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Amend 221 to License DPR-59,revising Primary Containment Atmosphere Monitoring & Drywell to Torus Differential Pressure Requirements
	ML20079B106
Person / Time
Site:	FitzPatrick
Issue date:	12/28/1994
From:	Michael Case; Office of Nuclear Reactor Regulation
To:	;
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ML20079B109	List: ML20079B106;
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	NUDOCS 9501050166
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UNITED STATES g-NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20066-0001

's,.....,o POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 License No. DPR-59 1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated August 4, 1994, as supplemented November 10, 1994, 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 Commiission'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-59 is hereby amended to read as follows:

i 9501050166 941228 PDR ADOCK 05000333 PDR

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. (2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 221, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

4J) Michael J. Case, Acting Director Project Directorate I-I Division of Reactor Projects - I/II' Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

^

Specifications-Date of Issuance:

December 28, 1994 t

I w

ATTACHMENT TO LICENSE AMENDMENT NO. 221 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

Remove Paaes Insert Paaes 54 54 77b 77b 77d 77d 86 86 180 180 180a 180a 181 181 e

4

JAFNPP 3.2 (cont'd) 4.2 (cont'd)

E.

Drywell Leak Detection E.

Drvwell Leak Detection The limiting condtions of operation for the instrumentation that Instrumentatim shall be calibrated and checked as indicated in monitors drywell leak detection are given in Table 3.2-5.

Table 4.2-f.

F.

(Deleted)

F.

(Deletee)

G.

Recirculation Pumo Trio G.

Recirculation Pumo Trio The limiting condtions for operation for the instrumentation that instrumentation shall be functionally tested and calibrated as trip (s) the recirculation pumps as a means of limiting the -

indicated in Table 4.2-7.

consequences of a faihre to scram during an anticipated transient are given in Table 3.2-7.

System logic shall be functionally tested aradicated in Table 4.2-7.

H.

Accident Monitorino Instrumentation H.

Accident Monitorino Instrumentation The limiting condtions for operation of the instrumentation that provides accident monitoring are given in Table 3.2-8.

Instrumentation shall be demonstrated operable by performance of a channel check, channel calibration and functional test as I

I.

4kw Emeraancy Bun Ur*zenitaga Trip indicated in Table 4.2-8, as applicable.

The limiting conditons for operation for the instrumentation that prevents dama0s to electrical equipment or circuits as a result of either a degraded or loss-of-voltage condition on the emergency electrical buses are given in Table 3.2-2.

'. Amendment No. S30;JlktJ8f. M 221 54

_ _ _ = _. _.

JAFNPP TABLE 3.2-8 ACCIDENT MONITORWG INSTRUMENTATION No. oft,hannels Minimum No. of Mode in Which Provided by Operable Channels Instrument Must Instrument Design Required be Operable Action 8.

Torus Water Level (wide r

)

2 1

Note J Note A 23LI-202A or 23LR-20 A

23Li-2028 or 23LR-202B/2038 9.

Torus Bulk Water Temperature 2

1 Note J Note A f16-1TI-131 A or 16-1TR-131 A)

(16-1TI-131B or 16-1TR-131B) 10.

Torus Pressure 2

1 Note J Note A (27PR-101A)

(27PR-101B1) j 11.

Primary Containment Hydrogen / Oxygen 2

1 Note J, K Note F Concentration (27PCR-101A (27PCR-1018 12.

Reactor Vessel Pressure 2

1 Note J Note A 06PI-61 A or 06PR-61 A 06PI-61B or 06PR-618 13.

Reactor Water Level (fuel zone) 2 1

Note J Note A f 02-3Lt-091)

(02-3LR-098) 14.

Reactor Water Level (wide range) 2 1

Note J Note A 85 )

Amendment No. 3,1&tyW; 221 77b

JAFNPP IABLE 3.2-8 (Cont'd)

ACCBENT RAONITORMG INSTRUARENTATION

~

NOTES FOR TABLE 3.2-8 A. With the number of operable channels less than the required minimum, either restore the inoperable channels to operable status vahin 30 days, or be in a cold condition within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate an alternate method of monitoring the appropnate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and: (1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 14 days following the event outlining the cause of the inoperability, the action taken, and the plans and schedule for restoring the system to OPERABLE status.

C. Each Safety / Relief Valve is equipped with two acoustical detectors, one of which is in service. Each SRV also has a backup thermocouple detector, in the event that a thermocouple is inoperable, SRV performance shall be monitored daily with the associated in service acoustical detector.

D. ~ From and after the date that both of the acoustical detectors are inoperable, continued operation is permissible until the next outage in which a primary containment entry is made provided that the thermocouple is operable. Both acoustical detectors shall be made operable prior to 4

restart.

E. In the event that both pnmary (acoushcal detectors) and secondary (thermocouple) indications of this parameter for any one valve are disabled and neither indicahon can be restored in forty-eight (48) hours, the reactor shall be in a Hot Shutdown condition within twelve (12) hours and in a Cold Shutdown within the next twenty-four (24) hours.

F. With the number of operable channels less than the required minimum, continued reactor operation is permissible for the following 30 days provided at least once each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , either the appropriate parameter (s) is monitored and logged using 27PCX.101 A, B. or an appropriate grab sample is obtamed and analyzed. If this condition can not be met, be in tie Hot Shutdown mode within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

G. This parameter and associated instrumentation are not part of post-accident monitoring H. This instrument shall be operable in the Run, Startsp/ Hot Stancby, and Hot Shutdown modes.

J. This instrument shall be operable in the Run and Startup/ Hot Stanchy modes.

K. Primary contamment (d.- asphere shall be continuously monitored for hydrogen and oxygen when in the Run and Startup/ Hot Standby modes, except when the Post-Accident Sampimg System (PASS) is to be operated. When the PASS is to be operated, the containment atmosphere monitoring systems may be isolated for a period not to exceed 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months in a 24-hour period.

Amendment No, jpf, jar, 221 77d w

y l

JAFNPP TABLE 4.2-8 MINIMUM TEST AND CAllBRATION FREQUENCY FOR ACCBENT MONITORMG INSTRUMENTATION Instrwnent Instrument Instrument Functional Test Calibration Frequency Cteck 1.

Stack High Range Effluent Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day -~

2.

Twbine Budding Vent High Range Effluent Monitor Once/ Operating Cycle '

Once/ Operating Cycle Once/ day 3.

Radwaste Buildng Vent High Range Effluent Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day 4.

Containment High Range Radiation Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day 5.

Drywell Pressure (narrow range)

N/A Once/ Operating Cycle Once/ day 6.

Drywell Pressure (wide range)

N/A Once/ Operating Cycle Once/ day 7

Drywell Temperature N/A Once/ Operating Cycle Once/ day 8.

Torus Water Level (wide range)

N/A Once/ Operating Cycle Once/ day 9.

Torus Bulk Water Temperature N/A Once/ Operating Cycle Once/ day 10.

Torus Pressure N/A Once/ Operating Cycle Once/ day l 11.

Primary Containment Hydrogen / Oxygen Concentration N/A Once/3 months Once/ day Analyzer 12.

Reactor Vessel Pressure N/A Once/ Operating Cycle Once/ day 13.

Reactor Water Level (fuel zone)

N/A Once/ Operating Cycle Once/ day 14.

Reactor Water Level (wide range)

N/A Once/ Operating Cycle Once/ day

~ Amendment No. ppf.jff, 221 as

JAFNPP 3.7 (cont'd) 4.7 (cont'd) 6.

Oxygen Concentration 6.

Oxygen Concentration The primary containment oxygen concentration shall be a.

The primary containment oxygen concentration shall l

maintained less than 4.0 volume percent while in the Run Qe verified to be within limits once each week.

l mode, except as specified in 3.7.A.6.a and 3.7.A.6.b Instrument surveillances shall be performed as below; specified in Table 4.2-8.

a.

Primary containment oxygen concentration shall be less than 4.0 volume percent within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of exceeding 15% of rated therrnal power during

startup, b.

De-inerting may commence up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing thermal power to less than 15% of rated before a plant shutdown.

c.

If oxygen concentration is greater than or equal to 4.0 volume percent at any time while in the Run mode, except as specified in 3.7.A.6.a or 3.7.A.6.b above, restore oxygen concentration to less than 4.0 volume percent within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise r@cn thermal power to less than or equal to 15% of rated within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

7.

Drywell-Torus Differential Pressure 7.

Drywell-Torus Differential Pressure a.

Differential pressure between the dryweil and torus a.

The pressure differential between the drywell and torus l shall be maintained at equal to or greater than 1.7 shall be verified to be within limits once each shift.

l psid except as specified in (1) and (2) below:

Instrument surveillances shall be performed as specified in Table 4.2-8.

" Amendment No. 36, )#T, 221 180

JAFNPP 3.7 - (Cont'd) 4.7 (Cont'd)

(1) The drywell to torus differential presswe shall be established within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of exceeding 15%

rated thermal power during startup. The differential presswa may be reduced to less than the limit up to 24 a;ours prior to reducing thermal power to less than 15% of rated before a plant shutdown.

(2) The differential presswe may be decreased to less than 1.7 psid for a maximum of four (4) hours dunng required operability testing of the HPCI, RCIC, and Suppression Chamber -

Drywell Vacuum Breaker System.

(3)

If 3.7.A.7.a above cannot be met, restore the differential presswa to within limits within eight hours or reduce thermal power to less than 15%

of rated within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 8.

If the specifications of 3.7.A.1 through 3.7.A.5 cannot be 8.

Not applicable.

met the reactor shall be in the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

't Amendment No. )frlp. 221 180a

JAFNPP 3.7 (cont'd) 4.7 (cont'd) i B. Stan4v Gas Treatment System B.

Stan&y Gm Traatment System 1.

Except as spncified in 3.7.B.2 below both circuits of the 1.

Standby Gas Treatment System surveillance shall be Stan@y Gas Treatment System shall be operable at all performed as indicated below:

times when secondary containment integrity is required.

a.

At least once per operating cycle, it shall be demonstrated that:

(1)

Pressure drop across the combined high-efficiency and charcoal filters is less than 5.7 in. of water at 6,000 scfm, and (2)

Each 39kW heater shall dissipate greater than 29kW of electric power as calculated by the following expression:

P = /TEI where:

P= Dissipated Electrical Power; E= Measured line-to-line voltage in volk (RI.1S);

l= Average measured phase current in amperes (RMS).

dmondment No.19ffer,)dr,Js'pe:Af')s', pf', 221 181

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ML20079B106

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