ML17056B866

Amend 128 to License DPR-63,revising TS to Require Administrative Check of Plant Records to Verify Operability of Redundant Sys/Component & Make Changes to Delete Superseded Matl

ML17056B866
Person / Time
Site:	Nine Mile Point
Issue date:	05/18/1992
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML17056B867	List: ML17056B866 ML17056B868
References
NUDOCS 9205290175
Download: ML17056B866 (28)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENS Amendment No. 128 License No.

DPR-63 1.

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

A.

The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated March 10,

1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-63 is hereby amended to read as follows:

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(2) Technical S ecifications The Technical Specifications contained in Appendices A 'and B, as revised through Amendment No. 128, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:

May 18, 1992

ATTACHMENT TO LICENSE AMENDMENT AMENDM NT NO.

TO FACILITY OPERATING LICENSE NO.

DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:

Remove Pa es 2

42 47 48 52 61 72 159 175 177 Insert Pa es 2

2a (added page) 42 47 48 52 61 72 159 175 177

1-2 1.3

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~ab e A system, subsystem, train, component or device shall be operable when it is capable of performing its specified function(s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation,

controls, normal and emergency electrical power-

sources, except as noted in 3.0, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem,

train, component or device to perform its function(s) are also capable of performing their related support function(s).

A verification of operability is an administrative check, by examination of appropriate plant records (logs, surveillance test records) to determine that a system, subsystem,

train, component or device is not inoperable.

Such verification does not preclude the demonstration (testing) of a given system, subsystem, train, component or device to determine operability.

0 e atin Operating means that a system or component is performing its required functions in its required manner.

1.4 otective Instrumentation Lo ic e

t s

Instrument Channel An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel.

b.

Tri S stem A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function.

A.

trip system may require one or more instrument channel trip, signalS related to one or more plant parameters in order to initiate trip system acti'on.

Initiation of protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.

Amendment No.

gg, 128

1.5 s

C e 1.6 A sensor check is a qualitative determination of acceptable operability by observation of sensor behavior during operation.

This determination shall include,

@here possible, comparison of the sensor with other independent sensors measuring the same variable.

C an e

est Instrument channel test means injection of a simulated signal into the channel to verify its proper response including, where applicable, alarm'nd/or trip initiating action.

Amendment No.

128 2a

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NG CONDITION FOR OPERAT ON SURV I C

The solution temperature shall be checked.

(4) t eas c

Verify enrichment by analysis.

u ve ce w t o e ab e When a component becomes inoperable its redundant component shall be verified to be operable immediately and daily thereafter.

Amendment No. /Nf, 128, 42

r

LIMITING CONDITION FOR OPERA ON SURVE LLANCE RE UIREMENT 3.1.3 CY COOL NG SYST 4.1.3 G

C COO NG SYS Applies to the operating status of the emergency cooling system.

Applies to periodic testing require-ments for the emergency cooling system.

To assure the capability of the emergency cooling system to cool the reactor coolant in the event the normal reactor heat sink is not available.

0 e t e:

To assure the capability of the emergency cooling system for cooling of the reactor coolant.

S ec cat a ~

During power operating conditions and whenever the reactor coolant tempera-ture is greater than 212 F except for hydrostatic testing with the reactor not critical, both emergency cooling systems shall be operable except as specified in 3.1.3.b.

The emergency cooling system surveillance shall be performed as indicated below:

a ~

The system heat removal capa-bility shall be determined.

b.

If one emergency cooling system becomes inoperable, Specification 3.1.3.a shall be considered fulfilled, provided that the inoperable system is returned to an operable condition within 7 days and the additional surveillance required in 4.1.3.f is performed.

b.

co The shell side water level and makeup tank water level shall be checked.

e t

The makeup tank level control valve shall be manually opened and closed.

Amendment No. 18,19,72,75g81$

47

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MI NG CONDITION FOR OPERATION SURVE LLANCE E UIREMENT c.

I d.

I e.

Make up water shall be available from the two gravity feed makeup Water tanks.

During Power Operating Conditions, each emergency cooling system high point vent to torus shall be operable.

1.

With a vent path for one emergency cooling system inoperable, restore the vent path to an operable condition within 30 days.

2.

With vent paths for both emergency cooling systems inoperable, restore one vent path to an operable condition with 14 days and both vent paths within 30 days.

If Specification 3.1.3.a, b, c, or d are

'ot

met, a normal orderly shutdown shall be initiated with one hour, and the reactor shall be in the cold shutdown conditions within ten hours.

d.

e.

At least once each shift The area temperature shall be checked; Dur eac ma or refue

~outa e-Automatic actuation and func-tional system testing shall be performed during each major refueling outage and whenever major repairs are completed on the system.

Each emergency cooling vent path shall be demonstrated operable by cycling each power-operated valve (05-01R, 05-11, 05-12,05-04R, 05-05 and 05-07) in the vent path through one complete cycle of full travel and verifying that all manual valves are in the oper position.

u e'

ce w't an e

b e S ste When one of the emergency cqoling systems is inoperable, the level control

.valve and the motor-operated isolation valve in the operable system shall be verified to be operable immediately and daily thereafter.

Amendment No. 18,72,N, 128 48

MIT NG CON I ON FOR OPERA ON SURVEI LANCE E UIREMEN d.

e.

If Specifications a,

b and c are not

met, a normal orderly shutdown shall be initiated within one hour and the reactor shall be in the cold shutdown condition within ten hours.

During reactor operation, except during core spray system surveillance testing, core spray isolation valves 40-02 and 40-12 shall be in the open position and the associated valve motor starter circuit breakers for these valves shall be locked in the off position.

In addition, redundant valve. position indication shall be available in the control room.

d.

e.

Core spray headers instru-mentation check calibrate test Once/day Once/3 months Once/3 months e

acew Co o e ts When a component becomes inoperable its redundant component or system shall be verified to be operable immediately and daily thereafter.

gi Whenever irradiated fuel is in the reactor vessel and the reactor coolant temperature is less than or equal to 212'F, two core spray subsystems shall be operable except as specified in g and h below.

If one of the above required subsystems becomes inoperable, restore at least two subsystems to an operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel.

gi With a core spray subsystem suction from the CST, CST level shall be checked once per day.

At least once per month when the reactor coolant temperature is greater than 212oF, verify that the piping system between valves 40-03, 13 and 40-01, 09, 10, 11 is filled with water.

Amendment, No. 1,14,45,64,165, 128 52

M TING CONDITION FOR OPERATION SURV UIREMEN b.

c If a redundant component becomes inoperable, the control rod drive pump coolant injection system shall be considered operable provided that the component is returned to an operable condition within 7 days and the additional, surveillance required's performed.

If Specifications "a" or "b" above are not met, the reactor coolant temperature shall be reduced to 2124F or less vithin ten hours.

b. t east o ce e

arter Pump floi rate shall be determined;'

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t o e When a component becomes inoperable its redundant component shall be verified to be operable immediately and daily thereafter.

Amendment No.

128 61

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ING CONDITION FO 0

E ION S

VE LANC E U REMEN

c. If Specification "a" and "b" are not

met, a normal orderly shutdown shall be initiated within one hour and reactor coolant pressure and tempera-ture shall be reduced to less than 110 psig and saturation temperature within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

Su ve' ce with Ino crab e When a component becomes inoperable its redundant component shall be verified to be operable immediately and daily thereafter.

Amendment No.

128 72

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G COND 0

OR OPE ON S

V VIRESCENT

c. If a redundant component in each of the containment spray systems or their associated raw water systems become inoperable, both systems shall be considered operable provided that the component is returned to an operable condition within 7 days and that the additional surveillance required is performed.

d. If a containment spray system or its associated raw water system becomes inoperable and all the components are operable in the other systems, the reactor may remain in operation for a period not to exceed 7 days.

e. If Specifications "a" or "b" are not

met, shutdown shall begin within one hour and the reactor coolant shall be below 215 F within ten hours.

c.

Raw Water Cooling Pumps At least.once per quarter manual startup and 'operability of the raw water cooling pumps shall be demonstrated.

d. Surveillance with Inoperable Components When a component or system becomes inoperable its redundant component or system shall be verified to be operable immediately and daily thereafter.

If both containment spray systems become inoperable the reactor shall be in the cold shutdown condition within ten hours and no work shall be

. performed on the reactor which could result in lowering the reactor water level to more than six feet, three inches

(-10 inches indicator scale) below minimum normal water level (Elevation 302'9").

Amendment No. 1,45,pe,

)p8 159

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LIMITING CONDITION FOR OPERATION SURVEILLANCE RE UIREMENT g.

At least once per operating cycle, not to exceed 24 months, automatic initiatioh of each branch of the emergency ventilation system shall be demonstrated.

h.

At least once per operating cycle, not to exceed 24 months, manual operability of the bypass valve for filter cooling shall be demonstrated.

When one circuit of the emergency ventilation system becomes inoperable all active components in the other emergency ventilation circuit shall be verified to be operable within two hours and daily thereafter.

Amendment No. 4,T3',

128 175

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BASES FOR 3. 4. 4 AND 4. 4. 4 EMERGENCY VENTILATION SYSTEM The replacement charcoal for the adsorber tray removed for the test should meet the same adsorbent quality.

Any HEPA filters found defective shall be replaced with filters qualified pursuant to ANSI 509-1980

'll elements of the heater should be demonstrated to be functional and operable during the test of heater capacity.

Operation of the inlet heater will prevent moisture buildup in the filters and adsorber system.

With doors closed and fan in operation, DOP aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal.

Any detection of DOP in the fan exhaust shall be considered an unacceptable test result and the gaskets repairs and test repeated.

If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use.

The determination of significant shall be made by the operator on duty at the time of the incident.

Knowledgeable staff members should be consulted prior to making this determination.

Demonstration of the automatic initiation capability and operability of filter cooling is necessary to assure system performance capability. If one emergency ventilation system is inoperable, the other system must be verified to be operable daily.

This substantiates the availability of the operable system and thus reactor operation or refueling operation may continue during this period.

Amendment No.4,7$,

128 177

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