO when one Power Range channel is inoperable.

' ( 16-15.17 j

V 5

1 11/98 i i

l i

(

j

l. The Testing Requirements for SLC 16.15-3.3.3.2 require that each detector be '

l, .1 fm demonstrated Operable at last once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by normalizing detector output

- V) when the system is required for the specified activities.

The interval of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months begins when the normalization procedure for the detectors has been initiated, such that each detector is normalized at least !

once in a given 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

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l:

-l10 16-15.18

\v'j i 11/98 i 3

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l 16.15. - CTS RELOCATED ITEMS I

'16.15-3.3.3.9 - EXPLOSIVE GAS MONITORING' INSTRUMENTATION COMMITMENT i

l l ,The gas monitoring instrumentation channels shown in Table 3.3-13 shall be .;

l OPERABLE with their Alarm / Trip Setpoints set to ensure that the' limits of ITS I 5.5.12.a are not exceeded.

APPLICABILITY: As shown in Table 3.3-13.

REMEDIAL ACTION:

a. With an explosive gas monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

.b. With less than the minimum number of explosive _ gas monitoring instrumentation channels OPERABLE, take the. ACTION shown in Table 3.3713.

I. Restore the inoperable instrumentation to OPERABLE status within the time l specified in the ACTION, if unsuccessful,' prepare and submit a'Special

[ Report to the Commission to explain why this inoperability was not 1 l corrected within the time specified.

l. c. The' provisions of SLC.16.2.3 are not applicable.

l.

-TESTING REQUIREMENTS:

16.15-4.3.3.9 Each explosive gas monitoring instrumentation channel shall be 1 l demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION

! and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3.9

-BASES:

-The gas instrumentation is provided for monitoring (and controlling) the f? . concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.

l SLC 16.15-3.3.3.9, Table 3.3-13 Item 2 requires that one hydrogen and two oxygen analyzers per station be OPERABLE in the Waste Gas (WG) System to ensure that explosive gas mixtures are not allowed in the WG System,

b. Only one recombiner train is in service at a time. In this case, the requirement for one hydrogen and two oxygen analyzers shall apply only to the train in service, l-i t, f 16-15.19 11/98

)

s/

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r.

ll

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I l

f\ The requirement for oxygen analyzers may be satisfied for Train "A" by using two

( of the following three analyzers:

i l

OWGMT5790 OWGMT6210 OWGMT6211 '

The requirement for oxygen analyzers may be satisfied for Train "B" by using two of the following three analyzers:

OWGMT5780 OWGMT6210 OWGMT6211 i

NOTE: )

l l The recombiner inlet oxygen analyzers (OWGMT5660/5670) shall not be used to satisfy the requirements of either train because these instruments

[ measure the oxygen concentration after the addition of bulk oxygen. This I j is not representative of the Waste Gas System as defined in SLC 16.15-l 3.11.2.5. These analyzers will henceforth be used for the operation of i the hydrogen recombiner but will not be used to satisfy the requirements of SLC 16.15-3.3.3.9.

i

REFERENCES:

Review of FSAR, Section 11.3, System Description, and the Catalytic Hydrogen Recombiner Operational Manual, MNM-1201.04-0174.

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16-15.20 l

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TABLE 4.3-9 t EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS :

ANALOG ;

CHANNEL MODES

/ CHANNEL CHANNEL OPERATIONAL REQUIRING MONITOR. CHECK CALIBRATION TEST SURVEILLANCE >

1. Not Used

2. WASTE GAS HOLDUP SYSTEM Explosive !

Gas Monitoring System i

a. Hydrogen Monitor D Q(1) M **

b. Oxygen Monitor D Q(2) M ** !

c. Oxygen Monitor (alternate) D M **

Q(2)

3. Not Used ,

t

4. Not Used i

TABLE NOTATION

- During WASTE-GAS HOLDUP SYSTEM operation.

(1) The CHANNEL CALIBRATION shall include the use of standard gas samples corresponding to alarm setpoints ;

in accordance with the manufacturer's recommendations.

(2) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the i manufacturer's recomendations. In addition, a standard gas sample of nominal 4 volume percent oxygen, i balance nitrogen, shall be used in the calibration to check linearity of the oxygen analyzer. !

16-15.21 11/98 +

_ . _ _ _ . ~ _ - _ . _ -- .-....-.m_=.. - ,,_ . _ . . _ _ _ _ _ _.._____m____=_____.____..__..______.._______.___._.___._._____.._.___u__.__m___.__.

) .

TABLE 3.3-13 ;

EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY 8CIION

1. Not Used i

2. WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System

a. Hydrogen Monitor 1 per station **

1

b. Oxygen Monitors 2 per station ** '2

3. Not Used

4. Not Used

- During WASTE GAS HOLDUP SYSTEM operation.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the-recombiner.

ACTION 2 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE !

requirement, operation of this system may continue for up to 14 days. With two channels inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i 16-15.22 11/98 i

_.. ._ ,.___ _.__ _.._.-.-_.._.._.-..~__.___._._..__..___._._.x 16.15 - CTS RELOCATED ITEMS E .

l 4 16.15-3.4.2.1 REACTOR COOLANT SYSTEM SAFETY VALVES -SHUTDOWN l I COMMITMEN'.; I A minimum of one pressurizer Code safety valve shall be OPERABLE with a lift j setting setting of 2485 psig +'3%, -2%*.

APPLICABILITY: MODES 4 and 5.

! REMEDIAL ACTION:

L With.'no pressurizer Code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE RHR loop Linto' operation in the shutdown cooling mode.

l TESTING REOUIREMENTS:

I

'16.15-4.4.2.1 No additional requirements other'than those required by Specification 5.5.8. Following testing, lift settings shall be within + 1%.

' BASES:

The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at the valve Setpoint. .The relief capacity of a single. safety-valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves

(

r are. OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure

-relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.

Demonstration of the. safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI l

of the ASME Boiler and Pressure Code. SLC 16.15-3.4.2.1 & ITS 3.4.10 allow a +

3% and - 2% setpoint tolerance for OPREABILITY; however, the valves are reset to ;

+ 1% during surveillance testing to allow for drift.

I l

p *The lift setting pressure shall correspond to ambient conditions of the valve j at nominal operating temperature and pressure, i l

, 16-15.23

,. 11/98 l

l

'16.15 - CTS RELOCATED ITEMS 16.15-3.4.7 REACTOR COOLANT SYSTEM CHEMISTRY COMMITMENT:

The Reactor Coolant System chemistry shall be maintained within the limits

-specified in Table 3.4-2.

APPLICABILITY: At all times.

REMEDIAL ACTION:

MODES 1, 2, 3, and 4:

a. With any one or more chemistry parameter in excess of its Steady State i Limit but within its Transient Limit, restore the parameter to within its Steady-State Limit within 24. hours or 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 ;-and

b. With any one or more chemistry parameter in_ excess of its Transient Limit, ,

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 3^ hours. !

At All Other Times:

With the concentration of either chloride or fluoride in the Reactor 1 Coolant System in excess of its Steady-State Limit for more.than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

!fN or in excess of its Transient Limit, reduce the pressurizer pressure to g

less than or equal to 500 psig, if applicable,.and perform an engineering evaluation to determine the effects of the out-of-limit condition on the _j structural integrity of the Reactor Coolant System; determine that the l Reactor Coolant System remains acceptable for continued operation prior to increasing the pressurizer pressure above 500 psig or prior to proceeding to MODE 4.

y TESTING REQUIREMENTS:

16.15-4.4.7 The Reactor Coolant System chemistry shall be determined to be j within the limits by analysis of those parameters at the frequencies specified j in Table A.4-3. I BASES:

The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System'is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection

-to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride-limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to'the Transient Limits, for the specified limited

' time intervals witho*ut having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation a-16-15.24 11/98

,~ ----a-

. - .. .. w.~ . . . . .- -. . =.. _ - ~- . . ~ - - -. ....- -_.

within the restrictions of the Transient Limits provides time for taking i

m corrective actions to restore the contaminant concentrations to within the '

Steady State Limits.

)

The Surveillance Requirements provide adequate assurance that concentrations in l excess of the limits will be detected in sufficient time to take corrective l

! ACTION, i i

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16-15.25 N ,h 11/98 i.-

TABLE 3.4-2 REACTOR COOLANT SYSTEM l CHEMISTRY LIMITS l

l !

STEADY-STATE TRANSIENT PARAMETER LIMIT LIMIT j Dissolved Oxygen

s 0.10 ppm i

s 1.00 ppm 1

,. Chloride . s 0.15 ppm l- s 1.50 ppm Fluoride s 0.15 ppm s 1.50 ppm I l

l-TABLE 4.4-3 REACTOR COOLANT SYSTEM !

j CHEMISTRY LIMITS SURVEILLANCE REOUIREMENTS 1

SAMPLE AND PARAMETER ANALYSIS FRE0VENCY :

Dissolved Oxygen ** At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Chloride At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Fluoride At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months I'

Limit not applicable with T,yg less than or equal to 250*F.

n **Not required with T,yg less than or equal to 250*F.

1 O

11/98 16-15.26

4 .- .._ _. _ -..._....m.____ _. _ . . _ _ _ . _ _ _ . _ _ - _. _ . . . _

l 16.15 - CTS RELOCATED ITEMS b

fg) ~ 16.15-3.4.9.2 - PRESSURIZER COMMITMENT:

.The pressurizer temperature shall be limited to:

a. A maximum heatup of 100*F in any 1-hour period, i

b.- A maximum cooldown of 200*F in any 1-hour period, and ;

i

c. A maximum spray water temperature dif ferential of 320*F.

APPLICABILITY: At all times.

REMEDIAL ACTION: i i

i With the pressurizer temperature limits in excess of any of the above limits, !

restore the temperature to within the limits within 30 minutest perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remaine acceptable fcr continued operation.or 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 reduce the pressurizer pressure to less than 500 psig.

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

~

i

~ TESTING REQUIREMENTS: l 16.15-4.4.9.2 The pressurizer temperatures shall be determined to be within the

,$/ } l s_/ limits at least once per 30 minutes during system heatup or cooldown. The spray l water temperature differential shall be determined to be within.the limit at

~

least.once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during auxiliary spray operation.

BASES:

The temperature and pressure changes during heatup arid cooldown are limited 'to i be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code,Section III, Appendix G:

(

The pressurizer heatup and cooldown rates shall'not exceed 100 F/hr and 200 l

F/hr, respectively. The' spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 320 *F, and System preservice hydrotests and inserv'ce i leak and hydrotests shall be. '

performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI.

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance within the ASME Code requirements.

16-15.27 11/98 1

_. . m_ -. . - ____,.m ._ -. . _ _ . _ . _ - . _ . _ . . . _ _ _ _ . _ . - .

i ;

e 16.15. - CTS RELOCATED ITEMS-16.15-3.4.10 REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY t

l COMMITMENT:

The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with ITS 5.5.7.

APPLICABILITY: All MODES.

REMEDIAL ACTION:

a. With the structural integrity of any ASME Code Class 1 component (s) not l conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected

l. component (s) prior to increasing the Reactor Coolant System temperature l

. more than 50*F above the minimum temparature required by NDT considerations.

b. With the structural integrity of any AS.!E Code Class 2 component (s) not conforming-to the above> requirements, rectore the structural integrity of i the affected component (s) to within its 1.mit or isolate the affected- l component (s) prior to increasing the.Reactsr Coolant System temperature

! above 200'F.

I c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of

[N the affected component (s) to within its limit or isolate the affected

( , component (s) from service.

TESTING REQUIREMENTS:

j.

16.15-4.4.10 In addition to the requirements of Specification 5.5.8, each reactor coolant pump flywheel shall be inspected per the recommendations of l Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. l l

I BASES: l i

'The inservice inspection and testing programs for ASME Code Class 1, 2, and 3 i components ensure that the structural integrity and operational readiness of l these components will be maintained at an acceptable level throughout the life of the plant. These programs are.in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the

!' Commission pursuant to 10 CFR Part 50.55a(g) (6) (i) . ,

i

~ Components of the Reactor Coolant System were designed to provide access to !

l permit. inservice inspections in accordance with Section XI of the ASME Boiler

.and Pressure Vessel Code, 1971 Edition and Addenda through Winter 1972. ,

r i

16-15.28 ggg

.. - _m. . ._. .. >_ .m. ._.m. _ _ . . - . _ _ . - - . _ _ _ _ . ~ _ _ _ _ _ _ . . _.-.m _ . _ . - _ _. _

l 16.15 --CTS RELOCATED ITEMS

'16,15-3.4.11 REACTOR COOLANT SYSTEM REACTOR VESSEL HEAD VENT SYSTEM I'

l

- COMMITMENT:

.Two reactor vessel head vent paths, each consisting of two valves in series powered from emergency buses shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3 and 4 f

l REMEDIAL ACTION:

l C a. With one of the above reactor vessel head paths inoperable, STARTUP and/or POWER. OPERATION may continue provided the inoperable vent path is )

[- maintained closed with power removed from the valve actuator of all the j

valves in the inoperable vent path; restore the inoperab]e vent path to OPERABLE status within 30 days or be in 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 .

b. With'both of the above reactor vessel head vent paths inoperable; maintain' l the inoperable vent path closed with power removed.from the valve

! actuators of'all the valves in the inoperable vent paths, and restore at j least two of the vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in !

i-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 l l hours.

[ '\ TESTING REQUIREMENTS * !

\-%

16.15-4.4.11 .Each reactor vessel head vent path shall be demonstrated OPERABLE l l

at least once per 18 months by:

1.' Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTWWN or REFUELING.

2. Verifying flow through the reactor vessel head vent paths during venting i during COLD SHUTDOWN or REFUELING. !

l BASES: i Reactor Vessel Head Vents are provided to exhaust noncondensible gases and/or I steam from the primary system that could inhibit natural circulation core l-- cooling. The OPERABILITY of at least one reactor coolant system vent path from

l. the reactor vessel head and the pressurizer steam space ensures the capability i exists to perform this function. (Operability of the pressurizer steam space IL vent path is provided by ITS 3.4.11 and 3.4.12.

The valve redundancy of the reactor coolant system vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve,: power supply or control system does not prevent isolation of_the vent path.

l l' The surveillance to verify Reactor Vessel Head Vent flowpath is qualitative as no' specific size or flow rate is required to exhaust noncondensible gases. The a is,j ; 1 & l5.29 3 3/9g L

l

.m. _

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

i i

function, capabilities, and testing requirements of the reactor coolant system vent'systemi are consistent with the requirements'of Item II.B.1 of NUREG-0737,

" Clarification of TMI Action Plan Requirements", November 1980. l

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16-15.30

D lI/98 l

l

1 16.15 CTS RELOCATED ITEMS p-( ,/ ,

16.15-3.5.2 ECCS SUBSYSTEMS - TAVG >= 3 5 0*F COMMITMENTS: See ITS LCO 3.5.2 APPLICABILITY: Modes 1-3 TESTING REQUIREMENTS:

16.15-4.5.2.c Each ECCS subsystem shall be demonstrated OPERABLE by visual inspection which verified that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed.

1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of each containment ent ty when CONTAINMENT INTEGRITY is established.

BASES:

None i

g i NY~

n) ,

16-15.31 1

'l s

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'16.15'- CTS RELOCATED ITEMS

,s

'l

\ 16.15-3.6.5.2 - ICE BED TEMPERATURE MONITORING SYSTEM. ,

i I

' COMMITMENT:

l The-Ice Bed Temperature Monitoring System shall be OPERABLE with at least two OPERABLE RTD. channels in the' ice bed at each of three basic elevations (10'6",

'30'9" and 55' above the floor of the ice condenser) for each one-third of the

p. ice condenser.

( APPLICABILITY: MODES 1, 2, 3, and 4.

l REMEDIAL ACTION:

1, t

a. With the Ice Bed Temperature Monitoring System inoperable, POWER OPERATION may-continue for up to 30 days provided:

l I - 1. The ice compartment lower inlet doors, intermediate deck doors,.and top p deck doors are closed; L

l 2. The last recorded mean ice bed temperature was less than or equal to 20*F and steady; and ;

i

3. The ice condenser cooling system is OPERABLE with at least:

l a) 21 OPERABil air handling units, l-

[/}

\m, b) 2 OPERABLE glycol circulating pumps, and c) 3 OPERABLE refrigerant units; 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 .

l -b. With the Ice Bed Temperature Monitoring System inoperable and with the Ice Condenser Cooling System not satisfying the minimum components OPERABILITY j requirements of ACTION a.3, above, POWER OPERATION may continue for up to 6

' days provided the ice. compartment lower inlet doors, intermediate deck doors, and top deck doors are closed and the last recorded mean ice bed temperature was less than or equal to 15'F and steady; 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 .

h I

j- TESTING REQUIREMENTS:

i

! 16.15-4.6.5.2 The Ice Bed Temperature Monitoring System shall be determined l~ . OPERABLE by performance of a CHAMIEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

BASES:

The OPERABILITY of the Ice Bed Temperature Monitoring System ensures that the capability'is available for monitoring the ice temperature. In the event the system is inoperable,1the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

c~

16-15.32 11/98 l

[

1:

r ,. . - , . - ,

The Ice Bed Temperature Monitoring System shall be operable with at least two OPERABLE RTD channels in the ice bed at each of three basic elevations (10'6",

30'9" and 55' above the floor of the ice condenser) for each one-third of the ice condenser.

Operations needs a list of applicable RTDs with their respective locations to make appropriate operability evaluations.

Location of RTD's in Ice Condenser DukeID# Westing- Radial Degree Elevation Recorder Region houseID# Location Location Pen #

NPRD5000 TE801-1 54'E 310 823 1 A NPRD5010 TE801-2 54'E 310 799 2 A NPRD5020 TE801-3 54'E 310 768 Bay 1 3 A Fir Sib NPRD5030 TE801-4 50' 347 823 4 A NPRD5040 TE801-6 50' 347 799 5 A NPRD5050 TE801-5 50' 347 779 6 A NPRD5060 TE801-7 46' 25 823 7 A NPRD5070 TE801-8 46' 25 799 8 A NPRD50'10 TE801-9 46' 25 779 9 A NPRD5090 TE801-10 50' 25 823 10 A NPRD5100 TE801 11 50' 25 799 11 A NPRD5110 TE801-12 50' 25 779 12 A g NPRD5120 TE801-13 54'E 25 823 13 A

\

NPRD5130 TE801-14 54'E 25 799 14 A NPRD5140 TE801 15 54'E 25 779 15 A NPRD5150 TE801-16 50' 62 823 16 A NPRD5160 TE801-17 50' 62 799 17 B NPRD5170 TE801-18 50' 62 779 18 B NPRD5180 TE801-19 46' 86 823 19 B NPRD5190 TE801-20 46' 86 799 20 B NPRD5200 TE801-21 46' 86 779 21 B NPRD5210 TE801-22 50' 86 823 22 B NPRD5220 TE801-23 50' 86 799 23 B NPRD5230 TE801-24 50' 86 779 24 B NPRD5240 TE801-25 54'E 86 823 25 B NPRD5250 TE801-26 54'E 86 799 26 B NPRD5260 TE801-27 54'E 86 768 Bay 27 B 12 Fir Slb NPRD5270 TE801-28 50' 122 823 28 B NPRD5280 TE801-29 50' 122 799 29 B NPRD5290 TE801-30 50' 122 779 30 B NPRD5300 TE801-31 46' 160 823 31 C 16-15.33 11/98

b

.O DukeID# Westing- Radial Degree Elevation Recorder Region G NPRD5310 houseID#

TE801-32 Location 46' Location 160 799 Pen #

32 C ,

NPRD5320 TE801-33 46' 160 779 33 C NPRD5330 TE801-34 50' 160 823 34 C NPRD5340 TE801-35 50' 160 799 35 C NPRD5350 TE801-36 50' 160 779 36 C NPRD5360 TE801-37 54'E 160 823 37 C EDM370 TE801-38 54'E 160 799 38 C j N- 1380 TE801-39 54'E 160 779 39 C '

I N HiD5390 TE801-40 50' 195 823 40 C NPRD5400 TE801-41 50' 195 799 41 C NPRD5410 TE80142 50' 195 779 42 C NPRD5420 TE801-43 54'E 232 823 43 C i NPRD5430 TE801-44 54'E 232 793 44 C j NPRD5440 TE80145 54'E 232 768 45 C l NPRD5450 TE801-46 83 828 46 B NPRD5460 TE801-47 83 828 47 B )

NPRD5470 TE801-48 SPARE 48 Miscellaneous information:

Each third of the Ice Condenser covers approximately 100 degrees of the containment structure ]

REGION A: 305 degrees to 45 degrees REGION B: 45 degrees to 145 degrees

'l REGION C: 145 degrees to 245 degrees The 3 basic elevations above the floor of the ice condenser and their relative elevations are:

55 ft. 823 ft.

30 ft. 9 in. - 799 ft.

10 ft. 6 in. - 779 ft.

48 total points available for monitoring; #48 not normally used (spare); should be bypassed.

5 points are not addressed by the SLC: #3,27 & 45 are at or near the ice condenser floor slab; #46 & 47 are in the ice condenser upper plenum at or near the intermediate deck doors.

CHART RECORDER POINTS Elevation Ice Condenser Ice Condenser Ice Condenser Section A Section B Section C 823 1,4,7,10,13 16,19,22,25,28 31,34,37,40,43 799 2,5,8,11,14 17,20,23,26,29 32,35,38,44,41 770 6,9,12,15 18,21,24,30 33,36,39,42 O 16-15.34 11/98

16.15 - CTS RELOCATED ITEMS

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16.15-3.6.5.4 ICE CONDENSER INLET DOOR POSITION MONITORING SYSTEM

'N Jf COMMITMENT: )

The Inlet Door Position Monitoring System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

REMEDIAL ACTION:

With the Inlet Door Position Monitoring System inoperable, POWER OPERATION may l continue for up to 14 days, provided the Ice Bed Temperature Monitoring System is OPERABLE and the maximum ice bed temperature is less than or equal to 27 F when monitored at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, restore the Inlet Door Position Monitoring System to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLDSHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

TESTING REQUIREMENTS:

16.15-4.6.5.4 The Inlet Door Position Monitoring System shall be determined OPERABLE by:

a. Performing a CHANNEL CHECK at least once per 7 days and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after receiving an " Ice Condenser Inlet Door Open" alarm on the control room annunciator portion of the system, p

t i

( ,/ b. Performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 18 months, and

c. Verifying that the Monitoring System correctly indicates the status of each inlet door as the door is opened and reclosed during its testing per Specification 4.6.5.3.1.

BASES:

The OPERABILITY of the Inlet Door Position Monitoring System ensures that the capability is available for monitoring the individual inlet door position. In the event the system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

6 16-15.35 11/98 l

l 16.15 --CTS RELOCATED ITEMS 16.15-3.6.5.4 ICE CONDENSER INLET DOOR POSITION MONITORING SYSTEM COMMITMENT:

The Inlet Door Position Monitoring System shall be OPERABLE.

APPLICABILTTT: MODES 1, 2, 3, and 4.

REMEDIAL ACTION:

-With the Inlet Door Position Monitoring System inoperable, POWER OPERATION may

~

co 2inue for up to 14 days, provided the Ice Bed Temperature Monitoring System is OPERABLE and the m..ximum ice bed temperature is less than or equal to 27 F when monitored at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, restore the Inlet Door

. Position Monitoring System to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLDSHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

TESTING REQUIREMENTS:

16.15-4.6.5.4 The Inlet Door Position Monitoring System shall be determined OPERABLE by:

a. Performing a CHANNEL CHECK at least once per 7 days and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after receiving an " Ice Condenser Inlet Door Open* alarm on the control room annunciator portion of the system,

b. Performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 18 months, and

c. Verifying that the Monitoring System correctly indicates the status of each inlet door as-the door is opened and reclosed during its testing per Specification 4.6.5.3.1.

BASES:

The OPERABIhITY of ,qe Inlet Door Position Monitoring System ensures that the capability is available for monitoring the individual inlet door position. In I the event the system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

O 16-15.36 11/98

16.15 - CTS RELOCATED ITEMS

'\

% ) 16.15-3.7.2 - STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION COMMITMENT:

The temperatures of both the reactor and secondary coolants in the steam generators shall be greater than 70*F when the pressure of either coolant in the steam generators greater than 200 psig.

APPLICABILITY: At all times.

REMEDIAL ACTION:

With the requirements of the above specification not satisfied:

a. Reduce the steam generator pressure of the applicable side to less than or equal to 200 psig within 30 minutes, and

b. Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator.

Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200 F.

TESTING REQUIREMENTS:

16.15-4.7.2 The pressure in each side of the steam generator s'.lall be determirL6

,s to be less than 200 psig at least once per hour when the temperature of either

/

\ the reactor or secondary coolant is less than 70*F.

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BASES:

The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RTmn of 10 F and are suf ficient to prevent brittle fracture.

A

/ \ 16-15.37 V 11/98

,- 16.15 - CTS RELOCATED ITEMS h*

l- 16.15-3.7.6 CONTROL ROOM AREA-VENTILATION SYSTEM

-COMMITMENTS:

Control Room Area AHU, Switchgear Room AHU, and Battery Rocm Exhaust shall be operable.

' APPLICABILITY: ALL MODES i l

REMEDIAL" ACTION:

l- ~

l 1. If either A or B train Control Room Area AHU fails, becomes ]

l unavailable or is unable to maintain the temperature as stated on }

l Table 1, restore within 7 days or declare the AHU INOPERABLE.

l I

2. A SWGR-AHU shall be declared INOPERABLE if:

a) The AHU unit of any sub-equipment is inoperable or unavailable, or, b) The inability to maintain the temperature below the maximum in the area served as listed on Table 1.

With any ONE SWGR-AHU (or support system) of any one of four SWGR rooms INOPERABLE, restore the inoperable equipment to operable within 30 days or declare the affected SWGR INOPERABLE. With.

l- both trains of SWGR AHU per SWGR room INOPERABLE, immediately restore one train of SWGR-AHU and comply with the above.

l 1

The redundant SWGR-AHU shall be immediately started following a single SWGR unit being declared INOPERABLE and the respective i SWGR room temperature verified trending towards or below Table 1, !

or else declare the affected SWGR INOPERABLE. (

}

, If any of these components becomes INODERABLE, a priority E work I l request shall be written, requiring prompt and continuing l

( attention.

3. With one train of BR-XF INOPERABLE, restore the equipment to operable within 30 days or declare the batteries INOPERABLE. I l

With both battery room exhaust fans INOPERABLE, within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months lock open all battery room BR-XF check dampers (lVC23, IVC 24, IVC 25,

)'

lVC26) and at least every 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months verify the ambient conditions of temperature $ 104" F and hydrogen concentration s 2%. Restore at ,

least one BR-XF to OPERABLE "with all check dampers j unlocked / restored" within 7 days or declare all the batteries l INOPERABLE. l

( If either BR ,XF becomes INOPERABLE, a priority E work request shall I be written requiring prompt and continuing attention. ,

i.

4 Q 16-15.38 n .

i I I

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(

v TESTING REQUIREMENTS: I BASES:

1 l

1. In order to maintain SWGR equipment operability, the following !

ventilation equipment shall be OPERABLE: )

l SWGR-AHU-1A SWGR-AHU-2A '

SWGR-AHU-1B SWGR-AHU-2B SWGR-AHU-1C SWGR-AHU-2C l SWGR-AHU-1D SWGR-AHU-2D

2. For clarity, each SWGR room has its own 30 day clock, i.e. 1 ETA's 30 day clock is independent of 1ETB's 30 day clock.

An INOPERABLE SWGR AHU should be entered in TSAIL with "For Tracking Purposes" entered in the " Remarks" column. For consistency, TSAIL entries should read 'VC-SWGR/AHU 1A", "VC-SWGR/AHU IB" etc.

NOTE: A hand held pyrometer, etc. is acceptable if the computer points for temperature are not available.

3. In order to maintain battery operability, the following l Equipment must be OPERABLE. For conservatism, assume that all I battery rooms are affected by a Bettery Room Exhaust fan inoperability:

BR-XF-1 l'D}

t

\-- BR-XF-2 An INOPERABLE battery room exhaust fan should be entered in TSAIL with "For tracking purposes" entered in the remarks column. For consistency, TSAIL entries should read 'VC/BR-XF-1" or *VC/BR-XF-2." l REFERENCES j Discussions with Mechanical Engineering and M.A. Tartaglia November 2, 1932 MEMO TO FILE. This interpretation is part of the corrective actions of PIR 0-M91-0114. i l

1

!A) 16-15.39 J

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,s

( )/ Table 1 EQUIPMENT AREA (S) SERVED MAXIMUM ALLOWABLE TEMPERATURE SGR-AHU-1A ROOM 803, EL. 750 SEE NOTE SGR-AHU-1B 90 SGR-AHU-2A ROOM 805, EL. 750 90 SGR-AHU-2B SGR-AHU-1C ROOM 705, EL. 733 90 SGR-AHU-1D SGR-AHU-2C ROOM 716, EL. 733 90 SGR-AHU-2D CRA-AHU-1 ELECTRICAL PEN RM. EL.767 104 i CRA-AHU-2 ELECTRICAL PEN RM. EL.767 104 104 l BATTERY ROOMS 707, 708, 104 l 706, 710, 711 EL. 733 104 MCC-'2 EMXA (821) 104 I

MCC-1EMXA (808) 104 l MCC-2EMXA 104 RESTRICTED INST. SHOP (807) 104 f

f INSTRUMENT STORAGE 104 CABLE RM. EL. 750 104 MECH. EQ. RM. EL. 767 104 1EMXB 104 2EMXB 104 Control Room 90 NOTE: The maximum allowable temperature indicates the temperature for continuous duty rating for equipment and instrumentation found in these zones. These temperatures are provided to assure that the equipment will have an acceptable service life.

i, ) 16-15.40

%J i

I

l l 16.15. - CTS RELOCATED ITEMS (O)

U 16.15-3.7.8 SNUBBERS COMMITMENTS:

1 All snubbers shall be OPERABLE. The only snubbers excluded from the l requirements are those installed on non-safety-related systems and then only if tic failure or the failure of the system on which they are installed would not have an adverse effect on any safety-related system.

l APPLICABILITY: MODES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

REMEDIAL ACTION: l l

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the !

inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per SLC 16.15-4.7.8.g. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

TESTING REQUIREMENTS:

16.15-4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

a. Inspection Types

[

\~-l As used in this specification, type of snubber shall mean snubbers of l

I the same design and manufacturer, irrespective of capacity.

b. Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation and may be treated independently. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2. The visual inspection' interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect bef o re Amendment No. 126.

/~N 1

< 16-15.41

\ i

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

, TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL i NUMBER OF ,

UNACCEPTABLE SNUBBERS ;

Population or Column A Column B Column C Category Extended Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes 5 and 6) 1 0 0 1 80 0 0 2 100 0 1 4 l

150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorizad, based upon their accessibility during power operation, as accessible or inaccessible. The categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2: Interpolation between population or category size and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as described by interpolation.

Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.

O 16-15.42 l

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p -Note 4: If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection shall be the same as the previous interval.

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i Note 5: If the number of unacceptable snubbers is equal to or greater than

the number in Column C, the next inspection interval shall ' e two-I thirds of the previous interval. However, if the numser of unacceptable snubbers is less than the number in Column C but i greater than the number in Column 3, the next interval shall be !

reduced proportionally by interpolation, that is, the previous I

' interval shall be reduced by a factor that is one third of the ,

ratio of the difference between the number of unacceptable snubbers i found during the previous interval and the number in Column B to l the difference in the numbers in Columns B and C. i Note 6: The provisions of SLC 16.2.7 are applicable for all inspection intervals up to and including 48 months.

c. Refueling Outage Inspections At . each refueling, the systems which have the potential for a severe dynamic event, specifically, the main steam system (upstream of the main steam isolation valves) the main steam safety and power-operated relief valves and piping, auxiliary feedwater system, main steam supply to the auxiliary feedwater pump turbine,

( and the letdown and charging portion of the CVCS system shall be inspected to determine if there has been a severe dynamic event.

In case of a severe dynamic event, mechanical snubbers in that system which experienced the event shall be inspected during the l refueling outage to assure that the mechanical snubbers have freedom of movement and are not frozen up. The inspection shall consist of verifying freedom of motion using one of the following:

(1) manually induced snubber movement; (2) evaluation of in-place

! snubber piston setting; (3) stroking the mechanical snubber through its full range of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced or repaired before returning to power. The l requirements of SLC 16-15-4.7.8b are independent of the requirements of this SLC.

I d. Visual Inspection Acceptance Criteria t

t Visual inspections shall verity: (1) that there are no visible indications of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure. Snubbers which appear inoperable as a result of visual inspections "shall be classified as unacceptable and may be reclassified acceptable" for the purpose of establishing the next visual inspecticn interval, provided that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible;

[

and (2) the affected snubber is functionally tested in the as found l condition and determined OPERABLE per SLC 16.15-4.7.Bf. A hy-

[

draulic snubber found with the fluid port uncovered and all hydraulic snubbers found connected to an inoperable common reservoir shall be classified as unacceptable and may be r

N 16-15.43 l

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reclassified acceptable by functionally testing each snubber i

starting with the piston in the as-found setting, extending the piston rod in the tension direction.

1

e. Functional Tests During the first refueling shutdown and at least once per refueling thereafter, a representative sample of snubbers shall be tested using one of the following sample plans. The large bore steam ,

generator hydraulic snubbers shall be treated as a separate !

population for functional test purposes. A 10% random sample from I previously - untested snubbers shall be tested at least once per l

, refueling outage until the entire population has been tested. This I l' testing cycle shall then begin anew. For each large bore steam generator hydraulic snubber that does not meet the functional test acceptance criteria, at least 10% of the remaining population of untested snubbers for that testing cycle shall be tested. The ,

sample plan shall be selected prior to the test period and cannot I be changed during the test period. The NRC shall be notified of l the sample plan selected prior to the test period. I

1) At least 10% of the snubbers required by SLC 16-15-3.7.8 shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of SLC 16.15-4.7.8f., an additional 10% of the snubbers shall be functionally tested until no more failures are found or until all snubbers have been functionally tested; l or l

{ 2) A representative sample of the snubbers required by SLC 16.15-3.7.8 shall be functionally tested in accordance with I

Figure 4.7-1. "C" is the total number of snubbers found not meeting the acceptance requirements of SLC 16.15-4.7.8f (fail-ures). The cumulative number of snubbers tested is denoted by "N." Test results shall be plotted sequentially in the order of sample assignment (i.e., each snubber shall be plotted by its order in'the random sample assignments, not by the order of testing). If at any time the point plotted falls in the

" Accept" region, testing of snubbers may be termincted. When the point plotted lies in the " Continue Testing" region, addi-tional snubbers shall be tested until the point falls in the

" Accept" region, or all the snubbers required by SLC 16.15-3.7.8 have been tested. Testing equipment failure during functional testing may invalidate that day's testin- and allow that day's testing to resume anew at a later tiri providing all snubbers tested with the failed equipment durang the day of equipment failure are retested; or

3) An initial representative sample of fifty-five (55) snubbers shall be functionally tested. For each snubber which does not meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the factor, 1 + C/2, where "C" is l the number of snubbers found which do not meet the functional

! test acceptance criteria. This can be plotted using an

( " Accept" line which follows the equation N = 55(1 + C/2).

lrO i i V 16-15.44

l i

Each snubber should be plotted as soon as it is tested. If '

p the point plotted falls on or below the

Accept" line, testing i nay be discontinued. If the point plotted falls above the J

l D " Accept" line, testing must continue unless all snubbers have l been tested.

l 10

9 8-l l

7-6' C Si

,r~g 4

(,/ CONTINUE TESTING

/

c/ ACCEPT 0 '

/

10 20 30 40 50 60 70 80 90 100 N

FIGURE 4.7-1 l SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST

{

16-15.45

1 l

1 The representative samples for the functional test sample plans shall

,q be randomly selected from the snubbers required by SLC 16.15-3.7.8 and I

) reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of sizes, and capacities. Snubbers placed in the same locations as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan.

If during the functional testing, additional sampling is required due ,

to failure of only one type of snubber, the functional testing results '

shall be reviewed at that time to determine if additional samples shorld be limited to the type of snubber which has failed the functional testing. I

, 1

f. Functional Test Acceptance Criteria l The snubber functional test shall verify that: )

1) Activation (restraining action) is achieved within the specified l range in both tension and compression, except that inertia depen- !

' dent, acceleration limiting mechanical snubbers may be tested to i verify only that activation takes place in both directions of travel; {

i

2) Snubber bleed, or release rate where required, is present in both !

tension and compression, within the specified range;

3) Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions p

of travel; and I D 4) For snubbers specifically required not. te d2 5, c ' der con-tinuous load, the ability of the snubber m witb v. wad with-out displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods,

g. Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.

For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evaluation shall be to determine if the componenta to which the inoperable snubbers are l attached were adversely affected by the inoperability of the snubbers l in order to ensure that the component remains capable of meeting the i designed service.

\s/- 16-15.46 11/98 i

I-t

1 If any snubber selected for functional testing either fails to l

! activate or fails to move, i.e., frozen-in-place, the cause will be '

evaluated and, if caused' by manufacturer or design deficiency, all

! snubbers of the same type subject to the same defect shall be j evaluated in a manner to ensure their OPERABILITY. This testing '

requirement shall be independent of the requirements stated in SLC 16.15-4.7.8e. for snubbers not meeting the functional test acceptance criteria. ,

l 1

h. Functional Testing of Repaired and Replaced Snubbers l

Snubbers which fail the visual inspection or the functional

it acceptance criteria shall be repaired or replaced. Replac aent snubbers and saubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent l

! service, and freedom-of-motion test must have been performed within 12 months before being installed in the unit.

i. Snubber Seal Replacement Program The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The expected service life for the various seals, seal l materials, and applications shall be determined and established based on engineering information and the seals shall be replaced so that the i expected service life will not be exceeded during a period when the l snubber is required to be OPERABLE. The seal replacements shall be i documented and the documentation shall be retained in accordance with {

l QA Topical Report All snubbers are required OPERABLE to ensure that the structural integrity of I l the Reactor Coolant System and all other safety-related systems is maintained l l during and following a seismic or other event initiating dynamic loads. Snubbers ;

l excluded from this inspection program are those installed on nonsafety-related I l systems and then only if their failure or failure of the system on which they I j are installed, would have no adverse effect on any safety-related system. l l Snubbers are classified and grouped by design and manufacturer but not by size. !

l For example, mechanical snubbers utilizing the same design features of the 2 kip, l'O kip, at.d 100 kip capacity manufactured by Company "A" are of the same I type. The same design mechanical snubbers manufactured Company *B* for the pur-

! poses of this sperification would be of a different type, as would hydraulic j snubbers from either manufacturer. i The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval l l

l varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to deter-mine the next inspection. However, the results of such early inspections per-formed before the original required time interval has elapsed (nominal time less l

250 may not be used to lengthen the required inspection interval. Any inspec-tion whose results require a shorter inspection interval will override the

~

previous schedule 4

q (0' ;6-15.47 11/98 3 1

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To provide assurance of snubber functional reliability one of the three sampling A and acceptance criteria methods are used:

1. Functionally test 10% of a type of snubber with an additional 10%

tested for each functional testing failure, or

2. Functionally test a sample size and determine sample acceptance or continue testing

using Figure 4.7-1, or

3. Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.

Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as l described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc. . .). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review not intended to l .QfN) affect plant operation.

1 l *1f testing continues to between 100-200 snubbers (or 1-2 weeks) and still the l accept region has not been reached, then the actual % of population quality (C/N) should be used to prepare for extended or 100% testing.

16-15.48

, v iI/98 i

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..m . --.m .. _ _ _ _.-,2 . - _ - ~ _ _ . - _ ___..._ _ . - -

P r

16.15 - CTS RELOCATED ITEMS.

16.15'-3.7.9 SEALED SOURCE CONTAMINATION' !

COMMITMENT:

f Each sealed source containing radioactive material either in excess of 100 '

microcuries of beta.and/or gamma' emitting material or 5 microcuries of alpha {

emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination. l APPLICABILITY: At all times.

J

' REMEDIAL ACTION:

1 l a.'With a sealed' source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:

1 1

1. Decontaminate and repair the sealed source, or l

2. Dispose of the sealed source in accordance with Commission Regulations.

b. .The provisions of SLC 16.2.3 are not applicable.

TESTING REQUIREMENTS:

-l 1

16.15-4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage !

,, and/or contamination by:

\,, a.'The. licensee, or l

1 b.-Oth- persons specifically authorized by the Commission or an Agreement j State. ,

The testimethod shall have a detection sensitivity of at least 0.005 microcurie per test sample.

16.15-4.7,9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described bclow,

a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogen 3), and,

2) In any form other than gas, i

-b.' .

Stored sources not in use - Each sealed source and fission detector shall be tested prior'to use or transfer to another. licensee unless. tested within the previous 6 months. Sealed sources and fission detectors

. transferred without a certificate indicating the last test date shall be

' tested prior ,to being placed into use; and,

's i 16-15.49 11/98 l

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c. Startup sources and fission detectors - Each sealed startup source and i

["'N fission detector shall be tested within 31 days prior to being subjected

( ,) to core flux or installed in the core and following repair or maintenance to the source.

16.15-4.7.9.3 Reports - A report shall be prepared and submitted to the l Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removal contamination.

BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.390 limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

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l- 16.15 - CTS RELOCATED ITEMS 16.15-3.7.12 AREA TEMPERATURE MONITORING i

l-COMMITMENT r

I The temperature of each area shown in Table 3.7-6 shall be maintained within the' limits indicated in Table 3.7-6.

APPLICABILITY: Whenever the equipment in an affected area is required to be l_ OPERABLE.

REMEDIAL ACTION:

l-L With one or more areas exceeding the temperature limit (s) shown in Table 3.7-6:

i

) a. For:more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , prepare and submit a Special Report to the Commission within the next.30 day providing a record of the amount by I

which and the cumulative time the temperature in the affected area exceeded its limit and an analysis to demonstrate the continued l OPERABILITY of the affected equipment. o

b. By more than 30'F, in addition to the Special Report required above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature limit or t

declare the' equipment in the affected area inoperable. !

l-TESTING REQUIREMENTS l

L 16.15-4.7.12 The temperature in'each of the areas shown in Table 3.7-6 shall

( be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , l'

j, TABLE 3.7-6

' AREA TEMPERATURE MONITORING

, AREA' TEMPERATURE LIMIT (*F) le5- -

1. Containment Spray Pump Rooms' 145

2. Miscellaneous Terminal Cabinets E a. TB208-209 (Turbine Bldg.) 150

(; b. TB496 (Fuel Bldg.) 150

3. Residual Heat Removal Pump Rooms 145

4. Diesel Generator Rooms 125 l'

5. Spent Fuel Pool Cooling Pump Room 145

~ BASES ~

The area temperature limitations ensure that safety related equipment will not j be subjected to temperatures in excess of their environmental qualification r! 16-15.51 i 11/98 i.

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temperatures.

Exposure to excessive temperatures may degrade equipment and can l-cause a loss of its OPERABILITY. The temperature limits include an allowance for instrument error of 3.9*F.

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16.15 - CTS RELOCATED ITEMS i

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If.15-3.7.13 GROUNDWATER LEVEL COMMITMENT:

The groundwater level shall be maintained at elevations less than the values in Table 3.7-7 for the five (5) Auxiliary Building monitors listed in Table 3.7-7.

APPLICABILITY: At all times.

REMEDIAL ACTION: For Units 1 and 2.

If groundwater level for any three (3) of the five (5) monitors is above the values shown in Table 3.7-7, take the following actions:

1. Within one hour, reduce the groundwater level to below the values shown in Table 3.7-7; or,

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

TESTING REQUIREMENTS:

16.15-4.7.13.1 During each shift, the groundwater level shall be demonstrated to be within the values of Table 3.7-7 by the absence of alarms or by visual observation of the monitor level gauge.

[

![\ 16.15-4.7.13.2 Each groundwater level monitor instrument / loop for locations

! \s,jl I

listed in Table 3,7-7 shall be demonstrated OPERABLE at least once per year by the performance of a loop calibration and operational test.

TABLE 3.7-7 l AUXILIARY BUILDING GROUNDWATER LEVEL MONITORS i

l l

l LOCATION l INTERIOR / EXTERIOR ELEVATION l UNIT (Feet - Mean Sea Level)

PP-51 Interior 731' ~ 0" 1 l l 00-56 Interior 731' - 0" 1&2 l

PP-61 Interior 731' - 0" 2 West Wall Exterior 731- - 0" 1 '

East Wall Exterior 731' - 0" 2 1

[- BASES This SLC is provided to ensure that. groundwater levels will be monitored and I prevented from rising to the potential failure limit for the McGuire Units 1 and

, 2 Auxiliary Buildings. This potential failure limit is based on engineering l l

calculations that have determined that the Auxiliary Buildings are susceptible !

to overturning due to buoyance at elevation 737 feet Mean Sea Level (MSL).

Under the requirements of this SLC, if groundwater level exceeds elevation 731 feet MSL, (3 out of 5 SLC groundwater monitor alarms), and cannot be reduced in

. j% l 5

16-1533 '

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11/98 l4 L

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_ - . _ _ _ _ _ . . = . . _ _ . . _ .-- _- _ _ , . _ _ ..

one (1) hour, McGuire must begin reducing Units 1 and 2 to Mode 5, Cold Q Shutdown.

Analysis performed by Design Engineering determined that the Reactor and Diesel Generator Buildings are designed to withstand hydrostatic loadings due to groundwater levels up to elevation 760 feet MSL; therefore, no SLC requirements are specified for these structures.

Elevation 731 feet MSL is the action level of the five groundwater monitors listed in table 3.7-7. The East Wall exterior monitor alarm at elevation 731 feet MSL is the Alert alarm. The other four (4) monitors are Hi-Hi alarms at elevation 731 feet (MSL).

The East Wall exterior monitor was originally on the exterior of the Unit 2 Auxiliary Building and subsequently was enclosed by the construction of the Equipment Staging Building.

As required by Operations procedures, any alarms on nwn-SLC groundwater monitors will also be investigated. Additionally, if three (3) out of the five (5) groundwater monitors alarm at levels below the action levels, operations will contact Duke Engineering (Civil) for investigation and resolution of the increased groundwater level.

If one or more of the 5 SLC groundwater monitors is determined to be Inoperable, the monitor (s) will be considered to be indicating above the 731'-0" level until repaired and returned to an operable status.

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5 16 15.54 11/98 i

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16.15 - CTS RELOCATED ITEMS '

) 16.15-3.8.1.1 - A.C. SOURCES - OPERATING COMMITMENTS: See ITS 3.8.1 i

APPLICABILITY: Modes 1-4 l

TESTING REQUIREMENTS: ;

16.15-4.8.1.1:.2 Each diesel generator shall be demonstrated OPERABLE:

f. .

j' b. By removing accumulated water: !

l

1) From the day tank after each occasion when the diesel is operated for greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months !

I

e. At least once per le months, by: ;

, 1) Subjecting the diesel to an inspection, during shutdown, in accordance with procedures prepared in conjunction with its !

manufacturer's recommendations for this class of standby l service.

12) Verifying that the fuel transfer pump transfers fuel from each I

fuel storage tank to the day tank of each diesel via the ;

installed cross-connection lines i

' [ 14) Verifying, during shutdown (#), that the following diesel

. generator lockout features prevent diesel generator starting only when required:

l j

a) Turning gear engaged, or b) Emergency stop.

-#This Surveillance Requirement'may be performed in conjunction with periodic preplanned preventative maintenance activity that causes the diesel generator to be inoperable provided' that l .

performance of the surveillance requirement does not increase the time the diesel generator would be inoperable for the FM activity alone,

g. At least once per 10 years by:

l 2) performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME I code at a ' test pressure equal to 110% of the system design I pressure.

16.15-4.8.1.1.4 Each diesel generator 125-volt battery bank and charger shall be demonstrated OPERABLE: 1

a. At least once per 7 days by verifying that:

l 1) The electrolyte level of each battery is above the plates, and I 1

i i 16-15.55

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l 2).The overall battery voltage is greater than or equal to 125 volts Under a float change

b. At least once per 18 months by verifying that:

l: 1) The batteries, cell plates, and battery racks show no visual Indication of physical damage or abnormal deterioration;

2) The battery-to-battery and terminal connections are clear, tight, free of corrosion and coated with anti-corrosion material; and'

! 3) The battery capacity is adequate to supply and maintain in i

OPERABLE status its emergency loads when subjected to a Battery service test.

l BASES:

The Surveillance Requirements for demonstrating the OPERABILITY of the i diesel generators are.in accordance with the recommendations of i Regulatory Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Supplies, " March 10, 1971, 1.108, " Periodic Testing of Diesel Generator Units Used as.Onsite Electric Power Systems at Nuclear Power Plants, " Revision 1, August 1977, and 1.137, " Fuel-Oil Systems j for Standby Diesel Generators," Revision 1, October 1979; Generic-j Letter 84-15, which modified the testing frequencies specified in j Regulatory Guide 1.108; Generic Letter 93-05, which reduced the l

surveillance requirements for testing of Diesel Generators during power '

' operation; also, Generic Letter 94-01, which removed the accelerated testing and special reporting requirements for Emergency Diesel Generators.

1 l

.Some of the Surveillance Requirements for demonstrating the operability of the diesel generators are modified by a footnote. The Specifications state the Surveillance Requirements are to be performed

[

during shutdown, with the unit in mode 3 or higher. The footnote {

allows the particular surveillance to be performed during preplanned l Preventative Maintenance (PM) activities that would result in the d diesel generator being inoperable. The surveillance can'be performed l at that. time as long as it does not increase the time the diesel'

)

generator is inoperable for the PM activity that is being performed.

The footnote is only applicable at that time. The provision of the 1

I footnota shall not be utilized for operational convenience. '

Since the McGuire emergency diesel generator manufacturer (Nordberg) is no longer in business, McGuire engineering is the designer of record. I Therefore, in the absence of manufacturer recommendations, McGuire engineering will determine the appropriate actions required for nuclear class' diesel service taking into account McGuire diesel generator !

maintenance and operating history and industry experience where i

applicable. i i

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161536 i \ .) ll 98 s

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16.15 - CTS RELOCATED ITEMS

! ) 16.15 -3.8.1.2 A.C. SOURCES-SHUTDOWN

%J COMMITMENT: See ITS LCO 3.8.2 APPLICABILITY: Modes 5 and 6, During movement of irradiated fuel assemblies.

REMEDIAL ACTION:

With less than the above minimum required AC electrical sources {

OPERABLE, immediately suspend all operations involving crane opration l with loads over the fuel storage pool. {

I TESTING REQUIREMENTS: l 1

BASES:

None !

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16.15 - CTS RELOCATED ITEMS P

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( 16.15-3.8.4~.1 - CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE

[1 \- DEVICES l f

COMMITMENT:

'All containment penetration conductor overcurrent protective devices !

shown in SLC 16.8.1 shall be OPERABLE. '

9 APPLICABILITY: MODES 1, 2, 3, and'4.

I REMEDIAL ACTION:

With one or more of the containment penetration conductor overcurrent 1 protective device (s) shown in SLC 16.8.1 inoperable:

a. Restore the protective device (s) to OPERABLE status or de-energize the circuit (s) by tripping.the associated backup circuit breaker

' or racking out or removing the inoperable circuit breaker within

~72 hours, declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out or removed at least once per 7 days r

' thereafter the provisions of SLC 16.2.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or removed, or

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

TESTING REOUIREMENTS:

16.15-4.8.4.1 All SLC 16.8-1 containment penetration conductor ,

-overcurrent protective devices be demonstrated OPERABLE: I

a. At least once per 18 months

1) By verifying that the medium voltage (4-15 kV) circuit breakers i are OPERABLE by selecting, on a rotating basis, at least 10% of I L the circuit breakers of each voltage level, and performing the .

following: '

a.CHANNELCALIBRATIONoftheassociatedprotectiverelayh',

l b. An integrated system functional test which includes simulated A automatic actuation of the system and verifying ;

that each relay and associated circuit breakers and control '

circuits function as designed and as specified in SLC 16.8.1, and'

c. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

2) By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for functional testing shall be-selected on a rotating basis. For the lower voltage circuit breakers the nominal Trip Setpoint and overcurrent response 1

i j 16-15.58 lI/98 i

l times are listed in SLC 16.8-1. Circuit breakers found '

inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each circuit !

breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the i

circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all i circuit breakers of that type have been functionally tested; j and t

3) A fuse inspection and maintenance program will be maintained to ensure that: q

1) The proper size and type of fuse is installed,.

2) The fuse shows no sign of deterioration, and

3) The fuse connections are tight and clean,

b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

l BASES-Containment electrical penetrations and penetration conductors are j_ protected by either deenergizing circuits not required during reactor f

operation or by demonstrating the OPERABILIT of primary and backup !

overcurrent protection circuit breakers during period surveillance, j The Surveillance Requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker. Testing of these circuit breakers consists of injecting a ,

current in excess of the breaker's nominal setpoint and measuring the a response time. The measured response time is compared to the manufacturer's data to ensure that it is less than equal to a value i l specified by the manufacturer. Each manufacturer's molded case and i metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers .

1 are tested. If a wide variety exists within any manufacture's brand of !

circuit breakers, it is necessary to divide that manufacture's breakers into groups and treat each group as a separate type of breaker for i

surveillance purposes.

Fuse testing is in accordance with IEEE Standard 242-1975. This program j will detect any significant degradation of the fuses or improperly sized fuses. Safety is further assured by the afail safe" nature of fuses, that is,-if the fuse fails, the circuit will deenergize.

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3 16-15.59 l

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'16.15.- CTS RELOCATED ITEMS l -SLC 16.15-3.9.3 DECAY TIME COMMITMENT:

The reactor shall be'suberitical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

APPLICABILITY: During movement of irradiated fuel in the reactor vessel.

REMEDIAL ACTION:

With the reactor suberitical for less than 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , suspead all operations:

involving movement of irradiated fuel in the reactor vessel.

TESTING REQUIREMENTS:

16.15-4.9.3 The reactor shall be determined to have been suberitical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months by verification of the date and time of suberiticality prior to movement of irradiated fuel'in the reactor vessel.

BASES The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has ele.psed to allow the radioactive decay of the short-lived fission products.

This decay time is consistent with the assumptions used in the accident

. . analyses.

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1615.60

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11/98 j l

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1 16.15 - CTS RELOCATED ITEMS

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J 16.15-3.9.5 COMMUNICATIONS -

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COMMITMENTS:

' Direct communications shall be maintained between the control room and personnel at the refueling station.

l APPLICABILITY: During CORE ALTERATIONS. ;

l REMEDIAL ACTION:

When direct communications between the control room and personnel at the refueling station cannot be naintained, suspend all CORE ALTERATIONS.

TESTING REQUIREMENTS:

I 16.15-4.9 5 Direct communications between the control room and personnel at the 1 I

refueling station shall be demonstrated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to the start of and l at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS.

l I

BASES:

The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status l or core reactivity conditions during CORE ALTERATIONS.

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l- l 16.15 - CTS RELOCATED ITEMS 16.15-3.9.6 MANIPULATOR CRANE

!- COMMITMENTS:

The reactor building manipulator crane and an auxiliary hoist shall.be used for i

i movement of' fuel assemblies or-control rods and shall be OPERABLE with: )

j- a. The manipulator crane used for movement of fuel assemblies having: I 1

E 1. A minimum capacity of 3250 pounds, and 1

l. 2. An overload cutoff limit less than or equal to 2900 pounds.

b. Auxiliary hoists used for latching, unlatching and drag load testing of control rods having: I 1.'A minimum capacity of 1000 pounds, and

2. A load indicator which shall be used to prevent applying a lifting force in excess of 600 pounds on.the core internals, j . APPLICABILITY: During movement of fuel assemblies and control rods within the

' reactor vessel.

I REMEDIAL ACTION: l i I. O r

[) With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend j

( ,/ use of any inoperable manipulator crane and/or auxiliary hoist from operations l

,. involving the movement of fuel assemblies and control rods within the reactor l

vessel. l l TESTING REQUIREMENTS

I 16.15-4.9.6.1 Each manipulator crane used for movement of fuel assemblies l within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior i to the start of such operations by performing a-load test of at'least 3250 ,

pounds and demonstrating an automatic load cutoff when the crane load exceeds l 2900 pounds.

l 16.15-4.9.6.2 Each auxiliary hoist and associated load indicator used for

< movement of control rods or control rod drag load testing within the reactor ,

l vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of I such operations by~ performing a load test of at least 1000 pounds.

L l

BASES:

The OPERABILITY requirements-for the manipulator cranes ensure that: (1)

L' manipulator cranes will be used for :novement of drive rods and fuel assemblies,

j. (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

'O 16-15.62

. Q' ' 11/98 l

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16.15 - CTS RELOCATED ITEMS .

j'~\- . . !

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) 16.15-3.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL ~ BUILDING-l l

COMMITMENTS:

\

. Loads in. excess of 3000 pounds

shall be prohibited from travel over i fuel assemblies in the storage pool. Truck casks'shall be carried L. along the path outlined in Figure 3.9-1 in the fuel pit and fuel pool l

area. I APPLICABILITY: With fuel assemblies in the storage pool. ;

i REMEDIAL ACTION l

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a. With the requirements of the above specification not satisfied, j L place the crane load in a safe condition '

b. The provisions of SLC.16 2.3 are not applicable.

TESTING REQUIREMENTS:

16'15-4.9.7 The weight of each load, other than a fuel assembly and control rod, shall .be verified to be less than 3000 pounds prior to moving it over fuel assemblies *. l l

I BASES:

i

("

The restriction on movement of loads in excess of the nominal weight of

'1 .a fuel _and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures-that in the event this load i is dropped: (1) .the activity release will be limited to that: contained I fin a singlelftti assembly, zand (2) any possible distortion of fuel in 1the storage tecks will not result in" a critical array. This assumption

'is consistent with-the activity release assumed in the accident i -- analyses.

L l

(See Figure 3.9-1 on next page) 1'

Weir gates of the spent fuel pool may be moved by crane over the stored fuel'provided the spent fuel has decayed for at least 17.5 days

, , since last being part of a core at power.

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( 16.15-3.9.10 WATER LEVEL - STORAGE POOL COMMITMENT: 1 i

r i At least 23. feet'of water shall be maintained over the top of irradiated fuel assemblies seated'in the storage racks. ]

1 APPLICABILITY: Whenever irradiated fuel assemblies are being stored in the !

storage pool.

l

, REMEDIAL ACTION:

l a. With the requirements of the above SLC-not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage E

areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. The provisions of SLC 16.2.3 are not' applicable.

TESTING REQUIREMENTS:

16.15-4.9.10'The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel are being stored in the fuel storage pool.

l t

BASES:

(

l. f The restrictions'on minimum water level ensure that sufficient water depth is )

available to remove 99% of the assumed 10% iodine gap activity released from'the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

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<2 16 15.65 11/98 i

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16.15 - CTS RELOCATED ITEMS ff 16.15-3.10.5 ROD POSITION' INDICATION SYSTEM - SHUTDOWN i

COMMITMENT:

)

The limitations of SLC 16.15-3.1.3.3 may be suspended during the I performance of individual full-length shutdown and control rod drop time measurements provided:

i

a. Only one shutdown or control bank is withdrawn from the fully l inserted position at a time, and

]

b. The rod position indicator is OPERABLE during the withdrawal of the rods.*

APPLICABILITY: HODES 3, 4, and 5 during performance of rod drop time. I measurements. I REMEDIAL ACTION:

With the Position Indication System inoperable or with more than one bank of rods withdrawn, immediately open the Reactor trip breakers.

TESTING REQUIREMENTS:

16.15-4.10.5 The above required Rod Position Indication Systems sha 2 "N

be determined to be OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during rod drop time measurements ff by verifying the Demand Position Indication System and the Rod Position Indication Systems agree:

a. Within 12 steps when the rods are stationary, and

b. Within 24 steps-during rod motion.

L BASES:

This special test exception permits the Position Indication Systems to be inoperable during rod drop time measurements. The exception is l- . required since the data necessary to determine the rod drop time are derived from the induced voltage in the position indicator coils as the rod is dropped. This' induced voltage is small compared to the normal voltage and, therefore, cannot be observed if the Position Indication

-Systems remain OPERABLE.

This requirement is not applicable during the initial. calibration of the Rod Position. Indication System provided: (1) Keff is maintained

, less than or equal to 0.95,.and (2) only one shutdown or control rod

l. bank is withdrawn from the fully inserted position at one time.

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16.15 - CTS RELOCATED ITEMS

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g,, 16.15-3.11,1.4 LIQUID HOLDUP TANKS i COMMITMENTS:

The quantity of radioactive material contained in each unprotected outdoor radwaste tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.

l APPLICABILITY: At all times.

I REMEDIAL ACTION:

a. With the quantity of radioactive material in any of the above tanks

. exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents j to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report.

l b. The provisions of SLC 16.2.3 are not applicable.

! TESTING REQUIREMENTS:

l 16.15-4.11.1.4 The quantity of radioactive material contained in each of the l

above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when i radioactive materials are being added to the tank.

BASES:

l L The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank l contents and that do not have tank overflows.and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the.specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water l supply and the nearest surface water supply in an UNRESTRICTED AREA. j i 1 i

i I

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!

Tanks included in this specification are those outdoor radwaste tanks that are ,

l not surrounded by liners, dikes, or walls capable of holding the tank contents !

and that do not have tank overflows and surrounding area drains connected to the !

f- Liquid Radwaste Treatment System, i

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16.15 - CTS RELOCATED ITEMS 16.15-3.11'2.5 - EXPLOSIVE GAS MIXTURE COMMITMENTS:

The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

REMEDIAL ACTION:

a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by. volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, and immediately take ACTION a. above,

c. The provisions of SLC 16.2.3 are not applicable.

TESTING REOUIREMENTS O 16.15-4.11.2.5 The concentrations of hydrogen and. oxygen in the WASTE GAS HOLDUP. SYSTEM shall be determined to be within the above limits by monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of SLC 16.15-3.3.3.9.

BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits. Maintnining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

16-15.68

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16.15 - CTS RELOCATED ITEMS

\

j 16.15-3.11.2.6 - GAS STORAGE TANKS COMMITMENTS:

The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 49,000 Curies noble gases (considered as Xe-133).

APPLICABILITY: . At all times, REMEDIAL ACTION:

a. With the quantity of radioactive material in any gas storage tank 1 exceeding the above limit, immediately suspend all additions of i radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank '

contents to within the limit,

b. The provisions of SLC 16.2.3_are not applicable.

TESTING REQUIREMENTS:

16.15-4.11.2.6 .The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per !

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank. I BASES:

The specification considers postulated radioactive releases due to a Waste Gas System leak or failure, and limits the quality of radioactivity contained in each pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that a release would be substantially below the dose guideline values of 10 CFR Part 100 for the postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank i provides assurance that in the event of an uncontrolled release of the tank's l contents, the resulting total body exposure to a MEMBER OF THE PUBLIC dt the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800.

July 1981.

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. [Aa T 16-15.69

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q 16.15 - CTS RELOCATED ITEMS 16.15-6.8.4.g RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COMMITMENT:

The following program shall be established, implemented, and maintained:

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sanple matrices are performed as

[~}

%J part of the quality assurance program for environmental monitoring.

APPLICABILITY: At all times l

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\ l 16-15.70 V

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16.15 CTS RELOCATED ITEMS 16.15-6.15.1 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID !

WASTE TREATMENT SYSTEMS

I B

COMMITMENT 1 Licensee initiated major changes to the Radioactive waste Systems ]

(liquid, gaseous and solid): I

a. Shall be reported to the' Commission in the Annual Radioactive l Effluent Release Report for the period in which the evaluation was reviewed by.the Station Manager. The discussion of each i

change shall contain: J

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and

processes involved and the. interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous

effluents and/or quantity of solid waste that differ

) from those previously predicted in the License application and amendments thereto;

5. An evaluation of the change, which shows expected maximum exposures to individual in the UNRESTRICTED AREA j and to the general populatio.n that differ from t hose l previously estimated in the License application and !

amendments thereto;

6. A comparison of the predicted releases of radioactive i materials,-in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made,

7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation ~of the fact that the change was reviewed and found acceptable by the station Manager or the .

Chemistry Manager. l

b. Shall become effective upon review and acceptance by a l qualified individual / organization.

Licensees may choose to submit the information called for in f l

' this SLC as pare nf the annual FSAR update.

! "q

. 16-15.71

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ML20196C921

Text

16.1 INTRODUCTION

REFERENCES:

REFERENCES:

REFERENCES:

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