ML20080F176
| ML20080F176 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/20/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20080F179 | List: |
| References | |
| DPR-46-A-084, TAC 52013 NUDOCS 8402100366 | |
| Download: ML20080F176 (9) | |
Text
..
I
/p ugk UNITED STATES
'j NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D. C. 20555 8
{
O A
,/
%g v
NEBRA'SKA PUBLIC POWER DISTRICT DOCKET N0. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-46 1.
The Nuclear Regulatory Cconission (tfie Commission) has found that:
A.
The acclication for amendrent by Nebraska Public Power District dated September 26, 1983, complies with the standards and recuire-ments of the Atomic Energy Act of 1954, as amended-(the Act), and the Commission's rules and regulations set forth in 10 CFF Chapter I; B.
The facility will operate in conformity with the applicat an, 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 reouirements have been satisfied.
2.
Accordingly, the licensee is amended by changes to the Technical Specifications as indicated in the attachment to this license amend ment and paragraph 2.C(2) of Facility Operating License No. OPR 46 is l
hereby amended to read as-follows:
(2) Technical Specification 1
The Technical Specifications contained in Appendices A and B, as l
l revised through Amendment No. 84, are hereby incorporated in the i
license. The licensee shall operate the facility in accordance-with the Technical Specifications.
8402100366 840120 PDR ADOCK 05000298 "DR
2-8 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
e
~,, : -
Domenic B. Vassallo, Chief
. Operating Reactors Branch 92 Division of Licensing
Attachment:
Changes to the Technical Specifications.
Date of Issuance:
January 20, 1984 G
a D
O e
A y
k, c'-
ATTACHMENT TO LICENSE AMENDMENT N0. 84 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET N0. 50-298 Revise the Aprendix A Technical Specifications as follows. The revised areas are indicated by marginal lines.
Remove Insert ii ii 137 137 138 through 145 138 through 145 (Intentionally Blank) 151 151 152 152 153 153 153a 153b 9
TABLE OF CONTENTS (cont'd)
Page No.
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS 3.5 CORE AND CONTAI!GiENT COOLING SYSTEMS 4.5 114 - 131 A.
Core Spray and LPCI Subsystems A
114 B.
Containment Cooling Subsystem (RHR Service Water) 3 116 i
C.
HPCI Subsystem C
117 D.
RCIC Subsystem D
118 i
E.
Automatic Depressurization Systen E
119 F.
Mi n 4 =- Low Pressure Cooling System Diesel Generator Availability F
120 G.
Maintenance of Filled Discharge Pipe G
122 H.
Engineered Safeguards Compartments Cooling H
123 3.6 PRIMARY SYSTEM 30UNDARY 4.6 132 - 158 A.
Thermal and Pressurisation Limitations A
132 B.
Coolant Chemistry 3
133a i
C.
Coolant Laakage C
135 D.
Safety and Relief Valves D
136 E.
Jet Pumps E
137 F.
Jet Pump Flow Mismatch 7
137 G.
Inservice Inspection G
137 H.
Shock Suppressors (Snubbers)
H 137a 3.7 CONTAINMENT SYSTEMS -
4.7 159 - 192-A.
159 3.
Standby Gas Treatment System 3
165 C.
165a D.
Primary Containment Isolation Valves D
166 3.8 MISCELLANEOUS RADIOACTIVE MATERIAL SOURCES 4.3 185 - 186 3.9 AUXILIARY ELECTRICAL SYST MS 4.9 193 - 202 A.
Auxiliary Electrical Equipment A
193 3.
Operation with Inoperable Equipment 3
195 3.10 CORE ALTERATIONS
'4.10 203 - 209 A.
Refueling Interlocks A
203 B.
Core Monitoring B
205-C.
Spent Fuel Pool Water Level C
205 D.
Time Limitation D
206 E.
' Spent Fuel Cask Handling E
205'
}
3.11 FUEL RODS
'+.11
.210 - 214e.
l A.
Average Planar Linear Heat Generation Race (APLHCR)
A 210.
3.
Lineer Heat Generation Race (L'AGF.)
3' 210 C.
Minimum Critical Power Ratio (TPR)
C 212:
D.
Thermal-hydraulic Stability D
-212a-l I
i
.it.
Amendment No.'84l
f SURVEILLA' C2 REQUIREMENTS '
LDfITING CONDZTIONS FOR OPERATION 3.6.E Jet Pumps 4.6.E.
Jet Pumns 1.
Whenever the reactor is in the start-1.
Whenever there is recirculation flow up or run modes, all j et pumps shall with the reactor in the startup or be operable.
If it is determined run modes, jet pump operability shall that a jet pump is inoperable, or be checked daily by verifying tha.c the if two or more jet pump flow in-following conditions do not octur'sim-struments failures occur and cannot ultaneously:
be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an orderly shutdown shall be initiated a.
The recirculation pump flow differs and the reactor shall be in a Cold by more than 15; from the established Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
speed ficw characteristics.
b.
The indicated value of core flow race varies from the value derived from loop flow neasurements by more than 10%.
c.
The diffuser to lower plenum differen-tial pressure reading on an individual jet pump varies from the mean of all jet pump diffsrential pressures by more than 10%.
j F.
Jet Pumn Flow Mismatch F.
Jet Pump Flow vismatch 1.
Deleted.
1.
Deleted.
2.
Following one-pump operation, the dis-charge valve of the low speed pump may not he opened ur. lass the speed of the faster pump is equal to or less than 50% of its rated speed.
3.
The teactor shall not be opersted for a period in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with one recirculation loop out of service.
G.
Inservice Inspection G.
Inservice Insnection To be considered operable, com-Inservice inspection shall be per-ponents shall satisfy the require-formed in accordance with the ments contained in Section XI of requirements for ASME Code Class 1, the ASME Boiler and Pressure Vessel 2, and 3 components contained in Code and applicable Addenda for Section II of the ASME 3o11er and continued service of ASML Code Pressure Vessel Code and applicable Class 1, 2, and 3 components except Addenda as required by 10 C7R 50, vhere relief has been grantad by th's Section 50.55a(g), except where l
Commission pursuant to 10 CF2 50, relief has been granted by the Section 50.55a(g)(6)(1).
Commission pursuant to 10 C7R 50, r
l Section 50.55a(g)(6)(1).
I l
l Amendment No. 84 l
l
-137-
"INTENTIONAtti LEFT 3LnT" 1
l l
-138, 139, 140, 141, 147, 743, 144, L45-Amendment No. 84
l 3.6;E & 4.6.E 3ASES (Cont'd) jet pump body; however, the converse is not true.
The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle l
riser system failure.
F.
Jet Pump Flow Mismatch l
1 l
Requiring tha discharge valve of the lower speed icop to remain closed until the speed of ' aster pump is equal to or less chan 50" of its rated speed provides assurance when going from one to two pump operation that excessive vibration of
~
the jet pump risers will not occur.
A loss-of-coolant accident analysis occurring during operation with one recircu-lacion loop has not been performed.
Therefore, operation with a single loop is prohibited except for a limited interval of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G.
Inservice Inspection i
The inservice inspection program conforms 'to the requirements of 10 C7R 50, Section 50.55a(g). Where practical, the inspec, tion of components c'onforms to the requirements of ASME Code Class 1, 2, and 3 components contained in Section II of the ASME 3o11er and Pressure Vessel Code.
If a Code required inspection is impractical, a request for a deviation from that requirement is submitted to the Commission in accordance with 10 C7150, Section 50.55a(g)(6)(1).
Deviations which are needed from the procedur'es prescribed in Section XI of the ASME Code and applicable Addenda will be reported to the Commission prior. co the beginning of each 10-year inspection period if they are known to be required at that time. Deviations which are identified during the course of inspection will be reported quarterly throughout the inspection period.
-151-Amendment No.,
q BASEss i
3.6.H and 4.6.H Cnubbers Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as night occur during an earthquake or severe trans-lent, while allowing normal chermal motion during startup and shutdown. The consequence of an inoperable enubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads.
It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.
j' "acause the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacement.
Since plant'startup should not commence with knowingly defective. safety related equipment, Specification 3.6.H.4 prohibits startup with inoperable snubbers.
All safety related snubbers are visually inspected for.overall 1
integrity and operability.
The inspection frequency is based upon maintaining a constant level of snubber protection.
Thus the required inspection interval varies inversely with the observed snubber failures.
The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.
Inspections performed before~ that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the.
results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) say not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schsdule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that say be generically susceptible, and/or verified by functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are.similarly located or exposed to the same environconcal conditions, such as temperature, radiation and vibration.
I i
4
=[$9 Amendment-No. 84' y
.- ~_- -
...~ -
l 1
e 3ASES (cont'd)
{
When a snubber is fcund inoperable, an engineering evaluation is per-formed, in additi'on to the determination of the snubber mode of failure, in order to determine if any safety related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure i
has imparted a significant effect or, degradation on the supported ccm-ponent or system.
In cases where the cause of failure has been identified, additional snubbers, having a high probability for the same type of failure or that are being used in the same application that caused the failure, shall be tested.
This requirement increases the probability of locating inoper-able anubbers without testing 100* of the snubbers.
Hydraulic snubbers and mechanical snubbers may each be created as a different entity for the above surveillance programs.
To further increase the assurance of snubber reliability, functiedal j
tests should be performed once each refueling cycle.
Ten percent of each type of snubber represents an adequate sample for such tests.
Observed failures on these sangles should require testing of additional 1
units.
Snubbers in high radiation areas or those especially difficult to remove need not be selected for functional tests provided opetability was previously verified.
4 The service life of a snubber is evaluated.via ' manufacturer input and consideration of the snubber service conditions.
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation JLn view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
J 6
1 i
I j
u l
-152-Ih Amendment No. 84
-,