ML20113E166

Amend 231 to License DPR-59,relocating Spec 3.11.B/4.11.B, Crescent Area Ventilation & Associated Bases from TS to Authority Controlled Procedure

ML20113E166
Person / Time
Site:	FitzPatrick
Issue date:	06/28/1996
From:	Jeffrey Mitchell NRC (Affiliation Not Assigned)
To:
Shared Package
ML20113E170	List: ML20113E166 ML20113E174
References
NUDOCS 9607050094
Download: ML20113E166 (7)

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UNITED STATES NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20066-0001 f

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. 231 License No. DPR-59

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1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated April 24, 1996, complies with the standards ano requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; i

B.

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

There is reasonable assurance (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 Comission's regulations; D.

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

E.

The issuance of this amendment is in accordance with 10 CFR Part l

51 of the Comission'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:

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6 9607050094 960628 PDR ADOCK 05000333 P

PDR

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(2) Technical Snecifications

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i The Technical Specifications contained in Appendices A and B, as revised through Amendment No.231, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.

1 3.

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

4 FOR THE NUCLEAR REGULATORY COMMISSION d,0 Oh Jocelyn A. Mitchell, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28, 1996 4

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ATTACHMENT TO LICENSE AMENDMENT NO.231 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

Remove Paaes Insert Paaes 11 11 237 237 239 239 243 243 f

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o JAFNPP TABLE OF CONTENTS (Cont'd)

Eage F.

ECCS-Cold Condition F.

122 G.

Maintenance of Filled Discharge Pipe G.

122a H.

Average Planar Linear Heat Generation Rate H.

123 (APLHGR) Generation Rate (LHGR) 1.

Unear Heat 1.

124 J.

Thermal Hydraulic Stability J.

124a SURVElLLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS 3.6 Reactor Coolant System 4.6 136 A.

Pressurization and Thermal Limits A.

136 B.

DELETED C.

Coolant Chemistry C.

139 D.

Coolant Leakage D.

141 E.

Safety and Safety / Relief Valves E.

142a F.

Structural integrity F.

144 G. Jet Pumps G.

144 H.

DELETED l.

Shock Suppressors (Snubbers) 1.

145b 3.7 Containment Systems 4.7 165 A.

Prima Containment A.

165 B.

Sta Gas Treatment System B.

181 C.

Se ry Containment C.

184 D.

Primary Containment isolation Valves D.

185 3.8 Miscellaneous Radioactive Material Sources 4.8 214 3.9 Auxiliary Electrical Systems 4.9 215 A.

Normal and Reserve AC Power Systems A.

215 B.

Emergency AC Power System B.

216 C.

Diesel Fuel C.

218 D.

Diesel-Generator Operability D.

220 E.

Station Batteries E.

221 F.

LPCI MOV Independent Power Supplies F.

222a G.

Reactor Protection System Electrical Protection G.

222c Assemblies 3.10 Core Alterations 4.10 227 A.

Refueling Interlocks A.

227 B.

Core Monitoring B.

230 C.

Spent Fuel Storage Pool Water Level C.

231 D. Control Rod and Control Rod Drive Maintenance D.

231 3.11 Additional Safety Related Plant Capabilities 4.11 237 A.

Main Control Room Ventilation A.

237 B.

DELETED I

C.

Battery Room Ventilation C.

239 i

l Amendment No. 20,43.08,113.1SS. 231 ii

JAFNPP 3.11 LIMITING CONDITIONS FOR OPERATIQN 4.11 SURVEILLANCE REQUIREMENTS 3.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES Anolicability:

Acolicability:

Applies to the operating status of the main control and l

relay rooms, and battery room ventilation and cooling.

Applies to the surveillance requirements for the main Applies to emergency service water system and intake control and relay room, battery room ventilation systems.

deicing heaters.

emergency service water and intake deicing heaters.

Obiective:

Obiective:

To assure the availability of the main control and relay To verify the operability or availability under conditions for which these capabilities are an essential response to l

room, and battery room ventilation systems, to assure plant abnormalities, the availability of the emergency service water system and intake deicing heaters, under the conditions for which the capabality is an essential response to plant abnormalities.

A.

Main Control Room Ventilation A.

Main Control Room Ventilation 1.

The reactor shall not have a coolant Each of the control room emergency ventilation 1.

air supply fans and dampers shall be tested for temperature greater than 212 *F and fuel may not be handled unless both of the control room operability every 3 months.

emergency ventilation air supply fans and fresh air filter trains are available for normal The fresh air filter trains shall be tested once operation except that one emergency every 6 months as follows:

a.

Pressure drop test across each filter and the filter system.

i Amendment No. 231 237

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JAFNPP 3.11 (cont'd) 4.11 (cont'd) l B.

DELETED B.

DELETED C.

Batterv Room Ventilation C. Batterv Room Ventilation Battery room ventilation shall be operable on a continuous Battery room ventilation equipment shall be demonstrated basis whenever specification 3.9.E is required to be satisfied.

operable once/ week.

1.

From and after the date that one of the battery room

1. When it is determined that one battery room ventilation ventilation systems is made or found to be inoperable. its system is inoperable, the remaining ventilation system shall associated battery shall be considered to be inoperable be verified operable and daily thereafter.

for purposes of specification 3.9.E.

2. Temperature transmitters and differential pressure switches shall be calibrated once/ operating cycle.

i Amendment No. 48d2r425.13-1.148-166. 231 239 N,

JAFNPP 3.11 & 4.11 BASES A.

Main Control Room Ventilation System B.

DELETED

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One main control room emergency ventilation air supply fan C. Batterv Room Ventilation provides adequate ventilation flow under accident conditions.

Should one emergency ventilation air supply fan and/or fresh Engineering analyses indicate that the temperature rise and air filter train be out of service during reactor operation, a hydrogen buildup in the battery, and battery charger repair time of 14 days is allowed because during that time, a compartments without adequate ventilation is such that redundant 100% capacity train is required to be operable.

continuous operation of equipment in these compartments cannot be assured.

The 3 month test interval for the main control room emergency ventilation air supply fan and dampers is sufficient D. Emernency Service Water System since two redundant trains are provided and neither is normally in operation.

The ESWS has two 100 percent cooling capacity pumps, each powered from a separate standby power supply. The ESW A pressure drop test across each filter and across the filter system supplies lake water to cool equipment required to system is a measure of filter system condition. DOP injection function following an accident. This equipment consists of:

measures particulate removal efficiency of the high efficiency emergency diesel generators, electric bay unit coolers, cable particulate filters. A Freon-112 test of charcoal filters is tunnet/ emergency switchgear room coolers, crescent area essentially a leakage test. Since the filters have charcoal of coolers, control room air handling units and relay room air known efficiency and holding capacity for elementaliodine handling units. Emergency service water is initially supplied to and/or methyl iodine, the test also gives an indication of the the control room chillers and chiller room air handling units relative efficiency of the installed system. Laboratory analysis unless ESW is manually realigned to supply the control room of a sample of the charcoal filters positively demonstrates and relay room air handling units. ESW will also supply water halogen removal efficiency. These tests are conducted in to the control rod drive pump coolers which are not accordance with manuf acturers' recommendations.

automatically isolated following an accident. The surveillance requirement compares pump performance with the pump curve The purpose of the emergency ventilation air supply system to determine pump operability. It also specifies testing at a capacity test is to assure that sufficient air is supplied to the main cont.ol room so that a slight positive pressure can be maintained, thereby minimizing in-leakage.

Amendment No. 444,120.223. 231 243 b