ML20078F829

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Proposed Tech Spec Changes,Allowing Relief from Inservice Insp Requirements of 10CFR50.55a(g)
ML20078F829
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/26/1983
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20078F825 List:
References
NUDOCS 8310110183
Download: ML20078F829 (6)
v • d • e


Text

TABLE OF CONTENTS (cont'd)

Page No.

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 114 - 131 A. Core Spray and LPCI Subsystems A 114 B. Containment Cooling Subsystem (RHR Service Water) B 116 C. HPCI Subsystem C 117 D. RCIC Subsystem D 118 E. Automatic Depressurization System E 119 F. Minimum 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 BOUNDARY 4.6 132 - 158 A. Thermal and Pressurization Limitations A 132 B. Coolant Chemistry B 133a C. Coolant Leakage C 135 D. Safety and Relief Valves D 136 E. Jet Pumps E 137 F. Jet Pump Flow Mismatch F 137 G. Inservice Inspection G 137 H. Shock Suppressors (Snubbers) H 137a 3.7 CONTAINMENT SYSTEMS 4.7 159 - 192 A. Primary Containment A 159 B. Standby Gas Treatment System B 165 C. Secondary Containment C 165a D. Primary Containment Isolation Valves D 166 3.8 MISCELLANEOUS RADIOACTIVE MATERIAL SOURCES 4.8 185 - 186 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 193 - 202 A. Auxiliary Elect 21 Equipment A 193 B. Operation with ..aperable Equipment B 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 206 3.11 FUEL RODS 4.11 210 - 214e A. Average Planar Linear Heat Generation Rate (APLHGR) A 210 B. Linear Heat Generation Rate (LHGR) 3 210 C. Minimum Critical Power Ratio (MCPR) C 212 D. Thermal-hydraulic Stability D 212a 8310110183 830926 PDR ADOCK 05000298 P pon _ - _ . _ -_-

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E. Jet Pumps

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 that the if two or more jet pump flow in- following conditions do not occur 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 flow characteristics.

b. The indicated value of core flow rate varies from the value derived from loop flow measurements 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 differential pressures by more than 10%.

F. Jet Pump Flow Mismatch F. Jet Pump Flow Mismatch

1. Deleted. 1. Deleted.
2. Following one-pump operation, the dis-charge valve of the low speed pump may not be opened unless the speed of

.the faster pump is equal to or less than 50% of its rated speed.

3. The reactor shall not be operated 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 Inspection 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 XI of the ASME Boiler and continued service of ASME Code Pressure Vessel Code and applicable Class 1, 2, and 3 components except Addenda as required by 10 CFR 50, where relief has been granted by the Section 50.55a(g), except where Commission pursuant to 10 CFR 50, relief has been granted by the Section 50.55a(g)(6)(1). Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

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" INTENTIONALLY LEFT BLANK" s

-138, 139, 140, 141, 142, 143, 144, 145-

  • 3s 6. E & 4. 6.E BASES (Cont'd) jet pump body; howsver, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle riser system failure.

F. Jet Pump Flow Mismatch Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is equal to or less than 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-lation 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 The inservice inspection program conforms to the requirements of 10 CFR 50, Section 50.55a(g). Where practical, the inspection of components conforms to the requirements of ASME Code Class 1, 2, and 3 components contained in Section XI of the ASME Boiler 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 CFR 50, Section 50.55a(g)(6)(1).

Deviations which are needed from the procedures prescribed in Section XI of the ASME Code and applicable Add.7da will be reported to the Commission prior to 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.

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BASES:

3.6.H and 4.6.H Snubbers Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe trans-1ent, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber 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 snubbcrs required to protect the primary coolant system or any other safety system or component be operable during reactor operation.

Because 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 allcwed 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 integrity and operability.

The inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required inspection intarval 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%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a' snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and/or verified by functional testing, that snubber may be exemptad 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 environmental conditions, such as temperature, radiation and vibration.

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BASES (cont'd)

-When a snubber is found inoperable, an engineering evaluation is per-formed, in addition 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 has imparted a significant effect or degradation on the supported com-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 snubbers without testing 100% of the snubbers.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

To further increase the assurance of snubber reliability, functional 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 samples should require testing of additional units. Snubbers in high radiation areas or those especially difficult to remove need not be selected for functional tests provided operability was previously verified.

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 in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

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