ML20003C499
| ML20003C499 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/25/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003C493 | List: |
| References | |
| NUDOCS 8103060287 | |
| Download: ML20003C499 (9) | |
Text
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'o, UNITED STATES i.
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-.- f j NUCLEAR REGULATORY COMMISSION O. "*b[,r!
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WASHINGTON, D. C. 20555
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f DAIRYLAND POWER COOPERATIVE r
DOCEET NO. 50 409
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LA CROSSE BOILING WATER REACTOR l
AMENDS'ENT_ TO PROVISIONAL OPERATING LICENSE Amendment No. II; License No. DPR-45 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated February 1P., 1931, as supported by i'
submittals dated October 14 and 26, 1950, and February 2,
19S1, complies with the standards and requirements of tha Atomic Energy Act of 1954, as amended (the Act), and the i
Commission's rules and regulations set forth in 10 CFR Chapter ];
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B.
The facility will operate in conformity with the application, r
the provisions of the Act, and the rules and regulations of I
f 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 (cr g! ion's regulations; a
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
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements j
have been satisfied.
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81030 60287
i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Provisional Operating License No. OPR-45 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 24, are hereby incor-i porated 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 issuana.
FOR THE NUCLEAR REGULATORY COMMI5JON Dennis M. Crutchfield, C6ief Operating Reactors Brand #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25. 1981 l~
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l ATTACHMENT TO LICENSE AMENDMENT NO. 24 PROVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET NO. 50-409 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of change.
REMOVE INSERT 37n 37n - 37r 38 38*
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i There is no change to the provisions contained on this page; it has merely been renumbered.
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2 37n PLANT SYSTEMS 4/5.2.21 EMERGENCY SERVICE WATER SUPPLY SYSTEM LIMITING CONDITION FOR OPERATION 4.2.21.1 The Emergency Service Water Supply System shall be OPERABLE, with:
a.
At least three portable gasoline engine-driven pumps connected in parallel and capable of delivering a combined flow of 900 gpn i
against a pressure of 50 psig within the reactor vessel.
b.
An operable flow path from the Mississippi River, consisting of pump suction and discharge hoses, a three-way ball valve distri-I butor, and relay hoses capable of transferring water to a valved l
inlet manifold into the High Pressure Service Water piping system.
APPLICABILITY: Operational Conditions 1, 2 and 3 i
t ACTION:
a.
With only 2 pumps OPERABLE, restore the inoperable equipment to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
'b.
With the ESWSS otherwise not OPERABLE:
1.
Verify OPERABLE status of the High Pressure Service Water Fire Suppression Water System per Sections 5.2.18.1.1.a and 5.2.18.1.2.a. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Restore the ESWSS to OPERABLE status with at least three pumps within seven (7) days or be in at least HOT SHUTDOWN within
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the next twelve (12) hours and in COLD SHUTDOWN within the following twenty-four (24) hours.
i 3.
Submit a report in accordance with Specification 3.9.2.
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If 1. above cannot be satisfied, place the reactor in at least HOT SHUTDOWN within the next twelve (12) hours and in COLD SHUTDOWN within the following twenty-four (24) hours.
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370 f
PLANT SYSTEMS SURVEILLANCE RE_QUIREMENTS x
5.2.21.1.1 The Emergency Service Water Supply System shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each manual or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
b.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel, c.
At least once per 18 months, during reactor shutdown, by performing an integrated system test which directs coolant flow through the Alternate Core Spray System test loop and back to the river.
l.
Verifying that the combined pump output develops 900 gpm at a l
minimum system test pressure of 90 psig, d.
At least once per 18 months, by performing a drill which assembles the system under simulated emergency conditions.
5.2.21.1.2 Each Emergency Service Water Supply System gasoline engine driven pump shall be demon:.trated OPERABLE:
At least once per 7 days by verifying an acceptable built-in battery a.
hydrometer indication, and voltage - 12 volts.
b.
At least once per 31 days by verifying that the fuel tank contains at least 5.0 U.S. gallons of gasoline, and that the crankcase oil is at r
a safe level.
i c.
At least once per 6 months on a STAGGERED TEST BASIS by starting an i
engine / pump unit from ambient conditions and operating at least 20 minutes with pump load.
l d.
At least once per 92 days by verifying that the fuel tank has been drained and replenished with fresh fuel.
e.
At least once per 6 montns, by performing inspection and maintenance in accordance with written procedures.
f.
At least once per 18 months, by performing inspection and maintenance in accordance with written procedures.
LACBWR Amendment No. 24 r
37p PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 5.2.21.1.3 Each Emergency Service Water Supply System pump suction hose shall be demonstrated OPERABLE:
At least once per 12 months, by testing the pump suction hoses and a.
couplings at a pressure -50 psig, and visually inspecting for damage and abnormal wear.
5.2.21.1.4 Each Emergency Service Water Supply Systens Relay hose, pump discharge hose, and the 3-way distributor shall be dmonstrated OPERABLE:
i At least once per 12 months, by testing the 5" relay hoses and a.
couplings at a pressure -225 psig and visually inspecting for 1
. damage and abnormal wt ar.
b.
At least once per 12 months.,225 psig and visually inspectin by testing the pump 3" discharge hoses i
and couplings at a pressure -
damage and abnormal wear.
At least once per 12 months, by testing the 3-way distributor and c.
couplings at a pressure -225 psig and visually inspecting for damage and abnormal wear.
d.
At least once per 12 months, by verifying that each 3-way distributor ball valve has been cycled through at least one complete cycle of full travel.
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LAC 8WR Amendment No. 24 i
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PLANT SYSTEMS i
B_ASES
_4/5.2.21 EMERGENCY SERVICE WATER SUPPLY SYSTEM The Emergency Service Water Supply System is designed to supply an additional alternate cooling source to the reactor.
because of the review of site liquefaction potential during seismic events.This The system enhances the safety factor in a seismic event where free field liquefaction at the Safe Shutdown Earthquake may, according to the results of this review, cause failure of the Crib House structure and the underground high pressure service water piping connecting the Crib House to the Turbine Building.
r The system consists of isolation valves to truncate the potentially damaged systems inside the Turbine Building, thus closing the oathway to seismically River and the necessary hoses and hardware to connect the L
Building piping, either inside the building or from the outside.
The system is capable of supplying 900 gpm flow rate against a 50 psig reactor The system installed piping can supply water to the High Pressure pressure.
Core Spray System, the Alternate Core Spray System, the Fire Suppression Systems,the Shutdown Condenser and the Low Pressure Service Water System (which is the ultimate heat sink for decay heat).
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i LACBWR Amendment No. 2.{.
37r PLANT SYSTEMS 4/5.2_.22 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES f
LIMITING CONDITIONS FOR OPERATION L
t 4.2.22 The leakage through the following pressure isolation valves shall W.
exceed Sgpm (a,b).
a.
Alternate Core Spray Valve 38-26-001 b.
Alternate Core Spray Valve 38-26-002 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 AND 3 XCTION:
l If seat leakage through one of the valves listed above excaedsat a.
limit, the valve must be repaired or replaced prior to enterin-Operational Condition 1 Otherwise be in cold shutdown withirII4 nours.
SURVIELLANCE REQUIREMENTS 5.2.22 Prior to entering Operational Condition 1 the seat leakage through act valve shall be individually verified to be equal to or less than 5 F:
After each refueling outage, a.
b.
Af ter each cold shutdown of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more if not done withh ust 9 months, and Frior to returning to service after mantenance, repair or repleent.
c.
BASES j
4/5.2.22 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES To increase the reliability of Primary Coolant System pressure isolation mies by establishing seat leakage limits and surveillance requirements, thereby reducing the potential of an inter-system loss of coolant accident.
Footnote:
(a)l.
Leakage rates less than or equal to 1.0 gpm are considered acceptatie.
2.
Leakage rates greater than 1.0 gpm but less than or equa to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that i
reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 505 or greater.
3.
Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gp-are considered unacceptable if the latest measured rate exceeded thI rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible ran of 5.0 gpm by 505 or greater.
4 Leakage rates greater than 5.0 gpm are considered unacceptable.
5 To satisfy ALARA requirements, leakage may be measured indirectly (r from the performance of pressure indicators) if accomplished in acted.
ante with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with 1m leakage criteria.
(b)
Minimum test differential pressure shall not be less than 150 osid.
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5.
MAINTENANCE 5.1 GENERAL 5.1.1 Maintenance operations, including refueling operations and t
routine tests, shall be performed in conformance with these specifi-
- cations, j
5.1. 2 Maintenance operations on the reactor coolant system, reactor f
components, or emergency systems shall be performed as authorized by
~l the Shift Supervisor whenever fuel is in the reactor. Maintenance involving the opening of systems containing radioactive materials shall f
be conducted under the surveillance of a Health Physics representative.
5.1. 3 Maintenance operationswhich invoive the opening of the reactor I
primary coolant system shall be performed with the reactor shut down and depressurized to atmospheric pressure. The reactor primary coolant auxiliary systems may be serviced during reactor operation if the system is first isolated, depressuri:ed to atmospheric pressure, and cooled to 150'F. The limitations of this paragraph do not apply to the super-vised collection of steam or water samples, and supervised venting of process instruments, j
5.1. 4 Radiation monitoring instrumentation for effluent streams from the plant may be removed from service for intervals up to 24 hrs for necessary maintenance operations provided that the effluent path is closed or provided that backup instrumentation is provided and the safety action function is maintained.
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l LACBWR Amendment No.,16 )[, 24