ML20149N101
| ML20149N101 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/22/1988 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20149N036 | List: |
| References | |
| NUDOCS 8803010234 | |
| Download: ML20149N101 (15) | |
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PAGE 37s CURRENT PLANT SYSTEMS 4/5.2.23 DEMINERALIZED VIRGIN WATER TANK LIMITING CONDITION FOR OPERATION 4.2.23 The Demineralized Virgin Water Tank shall be OPERABLE within a miniraum water level of 1 foot.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With the Demineralized Virgin Water Tank inoperable, restore it to OPERABLE status within 72 bours, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIRFMENTS 5.2.23 The Demineralized Virgin Water Tank shall be demonstrated OPERABLE by verifying the minimum water level in the tank at least once per 7 days.
BASIS FOR DEMINERALIZED VIRGIN WATER TANK A minisaum water level in the Demineralized Virgin Water Tank is specified to assure availability of a short term supply of cooling water for the shutdown condenser in the event of a loss of the Ultimate Heat Sink, the Mississippi River. The specified minimum of 1 foot of water in the tank will provide sufficient time to allow set-up of an alternate water supply.
PROPOSED Modify Section 4/5.2.23 as follows:
4/5,2.23 FUEL ELEMENT STORAGE WELL WATER SUPPLY f
LIMITING CONDITIONS FOR OPERATION 4.2.23 At least one of the following Fuel Element Storage Well water supplies should be OPERABLE:
8803010234 B00222 DR ADOCK O 4[
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The Demineralized Water Tank with a minimum water level of two a.
feet, or b.
The Overhead Storage Tank with a minimum contained water volume of 5,000 gallons.-
APPLICABILITY: At all times.
ACTION:
With neither the Demineralized Water Tank nor the Ovechead Storage Tank OPERABLE, restore level in at least one tank within 7 days.
SURVEILLANCE REQUIREMENTS
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5.2.23.1 The Demineralized Water Tank shall be demonstrated OPERABLE by verifying the minimum water level in the tank at least once per 7 days.
5.2.23.2 The overhead Storage Tank shall be demonstrated OPERABLE by verifying the minimum contained water volume at least once per 7 days.
JUSTIFICATION Spent fuel storage is provided in the spent fuel storage racks located in the Fuel Element Storage Well within the Containment Building. The spent fuel storage racks are designed with a nominal 7.0 inch center-to-center distance between fuel assemblies in each individual rack assembly with a boron containing position slab between each storage location to ensure K rg of 0.95 o
when flooded with unborated water. Fuel storage in the storage well is restricted to fuel with stainless steel cladding which har a U-235 loading of
< 22.6 grams per axial centimeter. A fuel handling system is provided which is capable of remotely handling fuel assemblies one at a time.
The Fuel Element Storage Well System is capable of maintaining water temperature no greater than 150 F and maintaining water quality within the established limits.
Minimum water coverage limits above fuel stored in the storage racks and fuel being handled have been established to provide adequate shielding to protect personnel and to provide adequate cooling. Limits to the handling of heavy objects over the Fuel Element Storage well have been established to reduce the probability of a heavy load drop into the storage well.
A minimum Fuel Element Storage Well water supply has been established to ensure that sufficient water is available onsite to provide short-term makeup to the storage well while an alternate supply is being established if needed.
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n PROPOSED Delete Section 4/5.2.24.4 JUSTIFICATION The Overhead Storage Tank was required to be operable to supply water for the High Pressure Core Spray System.
Since the reactor is permanently shut down and defueled, there is'no use or need for a core spray system and therefore the Overhead Storage Tank should not be-required to be operable for this purpose. Also, the Overhead Storage Tank limiting condition for operation is established in a previous Technical Specification.
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4 These pages are to replace corresponding pages in Attachment 2 of our letter (LAC-12383) dated September 30, 1987.
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4.
OPERATING LIMITATIONS-l 4.0.1 Definitions - (cont'd)
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY j
including alarm and/or trip functions and channel failure trips.
b.
Bistable channels - the injection of a real or simulated signal into the sensor to verify OPERABILITY including alana and/or trip functions.
CONTAINMENT INTEG2ITY CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be isolated during accident conditions are either:
1 1.
Capable of being closed by an OPERABLE containment automatic
' isolation valve system, or l
2.
Closed by at least one manual valve, blind flange, or
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deactivated automatic valve secured in its closed position.
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b.
The freight door is closed, c.
Each air lock is OPERABLE, d.
The containment leakage rates are within the limit, and The sealing mechanism associated with each penetration (e.3.,
e.
welds, bellow, o-rings) is OPERABLE.
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'4.2.1.3 The number of containmant vessel electrical penetrations may be varied, as may the containment vessel piping penetrations, provided the new penetrations are equivalent in design to the existing penetrations. New penetrations aro defined as conduit or piping requiring attachment to the containment vessel shell. After any such penetration changes, a leak test meeting the requirements of Section 5.2.1.2 shall be performed.
4.2.1.4 Existing containment vessel penetrations may be removed from or placed in service, provided the containment vessel is not affected and the closures are equivalent in strength and tightness to those previously installed. After any such change the penetration, exclusive of the containment shell connection, shall be tested for leak tightness using a test meeting the requirements of Section 5.2.1.2.
I 4.2.1.5 The reactor building vacuum breakers shall be set to relieve at'a differential (external-over-internal) pressure not exceeding 0.5 psi.
4.2.1.6 The reactor building ventilation system isolation dampers shall close upon loss of control air or loss of electrical power supply, and they shall oe automatically closed by abnormal conditions as specified in Table 1.
l 4.2.1.7 The main steam line, the reactor building vent header, and the decay heat system blowdown line shall be isolated automatically by abnormal conditions as specified in Table 1.
4.2.1.8 The containment building steel shell temperature shall be greater than 0 F during reactor operation or during any integrated leak rate test 0
performed with a pressure exceeding 10.4 psig.
4.2.1.9 Deleted.
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i THIS PAGE INTF ' TONALLY LEFT BLANK Deleted 4/5.2.2.4 4/5.2.2.5 4.2.2.6 4.2.2.7 4.2.2.8 4.2.2.9 4.2.2.10 4.2.2.11 4.2.2.12 4.2.2.13 1
4.2.2.14 1
4.2.2.15 4.2.2.1G 4.2.2.17 4.2.2.18 4.2.2.19 i
4.2.2.20 i
4/5.2.2.21 4.2.2.22 5.2.16 l
(Next page is Page 32e(1))
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(Pages 30 - 32e)
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4.2.4.3 t
4.2.4.4 4.2.4.5 4.2.4.6 l
4.2.4.7 1
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(Pages 32t - 33)
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4.2.8 Spent Fuel Storage and Handling 4.2.8.1 Deleted.
i 4.2.8.2 Irradiated fuel elements shall be stored underwater in spent fuel storage racks that are positioned on the bottom of the spent fuel storage well, or in an approved shipping cask.
4.2.8.3 During the handling of irradiated fuel elements that have been operated at power levels greater than 1 Mwt the depth of water in the reactor f
upper cavity and/or the spent fuel storage well shall be at least 2 feet above the active fuel.
7 4.2.8.4 Deleted.
4.2.8.5 With the exception of a spent fuel shipping cask, the core spray bundle, the transfer canal shield plug and the other components and fixtures that are normally located and used within the spent fuel storage well, no objects heavier than a fuel assembly shall be handled over the spent fuel storage well.
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PLANT SYSTEMS LIMITING CONDITIONS FOR OPERATION
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4.2.23 At least one of the following Fuel Element Storage Well Water supplied should be OPERABLE:
a.
The Demineralized Water Tank with a minimum water level of two feet, or b.
The Overhead Storage Tank with a minimum contained water volume of 5,000 gallons.
APPLICABILITY: At all times.
ACTION:
With neither the Demineralized Water Tank n<.ir the Overhead Storage Tank OPERABLE, restore lovel in at least one tank within 7 days.
SURVEILLANCF REQUIREMENTS 5.2.23.1 The Demineralized Water Tank shall be demonstrated OPERABLE by verifying the minimum water level in the tank at least once per 7 days.
5.2.23.2 The Overhead Storage Tank shall be demonstrated OPERABLE by verifying the minimum contained water volume at least once per 7 days.
BASIS FOR FUEL ELEMENT STORAGE UELL WATER SUPPLY
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A minimum Fuel Element Storage Well water supply has been established to ensure that sufficient water is available onsite to provide short-term makeup to the storage well while an alternate supply is being established if needed, t
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THIS PAGE INTENTIONALLY LEFT BLANK Deleted 4/5.2.21 4/5.2.22 4/5.2.24 i
37bb)
(Pages 370
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5.1.5 Components which have been repaired, replaced, or otherwise subjected to temporary or pennanent modification shall be tested in accordance with procedures which are appropriate in view of the nature of the repair, replacement or imodification, and in view of the condition of the system.
5.1.6 Deleted.
1-5.1.7 Deleted.
5.2 TESTING 5.2.1 containment Testing 5.2.1.1 Deleted.
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Reference S 5-2 affects this page.
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i the electrical penetrations the reactor building spray valve shaft penetration, the freight door, the main stems line penetration, the feedwater line penetration, the heating steam line and condensate return penetration, i
the containment building airlocks, and the flanges of the ventilation system inlet and exhaust ducts.
Component Leak Surveillance System: A leak surveillance system (i.e.,
continuous pressurization of individual containment components) that maintains a pressure not less than 52 psig at individual test chambers of containment penetrations and seals during normal reactor operation shall be acceptable in lieu of Type B tests for the components under such leak surveillance.
(b) Type C Tests: Containment isolation valve leak detection testing shall be conducted at a pressure of 52 peig.
(c) Acceptance Criteria:
The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 60 percent of the design Jeak rate of 0.1 percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the Containment Building volume, j
r (d) Corrective Actions:
Leaks which cause the acceptance criteria of (c) to be exceeded shall be repaired and retested until the crite;ia is set.
Repairs of lesser leaks are optional.
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(e) Test Frequency:
Type B tests (except for air Iceks and electrical penetrations) shall be performed at intervals no greator than two years.
Air
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locks shall be tested at 4-month intervals. The freight door shall be teated following each closure. Electrical penetrations shall be tested at intervals no greater than one year. Type C tests shall be performed at intervals no greater than two years.
5.2.1.3 Deleted.
l 5.2.1.4 Deleted.
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5.2.1.5 Report of Test Results:
The leakage re.te results of Type B and C tests that meet the acceptance criteria shall be ceported in the applicable LACBWR operating report.
Leakage test results of Type B and C tests that i
i fail to meet the acceptance criteria shall be reported in a separate summary i
that includes an analysis and interpretation of the test data, the least l
squares fit analysis of the test data, the instrumentation err or analysis, and the structural conditions of the containment or components, if any, which contributed to the failure i.1 meeting the acceptance criteria.
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Reference 5 4
5-4 affects this page.
5.2.1.6 CONTAI M NT VENTILATION ISOLATION VALVE LEAKAGE TESTS (a) Tests:
The containment ventilation system dampers shall be
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subjected to leakage tests, in addition to the tests required by f
Section 5.2.1.2.
The tests shall be conducted at an initial I
pressure of at least 52 peig.
(b) Acceptance Criteria:
Excessive degradation is determined not to exist and the isolation valve (s) is considered operable if pressure decreases by no greater than 10 psi in a tnn minute test period.
(c) Corrective Action:
If excessive degradation exists, the leakage path must be repaired or isolated, and retested until the criteria is met.
(d) Test Frequency:
The leakage tects of the containment ventilation incidtion dampers shall be conducted at least quarterly.
5.2.2 REACTOR BUILDING ISOLATION AND VACUlN RELIEF VALVE _ OPERABILITY TESTS 5.2.2.1 The reactor building isolation system will be tested for proper operation at least once per 18 months.
5.2.2.2 The reactor building vacuum relief valves will be tested for proper operation during each reactor shutdown for refueling but in no case at intervals greater than two years.
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5-5
f.
A Fire Brigade of at least 3 members shall be maintained on site at all times.*
g.
- Deleted, b.
The working hours of the Operators, the Duty Shift Supervisor, Mechanical Maintenance and Instrument 8 Electrical Technicians when performing duties which may affect nuclear safety, and Health Physics Technicians, when performing radiation protection duties which may affect the safety of the public shall be limited.
In the event overtime must be used, the following restrictions shall be folle.ned:
1.
The specified personnel shall not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
The specified personnel shall not be pemitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period.
3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shall be allowed following overtime before the next scheduled shift for the snecified personnel, if the above limits are exceeded.
1 In the event overtime must be used in excess of the above restrictions, the Plant Superintendent or his designate, must i
authorize the deviation and the cause zust be docamented.
6.2.3 Deleted.
Fire Brigade composition may be less then the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to i
restore the Fire Brigade to within the minimum requirements.
This provision does not permit any Fire Origade position to be unmanned upon shift change due to an oncoming brigade member being late or absent.
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Reference 6 6-1 affects this page.