ML20236H634
| ML20236H634 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/22/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236H638 | List: |
| References | |
| NUDOCS 8711040244 | |
| Download: ML20236H634 (12) | |
Text
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UNITED ATEs
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g NUCLEAR REGUL
)RY COMMISSION j
WASHINGTC O.C.20555
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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.113 License No. DPR-59 3
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State t
of New York (the licensee) dated March 16, 1987, complies with as amended (the Act)quirements of the Atomic Energy Act of 1954, the standards and re j
and the Comission'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 j
have been satisfied.
i 2.
Accordingly, the license is amended by changes to the Technical f
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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-(2) Technical Specifications The Technical ~ Specifications contained in Appendices.
A and B, as revised through Amendment No.113, 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.
FOR THE NUCLEAR REGULATORY COMMISSION 7 M (L.C W J
Robert A. Capra, Acting Director Project Directorate I-1 Division of-Reactor Projects, I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: October-22, 1987 u
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ATTACHMENT TO LICENSE AMENDMENT N0.113 FACILITV OPERATING LICENSE NO. DPR-59 00CKET NO. 50-333, i
Revise Ap'pendix A as follows:
Remove Pages Insert Pages 1
I (1
ii vii vii 136 136 137
'137 138 138 l
146 146 1
147 147
'148 148 1
163 163 R
i l
l l
l
I' i
I JAFNPP f
TABLE OF CONTENTS (cont'd) ln.
Page r
F.
Minimum Emergency Core Cooling System F.
122 Availability G.
Maintenance of Filled Discha rge Pipe G.
122 H.
Average Planar Linear Heat Generation H.
123 Rate (APLHGR)
I.
Linear Heat Generation Rate (LHGR)
I.
124 l
J.
Thermal Hydraulic Stability J.
124a SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.6 Reactor Coolant System 4.6 136 l
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 C.
142a F.
St ructural Integrity F.
144 G.
Jet Ptmps G.
144 H.
DELETED I.
Shock Guppressors (Snubbers)
I.
145b 3.7 Containment Systems 4.7 165 A.
165 4
B.
Standby Gas Treatment System B.
181
)
C.
184
]
D.
Primary Containment Isolation Valves D.
185 i
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 G.
222c Protection 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.
Crescent Area Ventilation B.
239 C.
Battery Room Ventilation C.
239 2, 4/[, 9[, 113 Amendment No.
11
U JAFNPP LIST OF FIGURES
- t.
Figure Title Paxe 3.1-1
- Manual Flow Control 47a 3.1-2 Operating Limit MCPR versus 47b 4.1-1 Craphic Aid in the Selection of an Adequate Interval Between Tests 48 4.2-1
. Test Interval vs. Probability of System Unavailability 87 3.4-1 Sodium Pentaborate Solution o'f System Volume-Concentration Requirements 110
,3.4-2 Saturation Temperature of Sodium Pentaborate Solution 111 3.5-1 Thermal Power and Core Flow Limits of Specifications 3.5.J.1 and 3.5.J.2 134 3.5-6 (Deleted) 135d 3.5-7 (Deleted) 135e 3.5-8 (Deleted) 135f 3.5-9 MAPLHGR Versus Planar Average Exposure Reload 4 P8DRB284L 135g
~3.5-10 MAPLHGR Versus Planar Average Exposure Reloads 4 & 5 P8DRB299 135h 3.5-11 MAPLHGR Versus Planar Average Exposure deload 6, BP8DRB299 1351 l
3.6-1 Reactor Vessel' Pressure-Temperature Limits 163 4.6-1 Chloride Stress Corrosion Test Results at 500*F 164 1
6.1-1 Management Organization Chart 259 i
6.2-1 Plant Staff Organization 260 I
I 7)
, 113 Amendment No.
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