ML20155F916
| ML20155F916 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/31/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155F899 | List: |
| References | |
| NUDOCS 8806170103 | |
| Download: ML20155F916 (10) | |
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p atog jog UNITED STATES
[g g NUCLEAR REGULATORY COMMISSION g ;j WASHINGTON, D. C. 20555 k . . . . . ,o#
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION :
SUPPORTING AMENDMENT NO. 62 TO PROVISIONAL LICENSE NO. DPR-45 LA CROSSE BOI!.ING WATER REACTOR (LACBWR)
DOCKET NO. 50-409
1.0 INTRODUCTION
On April 27, 1987, Dairyland Power Cooperative (DPC, the licensee) announced that their La Crosse Boiling Water Reactor (LACBWR) would be permanently shutdown because of economic reasons and on April 30, 1987 the shutdown was completed. On June 12, 1987, all fuel had been removed from the reactor and stored in the Fuel Element Storage Well (FESW). By letter dated May 22, 1987 (LAC-12234), DPC requested that Provisional License l No. DPR-45 for LACBWR be amended to a possession-only status. License I Amendment No. 56 issued on August 4, 1987 established the possession-only status.
By letter dated September 30, 1987 (LAC-12383) as revised by a letter dated February 22, 1988 (LAC-12500), DPC submitted a proposed amendment to the LACBWR Technical Specifications (TS). This proposed amendment is one of a series of changes to bring the TS into agreement with the possession-only license. The proposed TS changes would remove most of the requirements for operstional and refueling conditions, since the reactor is permanently shutdown and defueled. In some cases specifications with non-applicable operational conditions are modified or left unchanged since they interact with requirements which are still applicable in the shutdown or defueled condition. No TS changes or only minor changes are proposed for fire protection, electrical power systems, containment systems, radiation 3rotection systems, radioactive waste systems, the spent fuel storage and landling system, or administrative controls.
2.0 DISCUSSION AND EVALUATIOJ As an operating nuclear power plant, LACBWR had approved operational TS, meecing the requirements of 10 CFR 50.36. Since the reactor has been permanently shutdown and now has a possession-only license, many of these TS are no longer pertinent. In this proposed amendment the licensee proposed to anend the existing operational TS to remove those sections no longer applicable and to modify otner sections to more clearly state requirements still needed to maintain the facility in a safe shutdown ,
defueled condition with all fuel stored in the FESW. l l
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2.1 Operational Conditions With the license changed to a possession-only, Operational Conditions 1 - Power Operation, 2 - Startup, 3 - Hot Shutdown, and 5 - Refueling i are no longer permitted. Since applicability of a specification is often denoted by one or more of these operational conditions, those TS specific to Conditions 1, 2, 3 and 5 are no longer relevant and can be deleted.
Although the plant is now considered to be in Condition 4, Cold Shutdown, many of the existing requirements for this condition do not apply due to the reactor's permanent defueled condition and are being eliminated if they do not interact with other needed requirements.
In Section 4.0.1, Definitions, the licensee proposes to modify this section by removing 15 definitions. These are: average planar exposure, average planar linear heat generation rate (Page 27d), core alteration, critical power ratio (Page 27e), identified leakage (Page 27f), limiting control rod pattern, linear heat generation rate, minimum critical power ratio (Page 279), part hi scram, physics test, pressure boundary leakage, rated thermal power, shutdown margin (Page 27h), thermal power, and unidentified leakage (Page 271). These definitions are not applicable to a shutdown defueled reactor and any TS on these topics may be deleted.
The licensee also proposes to delete Section 4.1, General (Page 28) which contains three items; 4.1.4, control room operator direction of operations whenever fuel is in the reactor, 4.1.5, reactor operation instructions in case of a tornado warning, and 4.1.6, shutdown actions in case of high Mississippi River level. These items pertain to operational conditions which are no longer applicable since the reactor is defueled and not operable.
2.2 Safety Limits and Limiting Safety System Settings The licensee proposes to remove Section 4.0.2, Safety Limits and Limiting i Safety System Settings, and Bases (Pages 27y through 27qq). These limits and trip setpoints were included to maintain the integrity of the fuel cladding, pressure vessel, and primary piping during abnormal operating conditions and are not applicable since the reactor is no longer operable or fueled. l The Safety Limits and the Reactor Safety System Setpoints deleted are as i follows:
Safety Limits 4.0.2.1.1 and 4.0.2.1.2, Thermal Power Limits (Page 27y) applicable in Operating Conditions 1 and 2, limit thermal power and minimum critical pcwer ratio at low reactor pressure and core flows.
These are no longer required for a shutdown reactor.
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a Safety Limit 4.0.2.1.3, Reactor System Pressure (Page 27z), applicable in Operating Conditions 1, 2, 3 and 4, limits the reactor pressure to prevent overstressing the primary coolant system boundary. This is no longer of concern since the vessel will no longer be used as a nuclear reactor and cannot be pressurized since it is stored with the reactor vessel head untorqued and the vessel vented.
Safety Limit 4.0.2.1.4, Reactor Vessel Water Level (Page 27z), applicable in Operating Conditions 1, 2, 3, 4 and 5, specifies that fuel in the reactor vessel be covered by water at all times. This is no longer applicable since the reactor is defueled.
Limiting Safety System Settings and Bases 4.0.2.2, Reactor Safety System Reactor Shutdown Instrumentation Setpoints (Pages 27aa-27qq), applicable in Conditions 1, 2, and 3, specifies the trip setpoints at which the Reactor Protection System (RPS) automatically shuts down the reactor. The RPS is no longer in use; therefore, this specification is no longer needed.
2.3 Limiting Conditions for Operations The licensee proposes to delete the following Limiting Conditions for Operations (LCOs) including surveillance requirements and bases:
4/5.2.2.5 Coolant System Safety Valves (Pages 30g and 30h) 4/5.2.2.21 Reactor Coolant Operational Leakage (Pages 31a and 32b) 4.2.4.2 and Power Distribution Limits 5.2.17 Average Planar Linear Heat Generation Rate (Pages 32t, 32u and 32v) i Normal Power-Recirculation Flow Relationship (Pa l Minimum Critical Power Ratio (Pages 32x and 32y)ge 32w) l Linear Heat Generation Rate (page 32z)
Maximum Average Fuel Assembly Exposure (Pages 32aa, 32bb, 1 32ce, 32dd, 32ee, 32ff, 32gg, 32hh and 3211) l 4/5.2.21 Emergency Service Water Supply System (Pages 37n, l 37o, 37p and 37q) 4/5.2.22 Primary Coolant System Pressure Isolation Valves l (Page 37r) ;
1 4/5.2.23 Demineralized Virgin Water Tank (Page 37s) 4/5.2.24.2 Manual Depressurization System (Page 37w) 4/5.2.24.3 Alternate Core Spray System (Pages 37x and 3/y) !
4/5.5.1 Post-Accident Instrumentation - Containment Pressure, Water Level and Hydrogen Concentratien (Page 58)
l 4.2.3.3.1 and AC Distribution - Essential Bus Instruments and Reactor 5.2.11.5 Safety 32r(3), System Trip 32r(4) and Setp(oints 32r 5) (Pages 32r(1), 32r(2)
The above LCO's are no longer necessary since they are only applicable for operational conditions 1, 2 and 3 which can no longer be attained with the reactor permanently shutdown and defueled.
In five other cases, the deleted LCOs were applicable at all times or in operational conditions other than or in addition to 1, 2 and 3. The specific justification for their removal in each case is as follows:
4/5.2.2.4 Reactor Vessel Heatup and Cooldown rates (Pages 30, 30a, 30b, 30c, 30d, 30e and 30f), applicable at all times except when the vessel is vented. The vessel and forced circulation systems are being maintained full of water but the vessel head is not torqued down and the vessel vents are open. The vessel and attached piping are no longer considered to be pressure boundaries. Therefore, the limits on heatup/cooldown rates to protect the vessel and attached piping from thermal stresses are no longer required.
4.2.2.22 and Reactor Coolant Activity (Pages 32a, 32a(1), 32b, 32c, 32d, 5.2.16 32e and 32f), applicable in Operational Conditions 1, 2, 3 and 4. This LCO applies to radioactivity in the coolant caused by failed fuel cladding. Since the reactor is defueled and shutdown, this LCO is no longer applicable.
Table 4.2.2.22-1 (Pages 32d and 32e) specifying samples and analyses required to detect coolant activity is also deleted.
4/5.2.24.1 High Pressure Core Spray System (Pages 37t, 37u and 37v), i applicable in Operational Conditions 1, 2, 3 and 4 for the l low pressure core spray mode. This LC0 was needed in l' Operational Condition 4 to provide a water source for flooding the core in case of accidental vessel draining.
Since the reactor is shitdown with the core removed, this
> LC0 is no longer applict.ble.
4/5.2.24.4 Overhead Storage Tank (0HST) (Pages 37z, 37aa and 37bb), .
applicable in Operational Conditions 1, 2, 3 and 4, and is used as the water source in the low pressure mode of the High Pressure Core Spray. Justification for removal is the same as above.
4/5.3.2.5 Gaseous Radwaste System (Pages 49 and 55), applicable whenever the main condenser air ejector system is in operation. Since the reactor is shutdown, the air ejection system will no longer be used. The Air Ejector Offgas l Monitor instrument and surveillance requirements may also '
be removed from Tables 4.3.2.1 and 5.3.2.1 as the air .
injector system will not be used. j l
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2.4 Miscellaneous TS Deletions The licensee proposes to delete the following miscellaneous specifications.
4.2.2.6, 4.2.2.7 (Page 301), 4.2.2.8 and 4.2.2.9 (Page 31) and 5.2.5 (Page 5-6) specifying Operational Conditions and tests of the Forced Circulation Loops and Pumps which are no longer needed to protect the fuel.
4.2.2.10 (Page 31), 4.2.2.19 (Page 31a) and 5.2.6 (Page 5-6) specifying operational status and tests of the Shutdown Condenser which is no longer needed to shutdown the reactor.
4.2.2.11 and 4.2.2.12 (Page 31) specifying the isolation of and shutdown reactivity limits to protect the Decay Heat System from over pressurization. The Decay Heat System is no longer necessary for a shutdown, defueled reactor.
4.2.2.13 and 4.2.2.17 (Page 31) and 5.2.9 (Page 5-6) specifying operational limits and tests to assure boron injection is available when needed and boron is not removed by the Purification System when its presence is required. Backup reactivity control in the reactor is no longer necessary.
4.2.2.20 (Page 31a) specifying action required when the hydraulic control system for the Forced Circulation Valves and the Main Steam Isolation Valve (MSIV) is incperable. The automatic closures of these valves is no longer needed.
Section 4.2.4.2, Power Distribution Limits and Section 5.2.17 Surveillance Requirements are deleted since these relate to reactor operation which is no longer pernitted.
Section 5.2.1.6, Containment Ventilation Isolation Yalva leakage Tests, Subsection (c) (Page 5-5) has been modified by deleting the last sentence which specifies reactor shutdown in the action statement. This require-ment is no longer applicable since the reactor is permanently shutdown and defueled.
Section 4.2.8.1 (Page 37) which specifies only one fuel element or one control rod can be inserted or removed from the reactor vessel at one time has been deleted since the reactor is permanently defueled.
In Section 4.0.1, Definitions (Page 27e) the definition for core alteration has been deleted since the reactor is already defueled.
4.2.4.4 thru 4.2.4.9 (Page 33). These six sections specify reactor core reactivity limits and control rod operability limits which are no longer needed since the reactor is defueled and shutdown.
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4.2.5.1 thru 4.2.5.8 (Page 34) specifying eight various limits for Control Rods, Control Rod Position Indication, Forced Circulation Systems and Main Steam Bypass Valve control to regulate or prevent reactivity changes in the core. These are no longer required since the reactor is shutdown and defueled.
4.2.6.4 and 4.2.6.5 (Page 35) specifying Reactor Protection Trip System rod blocks and startup permits that are no longer necessary.
4.2.6.6 and 4.2.6.7 (Pages 35 and 36) specifying minim a nuclear instrument requirements for core changes and reactor operation. These specifications are no longer needed.
4.2.6.9 and Bases (Page 36) ssecifying high pressure and low water level automatic shutdown trips of tie Forced Circulation Pumps to protect the primary system from an ATWS event. These are no longer necessary.
4.2.8.4 (Page 37) specifies a 72-hour decay period before moving irradiated fuel elements into the FESW. This coo 18 q period is no longer required as all the irradiated fuel has been moved te the FESW.
5.1.3 (Page 5-1) specifying that the reactor be shutdown before opening the primary coolant system. This requirement no longer applies.
5.1.6 and 5.1.7 (Page 5-2) specifying adjustments in intervals of tests that must be made with the reactor shutdown and deletes definitions of channel check, channel test and channel calibrations which are redundant with Section 4.0.1, Definitions.
5.2.16 (Page 5-10) specifying Forced Circulation System corrosion test coupons and pipe replacement that are no longer applicable.
6.2.3 (Page 6-1) specifies a Shift Technical Advisor for safe operation of the facility, a requirement no longer necessary as his job relates to ;
reactor operations. J 5.2.4 (Page 5-6) specifies a 1400 psig hydrostatic test of the reactor ;
vessel prior to operation if it has been opened and resealed, a requirement no longer necessary.
5.2.12, 5.2.13 and 5.2.14 (Page 5-6a) specifying surveillance tests of the Control Rod scram times, periodic exercise of the Control Rods, and proper 1 operation of the hydraulic scram valve control solenoids. Operation of I the Control Rods and the scram system is no longer required with the reactor permanently shutdown.
2.5 Modifications to TS In addition to the deletions above, the licensee proposes to modify several sections to more clearly define requirements in the shutdown and defueled condition. These modifications are as follows: l
4.2.1, Reactor Building Operating Limits (Pages 28 and 29) have been !
modified by deleting the requirements for containment integrity during ;
operational conditions 1, 2 and 3, during core alterations, when fuel is i in the reactor, and when irradiated fuel aged less than 43 days is in the i FESW. Since the reactor is shut down and defueled, these conditions are no longer applicable. Containment integrity is still required when !
irradiated fuel is being handled.
Sections 4.2.1.3 and 4.2.1.4 (Page 29), The references to containment integrated leak rate testing (ILRT) have been deleted from these sections.
Type B and C leak testing requirements for newly installed or modified penetrations have been referred to Section 5.2.1.2, Individual Leak Detection Tests (Type B and C Tests) found on Pages 5-3 and 5-4. This change is needed to make these TS consistent with Amendment No. 59 dated March 15, 1988 which deleted ILRT requirements.
4.2.1.10, Operability of the Containment Ventilation Dampers (Page 29a) the LCO action statement and surveillance requirements for operability of the Containment Ventilation Dampers has been modified to require damper operability only during fuel handling and deleting o)erability requirements during reactor operation and shutdown wiich no longer apply.
4.2.2.2, Reactor Coolant Purity (Page 29b) has been modified by deleting .
the LCO while in Operational Conditions 1, 2 and 3; but retains the purity '
limits and frequency of determinations for Condit: ions 4 and 5 which are still applicable when the primary system contains water.
4.2.6.1, Safety Instrumentation (Page 34) has been modified by removing the scram actions which are no longer applicable but retaining isolation actions and other safety actions.
4.2.6.2, Safety Instrumentation (Page 35) has been modified by removing the reference to Table 4.0.2.2.1-1 that has been deleted.
4.2.6.3, Safety Instrumentation (Page 35) has been modified by removing l specific key bypass requirements concerning boron injection, source range I and intermediate range rod withdrawal prohibits, building locks interlock, and rod withdrawal permit since the reactor protection system is no longer required. Approval of the Shift Supervisor is still required to use by-pass keys to operate, test or conduct maintenances on the safety instrumentation.
4.2.6.8, Safety Instrumentation (Page 36) has been modified by deleting the bypass time limit for safety channels in the partial scram circuit since the scram circuits are no longer applicable. The TS still permit other redundant safety channels to be bypassed for maintenance and testing.
5.1.1, Maintenance (Page 5-1) has been modified by removing reference to refueling operations which are no longer conducted.
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l 5.1.2, Maintenance (Page 5-1) has been modified by requiring Shift Supervisor authorization to perform any maintenance. This is a more ,
conservative requirement. The specification still requires Health Physics l representation when a system containing radioactive material is opened. I 6.2.1.2 (e), Containment Testing (Page 5-4) has been modified by changing the Type B Containment Leak Rate Test frequency for the freight door to test each time it is opened, a more stringent requirement. The Type C Leak Rate Test frequencies have been modified by eliminating the test at each refueling outage, which no longer applies, but maintains a test frequency no greater than two years, the existing specification limit.
5.2.2.1, Reactor Building Isolation (Page 5-5) has been modified by deleting requirements for testing prior to each cold startup as there will be no more startups. System testing will now be required at least every 18-months, the normal refueling surveillance frequency.
The table for "Minimum Frequencies for Testing, Calibrating, and/or Checking of Instrumentation" (Pages 5-7, 5-8, 5-9 and 5-10) has been modified by deleting requirements for shutdown condenser indication, reduction of power for ATWS, and safety valve position indication.
Those instruments are not needed in the shutdown defueled condition.
The requirements for reactor water level, area radiation monitors, portable radiation detectors, and reactor building pressure are retained.
For the instrument systems retained, the minimum frequency of required surveillances remain the same except for the reactor water level and reactor building pressure calibrations which were changed from each refueling outage to every 18-months.
Table 1, Operating Limits (Pages 5-11, 5-12, 5-13, 5-14, 5-15, 5-16, 5-17, and 5-18) has been modified by deleting those instrument systems no longer needed for a shutdown-defueled reactor. The instrument channels deleted functioned to automatically shut down the reactor, operate the shutdown condenser, initiate core spray, initiate diesel generators for the purpose of supplying the high pressure core spray pumps, isolate the steam line on low main condenser vacuum or low main steam line pressure, divert offgas flow, trip forced circulation pumps to reduce reactor power, indicate safety valve position, or to isolate containment ventilation on high reactor pressure. The containment isolations on low reactor water level and high reactor building pressure have been retained since some of the isolation valves have no other closure signals. The setpoints and key switch bypass provisions for the three instrument systems retained have not been changed. Scram actions and the initiation of the High Pressure Core Spray Pumps, the Alternate Core Spray Pumps, and the 1A and 1B Diesel Generators have been deleted frem actions required for low reactor water level and high reactor building pressure safety trips as they are no longer applicable.
6.2.2.h (Page 6-1) specifying working hours of personnel in an operational reactor has been modified by changing Reactor Control Operator and Auxiliary Operator to Operators and deleting reference to the Turbine Generator Control Board Operator, a position no longer required.
Section 4/5.2.23, FESW Water Supply (Page 37n) , a new LCO, was added to assure an adequate backup coolant supply for the FESW from either the Demineralized Virgin Water Tank (DVWT) or the Overhead Storage Tank (OHST). The new LCO requires at least one of these sources be available at all times with a minimum volume requirement of 5000 gallons. If both of these systems are inoperable, the action statement requires one of the systems to be returned to operable status in seven days. The required minimum water volume in these tanks is to be verified once per seven days. This is adequate backup water for the FESW.
This new LCO replaces LCOs for the DVWT and the OHST which were deleted (SER pages 3 and 4). Previously Section 4/5.2.23, DVWT, specified a backup short term water supply for the shutdown condenser and Section 4/5.2.24.4, OHST, specified a minimum volume to assure a sufficient water supply for the HPCS system in the event of a LOCA. These water sources are also used to supply water to the FESW; therefore, the licensee proposes to continue to provide minimum volume requirements for these tanks.
3.0 SUlHARY The staff found that specifications for Operational Condition 1, 2, 3 or 5 as defined in TS Section 4.0.1, are no longer applicable or needed for the safety of the public or the LACBWR staff because the reactor may not be started up, operated, or refueled.
In reviewing the other TS deletions and modifications which were not referenced to Operational Conditions, the staff considered the effect each change would have on the safety of the shutdown, defueled reactor and the irradiated fuel stored in the FESW.
The staff has concluded that the proposed deletions concerned TS require-ments that were in place only to protect an operating plant and that all necessary requirements for protecting the irradiated fuel, and residual radioactive materials have been retained. The remaining TS include requirements for spent fuel storage, electrical power distribution, ,
emergency electric power systems, fire protection, radiation protection, containment facility, radioactive effluents, environmental monitoring and administrative controls. The staff finds that the safety of public and licensee's staff will not be reduced by these changes and that the i removal of no longer needed requirements will enhance the clarity of the l TS.
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4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves administrative changes and changes to requirements with respect to the installation or use of facility components located within the restricted areas as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment invo V s no significant hazards consideration and there has been no public ccanent on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in the 10 CFR 51.22(c)(9)&(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement nor environment assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the FEDERAL REGISTER on November 18, 1987 (52 FR 44243) and April 20, 1988 (53 FR 13013).
No public comments were received on either FEDERAL REGISTER notice.
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the connon defense and security nor to the health and safety of the public.
Principal Contributors: X. R. Ridgway P. B. Erickson Dated: May 31, 1988
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