ML20149C027
| ML20149C027 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/01/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149C030 | List: |
| References | |
| TAC-66980, NUDOCS 8802090046 | |
| Download: ML20149C027 (9) | |
Text
f A fic
o UNITED SYATES
!N-NUCLEAR REGULATORY COMMISSION e
{ \\
]1 WUHINGTON, D. C. 206H
%,*... /
CONSUMERS POWER COMPANY FALISADES PLANT DOCKET NC. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE kendment No.110 License No. OPR-20 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee)datedJanuary 19, 1988, complies with the standards and 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; B.
The facility will operatc in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
88P988n Bi8$p P
(
e.
f 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to reao as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B.
as revised through Amendment No.110, are 1ereby 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 1
V cmg 6
&c
, 7 4 Martin J. Virgilio Director Project Directorate 111-1 Division of Reactor Projects - III. IV Y
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 1, 1988 L
\\
C ;-
u ATTACHMENT TO. _ LICENSE AMENDMENT NO. 110 PROV!SIONAL OPERATING LICENSE NO DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT it 11 vii vii 3-82 3-82 3-33 3-83 4-14a 4-14a 6-38 l
8 1
I I
l l
1 a
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION
-DESCRIPTION PAGE NO 3.0 LIMITING CONDITIONS FOR OPERAT7.ON (Continued) 1 3.10 CONTROL ROD AND P0kTR DISTRIP'JION LIMITS 3-$8 l
3.10.1 Shutdown Margin Requirements 58 1
3.10.2 Individual Rod k' orth 3-58 3.10.3 Part-Length Control Rods 3-58 t
3.10.4 Misaligned or Inoperable Control Rod or Part-Length Rod 3-60 3.10.5 Regulating Grotp Insertion Limits 3-60 3.10.6 Shutdown Rod Limits 3-61 3.10.7 Low Power Physics Testing 3-61 c
3.10.8 Center Control Rod Misalignment 3-61
?
Figure 3-6 Control Rod Insertion Limits 3-62 l
3.11 P0k'ER DISTRIBUTION INSTRUMENTATION 3-65 3.11.1 Incore Detectors 3-65 3.11.2 Excore Power Distribution Monitoring System 3-66a
[
Figure 3.11-1 Axial Variation Bounding Condition 3-66d i
3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 6
3.13 CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES 3-69 3.14 CONTROL ROOM VENTILATION 3-70 3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3-70 l
3.16 ENGINEERED SATETY FEATURES SYSTEM INITIATION i
INSTRUMENTATION SETTINGS 3-71 Table 3.16.1 Engineered Safety Features System Initiation Instrument Setting Limits 3-75 3.17 INSTRUMENTATION AND. CONTROL SYSTEMS 3-76 l
Table 3.17.1 Instrumentation Operating Requirements for Reactor t
Protective System J-78 Table 3.17.2 Instrumentation Operating Requirements for Engineered Safety Teature Systems 3-79 i
Table 3.17.3 Instrument Operating Conditions for Isolation I
Functions 3-80 Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions 3-81 3.18 (Deleted) 3-82 /
/
l 3.19 IODINE REMOVAL SYSTEM 3-84 J
3.20 SHOCK SUPPRESSORS (SNUBBERS) 3-88
/
l i
/
l "l
3.21 MOVEMENT OF SHIELDED SHIPPING CASK IN TUEL HANDLING AREAS 3-92 l
3.22 FIRE PROTECTION SYSTEM 3-96 3.22.1 Fire Detection Instrumentation 3-96 l
l Table 3.22.1 Fire Detection Instrumentation Minimum Instruments l
Operable 3 97 i
r h
I 11 Amendment No. 31, 3), 88, SJ, $5, 188, 110 l
4 L
PALISADES PLANT TELHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PA.GE NO 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.5 REV!EW AND AUDIT 6-5 6.5.1 Plant Review Committee (PRC) 6-5 l
6.5.2 Nuclear Safety Board (NSB) 6-6a 6.6 (Deleted) 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 i
6.8 PROCEDURES 6-10 6.9 REPORTING REQUIREMENTS 6-11 6.9.1 Routine Reports 6-11 6.9.2 Reportable Events 6-12 6.9.3
-Other Reporting Requirements 6-18 6.9.3.1 Routine Reports 6-18 6.9.3.1.A Radioactive Effluent Releases 6-18 6.9.3.1.B Annual Radiological Environnental Operating Report 6 24 6.9.3.2 Nonroutine Reports 6-25b Table 6.9-1 Environmental lladiological Monitoring Program Summary 6-25c 6.9.3.3 Special Reports 6-26 l
6.10 RECORD RETENTION' 6-26 6.11 RADIATION PROTECTION PROGRAM 6 28 6.12 HIGH RADIATION AREA 6-28 6.13 (Deleted) 6-33 6.14 (Deleted) 6-33 l
6.15 SYSTEMS INTEGRITY 6-33 i
6.16 IODINE MONITORING 6 33
[
6.17 POST ACCIDENT SAMPLING 6-34 l
6.18 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6-35 6.19 PROCESS CONTROL PROGRAM (PCP) 6-35 6.20 MAJOR MODIFICATIONS TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-36 6.21 SEALED SOURCE CONTAMINATION 6-37 6.22 SECONDARY WATER CEEMISTRY 6-38 /
J l
l
}
1 i
i vii Amendment No. 195. 110 1
~ _, _
r
]
3.18 (Deleted) s e
THIS PAGE INTENTIONALLY BLANK 1
l 1
1 3-82
)
Amendment No. 20, 110
m..
i THIS PAGE INTENTIONALLY LEFT BLANK i
s k
3-83 Amendment No. 20, 110 l
l l
.y
=
Table 4.2'.1 Minimum Frequencies for Sampling Tests FSAR Section Test Frequency Reference 6.
Spent-Fuel Pool Boron' Concentration Monthly ( )
9.4 Bulk Water Temperature, Continuously when None bundles are stored in tilt pit racks.
with less than(6)~
one year decay
- 7. ' Secondary Coolant Gas Radioactivity by.
Continuous (5)
None Air Ejector Gas Monitor during power operation Coolant Gross Radio-3 times /7 days with None activity a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples
/
~/
/
/
/
/
Isotopic Analysis for a) 1 per 31 days, Dose Equivalent I-131 whenever the Concentration gross activity determination
-indicates iodine concentrations greater than 10%
of the allowable limit b) I per 6 months, whenever the gross activity determination indicates iodine concentrations below 10% of the allowable limit.
8.
Liquid Radwaste Radioactivity Analysis Prior to release 11.1 of each batch 9.
Radioactive Gas Radioactivity Analysis Prior to release 11.1 Decay of each batch 1
Weekly (')
10.
Stack-Gas Monitor Iodine 131 and Particu-11.1' Particulate Samples ulate Radioactivity 4-14a Amendment No. 27, 110 i
l i
E i(*
ADMINISTRATIVE CONTROLS
/.
.e.
/'
6.22 SECOIDARY UATER Cili 211STi1Y
/
I A'. program sh'all-be established, implemented-and naintained.for
'/
monitoring of secondary' water.chenistry to inhibit stean-generator.
/ -
tube-degradation and shall include:
. /
1.
-Identification ofia-sampling schedule:for the' critical
- /
1
~
/ ;
variables and control points for;these. variables,'
- /.
/.
2.
Identification of the procedures used to neasure the' values-
- //
of the critical variables,
/ -
/.
3.
Identification of process sampling points, which shall
/
include nonitoring-the discharge of che condensate punps
/-
for evidence of condenser-in-leakage,
/
/
4.
Procedures for the recording and management of data,
' /.
j.
5.
Procedures defining corrective actions for all off-control-
/
point chenistry conditions, and
/
/'
6.
A procedure identifying (a) the authority responsibic for-
/
the interpretation of the data, and (b).the sequence and;
/
timing ~of administrative events required to initiate corrective actions.
M I
1 1
A l
. l l
T 6-38 Amendment No. 110 f
i
[
t
= -,..,
m,,
.., _...--_,..i~.