Text

Amend 113 to License NPF-30,revising AOT for Component Cooling Water Motor Operated Containment Isolation Valves & Removes List of Containment Isolation Valves from TS
	ML20113E655
Person / Time
Site:	Callaway
Issue date:	06/28/1996
From:	Thomas K; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20113E658	List: ML20113E655; ML20113E663;
References
	NUDOCS 9607080205
	Download: ML20113E655 (10)
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UNITED STATES

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j NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 2006H001 o%

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UNION ELECTRIC COMPANY i

CALLAWAY PLANT. UNIT 1

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DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE i

~ Amendment No. 113 License No. NPF-30 1.

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

1 2

A.

The application for amendment by Union Electric Company (UE, the licensee) dated June 26, 1995, as supplemented by letter dated i

February 2,1996, complies with the standards and requirements of 1

the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly,.the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license ametubent and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

l 9607080205 960628 PDR ADOCK 05000483 P

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i (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 113 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the i

Technical Specifications and the Environmental Protection Plan.

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This amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 4

QM Qernc^

Kristine M. Thomas, Project Manager 2

Project Directorate IV-2 Division of Reactor Projects III/IV j

Office of Nuclear Reactor Regulation 1

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 28, 1996 1

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 113 TO FACILITY 0?E8ATING LICENSE NO. NPF-30 DOCKET NO. f,0-483 l

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1 Replace the following pages of the Appenc'1x A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and i

contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT IX IX l-2 1-2 3/4 6-1 3/4 6-1 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 l

3/4 6-21.

3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 4

3/4 6-26 3/4 6-27 3/4 6-28 3/4 6-29 3/4 6-30 3/4 6-31 B 3/4 6-4 B 3/4 6-4

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAGE I

4 ENERGENCY CORE COOLING SYSTEMS (Continued) 3/4.5.5 REFUELING WATER STORAGE TANK...................... 3/4 5-10 I

3/4.6 CONTAIMMENT SYSTEMS i

3/4.6.1 PRIMARY CONTAINMENT 4

l Containment Integrity.............................

3/4 6-1 Containment Leakage................................ Deleted

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Containment Air Locks.............................

3/4 6-4 Inte rnal Pre s sure................................. 3/4 6-6 l

Air Temperature...................................

3/4 6-7 j

Containment Vessel Structural Integrity............ Deleted j

Containment Ventilation System.................... 3/4 6-11 l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS l

Containment Spray System..........................

3/4 6-13 i

l Spray Additive System............................. 3/4 6-14 Contai nment Cool ing System........................ 3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES...................... 3/4 6-16 i

j TABLE 3.6-1 DELETED l

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3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers................................. Del eted i

j Hydrogen Control Systems.......................... 3/4 6-32 m

l 3/4.7 PLANT SYSTEMS

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3/4.7.1 TURBINE CYCLE 4

i Safety Valves.....................................

3/4 7-1 1

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX i

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HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION............ 3/4 7-2 i

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CALLAWAY - UNIT I IX Amendment No. 103,113 1

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j DEFINITIONS j

j CONTAINMENT INTEGRITY l

1.7 CONTAINMENT INTEGRITY shall exist when:

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a.

All penetrations required to be closed during accident conditions j

are either:

1)

Capable of being closed by an OPERABLE containment automatic i

isolation valve system, or i

2)

Closed by manual valves, blind flanges, or deactivated i

automatic valves secured in their closed positions, except for j

valves that are open under administrative control as permitted j

by Specification 3.6.3.

b.

All equipment hatches are closed and sealed.

l c.

Each air lock is in compliance with the requirements of j

Specification 3.6.1.3.

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d.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.

e.

The containment leakage rates are determined per Specification 4.6.1.1.d and are within the limits listed in the Bases of l

Specification 3.6.1.1.

l f.

Structural integrity is assured via the program described in j

Specification 6.8.5.c.

CONTROLLED LEAKAGE 1

1.8 CONTROLLED LEAXAGE shall be that seal water flow from the reactor coolant j

pump seals.

i CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel.

i Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document that provides core operating limits for the current operating reload cycle.

The cycle specific core operating limits shall be determined for each reload i

cycle in accordance with Specification 6.9.1.9.

Plant operation within these operating limits is addressed in individual specifications.

i DOSE EQUIVALENT I-131 j

1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131

-(microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of 1

Distance Factors for Power and Test Reactor Sites."

CALLAWAY - UNIT 1 1-2 Amendment No. 15,35,50,103,113

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAlletENT 1

i CONTAINMENT INTEGRITY l

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LIMITING CONDITION FOR OPERATION l

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

i Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour 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 .

i SURVEILLANCE REQUIREMENTS i

j 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

i a.

At least once per 31 days by verifying that all penetrations

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capable of being closed by OPERABLE containment automatic isolation j

valves and required to be closed during accident conditions are closed by manual valves, blind flanges, or deactivated automatic 1

valves secured in their closed positions, except for valves that are i

open under administrative control as permitted by Specification j

3.6.3; b.

By verifying that each containment air lock is in compliance with j

the requirements of Specification 3.6.1.3; c.

Deleted.

i d.

By performing containment leakage rate testing in accordance with the Containment Leakage Rate Testing Program of Specification l

6.8.4.g; and i

e.

By verifying containment structural integrity in accordance with the Containment Tendon Surveillance Program of Specification 6.8.5.c.

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Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

CALLAWAY - UNIT 1 3/4 6-1 Amendment No. 13,52,103,114,113

CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING _ CONDITIONS FOR OPERATION 3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with two fan systems to each group.

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

ACTION:

With one group of the above required containment cooling fans a.

inoperable and both Containment Spray Systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or be in at least NOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With two groups of the above required containment cooling fans inoperable and both Containment Spray Systems OPERABLE, restore at least one group of cooling fans 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 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 .

Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss 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 COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With one group of the above required containment cooling fans c.

inoperable and one Containment Spray System inoperable, restore the inoperable Containment Spray System to OPERA 8LE 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 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 . Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss 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 .

SURVEILLANCE REQUIREMENTS 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1)

Starting each non-operating fan group from the control room, and verifying that each fan group operates for at least 15 minutes, and 2)

Veritying a cooling water flow rate of greater than or equal to 2200 gpa to each cooler group.

b.

At least once per 18 months by verifying that on a Safety Injection test signal, the fans start in slow speed or, if operating, 'shif t to slow speed and the cooling water flow rate increases to at least 4000 gpa to each cooler group.

CALLAWAY - UNIT 1 3/4 6-15

CONTAINMENT SYSTEMS 1

3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION l

3.6.3 Each containment isolation valve shall be OPERABLE.*

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

ACTION:

l With one or more of the containment isolation valve (s) inoperable, maintain at l

l 1 east one isolation valve OPERABLE in each affected penetration that is open and:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position,**

or i

c.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange or check valve with flow through the valve secured,** or d.

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 .

e.

The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE RE0VIREMENTS 4.6.3.1' Each containment isolation valve shall be demonstrated OPERABLE prior l

to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power l

circuit by performance of a cycling test, and verification of isolation time.

Locked or sealed closed containment isolation valves may be opened on an intermittent basis under administrative control.

- For penetrations with parallel containment isolation valves, the penetration is considered isolated if the flowpath with the inoperable valve has been isolated. The penetration may still have flow through it utilizing a parallel flowpath. For the motor operated valves associated with reactor coolant pump cooling, automatic isolation valves (EGHY58, 59, 60,61,62) and remote manual isolation bypass valves (EGHV127,130,131, l

132,133),12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are allowed to conduct actuator diagnostic evaluations j

which are required for post maintenance testing to restore a motor operated valve to an OPERABLE condition, during which time, the valve may be i

energized for short periods of time for the purpose of cycling.

l CALLAWAY - UNIT 1 3/4 6-16 Amendment No.113 l

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE l

during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.# Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position, b.# Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position, and c.

Verifying that on a Containment Purge Isolation test signal, each purge supply and exhaust isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

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The specified 18 month frequency may be waived for Cycle I provided the 2

surveillance is performed prior to restart following the first refueling outage or June 1, 1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of tMs sww111ance.

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CALLAWAY - UNIT 1 3/4 6-17 Amendment No. 8,113 (Next page is 3/4 6-32) l

CONTAINMENT SY3TEMS BASES 3/4.6.2.3 CONTAllMENT COOLING SYSTEM The OPERA 8ILITY of the Containment Cooling System ensures that: (1) the containment air temperature will be maintained within limits during normal operation, and (2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray Systems during post-LOCA conditions.

The Containment Cooling System and the Containment Spray System are redundant to each other in providing post-accident cooling of the Containment atmosphere. As a result of this redundancy in cooling capability, the allowable out-of-service time requirements for the Containment Cooling System have been appropriately adjusted. However, the allowable out-of-service time requirements for the Containment Spray System have been maintained consistent with that assigned other inoperable ESF equipment since the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere.

3/4.6.3 CONTAINMENT ISOLATION VALVES 1

The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 thru 57 of Appendix A to 10 CFR Part 50. Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

The opening of locked or sealed-closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit (or the Purge System) is capable of controlling the expected hydrogen generation associated with:

(1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. The Hydrogen Purge Subsystem discharges directly to the Emergency Exhaust System. Operation of the Emergency Exhaust System with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," Revision 2, November 1978.

CALLAWAY - UNIT 1 8 3/4 6-4 Amendment No. Mh113

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ML20113E655

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